Salem Generating Station - Nuclear Regulatory Commission

STATION:

SYSTEM:

TASK:

TASK NUMBER:

JPM NUMBER:

OPERA TOR TRAINING PROGRAM JOB PERFORMANCE MEASURE

SALEM

Conduct of Operations - Administrative

Perform a Manual AFD Calculation IAW S2.0P-ST.NIS-0001

N0150010201

16-01 NRC RO-A1

KIA NUMBER: G 2.1.25 ALTERNATE PATH: D -----------l IMPORTANCE FACTOR: 3.9

APPLICABILITY: RO

EoD R0[8J STAD sRoD

EVALUATION SETTING/METHOD: Classroom

S2.0P-ST.NIS-0001, Rev. 13

REFERENCES: Salem Unit 2 Core Operating Limits Report Cycle 23, Rev. 7 Salem 2 Cycle 23 REM, Rev 17 ( checked 10-6-17)

TOOLS AND EQUIPMENT: Calculator

VALIDATED JPM COMPLETION TIME: 10 min

TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A

Developed By: R.Chan~~ Date: 10-6-17

Instructor ~ lo }d. 'l.011 Validated By: ILJvf-A,r.J ~~ 'CJ Date:

SME or lnstruc o~ l)t,~- ,{:, !<-,?LL

Approved By: . . rt 't1j{L Date: ,(ii (i.

am, e a men

Approved By: Date: \\ l 1'!> / 17

ACTUAL JPM COMPLETION TIME:

ACTUAL TIME CRITICAL COMPLETION TIME:

PERFORMED BY:

GRADE: D SAT D UNSAT

REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE: PSEG CONFIDENTIAL - Possession Requires Specific Permission from Nuclear Training

SRO

JPM NUMBER:

Rev# Date

00 10-6-17

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE

16-01 NRC RO-A1

Description

Added revision history and simulator setup pages. Updated NI currents from Rev. 5 of REM dated 6/4/17. Editorial comments from IP 71111.11 FASA.

Validation Required

Yes

PSEG CONFIDENTIAL - Possession Requires Specific Permission from Nuclear Training of 12

SYSTEM:

TASK:

TASK NUMBER:

SIMULATOR IC:


SIMULATOR SETUP INSTRUCTIONS



N0150010201

N/A

MALFUNCTIONS/ REMOTES: N/A

OVERRIDES: N/A

SPECIAL INSTRUCTIONS: None



NAME: ------------DATE: ------------

SYSTEM: Conduct of Operations - Administrative

TASK:

TASK NUMBER:


N0150010201

INITIAL CONDITIONS:

• Salem Unit 2 completed a down power to 73% power today at 0830 IAW TSAS 3.1.3.1.c.3.d due to a single control rod being declared inoperable.

• The AFD Monitor Alarm for the Auxiliary Annunciator was determined to be inoperable at 0840.

INITIATING CUE: • You are the Reactor Operator.

• The CRS directs you to perform a manual AFD calculation IAW Section 5.3 of S2.0P-ST.NIS-0001 (0), Power Distribution - Axial Flux Difference.

• Current AFD Channel Console Readings are:

Channel I: -9.8

Channel II: -9.7

Channel Ill: -10.3

Channel IV: -10.5

• All prerequisites are completed SAT.

• NOTIFY the CRS of the results of the surveillance after completing Step 5.3.1.F.


Successful Completion Criteria:

1. All critical steps completed.


2. All sequential steps completed in order.

3. All time-critical steps completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.

Task Standard for Successful Completion: 1. Completes applicable portion of Attachment 3 of 52.0P-ST.NIS-0001, and

determines Channel Ill and IV is outside the AFD Target Band.


OPERATOR TRAINING PROGRAM

JOB PERFORMANCE MEASURE System: Conduct of Operations - Administrative

Task: Perform a Manual AFD Calculation IAW S2.0P-ST.NIS-0001

c;il :y • >' .··•··•· .. < < :i'> STEP '.:: ·.·. . .·· •>· :; ,)STE~( i{(Shcld~~ ~re;:denotes Critlc:arst~p) I

·"jr(Nb .. :.:... . . );:·· /'.,'(tcriticarstep) /ii/<< # • '. i.'.Y\ .,: }{##§e~ilential Criticc3_( Step}'··

Provide the following materials:

• S2.0P-ST.NIS-0001, Power Distribution - Axial Flux Difference,

• Salem Unit 2 Core Operating Limits Report (COLR), and

• S2.RE-RA.ZZ-0011 (Salem 2 Cycle 23 REM, Rev 17)

CUE \ Fill in the JPM Start Time when the student acknowledges the Initiating Cue.

START TIME: _______ _

STANDARD;. (Bolded area]dentifies Task . . .. . .. Stc:1pdar~)' ..

Note: The data tables from S2.RERA.ZZ-0011 (Q), TABLES have been removed. The data tables from this procedure are now on Sharepoint and are located as follows:

Main Nuclear Webpage7Quick Links7 Operations-Salem 7 Reactor Engineering Manual7Salem Unit 27REM Data Salem Unit 2 Cycle ## Rev #.pdf

3.0 I Precautions and Limitations I Operator reviews and initials Precautions and Limitations.

5.3.1 I !E AFD Monitor (XA-8740), OR Monitor j Operator uses Attachment 3 to Alarm {Auxiliary Annunciator) is determine AFD. inoperable, THEN COMPLETE Attachment 3, AFD Data Log Sheet as follows:

NAME: __________ _

DATE: __________ _

> , . COMMENTS ··

EVA. L.• .. . 1 .. ii{R·e···.· .. ~ .. ·.u.'.ir .. edfo.JU·N·:sATi'· S/U.. . .. :;•evaluation)

, :·~.;-'·. ,, r:·):·,. , ·. ..,




Task: Perform a Manual AFD Calculation JAW S2.0P-ST.NIS-0001

.;...·

$TEP ;(Shaded afeadenotes CridcalStep)t

p/;},,; (*;:<;ritical Step[} / . . .. · . . <··(#Sequential CriJil;al Stf.!pJ

5.3.1.A I ENTER present Reactor Power

•· STANDARD"·' .: , · (Boldedarea ide"ntiflesTask

Standard)· '.\ · '.: < ;,'. '

Operator enters 73% power

5.3.1.B I ENTER AFD Target from S2.RE-RA.ZZ- , Operator enters (-1.5) for AFD Target 0011, Tables, Table 3 using the Salem 2 Cycle 23 REM,

Table 3

5.3.1.C I C:ALCULATE.the AFD Target Value IAW .thefollowing: . . .

(A) /(B)=AFD T~rgetVcilue (present .. ·•· f)ower) = (C)

Where: (A)= Present Reactor power :, (B)= AFDTarget.'(100% Value)

····(C)= AFcrrarget(present· power)

Calculates AFD Target for present power level as:

(73) X (-1.5) = -1.095 (100)

IAW P&L 3.2, round value to first decimal place (-1.1

NOTE I The Target Band Upper and Lower Limit I Operator reads the Note and continues shall be the more restrictive of the limits on. defined in the Core Operating Limits Report (COLR) OR $2.RE-RA.ZZ-0011 (Q), Tables.

NAME: __________ _

DATE: __________ _

COMMENTS (Required for UNSAT

evaluation);





*

. , . · ... · .· ,, . , STEP r ·. ·.·. .··. . ·: ; (S~a'.ded.iar~a<den,,otes'Critical Stip) . . :; ;;::; ecri,tig'al;~Ste,pf ··· ·· · ·'

(#sSeqUentiafCritical Step}

_.. +(C)=:= Upper limit

··~ +( C)=<LowerLirnit' .. " ,;,1 C ,, SS

STANDARD;;>,:> (Bolded are,a ider:,tifies Task

·· Standard) ·

Determines Upper Limit using Target Band values from Salem 2 REM Table 3:

+6.0 +(-1.1 )= +4. 9

Determines Lower Limit is:

-9.0 + (-1.1)= -10.1

NOTE I When the AXIAL FLUX DIFFERENCE I Operator reads Note and continues on. (AFD) Monitor is inoperable, the logged values shall be assumed to exist during the interval preceding each logging. (4.2.1.1.b)

5.3.1.E I ENTER AFD Channel Readings. Enters AFD values from initial conditions on Attachment 3.

5.3.1.F I DETERMINE if any Channel is operating Determines Channels Ill and IV (-10.3 outside ofJhe Target Band Upper.or and 10.5) is operating outside the Lower Limits (inclusive) ·· Lower Target Band.

JPM is Complete once the operator determines status of channels.

Cue: IF operator does not verbalize the results, THEN state: CRS requests the results of the calculation.

NAME: ------------DATE: __________ _

COMMENTS· . (Reqllir~d for,UNSAT ·

. ;. ~ evaluation),,··





CUE: J JPM is Complete.

RECORD the STOP TIME.

STOP TIME: ------

STANDARD • (Bolded"area, id~ntifies::rask · ' Standard) .

' C ,' .·J,', , x,t;(,:

Terminate JPM when operator performs Step 5.3.1.F

NAME: -----------DATE: -----------


JPM #: 16-01 NRC RO-A1


JOB PERFORMANCE MEASURE VALIDATION CHECKLIST

NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 8 and 11 below.

__ J_,~'-----1. Task description and number, JPM description and number are identified.

}Jl-__ / __ 2. Knowledge and Abilities (KIA) references are included.

}f~ ___ - _ 3. Performance location specified. (in-plant, control room, or simulator)

~R __ / __ 4. Initial setup conditions are identified.

,z __ ,,,~·_ s. Initiating and terminating Cues are properly identified.

-~~-·- 6. Task standards identified and verified by SME review.

--~ __ 7. Critical steps meet the criteria for critical steps and are identified with an asterisk(*).

__ .ff;. __ 8. Verify the procedure referenced by this JPM mat es the JllilSt current revision of that procedure: Procedure Rev. -11_ Date Id ,c,.u,~...,- ~

__ ·IB_9.PilottesttheJPM: ~ l ~Cot.£) a. verify Cues both verbal and visual are free of con lict, and b. ensure performance time is accurate.

__ 0_'1_,A..,__ 10. If the JPM cannot be performed as written with proper responses, then revise the JPM.

!'/) ]\ ___ I'\_ 11. When JPM is revalidated, SME or Instructor sign and date JPM cover page.

Z ,,ff J !Ill\ ,A/ v~,/'Q., If\ .f! £

SME/lnstructor: t?l __ ;JJrv v 1,rv.,vi '-' '>t.-

SME/lnstruct~ ~Iv;,~

SME/lnstructor: ~-~~ Date:

Date: _1,_o _/ v_' l_/_1 l_. __

1¢ It~, 'l'-' I T": I

}-0 r lo - ) o I 1 Date:


INITIAL CONDITIONS:

• Salem Unit 2 completed a down power to 73% power today at 0830 IAW TSAS 3.1.3.1.c.3.d due to a single control rod being declared inoperable.

• The AFD Monitor Alarm for the Auxiliary Annunciator was determined to be inoperable at 0840.

INITIATING CUE:

• You are the Reactor Operator.

• The CRS directs you to perform a manual AFD calculation IAW Section 5.3 of S2.0P-ST.NIS-0001 (Q), Power Distribution - Axial Flux Difference.

• Current AFD Channel Console Readings are:

Channel I: -9.8

Channel II: -9.7

Channel Ill: -10.3

Channel IV: -10.5

• All prerequisites are completed SAT.

• NOTIFY the CRS of the results of the surveillance after completing Step 5.3.1. F.


Condition

__ AFD Monitor Inoperable

~FD Monitor Alarm Inoperable

AFD Monitor Alarm Received

ATTACHMENT 3 (Page 1 of 1)

AFD DATA LOG SHEET

Log Started

Date Time

NOTE

s2.oP-ST.NIS-0001 (Q)

Page __ of __

AFD Monitor/Alarm OPERABLE OR Alarm Cleared

Date Time

When the Axial Flux Difference (AFD) Monitor is inoperable, the logged values shall be assumed to exist during the interval preceding each logging (T/S 4.2.1.1.b ).

Date ?odCl.f Time oir~b AFD Channel(s) in Alarm 0

Reactor Power(%) 73 AFD Target (100% Value) -1.s AFD Target (present power) - I, I \',,I ,/ ,/""

Upper l.-j I '1 - ~--¥' / AFD Target Band

-10.\ ., 1 ,, Lower - /

- 'l. s l~~ ..... - / CHI

-'t, I / AFD Channel CH II

1 Readings CH Ill -10.1 /

It!""

CH IV -10.s / Number of AFD Channels z. / Outside TarQet Band

Number of AFD Channels Outside COLR, FiQure 2 (1) 0

Penalty Minutes

Accumulated Penalt4 Min.ute)s (Previous 2 Hour penod

Initials

IV

( 1) ChOLR, Figure 2 is applicable between 50% and 90% Rated Thermal Power. If power is not within this band t en marK N/A

Salem 2 Page 15 of -17 Rev. 13

STATION:

SYSTEM:


SALEM


TASK: Perform a Channel Check of Reactor Coolant Temperatures JAW S2.0PDL.ZZ-0003

TASK NUMBER: S302000115

JPM NUMBER: 16-01 NRC RO-A2

ALTERNATE PATH: D G 2.1.18 KIA NUMBER: -------------, IMPORTANCE FACTOR: 3.6

APPLICABILITY: RO SRO

EoD R0[:8] STAD SRoD


S2.0P-DL.ZZ-0003, Rev. 109 REFERENCES: Salem 2 Cycle 23 REM, Rev 17 ( checked 10-11-17)

TOOLS AND EQUIPMENT: None



Developed By: R.Chan JlJ» ~ Date: 10-11-17 lnstrctor

Validated By: ~~~ r2.L Date: , 0 (t, · ?.Prf-SMEorlns~ (II( s (7 Approved By:

\../'\ - , Date: ing Depart

Approved By: Date: I\/ 1:J) ,1



PERFORMED BY:


, REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

PSEG CONFIDENTIAL - Possession Requires Specific Permission from Nuclear Training

JPM NUMBER:

Rev# Date

00 10-11-17


16-01 NRC RO-A2

Description

New JPM. Added revision history and simulator setup pages. Editorial comments from IP 71111.11 FASA.

Validation Required

Yes

PSEG CONFIDENTIAL - Possession Requires Specific Permission from Nuclear Training Page 2 of 12

SYSTEM:

TASK:

TASK NUMBER:

SIMULATOR IC:




Perform a Channel Check of Reactor Coolant Temperatures IAW S2.0P-DL.ZZ-0003 S302000115

N/A


OVERRIDES: N/A



SYSTEM:

·TASK:

TASK NUMBER:

INITIAL CONDITIONS:


NAME: ------------DATE: ------------


Perform a Channel Check of Reactor Coolant Temperatures IAW S2.0PDL.ZZ-0003 S302000115

• Salem Unit 2 is at 100% reactor power.

• Control room log readings IAW S2.0P-DL.ZZ-0003, Control Room Log (Modes 1-4), is in progress.

INITIATING CUE:


• PERFORM the 1830 log readings using the control room log sheet provided.

• 2CC1 Console Readings for OTDT Setpoint are:

RC Loop OTDT (deg F)

21 (Tl411 C) 74

22 (Tl421 C) 78

23 (T1431C) 75

24 (Tl441C) 72

• NOTIFY the CRS when log readings are complete.








Task Standard for Successful Completion: 1. Completes the 1830 log readings for 21 thru 24 OTDT Setpoints and Tavg Channel

Checks. 2. Determines 24 Loop OTDT Setpoint is UNSAT.




Task: Perform a Channel Check of Reactor Coolant Temperatures IAW S2.0P-DL.ZZ-0003

, . . $TEP/ . ·JShaded.areaJlen'otesCritfoa1·.step)/ ·.' i {.,'.:\, .• :·i,,, ;·tCriticatStepf\;> .. i, ,,J,·'•/.t ...

''{# S~queptial_Cri!i~c!l§_!e,~J'. .


• S2.0P-DL.ZZ-0003, Control Room Log (Modes 1-4), and

• S2.RE-RA.ZZ-0011 (Salem 2 Cycle 23 REM, Rev 17)

CUE I Fill in the JPM Start Time when the student acknowledges the Initiating Cue.

START TIME: --------

REACTOR COOLANT TEMPERATURES (Page 35 of 87 from S2.0P-DL.ZZ-0003)

Note: The data tables from S2.RERA.ZZ-0011(Q), TABLES have been removed. The data tables from this procedure are now on Sharepoint and are located as follows:

Note: Tavg readings for each RC loop must be provided on the log sheet.

Main Nuclear Webpage--)Quick Links--)Operations-Salem--)Reactor Engineering Manual--)Salem Unit 2--)REM Data Salem Unit 2 Cycle ## Rev #.pdf

NAME:. __________ _

DATE: __________ _

. ·. o,1o~Mef\J+s, . .(Required.for UNSAT .·. ',' '' evaluation) '





iir<1·•:~JEP0

·#\. ··• ::N·o. \> :,, , ':' ·- '-"" •''"/{,'",i

CUE I RC LOOP AVERAGE TEMP

21 - 24 AVE TEMP CHANNEL CHECK

*S/R 4.3.2.1.1 is applicable in Modes 1, 2, & 3. IF all 4 loop avg temperatures are within 3 degrees F, TEHN RECORD "SAT'.

21 LOOPOTDT STPT.CHAN·CHECK· .. ,•' ·e, ,ss' • ' .,

''*RECORb~'c;nsol;OTbTindic~tibn: Mustb~witAinREM{Reactor '' '' ,·.· .. ,' Engineering Manual) OTDJSepoint .. Band. ·

.. ·· STAND!-RD \ ...... ·<. ,, · JBolded area ·identifies.if ask' ·. · · .. Stahclarclf · · '·

Cue: The following Tavg Temps should be provided on the log sheet:

Loop 21 = 573.2 F

Loop 22 = 575.2 F

Loop 23 = 57 4.5 F

Loop 24 - 57 4.8 F

Operator determines all Tavg temps within 3 degrees F and records "SAT".

Operator records the OTDT sepoint on the log sheet.

Operator evaluates OTDT setpoint using REM FIGURE 5A and determines 21 Loop OTDT sepoint is within the OTDT setpoint band.

NAME: __________ _

DATE:.~----------



JOB PERFORMANCE MEASURE

NAME:. __________ _

DATE:. __________ _ System: Conduct of Operations - Administrative


· '·(Shaded.~rea cl:~:~ Critical $fop).. .. ' · .(B~lded:r::i~:~~~sTask> .. . ·~ . (*'9ritical Step) : . . ....... .. Standard) .

(# Sequential Critical Step).. .

Operator records the OTDT sepoint on the log sheet.

Operator evaluates OTDT setpoint using REM FIGURE 58 and determines 22 Loop OTDT sepoint is within the OTDT setpoint band.

23 .. LOOP.OTDtSTPtCHAN CHECK .. I Operator records the OTDT sepoint on

*RECORDConsble bYDT indicau'on: : ., Mustbiwithin REM{Reactor\ ....

. Engineering.Manual)OTDTSepoint Band.···· <. · .·. · ·

the log sheet.

Operator evaluates OTDT setpoint using REM FIGURE SC and determines 23 Loop OTDT sepoint is within the OTDT setpoint band.

.· .. COMMENTS· . . ·(RequiredJofUNSAT · · v }eva1uatio11r·





' . ' ' > STEP ; . .. ·.·.··.·•·· . . .. ··. . .. . STANDARD ... (Shadecfar,ea denotes CriUca)Step) .> ' . (Bolded area identifies Tas·I<. < t::):/~'ii'·s;JJJJifl~,trftltt!;J;i~)J:,:: . .;s!!~i~rf}:~;····'·~·•t .. '·

-·----------~~--

·2.4LOOP·Otot·sTPt'CHAN.CHECK ,'"-i', . ,,

Operator records the OTDT setpoint on the log sheet and may indicate a redcircled reading is required to denote OTDT setpoint is UNSAT OR notification to the CRS ( either method is acceptable).

Operator evaluates OTDT setpoint using REM FIGURE 50 and determines 24 Loop OTDT sepoint is NOT within the OTDT setpoint band.

Operator informs CRS that Loop 24 OTDT setpoint is outside the REM setpoint band.

CUE: I JPM is Complete. Terminate JPM when operator identifies 24 Loop OTDT sepoint is NOT within the REM sepoint band OR when the operator provides the results of the Channel Check of 21 -24 Loops OTDT.


STOP TIME: ------

NAME: _________ _

DATE: __________ _

.. ·. COMMENTS (Requifecffor,UNSAT

' .. evaloationr . ..


JPM #: 16-01 NRC RO-A2




_r1_l __ 1. Task description and number, JPM description and number are identified.

_fl_l __ 2. Knowledge and Abilities (KIA) references are included.

--~-"-- 3. Performance location specified. (in-plant, control room, or simulator)

_~_l __ 4. Initial setup conditions are identified.

__ //_c _ 5. Initiating and terminating Cues are properly identified.

_rl_l __ 6. Task standards identified and verified by SME review.

_;z._c_ __ 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).

_(l_l __ 8. Verify the procedure referenced by this JPM matches the most current revision of that procedure: Procedure Rev.~ Date 1<0-11-1 l

fLl 9. Pilot test the JPM: ----a. verify Cues both verbal and visual are free of conflict, and b. ensure performance time is accurate.

_,,..r_/_4_ 10. If the JPM cannot be performed as written with proper responses, then revise the JPM.

_r/_//r __ 11. When JPM is revalidated, SME or Instructor sign and date JPM cover page.

SME/lnstructorfi:!36~:.~ Lo SME/lnstructor:_:=.---;::;:;~~-t;t~-~'._ _____ _

Date: ) 0-//-Jl

Date: /c, }t, · '2.-dt~

SME/lnstructor: Date: ------------- ------


INITIAL CONDITIONS:

• Salem Unit 2 is at 100% reactor power.

• Control room log readings IAW S2.0P-DL.ZZ-0003, Control Room Log (Modes 1-4), is in progress.

INITIATING CUE:


• PERFORM the 1830 log readings using the control room log sheet provided.

• 2CC1 Console Readings for OTDT Setpoint are:

RC Loop OTDT (deg F)

21 (Tl411 C) 74

22 (Tl421C) 78

23 (Tl431 C) 75

24 (Tl441C) 72

• NOTIFY the CRS when log readings are complete.


ATTACHMENT 1

Page 23 of 51

S2.0P-DL.ZZ-0003(Q)

MONDAY DATE: / / ------

CONTROL ROOM LOG (MODES 1-4)

DESCRIPTION SURV. 'INSTR I I I MON TUE WED THU FRI SAT SUN RQMT NO. UNITS MIN MAX 1830 0630 1830 0630 1830 0630 1830 0630 1830 0630 1830 0630 1830 0630

REACTOR COOLANT TEMPERATURES

~~~~06 ~~;T~~~T_J4:·~1.1.1 I r14~1cl_~F _ _1__· i · __ I_ ___ J_ I ____ j ____ l __ I ._ ___ i ________ _

l· RECORD Console OTDT indication. Must be within REM (Reactor Engineering Manual Data) OTDT Setpoint Band. ------------------·---

1

22 LOOP OTDT STPT 14.3.1.1.1.7 I Tl421C I °F I * CHAN CHECK

I: RECORD_ Co-nsole~OTDT indication. Must be within REM (Reacto_J"_ En9_i_t1_El_Elr_!r:19 Man~al Data)_9_IDT Setpoint Band.

~~~~o{H~6~T STP~ _1~3:::~7~l Tl431Cl-_°F __ [_ ~ _r * I --_ I_ _I I _ J ___ _I_ __ _I__ I - J ___ J ____ l __ 1* RECORD Console 9IQ'I in_dication. Must be~ithin ~EM (Reac_torE_ngin_eering Manual Data) 01-0-f_ Setp()it1t_ B_a_n_cj._ ______ _

1~~~~06H~6~~ST:~_!~3::·~7 I Tl441C_I_~~_[_-~ I * J ___ _J ___ I I ___ J ___ _I_ I I_ - _ _I ___ _! ___ _I I t_RECORD Console OTDT indication. Must be within REM (Reactor Engineering Manual Data) OTDT Setpoint Band. ______ __:_ --

ILOOP 21 AVERAGE TEMP I _ -- - - - - - - - - -

\LOOP 22 AVERAGE

IT:MP -- - -

14.2.5.1 13.1.1.4

!

1

'4.2.5.1 3.1.1.4

LOOP 23 AVERAGE 14.2.5.1 [TEMP 13.1.1.4 I ___ I __ _

ILOOP 24 AVERAGE 14.2.5.1 \TEMP 13.1.1.4 L_____ ··- -------- -----

Tl-412

Tl-422

Tl-432

Tl-442

OF 541 579.9

I I ____ I OF 541 579.9

____ I _ _ _ _ I _ _ _ _I °F I 541 I 579.9

°F I 541 I 579.9

1

21 - 24 AVE TEMP 14,3.2.1.1.1.f \ - - - \ • • • \ UNSAT I SAT CHANNEL CHECK 1

4·3·2·1·1.4.d

\ ! I U I I I l I I I I

I* ?~R_ '!:3.2.1.1 is applicable in Modes 1, 2, & 3. IF a~ j J()()p_ c1v_g _temperatures _a~e_ ~i_thJr1_~0

£,_J::f::IE_N_RECORD "S~ T" ________ _ -------------- ------------ - - - -- . - ------------

COMMENTS:

Salem 2 Page 35 of 87

--j

I - _____ _[_ - -

Rev. 109

STATION:

SYSTEM:

TASK:

TASK NUMBER:

JPM NUMBER:

ALTERNATE PATH:


SALEM

Equipment Control - Administrative

Perform a Manual QPTR

N0150020201

16-01 NRC RO-A3

K/A NUMBER: G 2.1.43 I X I ----------1 MP ORT AN CE FACTOR: 4.1 -----APPLICABILITY: RO

EoO RO[TI STAO SROLJ


REFERENCES: S2.0P-ST.NIS-0002 Rev. 14 (checked 10-11-17) S2 Reactor Engineering Manual Data, Cycle 23 Rev .17 Tech Spec 3.2.4 (QPTR)




Developed By: R.Chan~~ Date: 10-11-17

Validated By:

Instructor

Date: 16f t ~ U I ff

Approved By: ,,/; "J/1J Date:

Date: Approved By:



PERFORMED BY:





SRO

JPM NUMBER: -

Rev# Date

00 10-11-17


REVISION HISTORY

16-01 NRC RO-A3

Description

Added revision history and simulator setup pages. Editorial comments from IP 71111.11 FASA. Added pre-determined 100% NI Current Values.

Validation Required

Yes


SYSTEM:

TASK:

TASK NUMBER:

SIMULATOR IC:



Equipment Control - Admin

Perform a QPTR

N0150020201

N/A


OVERRIDES: N/A

SPECIAL INSTRUCTIONS:

1. Due to the continuous changes to the 100% NI Current Value, the Operator will be given a pre-determined 100% NI Current Value in lieu of the most current REM document.


SYSTEM:

TASK:

TASK NUMBER:

INITIAL CONDITIONS:


NAME: -----------0 ATE: -----------

Equipment Control - Admin

Perform a OPTR

N0150020201

• Unit 2 was operating at 100% power when rod 204 dropped fully into the core.

• OHAs E-46, LOWER SECT DEV ABV 50% PWR, and E-38 UPPER SECT DEV ABV 50% PWR, are both illuminated.

• The crew has entered S2.0P-AB.ROD-0002, Dropped Rod, and is making preparations to perform a load reduction to< 75% Rated Thermal Power to comply with Tech Spec 3.1.3.1, Action c.3.d.



INITIATING CUE:

• The CRS has directed you to PERFORM a Manual QPTR Calculation !AW S2.0P-ST.NIS-0002, Power Distribution - Quadrant Power Tilt Ratio.

• The100% NI Current Values from the Reactor Engineering Manual (REM) are given below:

TOP BOTTOM

N41 185.0 186.4

N42 187.1 197.2

N43 183.1 179.0

N44 140.4 145.0

• The Lower and Upper NI Detector current readings are:

Upper Detectors Lower Detectors N41 N42 N43 N44

184 192 182 139

• NOTIFY the CRS with the results of the surveillance.

lj Successful Completion Criteria:




181 198 174 142


Task Standard for Successful Completion: 1. Perform the QPTR and calculates the highest QPTR as UNSAT (highest N42T AND N42B)

with a value of 1.025 and 1.023 respectively (acceptable range+/- 0.002). 2. Identifies Maximum Power Tilt exceeds 1.02 and enters TIS 3.2.4.


SYSTEM:

TASK:

CUE:

2.1

3.0

5.1.1

5.1.2


Perform a QPTR

Provide the following: • S2.0P-ST.NIS-0002, Power

Distribution - Quadrant Power Tilt Ratio.

Fill in the JPM Start Time when the student acknowledges the Initiating Cue.


IDENTIFY sections of this procedure that are NOT to be performed with "N/A".

PRECAUTIONS AND LIMITATIONS

IF one PR channel is inoperable, AND RTP is >75%, THEN ...

RECORD the following data on Attachment 2 • Date • Time • Reactor Power • Reason for performing QPTR Calculation



. i. STANDARD· l

(Bold~d.area'ideritifies·task.Standard)

Evaluator's Note: The operator will NOT be given the current REM document. All data required to perform this task is provided on the Initial Condition Sheet provided to the operator.

Cue: CRS has already removed sections of the procedure not related to your task.

Reads and initials PRECAUTIONS AND LIMITATIONS 3.1-3.5

Determines all PR channel are operable and step is N/A.

Records current date, current time, 100% reactor power and checks OHA E-46 as reason for performance in Attachment 2.

TQ-AA-106-0303 Rev. 4

NAME:

DATE: ----------

· .. COMMENTS (Requiredfo'r/.! . ONSAt ····· . . evaluation


SYSTEM:

TASK:

5.1.3

Equipment Control - Administrative Perform a QPTR

>)_;::.,,,i><·.+ ,•§TEP · .... :.: ... •··: .. •·. (·: ' ~·::'.(Snaded arei!Cdenotes.Critjca[Step) >

,······· • :' 1 \''/://(~'~nticaFstEip};.t,~:\fy::·~.·s,:.i · #.;Sequential Critical Ste

RECORD the following data on Attachment 1:

• NI Channels N-41, N-42, N43 and N-44 Upper Detector current readings

• NI Channels N-41, N-42, N43 and N-44 Lower Detector current readings

• Respective 100% NI Current Values for Channels N-41, N-42, N43 and N-44 Detectors from S2.RE-RA.ZZ-0011, Table 2

OPERA TOR TRAINING PROGRAM


.... · ...•. · ... STANDARD ,.· . ·· .. ·········,······ ···(Soldedatea··ideotifies·JasKStancl~r,cl)\.·'

' ~,j' "' ' ~• ' "' ' < 0 C

Records on Attachment 1: (From initial conditions)

• NI channels N41-44 Upper Detector Current Readings

• NI channels N41-44 Lower Detector Current Readings

• 100% NI Current Values from S2.RE-RA.ZZ-0011, TABLES

NOTE: Attachment 1, Section 3 is NOT required to be performed to determine detector currents. It was added at Rev. 12 to use "when any NIS meter is suspect."

If asked, CUE that all Power Range Detectors are Opmable.

TQ-AA-106-0303 Rev. 4

NAME:

DATE: ---------

C.OMMENT.S · · , (Required for.~ .

/'uNsAr, .. evaluation·


SYSTEM:

TASK:

5.1.6

Equipment Control - Administrative Perform a QPTR

\':RECORtflk~foJlowing·on•·Att~chment2•· .. ••.• ;) .

0 1: /'Power Tilt'' for each detector ;,S .'2. ,•·;,Maxln]~mPower Tilt" and.applicable' . ·:.1 ·aetector,ide'ntification'inform1;3tion .. , 3. 1 esfResults.by.1nitiali~gSAJ' or

, UNSATcolUmn IAW stated · AcCeptance Criteria.

DIRECT a second Operator to perform Independent Verification of calculations in Attachment 1, Sections 1.0, 2.0 and 3.0 as applicable.



.···· ·. .. ·· STANDARD ,... , ·. : (E3oldedareaidentifiesTask $fa11clard} ··.

Correctly performs calculations using Attachment 1 (numbers as per ANSWER KEY)

• Calculates Detector Ratio for each top and bottom detector.

• Adds detector ratios to get Sum of detector ratios.

• Divides Sum by number of operable detectors (4) to get Average Detector Ratios.

• Places Average Detector Ratios in 4th

column of Att. 1 • Divides each detector ratio by the

average ratio to get the power tilt for each detector.

Cue: IV is complete when asked for IV of calculations

Records information on Attachment 2 (as per ANSWER KEY)

Maximum Power Tilt for N42T OR N42B will be marked UNSAT at 1.025 and 1.023 respectively (acceptable range of+/- 0.002 was provided to allow for rounding in calculation and Excel).

Cue: IV is complete SAT.

TQ-AA-106-0303 Rev. 4

NAME:

0 ATE: ---------

COMMENTS (Reqilired for

. ... · ... UN.SAT . ;., . ·evaluation


SYSTEM:

TASK:

5.3.1

CUE:


Perform a QPTR

::iF'tne:rJ~:~imum··r,o~e{1i1t·¥~{an~cie_tector . . :exceeds~·1.02,JHENREFER'to.T/S.3;2.4 for. ' corrective actions ... ·.. . . . . ..

This surveillance is satisfactory when Attachment 2 or 3 is completed with the Test data meeting the Acceptance Criteria stated .

. . ·':rhlssurveill~~J:;ihs'atisfactoff ! ,_ '• • ; • ' ~'.,' • • • • <

. : 1Nir,l1E·~bTF;(~}fo corr;ctthe Urisatisfactor/oon'difio11(s) .....

B. ;~~td~bfh;'~til,~umber(s) AND···· i .tfie reason for ur:isatisfacfory." ·. \ •· .. <·:completion onAttachment 4 in the< •:Comments.Section. . . './'"J'\Ct. ·<, ,· , '

: C:. NOTIF'( Reactor Eriglrieerjng.• JPM is Complete.

REPEAT BACK any message from the operator on the status of the JPM, and then state "This JPM is complete".

STOP TIME: _____ _



.· ' -STANDARD , . . , . (Bolded area· identifies Task Standard)

Determines maximum power tilt exceeds 1.02 and determines entry into Tech Spec 3.2.4 IS required.

Determines surveillance is UNSAT and marks step N/A.

Determines surveillance is UNSAT.

Cue: The CRS will initiate the NOTF and Notify Reactor Engineering.

JPM is Complete.

Terminate JPM when operator notifies evaluator results of surveillance.

TQ-AA-106-0303 Rev. 4

NAME: -----·

DATE:

·EVAt·· . S/U.

COMMENTS (Requirecf for . ·· UNSAT

evaluation



TQ-AA-106-0303 Rev. 4


JPM#: 16-01 NRC RO-A3


A_ 1. Task description and number, JPM description and number are identified.

-~--4. Initial setup conditions are identified .

. .A- 5. Initiating and terminating Cues are properly identified .

., A- 6. Task standards identified and verified by SME review.

A- 7. Critical steps meet the criteria for critical steps and are identified with an asterisk(*).

~ 8. Verify the procedure referenced by thi1 JPM matches e most current revision of · that procedure: Procedure Rev. _l_y_ Date /c) ( r "'L.C/ ~ 4 9. Pilot test the JPM:

a. verify Cues both verbal and visual are free of conflict, and ft b. ensure performance time is accurate.

,,I (~ 0. If the JPM cannot be performed as written with proper responses, then revise the

-;[ JPM.

/I k 11. When JPM is revalidated, SME or Instructor sign and date JPM cover page.

SME/lnstructor: -------------

Date: '"'' (. 'Z-41 y

Date: _I O_-l~f-~!_7~-

Date: ------

PSEG CONFIDENTIAL- Possession Requires Specific Permission from Nuclear Training Page 10 of 11

TQ-AA-106-0303 Rev. 4

INITIAL CONDITIONS:

• Unit 2 was operating at 100% power when rod 2D4 dropped fully into the core.

• OHAs E-46, LOWER SECT DEV ABV 50% PWR, and E-38 UPPER SECT DEV ABV 50% PWR, are both illuminated.

• The crew has entered S2.0P-AB.ROD-0002, Dropped Rod, and is making preparations to perform a load reduction to< 75% Rated Thermal Power to comply with Tech Spec 3.1.3.1, Action c.3.d.

INITIATING CUE:

• The CRS has directed you to PERFORM a Manual QPTR Calculation IAW S2.0P-ST.NIS-0002, Power Distribution - Quadrant Power Tilt Ratio.

• The100% NI Current Values from the Reactor Engineering Manual (REM) are given below:

TOP BOTTOM

N41 185.0 186.4

N42 187.1 197.2

N43 183.1 179.0

N44 140.4 145.0

• The Lower and Upper NI Detector current readings are:

Upper Detectors Lower Detectors N41 N42 N43 N44

184 192 182 139

• NOTIFY the CRS with the results of the surveillance.

181 198 174 142


An lwrr key s2 .OP-ST .NIS-0002(Q)

ATTACHMENT 1 (Page 1 of2)

QPTR CALCULATION DATA USING :MANUAL CALCULATION

1.0 UPPER DETECTORS:

Detector Current ..,-100% NI = Detector (microam eres) Current (2) Ratio

N41T= I f3 L( !BS.O 0, q q.5

N42T= I c, 2- , e 1. , /. e;Z,6

N43T= I Bz. ,e:3.{ o. 'ill<-1

N44T= / 'J q {L.f O. ', o. qqo

Sum of Detector Ratios 4,00..;

# of Operable Detectors L.f

Average U er Detector Ratio = /. oo I

Inde endent Verification of calculation erforrned b :

2.0 LO\VER DETECTORS:

Detector Current ...,...100% NI = Detector Ratio (microam eres) Value (2)

N41B= /$1 /96.Lf 0. Cfl t

N42B= /qB / G 7. -z... l • 00<-(

N43B= ' ( '1 ,1q. 0 (). Cfl'Z-

N44B= l <--1 '2,... {'-ls. 0 o, q 79 Sum of Detector Ratios = ".S. qz.G

# of O erable Detectors Lt A vera0 e Lower Detector Ratio = o.ct~'Z..

Inde endent Verification of calculation erforrned b :

..,... Average Upper Detector Ratio

/. oo I

..,... Average Lower Detector Ratio

o.qsz

(1) RECORD Power Tilt to three significant digits to the right of the decimal.

= PO\ver Tilt (1)

\. o 2.S O.CC'13

cJ. o,ecr

= Power Tilt (1)

().9S9

I · ~ 2- 1

0. q q 0

0,'1Cf8

(2) OBTAIN from S2.RE-RA.ZZ-001 l(Q), Table 2, 100% N.I. Currents 0% Axial, Radial Tilt. Refer to the NOTE on Table 2 for specific applicability requirements.

Salem 2 At\ s~=e~Ooflr,1 Rev.14

s2.oP-ST.NIS-0002(Q)


QPTR CALCULATION DATA USING :MANUAL CALCULATION

3.0 CALCULATED DETECTOR CURRENT

Computer Point (3)

UPPER DETECTORS

N0041N

N0043N

N0045N

LO\VER DETECTORS

N0042N

N0044N

N0046N

Voltage Reading 100% NI Current (4)

(3) ENSURE the quality o each Computer Point is "Good".

(4) OBTAIN the "inst ed" current value from S2.RE-RA.ZZ-0011(Q), Table 2, [70085101] 100% N.I. Curre s 0% Axial, Radial Tilt. The "installed" current value used in the calculation is normally the ewest value (bottom row) in Table 2. However, the previous current value (second from ottom row) is to be used when Power Range Channel Current Adjustments are in pro gr s and the PR Channel with the questionable meter has NOT been updated with new curre values.

(5) LATE Detector Current using the CALCULATION above RECORD calculated Detector Current in the Detector Cunent (microamperes) column

(S ction 1.0 and Section 2.0 of this attachment), as applicable.

Salem 2 Rev. 14

A n JW~r s2 .OP-ST.NIS-0002(Q)


QPTR TEST DATA USING MANUAL CALCULATION

Date: Time: Reactor Power:

REASON FOR PERF0Rl'1ING OPTR: (Check as applicable)

Unit in Mode 1 operating at >50% thermal power.

Unit in Mode 1 operating at :::;50% thermal power and verification that QPTR is within limits prior to exceeding 50% thermal power.

~ OHA E-38 or E-46 annunciated or is inoperable and thermal power is >50%.

IA W T/S 3 .3. I. I Action 2c, One Power Range Channel is inoperable Al'\TD trip setpoints are >85% or thermal power is >75%.

Upper Detector Power Tilt (1) Lo,ver Detector

N41T o. qq'3 N41B

N42T /. OZ_5 N42B

N43T o. ctct'J N43B

N44T o.crBc.r N44B

Maximum Power Tilt (1)

Detector Acceptance Criteria

/. 0 Z ..£ /v 42. Upper

/.o-z-:S IV'-/ 2-:::; 1.02 and (2)

Lower

too O/o

Power Tilt (1)

~. qg9 /.02-'J o. c;c,o C?,ctct8

Test Results

SAT UNSAT

v---v

(1) Carry forward the Power Tilt value on Attachment 1 with three significant digits to the right of the decimal.

(2) IAW TIS 3.3.1.1, Actions 2c and d, when applicable, the 3 channel QPTR is verified consistent with Reactor Engineering core power distribution measurement to satisfy TSSR 4.2.4.2.

A" s c-dr

Salem 2 Page 12 of 15 Rev.14

STATION:

SYSTEM:

TASK:

TASK NUMBER:

JPM NUMBER:


SALEM

Emergency Plan - Administrative

Activate EROS IAW EP-SA-111-FS

N1240110501

16-01 NRC RO-A4

KIA NUMBER: G 2.4.43 ALTERNATE PATH: D _________ _,

IMPORTANCE FACTOR: 3.2 ----APPLICABILITY: RO SRO

EoD RO[TI STAD SROD

EVALUATION SETTING/METHOD: Simulator/ Perform O'( ~ ll .. C\-\1

REFERENCES: EP-SA-111-FS, Rev~ (checked 10-11-17)

TOOLS AND EQUIPMENT: "EROS XXX" LAN Computer



Developed By: R. Chan 2,J),} cl_ Date: 10-11-17 Instructor

Validated By:

Approved By:

Date: 1 o J z'-f / 17 ();JS~,rln~u}t~r VI(· ~ Date: v- 11 ,3 ,,

Traini g Department ~Jf(_ 7 /.· (. Approved By: Date: ''/I:!>} 1 J

0 erations Department



PERFORMED BY:





JPM NUMBER:

Rev# Date

00 10-11-17


16-01 NRC RO-A4 r-~-~ Description

I


Validation Required

Yes


SYSTEM:

TASK:

TASK NUMBER:

SIMULATOR IC:




Activate EROS IAW EP-SA-111-FS

N1240110501

N/A

MALFUNCTIONS / REMOTES: N/A

OVERRIDES: N/A


• PRIOR to conducting this JPM; CONTACT the NRC EROS Test monitor and NOTIFY EROS being used for Training. (Day time: 301-287-9386, Night time: 240-888-2326, Day time cell: 301-731-2581, [email protected])

• OPEN the EROS program using the SPDS computer terminal in the back computer room. Single click the EROS program using the mouse, this will now enable the computer in the simulator to connect EROS to NRC using EP-SA-111-F8.

• ENSURE the "EROS XXX" computer is available and working.



SYSTEM:

TASK:

TASK NUMBER:

INITIAL CONDITIONS:


Activate EROS IAW EP-SA-111-F8

N1240110501

NAME: ------------DATE: ------------

• Salem Unit 2 was manually tripped from 100% power due to an RCS leak.

• Safety Injection was manually initiated and all ECCS pumps are running

• The Shift Manager has declared an ALERT.

INITIATING CUE:

• You are the Work Control NCO and designated Secondary Communicator.

• ACTIVATE EROS IAW Step 1.2.b of EP-SA-111-FB, Secondary Communicator Log.

• Notify the Shift Manager when EROS is activated.






Task Standard for Successful Completion: 1. Activates EROS IAW EP-SA-111-FS.


System: Emergency Plan - Administrative

Task: Activate EROS IAW EP-SA-111-F8



NAME: __________ _

DATE: __________ _

\ . . ' ' . . '. . STEP· \ .... 0 •• ' ' . ';: ,; '; ••• ••• ••• ST~ND,,t\80 i:,. ' . ::: . ;•. . . . . : }Jc; 'CQMMENTS;;' . ; .. , :,SjEP/ :. '(Sha.dat(ar~a ~Ei~'?t~~:·~riffoal Stekt.: :',F;t\~~"()"~~;,fl :,t~,,.ic:tJm!if;!~·~l~~.~/ii\ . :;: E\IAI.}; ····· I,}t{R,~·<t\Jif~~~f£>f ;yN~AT •.• · ..

Simulator Operator:

• NOTIFY NRC EROS Test monitor of pending Training evolution.

• OPEN EROS program on SPDS computer.

CUE I Fill in the JPM Start Time when the student acknowledges the Initiating Cue.


1.2.b I Within 60 minute, ACTIVATE EROS from a LAN computer

'PROCEEDto a;compLlterwith its.·. . mo~itor labeled "EROS X?(X",()Q<X:i$. :

•·1 .. :i~7du~:~it~~>tta~irtJf·i8e1~

8 ·

. , 'program by,SELECTINGjh~; .; , ' . J. ,. • .. "·· .•.. • •• ···. .

EROS ...:Sa tern, desktop icon;

Operator proceeds to EROS XXX computer located inside Salem Simulator horseshoe area .

Operator selects the EROS_ Salem desktop icon.



JOB PERFORMANCE MEASURE System: Emergency Plan - Administrative

Task:

• ,. . +• . .··.· .. <s . >,<SJEJ:>: . . /· , . . ,, ;5:rei:t."' y (S haded,afoa1 denotes Critica I 'Step) \,

·· · ~9:?i:1:•· .r;t~t1f:,{i:·~~fif JJtlt~;f t\t~I;~~i~r:;::··~~}:1; rQn,·the·t'LAginJ=:,oPl313Q$·pi~play,,'.• Epopup:window,ENTER th~ •:))·,, " J:ASSWQ~D (P.asswotd. is'th~ same as.·.

:the l:Jsername), al1d .. SELECT.''.Logfri'::t8 :· .. , p~o'c~~d.,l:/ ,% • · .··• · 'ts:

Operator enters the PASSWORD and selects "Login" to proceed.

Operator selects the button labeled <CONNECT> for Salem 2 "EROS Link Control and Status Display Screen".

Operator selects <YES> button in the "Current Link Control State is Disconnect. Do You Want To Connect?" box.

Operator checks that the Status changes to "Transmitting Data"

Operator verifies that the "Message Sent" value is increasing from zero "0" to some positive integer > "O".

NAME:

DATE: -----------

-----------

.... ·COMMENTS . \(Reqi.ffred fol'..UN'SAT

"fr ,{:.,evaluation),


System: Emergency Plan - Administrative

Task: Activate EROS IAW EP-SA-111-F8



, ,. _ · STANDARD ···.·.···· ....•.... ·· ... ··: .•.. (Boldect'area .identifies rasi;" ··

· .. ·····:;;,'.,'"':,;<~--.~·<·· •$!:~f -1~.ft?}t;~:/;:,}···{···.·, Ji}~f~t%~tf 1!~f i;~iit'.Jjft :c:_t'()C#•Sequentiat criticarstepy;·.~: •.

1.2.b.7 INFORM the CRS of successful EROS activation status

OR

IF EROS activation is not successful, THEN CONTACT IT Support: Network Operations (Ext. #7008), EOF IT Supervisor (NETS# 5009), or the IT Help Desk (Ext. 5555) for assistance.

CUE: I JPM is Complete.


STOP TIME: ------

Terminate JPM when CRS/SM is notified EROS is activated.

Terminate JPM when operator notifies you that EROS is activated.

NAME: ---------· DATE: _________ _

. .... · ··· CoMMENrs· •.. ... (Required)or UNSAT

;~,:icevaii.faflori)'.




Task: Activate EROS IAW EP-SA-111-FS

. i'.STEP> \':i,, · \\ : ~TE~;':\ ,~'.(Shadedi~rea/d.enotes Critical '$tep)t·

':'ii ••••},{~f\~·{'.: ?1\j:~}c1f it~~f l:~t:~~7:]f'~if ~i.?t~./:: When all operators have completed this JPM, THEN:

Simulator Operator:

• NOTIFY NRG ERDS Test monitor of that Training evolution has ended.

• CLOSE the EROS program on the SPOS computer in back computer room.

N/A

NAME: ----------DATE: _________ _


JPM #: 16-01 NRG RO-A4




-~...---,,__- 1. Task description and number, JPM description and number are identified.

-,IC----'.--- 2. Knowledge and Abilities (KIA) references are included.

---- 3. Performance location specified. (in-plant, control room, or simulator)

-c--::i-- 5. Initiating and terminating Cues are properly identified.

(j 6. Task standards identified and verified by SME review.

(:} 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).

~. . . 8. Verify the procedure referenced by this JPM matches the most current revision of 0- that procedure: Procedure Rev. ~ Date 10/tLf./tJ

\ 9. Pilot test the JPM: ---0--- a. verify Cues both verbal and visual are free of conflict, and

b. ensure performance time is accurate.

~ 10. If the JPM cannot be performed as written with proper responses, then revise the JPM. d-11. When JPM is revalidated, SME or Instructor sign and date JPM cover page.

SM E/1 nstructor: Date: 10/2'-f /I/

SME/lnstructor: Date: tO ,~'1(0 SME/lnstructor: Date:


INITIAL CONDITIONS:

• Salem Unit 2 was manually tripped from 100% power due to an RCS leak.

• Safety Injection was manually initiated and all ECCS pumps are running

• The Shift Manager has declared an ALERT.

INITIATING CUE:

• You are the Work Control NCO and designated Secondary Communicator.

• ACTIVATE EROS IAW Step 1.2.b of EP-SA-111-FS, Secondary Communicator Log.

• Notify the Shift Manager when EROS is activated.


ATTACHMENT 8 SECONDARY COMMUNICATOR LOG

EP-SA-111-FB ATT8

Page 2 of 17

1.2 For an Alert or higher Emergency Classification Level:

a. IF an on-shift SRO is not available to fill the OSC Operations Supervisor position, CALLOUT an additional SRO and have him/her report to the OSC.

Name: Time: ------------ ---

NOTE

EROS Activation and Termination is normally performed by the CM2 in the Control Room but if needed, could be performed by any communicator in the TSC or EOF by following the same directions below and substituting TSC or EOF for Control Room

SGS

b. Within 60 minutes, ACTIVATE EROS from a LAN computer:

1. PROCEED to a computer with its monitor labeled "EROS XXX" (XXX is the computer's asset tag number) in the Salem Control Room and START the program by SELECTING the ERDS_Salem desktop icon.

2. On the "Login For EROS Display" popup window ENTER the PASSWORD (Password is the same as the Username) and SELECT "Login" to proceed.

3. SELECT the Action button labeled <CONNECT> on the appropriate Salem 1 or Salem 2 "EROS Link Control and Status Display Screen".

4. SELECT the <YES> button in the "Current Link Control State is Disconnect. Do You Want To Connect?" box.

5. OBSERVE that Status changes to "Transmitting Data."

6. VERIFY successful communications status by observing that the "Messages Sent" value is increasing from zero "O" to some positive integer> "O".

7. INFORM the CRS of successful EROS activation status

OR

IF EROS activation is not successful, THEN CONTACT IT Support: Network Operations (Ext. #7008), EOF IT Supervisor (NETS # 5009), or the IT Help Desk (Ext. 5555) for assistance.

Initials

CM2

CM2

CM2

CM2

CM2

CM2

CM2

CM2

CM2

CM2

Rev. 04

ATTACHMENT 8 SECONDARY COMMUNICATOR LOG

EP-SA-111-FS ATT8

Page 2 of 17

1.2 For an Alert or higher Emergency Classification Level:

a. lE an on-shift SRO is not available to fill the OSC Operations Supervisor position, CALLOUT an additional SRO and have him/her report to the OSC.

Name: Time: ------------ ---

NOTE

EROS Activation and Termination is normally performed by the CM2 in the Control Room but if needed, could be performed by any communicator in the TSC or EOF by following the same directions below and substituting TSC or EOF for Control Room

b. Within 60 minutes, ACTIVATE EROS from a LAN computer:

1. PROCEED to a computer with its monitor labeled "ERDS XXX" (XXX is the computer's asset tag number) in the Salem Control Room and START the program by SELECTING the ERDS_Salem desktop icon.

2. On the "Login For EROS Display" popup window ENTER the PASSWORD (Password is the same as the Username) and SELECT "Login" to proceed.

3. SELECT the Action button labeled <CONNECT> on the appropriate Salem 1 or Salem 2 "EROS Link Control and Status Display Screen".

4. SELECT the <YES> button in the "Current Link Control State is Disconnect. Do You Want To Connect?" box.

5. OBSERVE that Status changes to "Transmitting Data."

6. VERIFY successful communications status by observing that the "Messages Sent" value is increasing from zero "O" to some positive integer> "O".

7. INFORM the CRS of successful EROS activation status

OR

IF EROS activation is not successful, THEN CONTACT IT Support: Network Operations (Ext. #7008), EOF IT Supervisor (NETS# 5009), or the IT Help Desk (Ext. 5555) for assistance.

SGS

Initials

CM2

CM2

CM2

CM2

CM2

CM2

CM2

CM2

CM2

CM2

Rev.04


~---------·----STATION: SALEM


TASK: Identify and Isolate Non-Essential Chilled Water Loads IAW S2.0P-SO.CH-0001, Attachment 2

TASK NUMBER: 0980020202

JPM NUMBER: 16-01 NRC SRO-A 1

KIA NUMBER: G 2.1.25 ALTERNATE PATH: D -----------; IMPORTANCE FACTOR:

APPLICABILITY:

EOD ROD STAD SRO[Z]


REFERENCES: S2.0P-SO.CH-0001 Rev. 34 (checked 10-3-17) Salem 2 Tech Specs



TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS:

Developed By: R.ChanµJ) ~ Validated By:

Approved By:

lnstr~ctor

/JV~ ~Jttt,w~P' SME or Instructor !(i

Traini De artm':1.1 ~ Approved By:

ns Representative

~eU..;>



PERFORMED BY:



EVALUATOR'S SIGNATURE:

RO

N/A

Date: 10-3-17

Date: io-,·/7

Date: 11/13/ ;7

DATE:

4.2 SRO



REVISION HISTORY

JPM NUMBER: 16-01 NRCSRO-A1

Rev# Date Description Validation Required

00 10-3-17 Added revision history and simulator setup pages. Editorial No comments from IP 71111.11 FASA.




SYSTEM: Conduct of Ooerations - Administrative

TASK: Identify and Isolate Non-Essential Chilled Water Loads IAW S2.0P-SO.CH-0001


SIMULATOR IC: N/A


OVERRIDES: N/A





TASK: Identify and Isolate Non-Essential Chilled Water Loads IAW S2.0PSO.CH-0001


INITIAL CONDITIONS:

• It is July 151h time 1800 and you have just assumed the watch as the Unit 2 CRS. It was

turned over that both 21 and 22 Chillers tripped at 1600 and you are currently in TIS 3. 7.10 action 'b', entered at 1600.

• To comply with the T/S action, the crew is implementing S2.0P-SO.CH-0001, Chilled Water System Operation, Section 4.6, Isolation of Non-Essential Heat Loads.

• During preparations to align #2 ECAC cooling to Service Water IAW S2.0P-SO.CA-0001, Control Air System Operation, it was reported that the spool pieces required to align to service water cannot be located.

• Unit 2 CREACS has been removed from service IAW step 4.6.2 of S2.0P-SO.CH-0001.

• CW Inlet Water Temperature Readings from SC.OP-DL.ZZ-0008(0), Circulating/ Service Water Log are:

2TL3756 = 83.4 °F 2TL3757 = 83.6°F

INITIATING CUE:

• You are the Unit 2 CRS.

• The Shift Manager directs you to NOT isolate the #2 ECAC and to re-perform the NonEssential heat load determination IAW Attachment 2.

DETERMINE the total Non-Essential heat load and SELECT the required components for isolation IAW S2.0P.SO-CH-0001, Chilled Water System Operation, Attachment 2 to comply with Tech Specs.

Successful Completion Criteria: 1. All critical steps completed. 2. All sequential steps completed in order. 3. All time-critical steps completed within allotted time. 4. JPM completed within validated time. Completion time may exceed the validated time if

satisfactory progress is being made.

Task Standard for Successful Completion: 1. Determines the Total Heat Load Isolation value required is 902.8 kBTU / HR. 2. Selects the required components on Table B for isolation and ensures that the

total value is greater than 902.8 kBTU / HR.



System: Conduct of Operations - Administrative Task: Identify and Isolate Non-Essential Heat Loads IAW S2.0P-SO.CH-0001

CUE:

:!, ii, i;,,SJSP,,;~),>~~5:;'~o, 1 ·•.· As• , c . . s'cSTJ>;t;i,g/lRD ~!' S ·· fe~ .de·notijs' C.ritical~StepJ;.;;t;, ,~ . :~ (Boldedar:ea:·iaentifies;Task '(;:p. ritic'afi~t~p.).:' .... '§~r,~::···•.:x;·~~.:r.· t:? . .:}tj . S,taJ:l&ard)~l~f · .. · '

"<:.(# Sequential CriticaHStep) .. :::· 11:0 t. . . . Provide the following:

• blankcopyofTS3.7.10, Chilled Water System -Auxiliary Building Subsystem, and

• S2.0P-SO.CH-0001 (Q), Chilled Water System Operation.

PROVIDE the operator the initiating cue AND ENTER START TIME AFTER operator repeats back the Initiating Cue.


Name: Date:

{t~~t! 0}0

:·:· c.g~,IYIE~lif .. ·. , ~YA[j: ,,;, ·(Requ.!re.dfor:JJNSAT ...

. ";:SIU .'tIL, :e"aluation) . : \Jt'f <)''· \\'h\~', '·:\\.·




Attach 2 1.A

1.B

.\f fI~~f, ;;i" b'" ,t :~!~f> l·: ; ... \t. , .. jii'.. !I'.·(~baded'are,a·•.denofes:;cnt1cal~Step).\,·

'l:H:ijf ::~;}~{#)i~~~f £}f l1:~~~t11~l}~¥iir''::f;f,:i.· RECORD the following data for use in Table A:

Inlet Water Temperature from SC.OPDL.ZZ-0008(0), Circulating / Service Water Log:

2TL3756= °F 2TL3757= °F

From the above indicated 2TL3756/2TL3757 temperatures,

RECORD the highest temperature AND ADD 1.5°F to account for instrument uncertainty. Utilize this temperature when referring to Table A

____ 0-'---F + 1.5°F = °F

(highest temp)

Number of inoperable Chiller Units:_

,c' ::,~1J'.S]~NQ~~[).;., (Boldedarea identifies.Task', , . .. . .,/'sta~!fi~it .· .·.. .... ..z,,;:,.

Enters temperatures from cue sheet onto Attachment 2 form.

[83.6 F + 1.5 F = 85.1 F]

Lists 2 Chillers Inoperable.

Date: Name:

. ·.· dcf~:MENTS.;: ·:. '·(Reql:ii're'd for\UNSAT ·J'<~),ft ~valuation}'t1 '




,~Stl~JJiei1l¥1~~:if~{J£~e>·/. .,,,.; ··· ·-"" <:· 't\t"-''(* Cntlcal•Step) ·· "·. '"" '""';'°.,

<,'~(' · ·~:>;.0il;:i ~t~ .. '.. ,1 ... : . '.;}:, '< · 0'.i,- ( '!·'.:(. ~i :}. . .· i ."\{: , '.}§~;%~'.,:, :<; .. ,::~'i.:PY(#) Sequential .C1;1t1cal >Step)1. 1,+l' ~'~''""'"',· ·"_.· ... ' .' '''· . ..'. ....... :· .":"' - . ,,,_ --'" ... ' .. ".::.".' __ ' ., __ . ''""'"''

* REfORD)he.;TqJe,L:. f1EATLQ~9 · ... . 1"1S'G>l£ATIGN from'ffiable'·A· .·h'·";;c;);tr\:< tit ,,;f~[.'t;, .\/~BTtlJ ~R'.:1(~}; '"<;{tt'~illi

IDENTIFY the components to be isolated in Table Bas follows:

· 1,,;RESORD/the3yalde frdrr,ltffe HEAT'. . , f, LQ1D CC)lqniQ)nto t.he ls9lation colllmh ; ·. forthEH;omponents .. selectecfafo( ··... . : . t Jsc,lafif n:2 :f · · · · · ·

···RECOR.b.i·NiA'}Jot.the components.·• s~·1ected2tc{remain available:·

From Table A, Determines 902.8 kBTU / HR. {Based on Inlet water temp of 85.1 F, 2 chillers Inoperable and in Maintenance Mode with Unit 2 EACS Out of Service)

Selects the value of heat load by annotating the values in Table B to ensure value greater than value recorded in step 1.C.

21 PACU = 145.7 22 PACU = 145.7 23 PACU = 145.7 Secondary Lab= 192.1 Primary Lab = 165.9 Counting Room = 73.0 PASS= 38.5 Selects N/A for Emergency Control Air Compressor ECAC

Name: Date:

~':~~:[\ .,·.~· :;, ::: ;.:'··· . : ''>

% .. \:: COMMENTS: . (R~c{u

0

iredforlJNSA1F,'; & :~tEivalu,~!ipn)\} ·




1.1

CUE:

... , .. ·· '~(:!;tl~i;tlr:J;tpi}f. f './(# S~J:iu'e'iitt~IVCr(ticaTS.tep)

· SADD 0the values·:;reco~ded ihthe •. ? ;;flsolatioo doiumri:ANQ'.,RE~ORDJh~l:·:,

iff .. !~;t?1~$~1at::~t· .. "IW~ ... tq:I~;~I:!~·~kt·:.··> ':ENSURE thattheil;otal Isolation value\•. reco'rde<r in .. tabhfa:3 isi.~ fhe rotarHeat'

•· !fioad' 1sofatio'nTredorded1in:Sfep ;:'.tfils•attachmerit·· . . .. : •.··/<c ,(':,.-,·. ' ;·,,!,, ,.·;,,,

ISOLATE the selected components IAW Section 4.6 of this procedure.

JPM is Complete

THEN RECORD the STOP TIME.

STOP TIME: _______ _

:': .. \.:~]i~ND~BQ:f . ;!~£,. . (Bolde(P:trea identifJes Task .. : \iF ·

.· .. 3\~1,I;,~f ~:t~.;~t:f·· ..... 1. :·. •· ,~1;:\:,• •

Determines that the Total Heat Load Isolation value per Table B is 906.6 kBTU / HR.

Determines the Total Heat load Isolation value recorded in Table B (906.6 kBTU / HR) is greater than or equal to the Total Heat Load Isolation in Step C (902.8 kBTU / HR).

CUE: The NCO will isolate the selected components IAW Section 4.6.

Terminate JPM when operator determinestheloadsthatneed to be isolated.

Name: Date:

.......... ;coMMENTs ·i<<'iY>'·· '· ·;..;,:'fr '•">;:•:<:::··: · .'· '""Y· li'.L:;::t(Requ,red 1or:UNSAT . . . .,;;j;{ijvalua'tion) :, ,• .




JPM #:16-01 NRCSRO-A1


~ 1. Task description and number, JPM description and number are identified. -+ 2. Knowledge and Abilities (KIA) references are included.

~ 3. Performance location specified. (in-plant, control room, or simulator) --e-- 4. Initial setup conditions are identified.

-f,f-- 5. Initiating and terminating Cues are properly identified.

~ 6. Task standards identified and verified by SME review.

tvt 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).

_f±___ 8. Verify the procedure referenced b}".,this JPM matches the most current revision of / that procedure: Procedure Rev. ,Y-1 Date iC - ~ -11

/iiA- 9. Pilot test the JPM: , a. verify Cues both verbal and visual are free of conflict, and b. ensure performance time is accurate.

_t_l_{ A_., __ 10. If the JPM cannot be performed as written with proper responses, then revise the JPM.

_rJ---'-'-{C,,___ 11. When JPM is revalidated, SME or Instructor sign and date JPM cover page.

rJ ./") ~- .

SME/lnstructor: {r~ fiv\liV·"-1,J I \

Date: /0 /1 /11 -+-, _,,_.._...l ~--





INITIAL CONDITIONS:

• It is July 151h time 1800 and you have just assumed the watch as the Unit 2 CRS. It was

turned over that both 21 and 22 Chillers tripped at 1600 and you are currently in T/S 3.7.10 action 'b', entered at 1600.

• To comply with the T/S action, the crew is implementing S2.0P-SO.CH-0001, Chilled Water System Operation, Section 4.6, Isolation of Non-Essential Heat Loads.

• During preparations to align #2 ECAC cooling to Service Water IAW S2.0P-SO.CA-0001, Control Air System Operation, it was reported that the spool pieces required to align to service water cannot be located.

• Unit 2 CREACS has been removed from service IAW step 4.6.2 of S2.0P-SO.CH-0001.

• CW Inlet Water Temperature Readings from SC.OP-DL.ZZ-0008(0), Circulating/ Service Water Log are:

2TL3756 = 83.4°F 2TL3757 = 83.6°F

INITIATING CUE:

• You are the Unit 2 CRS.

• The Shift Manager directs you to NOT isolate the #2 ECAC and to re-perform the NonEssential heat load determination IAW Attachment 2.

1. DETERMINE the total Non-Essential heat load value and SELECT the required components for isolation IAW S2.0P.SO-CH-0001, Chilled Water System Operation, Attachment 2, to comply with Tech Specs.



STATION: SALEM

SYSTEM: Conduct of Operations

TASK: Determine Heat Stress Requirements for Containment Entry IAW SA-AA-111

TASK NUMBER: N1220400302

JPM NUMBER: 16-01 NRC SRO-A2

ALTERNATE PATH: KIA NUMBER: G 2.1.26 ------------, IMPORTANCE FACTOR: 3.6


EoD ROD STAD SRO[g]

EVALUATION SETIING/METHOD: Classroom

REFERENCES: SA-AA-111 Rev. 12 ( checked 10-3-17)




Developed By: R.ChanWM ~ Date: 10-3-17

Validated By: ;l,nstruc or .

!' Mwtt,;trf' Date: ),: -'/- I 7

~~-~ Tra111111D1 Lment

Date: ·/·{, Date:

Approved By:

Approved By: Operations Representative P / 13 Pl



PERFORMED BY:





JPM NUMBER:

Rev# Date

00 10-3-17


REVISION HISTORY

16-01 NRG SRO-A2

Description


Validation Required

Yes







SIMULATOR IC: N/A


OVERRIDES: N/A







INITIAL CONDITIONS: • Unit 2 is at 100% power.

• 2PS3, PZR Spray Valve, is operating erratically and a decision has been made to enter containment to isolate the 2PS3 by closing the manual isolation valve (2PS28).

• The 2PS28 is located inside the PZR housing (dog house), upper elevation, and is known to be very hard to operate. Operators will also have to climb ladders to access the 2PS28 in the dog house.

• The Shift Manager needs to determine amount of resources needed to close this valve given the Heat Stress conditions.

• Rad Pro has provided a WBGT temperature of 89 F for the work area.

• Rad Pro has determined that operators will need to wear double PCs.

• Cooling Garments will not be used.

INITIATING CUE:

• You are the Unit 2 Control Room Supervisor.

• DETERMINE the following using SA-M-111, Heat Stress Control:

1. What is the Stay Time?

2. Assume the task will need more time and Check Times will be used. What is the Maximum Extended Stay Time?

3. Assume the task required the use of the maximum extended stay time. What is the Recovery Time?

• Provide your answers on the Initiating Cue sheet.


1. All critical steps completed. 2. All sequential steps completed in order. 3. All time-critical steps completed within allotted time. 4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory

progress is being made.

Task Standard for Successful Completion: 1. Determines; Stay Time= 20 mins, Maximum Extended Stay Time = 30 mins, and Recovery

Time = 90 mins.



System: Conduct of Operations Task: Determine Heat Stress Requirements for Containment Entry IAW SA-AA-111

CUE:

Provide blank copy of SA-AA-111, Heat Stress Control procedure.

PROVIDE the operator the initiating cue AND ENTER ST ART TIME AFTER operator repeats back the Initiating Cue.


J; .:i~·: 'vf.ST~~l?~RD:1{ §il1;· .{;(Boldecf "a(f.la:icl~iitifi~s:Ja$I<+;}.

,iit1·, . ·::· ;i\s~~n~?/~)il7 .. J "'

Name: Date:

fk.)§i~;~~~Q!~At~'.t . "'\evaluation}J; · · · , ,', i/~<i~::, ,, S C




4.1.1

.•..... ;&+·. :::,tT.B;.§JE,Pf t;F!t~t ::~t: . 11,t ($h~de.cl,ar~a:tle'ijpte~.Cfltl~al'St~'p).·h

;; {:2Tt;I:'\f:;J(t CriJic~~L0st~P )i:j:·t::.;i:f,;;:ltii: •

.• ::,:;{#•1Seque11tia1.crmca1Jistep)..J OBTAIN the Dry Bulb or Wet Bulb Globe Temperatures in the location where employees will be physically performing work activities. Heat Stress surveys may be conducted in conjunction with radiation surveys. Remote temperature monitors may be used to obtain dry bulb temperatures. RECORD the temperatures in lines 1 and 2 of Attachment 4.

1. For locations such as the drywell, areas with multiple elevations, areas with changing ventilation or areas where work is being performed in various physical locations, temperatures should be obtained, at a minimum, at the location where most work activities will be performed (>50% of work time).

2. In areas where varied environmental conditions exist or if the worker may be exposed to varied environmental conditions, due to the type of activity performed, the worst case area WBGT must be used for determining Stay Times. This method represents the only practical solution to this set of circumstances.

CRS records Wet Bulb Globe Temperature given from Initiating Cue as 89 F on Attachment 4.

Name: Date:



System: Conduct of Operations Name: Task: Determine Heat Stress Requirements for Containment Entry IAW SA-AA-111 Date:

4.2

4.2.1

eJ~!t~~lf ~i~l~ ~~(~tt2r1;~~i~!i~~~ ~%t~! ~,~~\~~~~~V~t~~~~(,, ;f CL.ASSll:Ytlie wor.k'.environment:as· High<· :;,terQp'efatLire.{HT);Vert}iigfj,,T ~mpefatUre,' : ;I::{VliT}~orExfremely 1:Jigfi\Temperature,.:f·<· i10(EHT)tRECORb1:ir1Jin~3·of;.Attactih,enl ;tt~!{;; ·;;J0~t ; > .. ,}('¥ >1'1' • . ~0?:,F;~:f·J\\.::1 '.,{V: . . ..

··• 1 ", .• J';':l:Jig h:iEE!n:i.peratu~e ::Environn:i.,ei x:L"worl<'"cdndftltinstharres\)it:h)fc'a

:~' ,; .. ~ .,..;~·(c~r1:"'''c, ·:c:", ::- , , /fLs~}?:i._is:~)

dft\}';f.' .,,/~-;ti;3;:,,,}·r:;;(\:_zt~l""'::J>;·{:?{/>\:J:: ?'.;t~rlt'<:{ ;, , . ,, __ ·•ery:11::Vcih T~tfir>eratures:,Y:JorKareas:,"'+£}' i'ar.' B'u1o'terrtpe'raturbs:HetW~en;:145ciF:.\ ......

• · "''' . • )/,, .. ... ·.,;,, ... ,, "·, · .•.. , ·,~ ,. '·.• ,. '>" ·.'"

,c,ariq",:16b°Fo("W:S~l.1:>etweelf110°F:"ar1d·'

;t;i~{1;:;;';~;):•il::s~::·?J~i{'.4;",~:c~:,:;:.:, .. ,\ti/' .;;:J,. E,xtre"mely l;ligh;f emp~catpre: Dry,bulb ;*: .• t~Jn per;atut~s1greaf tlianT1"60qF.for WBGT c::igrea1er than:1 ns0 F: refeFtdAttachroerlt !,) ;,},?h "";.;~,.. ',:,:..-._)\,,,:' 'zt'"<;, :,-.. -'''./:, :ct ; :.J{_..,:' ;.,,..(:';\>' .. ,'

Evaluation of Work Rate as Low, Moderate or Hiqh DETERMINE Work Rate through the use of Attachment 2, Work Rate Metabolism Guideline. RECORD results in line 4 of Attachment 4. 1. When determining the work rate, the clothing ensemble for the exposed employees should not be considered. Determination should be limited to the

hvsical effort of activities.

environment as High Temperature based on work area temperature

of 89 F.




, . ' STEP ··d ::· / ., -~1

;JC · STANDARD'.''.; .. . l'iadedarea'denotes Criti~al:Steph,· ······•·······(Bc>fo~dare:fa10idepfifiij$11,'ii~k .. f

ett~en1~iY~;f 1lt!Vi-:!~f ;::~~:tt? ;~~':::'.\:&/:l:,.'::\i,;,$t~O:~~r~,;::it,:~\t/~'lt/!,t~ 2. Low Work Rate activities involving the use of negative pressure, air-purifying respirators should, at minimum, be classified as Moderate Work Rate activities. Moderate Work Rate activities should be classified as High Work Rate if they involve the use of negative pressure, air-purifyinq respirators. 3. When determining the work rate using Attachment 2, Work Rate Metabolism Guideline, the evaluator should use the most frequent workload activity (>50% of work time) to characterize the overall activity as being Low, Moderate or High exertion. Higher exertion levels result in higher metabolic body heat generation.

A. Low Work Rate is defined as sedentary activities involving sitting, standing still, and low physical effort. These include inspections and operation of instruments and powered equipment.

B. Moderate Work Rate is defined as activities that are easily accomplished in a thermally comfortable environment. These types of tasks include pump and valve rebuilds and the sorting of materials. Additionally, heavy exertion activities that are broken up by periods of light activity or rest and do not involve the use of negative pressure, air-purifying respirators should be classified as Moderate Work Rate.

Name: Date:




4.4

;;C}Higti ,Work Rate'.iS defined as' < ::01+'•~/.· • :fdem.~n'din'g pbx$icalwork)ottg.teatetJhar, < ,,\.

.. ; >5op;(j:Bt work~ime~:Abtivitiesicharacterized , . f}(~i'gh:.~orf'g~t~iipcru~~. lilti?g ~rldt;:.

m·overuent of· heavy objects and manual: 2,,

decdnfarrifnaiion of. internal; planf'locations:>: .. d:Addffroq$ily{~lf MoaElrclte,Wor'ifRate. ·······'.•·.·: ••.. ,.· ·r actiyitieS::in\iolvjrnftbe:~;S.e!qf negatfve.j'.·\1!,+f •:;Rr$ss(:)rE:?; ·§lit~p~r'if>~ing respi.rator,s,;s.hq!J.1~ .· ·5 .

be dlassiffedai:;·HiQh·w or'k Rafe·activfties: . ::

Determination of Stay Times

:1 >\,• 0( }'i\f.S:J:~NPA~D .. ,. .. ······.,."(Bolded area'.:idenUfieS•:.l'ask•

.. · '!it*ff~n;~~r,l,;,:,~/1{{·.,tr CRS determines that this task is a HIGH work rate .

This can be based on the initial condition provided that the 2PS28 is historically very hard to operate and physically demanding on them giving the high temperatures inside the PZR dog house.

Determines the clothing ensemble to be Double Cloth Coveralls (also known as double PCs) and the adjustment factor to add 9 F to the WBGT.

Name: Date:




4.6

~r,~17;1tlii!ttt:1~ t1~~i,~??i~1~;~,Jt· tpETERMINEtheSfayTime·by'usiQgthe<:· CRS uses the following .\£/V\f eG'l'./D[y\Bqlb.v'alues :obtairiecl in 4;1, the information and Attachment 3 to ;;':workrate~determlhed M'\l.2,'~nd ttfe ;;, . > determine Stay Time: 1£\cj9,t11irjg·e·9seJnb1,ei1aeh~fied;in'4 .. 3),YthEi :

·: ,l<o,ti~:J~t,::l~f;f,~~!!!1'~.r~~:,1:I;~.·: ....... · ,., '1:i•:L:OCATE'the;tablei11 Attachment ;3, Heat I 4.1 - WBGT = 89 F

·.u'.~Jr~~!;·.1:~tjt.0··.~'.~)~,.;·::t~::.·~ ·······.·;,;~.:(~: ':'·2 .. :. l.OCATE.the .clothjng enserrjble' mpst

applicable. to the Work activif{as · '''

J1e.!~ri&f,?{C ~{~<;<:I:;~\<;'l?/ · ... • . .. 3"'.·.the;teft"side of the)abte;has WBG't/Dry"

1;~~~;}ti~f:;~o{~~t~}~~;J~J·· . ·i .• 1(J?E'tER,MU:JE)he §fay T\rne;t>Y c1d<:1Jng · ;:~theW§Gt/D~y,Bvlb ,plu~ the Qlothing':, · :JiAdjcistrnerff fact~r·and delehnl.ntri{rtbe } : work aernand.~Rebord ttiis 'value'ih'.' it;,2,c :~mne'6:.of Att~chrnerit~: · · · · · ·· ····· ).;,~··, "· ' '. ;,,. . " ' , " ' ... •, ' ,,,,

Extending the Stay Time through the use of Check Times

4.2 - Work Rate = High 4.3 - Clothing = Double PCs

CRS adds adjustment factor to WBGT (89 F + 9 F = 98 F)

Using Attachment 3; CRS uses the WBGT value of 98 F and a High work demand to determine a Stay

Time= 20 min.

Name: Date:

· ·<:c,coiviMlNTs .. • i!?'(Requi(~((forUNSAT'·

f i!t"i2;1/'.~y~rq~tio~r;•




4.6.1

4.8

~f!1,~tr!i~~:i:,s· The following limitations apply to the use of Check Times.

1. USE Check Times only for work activities involving Stay Times contained in Attachment 3, Heat Stress Stay Time Limits.

2. Check Times cannot be used to extend beyond 1.5 times the established Stay Time for a given work activity. (1.5 X ST)

3. The Check Time process is designed to supplement self-determination by employees. Essentially, the process allows Stay Times to be extended if a set method of determining the physical condition of employees has been established.

4 .......

· RECORD the-Maxfm~m Extended Stay. :Time in. line86rAttaohment4,-Job------

,;Evaluation Worksheet. \.r,::;T .. , -{;'!X·.;(,.:), -,, . . ,~ .

.{{ The~rp~xirnumex,iended,St~y.Time_ wh~n using the Check Time Process is•

·.;1 :5 times the Stay Time determined in 04.4). (1i5 X SI) .. . .. · " ....... .

Determination and Application of Recovery Times

t~~iu;=J£1!!~i,r;1i~;;' CRS reads step and continues on.

CRS calculates Maximum Extended Stay Time (1.5 x ST) of:

1.5 X 20 mins = 30 minS

Name: Date:

. (Req~itaig~Gi~ATC . ... ,evalu'atioh);

' ,,, . . ' '""" '., ~ '" .,




~{\"·S\jf14i:;}'.~::',:,<. "}.~:r~/~:r/:;;t;\S.);C,~~,'(» ',.:·f~it:1{tit?~t:;\<:.;,::'· ;r·,. ,' ;::,:(sha~iid aria d~hotes 'Critical Step )f xt:~t:/;'·'~'.~,,'

11 ,~1f1!(*:'crJ!!c~J~,§i~•eE5:~i2,;:,tt;;;;,\"'; i,:i qf\ (# Sequential; Cti'fical Step) if

DETERMINE the Recovery Time. RECORD the Recovery Time in line 12 of Attachment 4, Job Evaluation Worksheet.

· ',The RecoveryJime calculation is used to ltcieterm lne~the'arnourit. of: tim.~.riecessary ) ' .:f for:~fllployees to\rec:ove~Jrom'a high ..... .. temperature job exposlJre::: / ' .

. , )/~.t~~8Af{ffiiR~~6iiY45;'(RJ\ ., .}t;:~~~t , ·\~(:c... . _ .. ,", ~S~{t \ .. :·. ,. ."~<:.' . . ,._ ., ....

•• 11tJ1, (fXctuaJJWorl<'Time l$tayJJme )X: 60'. ,. , .

. . . ,:i~J.r~l~~'</}s?,i,,:0:7?t;\' ··~{:·,r' :,:··::,;;~::.:.:,:;,,:·"}:,·•· ·. ; 1 ~i'Wt1en'tlsingliqu1c:1;coo11ngg'arrnents,,:y\ . r;tinBet8igh met.at>dfic·rnteconditions or· .. ,~

. . ;Jl;r'w~~!Jr:llSing :!q~ '.ve~t~;c usefqu,r)im~~: t~~~::: . · .,;l,\ttachr:n§lnt 3·s.t~y·ff 1me. fors<:;omput1.ng'

)t·.~~,~~~~:::irn~·77':z.::s:;}0\:/.1.·f 4;':"'1::'f~:~*·.,. · .. 3', !Mh.e .. 'AUaQhment:3 Stay,Tim:e'is less .....

. Jhart)t5;minotes and,.cooling garmentsj,a're\, :'.'.':W9rp. t6~n us.~,~~ St9Y1;ime of?O·minlJtes . "forcalculating Re'coveryTime. '.'' ·. , }1~ .· ,\iz ., ·' C , , <.::/'" · \, / .. ,,. ,

Stay Time (ST)= 20 mins

Max Extended ST= 30 mins (in this case this is the actual ST)

Recovery Time = 30/20 x 60

Recovery Time= 90 mins

Name: Date:

foss'.{'.~;}/;;f• , C()MM~NT$?" <

.• .. EVAL.I :;1\.(RequireclJ6r;.l)t\JSAT :\,·~s/01·;~: '.;;;j~'.~' .. ;

1.:0·;'eva1uation)h'···



System: Conduct of Operations Name: Task: Determine Heat Stress Requirements for Containment Entry IAW SA-AA-111 Date:

CUE:

.. \,:~}i;'·\~!~~si}t: ... ;·· .. · .. ·. . . ;~,:~aiden:otes ,Gr•ticat.Step) .

(*. •1c· .· .. ·.· · .. t. ····"'."""·····,· '.:.··s·'. ··t· ····· .. \

0. )'>.· ... ·.J· ....... ·.;.., ..•. t.·.'.

1.'i': · , \ · n 1ca, ep \,,,., .. , .. ;, ., eitu~htia1:~ritica'f §!lP> .. ··

WHEN operator informs you the task is complete, OR the JPM has been terminated for other reasons, THEN RECORD the STOP TIME.

REPEAT BACK any message from the operator on the status of the JPM and then state "This JPM is complete"

STOP TIME: _______ _

.. J<~JJ:i&JW~i?r~~~'1 ·~&~ ~it!~t~~!~AT . " '."~,(




JPM#: 16-01 NRC SRO-A2


--/!:;;-- 1. Task description and.number, J PM description and number are identified.

/1,1 2. Knowledge and Ab1l1t1es (KIA) references are included.

~~ 3. Performance location specrfied. (in-plant, control room, or simulator)

//ri,~ 4. Initial setup conditions are identified. ---t;-;-;-

·,11 \[, 5. Initiating and terminating Cues are properly identified.

)tM ~ 6. Task standards identified and verified by SME review.

~ 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (').

+ 8. Verify the procedure referenced by this JPM matc~es the most current revision of that procedure: Procedure Rev. J,J Date lil/JJi J - -'-,+-+, ----

/I~}" 9. Pilot test the JPM: i a. verify Cues both verbal and visual are free of conflict, and


~ 10. If the JPM cannot be performed as written with proper responses, then revise the JPM.

' MA 11. When JPM is revalidated, SME or Instructor sign and date JPM cover page. J

1JJ ~ ., J .

SM E/1 nstructor:__,_Jt---+-V\---"'-c!vc.._,--'!1_,_i _,_•~-+-·_i'l_,_(1,"-o_t_~_I,,_·~--,; I

Date: _1_.:1+-/_4.,_,} l_-1 __ _

SME/lnstructor: ____________ _ Date: _____ _




INITIAL CONDITIONS:

• Unit 2 is at 100% power.

• 2PS3, PZR Spray Valve, is operating erratically and a decision has been made to enter containment to isolate the 2PS3 by closing the manual isolation valve (2PS28).

• The 2PS28 is located inside the PZR housing (dog house), upper elevation, and is known to be Y!!D/. hard to operate. Operators will also have to climb ladders to access the 2PS28 in the dog house.

• The Shift Manager needs to determine amount of resources needed to close this valve given the Heat Stress conditions.

• Rad Pro has provided a WBGT temperature of 89 F for the work area.

• Rad Pro has determined that operators will need to wear double PCs.

• Cooling Garments will not be used.

INITIATING CUE:

• You are the Unit 2 Control Room Supervisor.

• DETERMINE the following using SA-AA-111, Heat Stress Control:

1. What is the Stay Time?

2. Assume the task will need more time and Check Times will be used. What is the Maximum Extended Stay Time?

3. Assume the task required the use of the maximum extended stay time. What is the Recovery Time?

[Provide your answers on this sheet]


STATION:

SYSTEM:

TASK:

TASK NUMBER:

JPM NUMBER:

ALTERNATE PATH:


SALEM


Review a Tagging Request and Evaluate Tech Specs

N1220050302

16-01 NRC SRO-A3

KIA NUMBER: IMPORTANCE FACTOR:

G 2.2.13 4.3


EoD ROD STAD SROCK]


OP-AA-109-115, Rev.12 (checked 10-24-17) DWG 205228 Sheet 2, Rev 85

REFERENCES: S1 .OP-SO.CVC-0002, Rev 41

TOOLS AND EQUIPMENT: Marked up Pl&D Drawing 205228 Sheet 2



2-,l},J_~ Developed By: R. Chan /

Instructor

NIA

Date: 10--24-17

Validated By: AJ / Date: ,op.'-11" SME or lnstructoA~#1;:-6S

'-----z_) rO Date: I ( {; (n Approved By:

Approved By:

Training Department ~/1Jlk i"'

Operations Departme



PERFORMED BY:






REVISION HISTORY


Rev#

00

Date Description Validation Required

10-24-17 New JPM. Added revision history and simulator setup Yes pages. Editorial comments from IP 71111.11 FASA.




SYSTEM: Equipment Control - Administrative

TASK: Review a Tagging Request and Evaluate Tech Specs


SIMULATOR IC: N/A


OVERRIDES: N/A


1. ENSURE available copies of drawings 205228 sheet 1 (for Note 11 ), 205227 Sheet 1 (Drain Header), and 600658 (Legend Sheet), IF requested by operator.



NAME:

DATE:

SYSTEM: Equipment Control - Administrative

TASK: Review a Tagging Request and Evaluate Tech Specs


INITIAL CONDITIONS: • Unit 1 is at 100% power.

• No Tech Specs are currently active.

• 11 Charging pump 405p surveillance was just completed.

• Following the surveillance, excessive leakage from the pump seal was noted by the field operator.

• The Work Control NCO is preparing a Tagout package as part of the TAGOUT INITIATION section of OP-AA-109-115 and has requested you to review the marked up drawing for adequate blocking points.

• The charging pump will be removed from service IAW S1 .OP-SO.CVC-0002, CHARGING PUMP OPERATION.

INITIATING CUE: • You are the extra SRO.

• REVIEW the blocking points on the supplied drawing AND DETERMINE the following using ONLY the provided

drawing and procedures:

1. Are the blocking points on the supplied drawing adequate to isolate the equipment to be worked?

2. Justify your answer.

3. Applicable Tech Specs from removal of the component.


1. All critical steps completed 2. All sequential steps completed in order 3. All time-critical steps completed within allotted time 4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory

progress is being made (and NRC concurrence is obtained).

Task Standard for Successful Completion: 1. Identifies the following discrepancies from 205228 and Tech Specs:

a. 1CV81 is not a selected Blocking Point. b. 1CV136 is not a selected Blocking Point. c. 1CV356 is not a selected Blocking Point (2nd vent path)

2. Identifies T/S 3.5.2 as applicable LCO's.




NAME: __________ _

DATE: __________ _

System: Equipment Control - Administrative

Task:

CUE:

CUE:

1

PROVIDE the following:

• marked up DWG 205228 Sheet 2, and

• OP-AA-109-115, Safety Tagging Operations

• S1 .OP-SO.CVC-0002, Charging Pump Operation


START TIME: ------

Review provided Drawing for adequate Blocking Points.

Operator reviews drawing and identifies the following discrepancies:

Cue: IF operator requests to see the complete tagging package, THEN state: the package is still be developed by the NCO and you are being requested to ONLY review the drawing and procedures provided.




NAME: __________ _

DATE: __________ _

System: Equipment Control -Administrative

Task: Review a Tagging Request and Evaluate Tech Specs

(1:tJtt!~e~.'~lJ?~~'Jt}if ltiil'q~I,~;; } . :·: }iJ.·• ,.,/ •. .. :~,;r;??f ~t ~N QArio if J~·.;;~t~ttti)c\·.•·• '" , z7, $tep) . , .. th> ,, ,, ''.'t(Bc,lde~ area identifies;Task,.S.tandard) .

. .·. .'(*-Critical.Step). ·<>Ji . >>,ii 'J?; •)' . • ' .. • .

• : (#iSe'quentia.l C'riti'cali:Step) 1CV81, 11 CHG PUMP DISCH VALVE, is NOT listed as a Blocking Point and position should be CLOSED. [ see S1 .OP-SO.CVC-0002 step 4.9.4.2]

Both 1 CV48 and 1 CV81 are required to be closed to isolate the discharge of 11 Charging pump.

Evaluator's Note: The operator may identify that the discharge piping between the 1CV47 ( check valve) and the 1CV81 and 1CV48 (discharge valves) has no vent or drain path to release energy. This would make the Tagout "exceptional". Also double isolation on the discharge side of the pump is not possible and would make it exceptional as well.

Identifying the tagout as "exceptional" is not required to complete the JPM Task.




System: Equipment Control -Administrative


1CV136, 11 CHG PUMP RECIRC STOP VALVE, is NOT listed as a Blocking Point and position should be CLOSED. [ see S1 .OP-SO.CVC-0002 step 4.9.4.4]

1CV135 is a check valve and incorrectly used a Blocking Point on the recirc flow line.

Note: The operator may also identify 1 CV382 and 1 CV370 as vent paths for the recirc line.

1 CV356, CHG PUMP SUCT VENT, is NOT listed as a Blocking Point and position should be OPEN. [ see S1 .OP-SO.CVC-0002 step 4.9.4.7]

Both 1 CV356 and 1 CV45 need to be OPEN to properly vent and drain.

OP-AA-109-115, Attachment 2, page 71, specifies liquid systems shall have a minimum of one vent and drain tagged.

NAME: __________ _

DATE: __________ _




System: Equipment Control - Administrative


CUE:

<;:.f.;c•<,.,;;J//>i:z{·•:,,44;;4SJ§P,'t .. 1 f't:>···~;t;J;:\;'.C,J:1 ' .. :: : : :;c . ; (Shadea·area·dei'lotes Critical"""; ·MC ;:.;0r, '"'';

ic,t,t;,:~cii~PJtf f ~f ;;;i:''J t(#Sequ'ential.Critical'.step)

Note 11 for 1 CV45

Found on 205228 Sheet 1.

ApplicableTechSpecs frorr, .reITloJal .of ¢omponent.: . ; .··. f ,. •••·

Operator identifies and records discrepancies.

Cue: IF operator request to see Note 11, THEN provide drawing 205228 Sheet 1.

Cue: lE the operator asks about the status of the flange connection or spool piece downstream of 1 CV45, THEN state; the spool piece will be installed as part of a separate Tagout to connect the 1 CV45 to the drain header.

Operator evaluates Tech Specs and identifies T/S 3.5.2 is applicable.

Operator RECORDS any discrepancies and applicable Tech Specs on Initiating Cue Sheet.

CUE: I JPM is Complete Terminate JPM when operator records the discrepancies and Tech Specs.


STOP TIME: ------

NAME: __________ _

DATE: __________ _




JPM#: 16-01 NRCSRO-A3


_0_· __ 1. Task description and number, JPM description and number are identified.

_J ___ 2. Knowledge and Abilities (KIA) references are included.

___,_~...,,__ __ 3. Performance location specified. (in-plant, control room, or simulator)

-d=---- 4. Initial setup conditions are identified.

_____,,,(1 ___ 5. Initiating and terminating Cues are properly identified.

__,,(1..._ __ 6. Task standards identified and verified by SME review.

---'~=---- 7. Critical steps meet the criteria for critical steps and are identified with an asterisk(*). + 8. Verify the procedure referenced by this JPM matches the most current revision of that procedure: Procedure Rev. !:I_L_ Date lclc,lt./ h 1

~ ~ I / \ K/Ev', It.

-cr-9. Pilot test the JPM: a. verify Cues both verbal and visual are free of conflict, and b. ensure performance time is accurate.

(j~ /A 1 o.@),e JPM cannot be performed as written with proper responses, then revise the JPM.

& 11. When JPM is revalidated, SME or Instructor sign and date JPM cover page.

SME/lnstructor: ____________ _

Date: __ 1_0__,_/_J_'{~/-'_1_

Date: , 0/z11/n --1 -=-+1 ~---

Date: _____ _


INITIAL CONDITIONS:


• No Tech Specs are currently active.

• 11 Charging pump 405p surveillance was just completed.

• Following the surveillance, excessive leakage from the pump seal was noted by the field operator.

• The Work Control NCO is preparing a Tagout package as part of the TAGOUT INITIATION section of OP-AA-109-115 and has requested you to review the marked up drawing for adequate blocking points.

• The charging pump will be removed from service IAW S1 .OP-SO.CVC-0002, CHARGING PUMP OPERATION.

INITIATING CUE:

•

You are the extra SRO.

REVIEW the blocking points on the supplied drawing AND DETERMINE the following using

ONLY the provided drawing and procedures:

1. Are the blocking points on the supplied drawing adequate to isolate the equipment to be

worked?

2. Justify your answer.

3. Applicable Tech Specs from removal of the component.


l l'·IPRl01S ICV.43 ~ ~n •• \i.r,,, . ... ... ~-.. ~-.. i I ICVl'l \CV\8 I CV17 6i FE I ~ ~'-114.1611 ~C.£.2 ~m la

' ~ ~ ~ Cf!Allt

4

i ;;;

6'

M-,q FA·l7 ~

I l 2'·1101 Xi!l·3 FA·l 7 .' I

i,,t. 2' SET D TO E/P }- />fl. 3~ I 220 PSJG

~ \IENl 20523\ -A-S76l - - - -

___ .1

ICV382 SH,, lG·5l ICY\6 ICVl5 I I 3'·ll63 T~, ~ PL Fi!l·27 ll FA·U FA·14

ICV370 z: 51 z ICV3oB ~~07. SGlJ ' :I: ~ l I ~·-111s ICV522 FA-27 :,:

'·ISJt\25 M·l69 ~ ""' sl "' i:.. 1M4 z r- ,._

DRA!N. :I: 00

~ = !CVJ17 ICV38B ~

FA·17 N 1CV371 IC~383 C7' J.!i'·IWL1610 F~-27 FA·27

DRAIN O"'

VEN.Ti FA·27 FA·27 lSJll2G w .;,c 2'

I I I !\

~ ~1 ® 3000 H-~ 1CV1,35 ~: 1'1'11~~4

ICV356 3~03 H·N {.]j I I I 4SA I 1CVIJ6 ~ ___ I ~··12'*1 M·16q I 1c-,1i. CA-ti._. /IT'\ -- UMU 42 I FA-45 ;,; , S·22 mcc2 r~m I~ T _1~11 I --- IXIM2 /- _ I ~ FA·l4 ~. ! -~~- I ICV93 F~-U

I FA-27 IM7 FA·34

k '°"' 2~t22fla,t1 I SH 11- 1

--111a-----l lCv<il MXATP·4650 P.S.l,1 1cvq0 "' ~ MNATT ·100° F

CHHfGING SAfETY INJECTION PUMPS

ig

~ 0-L~:~ i...,._ I~ II ~ ,.,,m ;.;;-: 0 f@·-~TE ~ 1

FtH7 - q3 ~ \IENl ',J ,. ~ BJ 4qr, rrJ

IC\'361 I ~. 9113-l ~ 12m07nvEN.1 CV,5o =, " S·22m M·169 M·6] ~ 1 D ~I ."4"! JA CC2

I i i i u r 5311 1 ~ l>I"- ;i« &'·1085 /tt 'IDTE 12 I ___ I__ _ _ Q, ..[JQJ CC2 ~

~ 0,!,A lilt

t«llE 1

TSS-S !:,! _ , _ TE

fsl ~ .. ~

FA·27 ~ I ~'·1291 .._ _. ~'·11Jll6~9

111LIM7

IC~81 FA-4 NOTE I

48A

4'·1SJlll3

lCV270 F~·27

J'·\285

m VENT ~'-1171 ~01cvm 'IENl I: C>*--1 7, Fi'l-27 ICV37G

l>JII

ORAIII I ra:JI

~ TEMPORARYY@;* ~A 12i..&.-===----.....a.---..a....-~ STRAINER - 46 @ @• e

PL ..,. ~:::; ·1lr/L201B ~ I r - -- - -~ 4S 3409 H-N ,saj , Iii! I_ ___ J I I ima

,_ { FROM ltFUELlNG ~~ 1 ·IWL2~0q _ I\! @TE @*' 0 !1tLl

54e FA·52 _J 20~~n-_A·8761 '-.~ •• ~~~~... \IATEA STCJ!AGE T~ PD ____ • __ , / JCV5~ 2i! l~ I 0~A I I ! SH.:J (£ 5) ./

D\10 '2~5234-A·SJSI 4e FA-Ill ~ I I ~qG 4M ~ m VEl'H 5HT 1 !C·ll - - - - - - =>I(' u'i • IT\ ill t TE , =r= NnTI' 11 • • 2'·1WL21l1B i dfijll':;:; S.X. BJ81 ,,._ - IC~J73

~-r-:===-~lill~ / 1cVEii"" f l,.'rw,~u1 '@E1 cc2 s3al .. sH~ .. i"'1c-~T'"' ? 1wu~~1~ i 3·-12se~ I r~-21 I ~ 1

11 ~L rE --sEAL 'IIATER TANK 141A 0,1,A rsn ccz "'

1

1 <f:--7'r I 1 ~ q3J ~·-10q5 r-r, - - - - - - - - - t-r:rr-1 r ~ f>! I ICV82 I I ' 2

'

STATION:

SYSTEM:

TASK:

TASK NUMBER:

JPM NUMBER:

ALTERNATE PATH:


SALEM

Radiation Control

Authorize a Radioactive Gas Release Form

N1120650302

16-01 NRC SRO-A4

KIA NUMBER: G 2.3.6

' I

------------1 IMPORTANCE FACTOR: ---

APPLICABILITY: RO

EoD ROD STAD SROITJ


REFERENCES: S1.0P-SO.WG-0010 Rev. 31 (checked 10-4-17)

TOOLS AND EQUIPMENT:



Developed By: R.Chan µ4/ ~ Date: 10-4-17 Instructor

Validated By: ·711fl,(}_t}?-1tVulc I SME or Instructor

Date: 1.;·y-1,

Approved By: epartm~ • fk.-c Date: 11/3/11

Approved By: Date:

"''~In Operations Department



PERFORMED BY:





3.8 SRO


REVISION HISTORY


Rev#

00


10-4-17 Added revision history and simulator setup pages. Editorial Yes comments from IP 71111.11 FASA.


SYSTEM:

TASK:

TASK NUMBER:

SIMULATOR IC:



Radiation Control - Administrative


N1120650302

N/A


OVERRIDES: N/A


Evaluator's Note: A cue directing the performer to review the entire procedure is embedded several places in body of JPM, based on previous performance of this JPM where an operator will find the first flaw and discontinue reviewing the remainder of the procedure. If required, stress during initiating cue that the entire procedure is to be reviewed to ensure the candidate is allowed to identify all deficiencies.


SYSTEM:

TASK:

TASK NUMBER:

INITIAL CONDITIONS:


NAME:

DATE:

Radiation Control - Administrative


N1120650302

---------------

• 13 WGDT is in holdup in preparation for performing a gas release via the Plant Vent.

• Chemistry has performed all required sampling and authorized the gas release.

• The release procedure, S1.OP-SO.WG-0010, Discharge of 13 Gas Decay Tank to Plant Vent, has just been handed to you by the Unit 1 Plant Operator, who informs you the release is ready for CRS approval.

• All procedure sections are complete up to Step 5.2.9.

INITIATING CUE:

• You are the Unit 1 Control Room Supervisor (CRS).

• REVIEW all completed sections of the procedure for accuracy and completeness.

• DETERMINE the following:

a. Can you authorize the gas release?

b. Justify your answer.


1. All critical steps completed 2. All sequential steps completed in order 3. All time-critical steps completed within allotted time 4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory


Task Standard for Successful Completion: 1. Review Gas Release and identify that:

a. Pre-Release verification has not been performed in Attachment 1, Section 1.0. b. Calculated Maximum Allowable Release Rate is not> 32 SCFM. c. CRS does not authorize the gas release.


System: Radiation Control - Administrative

Task: Authorize a Radioactive Gas Release Form

CUE:

\C (?/t': \c'l;,~,t"STER;};c:::.:y,,.t{,.'" ;;~'(S h·acH{d,a~ea ;a~:ho'.tes:Critical , tj~:~it~?:'y:.;: ,~\;;'. :.:'~~i!ip);;::>:,~: t:'; !*;,::'. •+:\;:::,

;,.ci.;.··· .... ,,..;rr; ... ·····•2·(*'Cnt1cal Step)·.k,,., .... \.·,,. ·'··'·''· C <;f::C••\:(:/\:;:'"'.i~.: ;, ;"~'.:t\•~w; ----,<;,"' ,"" ,}: <', •+, • "' j'. ;~/?<\;;) ''\\'~\~ t' (#Sequential Critical Step) Provide marked up S1 .OP-SO.WG-0010 to operator.


START TIME: ------



Operator reviews procedure.

Possible Cue Required: On page 17, the Estimated Total Volume of Waste Gas to be released is entered by Chemistry during performance of Attachment 2, section 3.0, DOSE, VOLUME ESTIMATES AND APPROVAL.

IF an operator requests the Release Permit, or questions the estimated release volume or ANY aspect of Section 3.0, THEN provide the following cue:

Cue: The data provided in Section 3 of Attachment 2 was transfem=!d properly by Chemistry from the Radioactive Gaseous Release Permit.

NAME: ----------DATE: -----------




Operator identifies and records discrepancies.



The first error in the procedure is that the PRERELEASE VERIF in Attachment 1, Section 1.0 has not been performed at step 5.2.8, prior to the procedure being given to the CRS for release approval.

Possible Cue Required: IF operator identifies that Step 5.2.8 has not been performed and does not go any further to see if the rest of the procedure is correct, THEN state; that the operator needs to review the entire procedure.

The second error is that the Maximum Allowable Release Rate of 32 SCFM recorded in Step 3.4 and 4.1 is not > 32 SCFM. IAW NOTE in Step 3.4; Tanks with a calculated maximum allowable release rate of S 32 SCFM cannot be released.

Possible Cue Required: IF operator identifies that the release rate has been entered incorrectly and does not go any further to see if the rest of the procedure is correct, THEN state, that the operator needs to review the entire procedure.

NAME: _________ _

DATE: ----------

.. ;: ·:·,~9~~:~~r~. • !'

· (Require.d f6rl)NSAT:e.va!u·ation)·~\ ~. . ",.<'. : ' . . ~,,!' .. · • ' , ,, • ;,, • .·,, _.,_. • ,.· .,.· ., '.c




>; ii,,'\$1.EPL ....•.• ····. ' (Shaded•area;denotes•CriticaJ:c.

\~:.;·.;f ~;)i/1~l'X!JtJ~r" . . ; #·Sequential Cri_ti~c!I Step)

CUE: JPM is Complete


STOP TIME: _____ _



Terminate JPM when operator determines if release is authorized, records discrepancies, AND the entire procedure has been reviewed.

NAME: _________ _

DATE: _________ _




JPM#: 16-01 NRCSRO-A4


~ 1. Task description and number, JPM description and number are identified.

'~, :Jr 2. Knowledge and Abilities (KIA) references are included. A.~ f 111 3. Performance location specified. (in-plant, control room, or simulator)

~ 4. Initial setup conditions are identified.

/{~\- 5. Initiating and terminating Cues are properly identified.

ft/a ~ 6. Task standards identified and verified by SME review.

~ 7. Critical steps meet the criteria for critical steps and are identified with an asterisk(*).

' /lif 8. Verify the procedure referenced by this JPM matches the most current revision of / that procedure: Procedure Rev.~ Date l(Y~~n Lif.' _J__ 9. Pilot test the JPM:

J a. verify Cues both verbal and visual are free of conflict, and b. ensure performance time is accurate.

~ 10. If the JPM cannot be performed as written with proper responses, then revise the JPM.

fJ/l 11. When JPM is revalidated, SME or Instructor sign and date JPM cover page.

SME/lnstructor:_

1

""'"/j,_.~l~W-',-J.)~_-+-/J2-r,_.rJ_f'_,;S'_· _ v ~ Date: iD·'-/··(7


SME/lnstructor: ____________ _ Date: ------


INITIAL CONDITIONS:

• 13 WGDT is in holdup in preparation for performing a gas release via the Plant Vent.

• Chemistry has performed all required sampling and authorized the gas release.

• The release procedure, S1.OP-SO.WG-0010, Discharge of 13 Gas Decay Tank to Plant Vent, has just been handed to you by the Unit 1 Plant Operator, who informs you the release is ready for CR:S approval.

• All procedure sections are complete up to Step 5.2.9.

INITIATING CUE:


• REVIEW all completed sections of the procedure for accuracy and completeness.

• DETERMINE the following:

a. Can you authorize the gas release?

b. Justify your answer.


PSEG Internal Use Only Page .1_ of .1_

PSEG NUCLEAR L.L.C.

SALEM/OPERATIONS IO /'3 J 11

S1.0P-SO.WG-0010(Q)- RE~ f(Z.,

DISCHARGE OF 13 GAS DECAY TANK TO PLANT VENT

USE CATEGORY : I

A. Biennial Review Performed: Yes No _ v _ B. Change Package(s) and Affected Document Number(s) incorporated into this revision: None C. The following OTSC(s) were incorporated into this revision: None

REVISION SUl\ilMARY:

The following changes were incorporated into this revision:

+ Revised Prerequisite 2.2. l to indicate Auxiliary Building Ventilation IAW S 1.0P-SO.ABV-000 l(Q), Auxiliary Building Ventilation Operation", and the Auxiliary Building is being maintained at a slightly negative pressure". This change supports implementation of Unit 1 Technical Specification Amendment 271 and SCN 03-031. [80056801]

+ Incorporated Precaution and Limitation 3.9 indicating "With the Auxiliary Building Pressure NOT maintained slightly negative, suspend all operations involving radioactive gaseous releases via the Auxiliary Building immediately. This requirement is applicable at all times IA W TIS 3.7.7.1 ". This change supports implementation of Unit 1 Technical Specification Amendment 271 and SCN 03-031. [80056801]

+ Revised Steps 6.1 aqd 7.6.4 to indicate "RM-AA-101" versus "NC.NA-AP.ZZ-OOOl(Q)". This change was incorporated to ensure current procedure references are indicated, and is considered to be editorial in nature.

IMPLEMENTATION REQUIREMENTS Effective Date '5 //7/ o"-' + Technical Specification Amendment 271 and UFSAR SCN

. APPROVED: Operations Director - Salem

SECTION TITLE

S l .oP-SO.WG-001 O(Q)

DISCHARGE OF 13 GAS DECAY TANK TO PLANT VENT

TABLE OF CONTENTS

PAGE

1.0 PURPOSE ................................................................ 2

2.0 PREREQUISITES .......................................................... 2

3.0 PRECAUTIONS AND LIMITATIONS ......................................... 3

4.0 EQUIPMENT/MATERIAL REQUIRED ........................................ 3

5.0 PROCEDURE ............................................................. 4

5.1 13 Gas Decay Tank (GDT) Release Preparation ............................ 4

5.2 13 Gas Decay Tank Release ........................................... 5

5.3 Completion and Review ............................................. 10

6.0 RECORDS ......................................................... ', ..... 11

7 .0 REFERENCES ............................................................ 11

ATTACHMENTS

Attachment 1

Attachment 2

Attachment 3

Attachment 4

Attachment 5

Salem 1

13 Gas Decay Tank AlignmenWerification . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14

13 GDT Radioactive Gaseous Release Form ............................. 16

13 GDT Release Rate Calculation ..................................... 22

Plant Vent Flow Rate Discharge Estimation .............................. 23

Completion/Sign-Off Sheet ........................................... 24

Page 1 of25 Rev. 31

S l .oP-SO. WG-001 O(Q)

1.0 PURPOSE

1.1 To provide instructions necessary fo:

1.1.1 Place 13 Gas Decay Tank ( GDT) in Holdup.

1.1.2 Conduct a controlled Radioactive Gas Release from 13 GDT.

1.2 This procedure satisfies Technical Specification 6.8.4.g.1 for Channel Operabl,e and Source Check prior to each release.

2.0 PREREQUISITES

~ 2.1 REVIE'\V Components "OffNonnal and Off-Normal Tagged" List(s) for systiem

[C0160J

and support system(s) associated with the evolution to be perfonned in this procedure.

<yo 2.2 The following systems are in service:

~ 2.2.1 Auxiliary Building Ventilation IA W S 1.0P-SO.ABV-0001 (Q), Auxiliary Building Ventilation Operation, and the Auxiliary Building is being maintained at a slightly negative pressure.

<yo 2.2.2 Fuel Handling Building Ventilation System IA W S1.0P-SO.FHV-000l(Q), FuelHandling Building Ventilation Operation.

fi2._ 2.3

~ 2.4

~o 2.s

Salem 1

ENSURE Plant Vent Flow Rate Monitor and Sample Flow Rate Monitor are OPERABLE (or ODCM entered). ·

ENSURE Noble Gas Activity Monitor 1R41A & Dis OPERABLE (or ODCM entered).

ENSURE Iodine Sampler and Particulate Sampler (Chemistry Dept.) are OPERABLE (or ODCM entered).

Page2 of25 Rev. 31

S l.oP-SO.WG-OOlO(Q)

3.0 PRECAUTIONS AND LIMITATIONS

?O

vo (70

eo

3.1

3.2

3.3

3.4

Procedure Use and adherence policy as found in NC.NA-AP.ZZ-OOOl(Q), Nuclear Procedure Program, is applicable to this procedure.

DO NOT release more than one GDT at a time.

DO NOT transfer Waste Gas from one GDT to another during the GDT release.

The actual maximum GDT release rate is 32 SCFM based on system design. The calculated maximum allowable release rate shall be >32 SCFM. Tanks with a calculated maximum allowable release rate of ~32 SCFM shall not be released.

'yO 3.5 GDT Release shall be terminated if pressure downstream of 1WG38, Gas Decay Tank Vent Pressure Control Valve, is >8.0 psig once the gas release has stabilized following the initial start. This will ensure the actual release rate does not exceed 32 SCFM (IAW the ODCM).

(7° 3.6 The program requirements of Radiological Effluent Technical Specifications (RETS) are located in the Off site Dose Calculation Manual (ODCM) and Process Control Program (PCP). (80018643)

'?0 3.7 Inoperability of the Noble Gas Activity Monitor (1R12A, 1R41A & D), Iodine Sampler, Particulate Sampler, Flow Rate Monitor, or Sampler Flow Rate Monitor for >30 days is reportable "IA W NC.WM-AP.ZZ-0002(Q), Perfonnance Improvement Process (IA W the ODCM).

'? 0 3 .8 The Independent Verification requirements contained in the ODCM SHALL BE PERFORMED prior to the release of radioactive waste gas to the environment. (970630118)

~ O 3.9 With the Auxiliary Building Pressure NOT maintained slightly negative, suspend all operations involving radioactive gaseous releases via the Auxiliary Building immediately. This requirement is applicable at all times IA W T/S 3.7.7.1. For the purposc~s of satisfying T/S 3.7. 7.1, ACTION e, "radioactive gaseous releases" is defined as Waste Gas Decay Tank releases. (80056801~0313)

4.0 EQUIPMENT/MATERIAL REQUIRED

None

Salem 1 Page 3 of25 Rev. 31

S 1.0P-SO..WG-001 O(Q)

5.0 PROCEDURE

5.1 13 Gas Decay Tank (GDT) Release Preparation

f O 5.1.1 ALIGN 13 GDT for Holdup as follows:

fD A. OBTAIN a CRS Tagging Request for 13WG31, GDT INLET VALVE, in the CLOSED position and with specific instructions that this tag should only be released IA W this procedure.

f o B. PERFORM 13 GDT Holdup Alignment IAW Attachment 1, Section 1.0.

'? D C. DIRECT second operator to complete Independent Verification (N) of 13 GDT Holdup Alignment IA W Attachment 1, Section 1.0.

p O 5.1.2 INITIATE 13 GDT Radioactive Gaseous Release Form as follows:

r o A. COMPLETE Attachment 2, Section 1.0.

P O B. FORWARD entire procedure to Chemistry Department for completion of Attachment 2, Sections 2.0 and 3.0.

fv A 5 .1.3 IF Chemistry has NOT granted permission for the release, OR the release is no longer required, THEN:

A. OBTAIN a CRS Tagging Release for 13WG31, GDT INLET VALVE.

B. OPEN 13WG28, 13 WASTE GAS DECAY TANK Il\1LET VALVE.

C. DIRECT second operator to complete Independent Verification (N) of valves manipulated IA W Attachment 1, Section 6.0.

µ A D. TERMJNATE this procedure.


S 1.0P-S0.,WG-0010(Q}

5.2 13 Gas Decay Tank Release

~ 5.2.1 ENSURE Attachment 2, Sections 2.0 and 3.0, are complete with approval for Radioactive Gaseous Release.

? D 5.2.2 IF 1R41A & D, Plant Vent Noble Gas monitors are OPERABLE, THEN:

~ A. ENSURE 1R41D and 1 WG41, Gas Decay Tank Vent Control Valve, are OPERABLE, as required by ODCM, IA W SH.OP-AP.ZZ-0108(Q), Operability Assessment and Equipment Control Program.

ry, O B. ENSURE 1R41 sample system flow control is OPERABLE, as required by ODCM, JAW SH.OP-AP.ZZ-0108(Q), Operability Assessment and Equipment Control Program. [C0332, C0333]

~ C. PERFORM a source check and channel check (visual inspection of monitor read out).

\'b D. ENSURE 1ND17572-1WG41 WasteGasDecayTankinNORMAL.

tJ P.. 5.2.3 IF RMS Channe11R41A or Dis inoperable, THEN:

A. ENSURE Chemistry Department has documented completion of the following contingency actions on Attachment 2, Section 3.4 (IA W the ODCM):

1. ANALYZE at least two independent samples of 13 GDT contents.

2. INDEPENDENTLY VERIFY release rate calculations by at least two technically qualified members of the Facility Staff.

3. OBTAIN grab samples at least once per 8 hours, AND ANALYZE for gaseous principal gamma emitters within 24 hours.

fV A B. PLACE 1ND17572 - 1WG41 Waste Gas Decay Tank in BLOCK.

tJ A 5.2.4 IF Iodine Sampler OR Particulate Sampler is inoperable,

Salem 1

THEN ENSURE Chemistry Department is collecting a continuous sample of the effluent release pathway with auxiliary sampling equipment (IA W the ODCM}.

Page 5 of 25 Rev. 31

S l .oP-S0.WG-0010(Q)

NA 5.2.5 IF Plant Vent Flow Rate Monitor is inoperable, THEN ESTIMATE the Plant Vent Flow Rate at least once per 4 hours IA W Attachment 4 and the ODCM.

/VA 5 .2. 6 IF Sampler Flow Rate Monitor is inoperable, THEN ENSURE Chemistry Department is estimating flow rate at least once per 4 hours JAW SC.CH-AB.ZZ-1102(Q) and the ODCM.

? 0 5.2. 7 RECORD the following on Attachment 2:

• Section 4.1, Release Verification

+ Section 4.2, Ventilation Configuration

+ Section 4.3, Radiation Monitor Release Data

+ Section 4.4, Release Review

~ 0 5.2.8 PERFORM Pre-Release Verification of 13 GDT Holdup Alignment IAW Attachment 1, Section 1.0.

5.2.9 SM/CRS REVIE\V AND COMPLETE Attachment 2, Section 4.5.

· CAUTION

00 NOT release 13WG31, GDT INLET VALVE, until commencing the release.

5.2.10 OBTAIN the CRS Tagging Release for I3WG3l.

5 .2.11 PERFORM the following preparations at Panel 104-1 for the GDT release:

A. ENSURE 13 GbT is NOT in service.

B. ENSURE 13 GDT is NOT selected for "Standby".

C. RECORD 13 GDT "Initial Pressure" (PIS1038) on Attachment 3.

(step continued on next page)


S 1.0P-80. WG-001 O(Q)

5.2.11 (continued)

D. LATCH AND SET 1WG41, GDT VENT CONT VALVE, as follows:

NOTE

1WG41 Controller 1HIC-14 must be set to <0% or 1WG41 will NOT latch.

1. TURN controller fully counterclockwise until indicator <0%.

2. POSITION Selector Switch to OPEN AND RELEASE to AUTO position (spring return to AUTO).

3. TURN controller clockwise until indicator~ 100%.

NOTE

4. ENSURE with Unit 1 Control Room that 1 WG41 valve has lost the CLOSED indication AND audible alarm received.

S. TURN controller fully counterclockwise until indicator <0%.

6. ENSURE with Unit 1 Control Room that 1WG41 has closed indication.

E. PERFOR1"1 an Independent Verification of the l WG41 valve position controller, AND RECORD the Independent Verification on Attachment 1, Section 2.0.

F. NOTIFY Unit 1 Control Room to mark 1R41 Chart Recorder with the following information in preparation for the GDT release:

+ 13 GDT

+ Date/Time

+ NCO Initials

G. OPEN 13WG31, GDT INLET VALVE.

( step continued on next page)

Salem 1 Page 7 of 25 Rev. 31

S 1.oP~SO.WG-OOlO(Q)

5.2.11 (continued)

NOTE

While 1WG41 is opening, pressure downstream of 1WG38 will fluctuate between "O" psig and 1110" psig until 1WG41 is fully open (100%). Once 1WG41 is fully open, 1WG38 will throttle to maintain <8 si durin the release. 20016988

H. Slowly OPEN 13WG34.

I. RECORD Independent Verification (IV) of 13 GDT discharge valves 13WG31 and 13WG34 on Attachment 1, Section 3.0, prior to commencing 13 GDT release.

5.2.12 COMMENCE 13 GDT release as follows:

A. POSITION 1WG41 Selector Switch to OPEN AND RELEASE to AUTO position (spring return to AUTO).

B. SLOWLY SET 1 WG41 controller to :d 00% position which corresponds to a maximum release rate of 32 SCFM.

C. PERFORM an Independent Verification of the positioning of 1WG41 on Attachment 1, Section 4. 0.

D. RECORD In Progress Release Data on Attachment 2, Section 5 .1.

5.2.13 PERFORl\'I the following during 13 GDT release:

NOTE

An operator should be stationed at Panel 104-1 to immediately close 13WG34 upon receipt of a Hi h RadiaUon Alarm or indication of 1WG41 closure.

A. CALCULATE 13.GDT Average Release Rate every 10 minutes on Attachment 3, AND ADJUST 1 WG41 controller position as required based on results.

B. IF Plant Vent Flow Rate Monitor is inoperable, THEN RECORD Plant Vent Flow Rate Discharge Estimation on Attachment 4 at least once every four hours during GDT release.

(step continued on next page)


. \

'

Salem 1

S 1.0P-S0.WG-0010(Q)

5 .2.13 ( continued)

C. . RECORD Meteorological Data in Attachment 2, Section 5.2.

+ IFMeteorological Monitor is NOT OPERABLE, THEN NOTIFY the SM/CRS (UFSAR 7.7.2.12).

D. IF at any time during the release pressure downstream of 1 WG38 is >8.0 psig (1PL8678), OR 1WG41 CLOSES, THEN TER1'1INATE the GDT release as follows:

1. TURN 1 WG41 controller fully counter-clockwise until indicator is <0%.

2. PLACE 1 WG41-SWT in CLOSE position, AND ENSURE 1WG41 is CLOSED.

3. CLOSE 13WG34.

4. RECORD Final Release Data in Attachment 2, Section 5.3.

S. INITIATE a NOTF to correct the malfunction.

5.2.14 When 13 GDT pressure ~ 10 psig OR as directed by SM/CRS, SECURE the·GDT release:

A. TURN 1 W941 controller fully counter-clockwise until indicator is <0%.

B. PLACE 1 WG41-SWT in CLOSE position, AND ENSURE 1WG41 is CLOSED.

C. CLOSE 13WG34.

D. RECORD Final Release Data in Attachment 2, Section 5.3.

5.2.15 IF GDT release is completed, THEN OPEN 13WG28, 13 Waste Gas Decay Tank Inlet Valve.

5 .2.16 IF 1 ND 17572 - 1 WG4 l Waste Gas Decay Tank is in BLOCK, THEN PLACE 1ND17572 in NORMAL.

5.2.17 Direct second operator to PERFORM Independent Verification of valves manipulated in this procedure IA W Attachment l, Section 5.0.

Page 9 of25 Rev. 31

s1.oP-S0.WG-0010(Q)

53 Completion and Review

Salem 1

5.3.1 COMPLETE any additional paperwork required by the Chemistry Department AND ATTACH it with this procedure.

5.3.2 COMPLETE Attachment 5, Sections 1.0 and 2.0, AND FORWARD this procedure to SM/CRS. for review and approval.

5.3.3 . SM/CRS PERFORM the following:

A COMPLETE Attachment 2, Section 5.4

B. REVIEW this procedure with Attachments 1-5 for completeness and accuracy .

. C. COMPLETE Attachment 5, Section 3.0.

D. FORWARD completed procedure to Technical Supervisor - Chemistry for completion and record retention.

END OF PROCEDURE SECTION

Page 10 of25 Rev. 31

6.0 RECORDS

6.1 Retain entire procedure IA W RM-AA-101, Records Management Program.

7 .0 REFERENCES

7 .1 Salem Generatin2 Station Updated Final Safety Analysis Report:

7.1.1 Section 11.3, Gaseous Waste System 7.1.2 Section 11.4,Radiological Monitoring 7.1.3 Section 9.4, Heating, Ventilation, and Air Conditioning Systems 7.1.4 Section 15.3.6.3, Gas Decay Tank Rupture Analysis

7.2 Technical Specifications - Unit l:

7.2.1 3.7.7.1, Auxiliary Building Exhaust Filtration System 7.2.2 3.9.12, Fuel Handling Area Ventilation System

7.3 Procedures:

7.3.1 NC.NA-AP.ZZ-0020(Q), Control ofNonconfonning Components and Structures 7.3.2 SC.OP-AP.ZZ-0102(Q), Use of Procedures 7.3.3 SC.OP-DL.ZZ-0030(Q), Radwaste Monitoring & Control Program 7.3.4 S1.0P-DL.ZZ-0002(Q), Control Room Readings (Modes 5, 6 & Defueled) 7.3.5 S1.0P-DL.ZZ-0003(Q), Control Room Readings (Modes 1-4) 7 .3 .6 S l.OP-SO.ABV-0001 (Q), Auxiliary Building Ventilation System Operation 7.3.7 S1.0P-SO.CA-0001(Q), Control Air System Operation 7.3.8 Sl.OP-S0.CVC-0010(Q), Establishing VCT Atmosphere 7.3.9 SI .OP-SO.FHV-OOOl(Q), Fuel Handling Building Ventilation Operation 7.3.10 Sl .OP-SO.RM-OOOl(Q), Radiation Monitoring System Operation 7 .3 .11 S l .OP-SO. WG-0003(Q), Waste Gas Disposal System Operation 7.3.12 S 1.0P-S0.WG-0006(Q), Containment Purge to Plant Vent 7.3.13 Sl.OP-S0.WG-0007(Q), Transfer of Waste Gas

7.4 Drawines:

7.4.1 203461, No.1 Relay Room Terminal Block Rack 7.4.2 205237, Auxiliary Building - Ventilation 7.4.3 205240, Waste Disposal - Gas 7.4.4 246548, RMS Plant Ventilation Monitor, Flow and Velocity Comparator


7.5 Others:

7.5.1

7.5.2 7.5.3

7.5.4

7.5.5

7.5.6 7.5.7 7.5.8 7.5.9 7.5.10

S l .oP-SO.\VG-001 O(Q)

DCP lEE-0205, 1 WG41 Valve Modification to Mechanically Restrict Flow to s32 SCFM DCP · 1 EC-3244, R.t\1S Channel 1 R41 Replacement DE-CB.ABV-0022(Q), Configuration Baseline Documentation for Auxiliary Building Ventilation System DE-CB.FHV-0021(Q), Configuration Baseline Documentation for Fuel Handling Building Ventilation System DEF-DES-91-00064, PUP-90-0073 (File: 670), Design Basis for Gaseous Radwaste Release Path Components 1 WG41, 1 WG38, 2WG41, and 2WG38 PIR 970630118, Independent Verification Missed on Liquid Release. SER Section 11.0, Radioactive Waste Management SER Supplement 1, Section 11.0, Radioactive Waste Management Reg. Guide 1.33, Quality Assurance Program Requirements (Operations) Reg. Guide 1.21, Measuring, Evaluating and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants

7.5.11 SC-WGOOl-01, Salem Unit 1, 2 Gas Decay Tank Pressure -Alarm mid Recorder (Setpoint Cale & Scaling)

7.5.12 10CFR50, Appendix I 7.5.13 Technical Specification Amendment 234 7.5.14 DCP 80030824, Deletion of Sl RMS 1Rl6 (1RA8346) and Recorder 1RR2

(1XA9194)

7.6 Cross References:

Salem 1

7.6.1 Updated Final Safety Analysis Report:

A. Section 7.7.2.12, Seismic Monitoring Instrumentation

7.6.2 Technical Specifications· Unit 1:

A. 6.8.4.g - Radiological Effluent Controls Program

7.6.3 Others:

A. GL 89-01, Implementation of Programmatic Controls for Radiological Effluent Technical Specifications in the Administrative Controls Section of the Technical Specifications and the Relocation of Procedural Details of RETS to the Offsite Dose Calculation Manual or to the Process Control Program

B. Offsite Dose Calculation Manual


S l .oP-SO.WG-001 O(Q)

7.6.4 Procedures:

A. NC.NA-AP.ZZ-OOOl(Q), Nuclear Procedure Program B. RM-AA-101, Records Management Program c.· NC.WM-AP.ZZ-0002(Q), Perfonnance Improvement Process D. SC.CH-AB.ZZ-1102(Q), Response to Inoperable Technical Specification

Effluent Monitors and Equipment E. SC.CH-TI.ZZ-0145(Q), Radioactive Gaseous Effluent Pennits F. SH.OP-AP.ZZ-0108(Q), Operability Assessment and Equipment

Control Program

7.7 Commitments:

7.7.1 C0160 -AR M29-89-124 Quality Assurance Audit Radioactive Effluents and Controls

7.7.2 C0317 - NSO Incident Report 89-679 7.7.3 C0332 - NSO LER 90-016-00 7.7.4 C0333 -NSO LER 88-026-00

Salem 1 Page 13. of 25 Rev. 31

ATTACHMENT 1 (Page 1 of2)

S l .oP-SO.WG-OOlO(Q)

13 GAS DECAY TANK ALIGNMENTNERIFICATION

1.0 PRE - RELEASE ALIGNMENTNERIFICATION

VALVE OPER IV PRE-

NO. DESCRIPTION POSITION INITIALS INITIALS

RELEASE VERIF

13WG31 GDTINLETV *CLOSED f./6-o I IJcO 2..

13WG32 GDT PRESS TAP OPEN N€0 I IJ (5 0 'Z..

11WG34 GDT STOP TO PLNT V CLOSED tJGO \ tJEo z... 12WG34 GDT STOP TO PLNT V CLOSED IJ~O ( µ{;o z. 13WG34 GDT STOP TO PLNT V CLOSED µ60 z_ f.JGO \

14WG34 GDT STOP TO PLNT V CLOSED Ne.O I /J£0 2... 13WG35 GDT STOP V TO HUT CLOSED tJ {:;, 0 ( /JcO 2

13WG28 WG GDT INLET V CLOSED NGO \ rJGO l.

13WG29 GDT INLET CONT V CLOSED N€0 I tJEO 2·

13WG56 GDTDRV CLOSED rv e--o r fJE O 2.

13WG60 N2 SUP TO GDT STOP CLOSED f../€0 I tJEO Z...

1WG41 GOT VENT CONT V CLOSED tJE. 0 ( /JcO 2

1WG928 GDT TO VENT HDR CLOSED STOPV fJ E.O f f\/60 2

1WG81 WO VENT PRESS TAP OPEN /JE.O I NGO 2

13WG131 GDT PRESS TRANS V OPEN rJ 60 < fJ€-O Z, [C0317]

* Cleared and Tagged for CRS.

2.0 1 WG41 VAL VE POSITION CONTROLLER

VALVE NO. I DESCRIPTION POSITION I IV INITIALS I 1WG41 I. GDT VENT CONT V 0°1o I I


S l .oP-SO.\VG-001 O(Q)


13 GAS DECAY TANKALIGNMENTNERIFICATION

3.0 PRE-RELEASE VERIFICATION

VALVE NO. DESCRIPTION POSITION

13WG31 GDTINLETV OPEN

13W034 GDT STOP TO PLNT V OPEN

4.0 IN-PROGRESS VERIFICATION

VALVE NO. DESCRIPTION POSITION

1WG41 GDT VENT CONT V ~100%

5.0 POST RELEASE VERIFICATION

COMPONENT DESCRIPTION POSITION

13WG28 WG GDT INLET V OPEN


13W034 GDT STOP TO PLNT V CLOSED

1WG41 ODT VENT CONT V CLOSED

1ND17572 1WG41 WASTE GAS DECAY NORMAL TANK

6.0 RELEASE TERMINATION VERIFICATION

COMPONENT DESCRIPTION POSITION

13W028 WO GDT INLET V OPEN


Salem 1 Page 15 of 25

IV INITIALS

3 IV INITIALS

IV INITIALS

IV INITIALS

Rev. 31

sl.oP-S0.WG-0010(Q)


13 GDT RADIOACTIVE GASEOUS RELEASE FORM

RELEASE NO.----

1.0 SAMPLE REQUEST (Operations)

R 1.1 13 GDT has not been added to since (time) I g O O

and is ~t ~ B PSIG as indicated by 1PIS1038.

f2.. 1.2 A pre-release sample of 13 GDT and release rate computation is requested.

R.. 1.3 13 Gas Decay Tank release will be concurrent with a Unit 1 Containment Purge:

• YES v'No (2- 1.4 13 Gas Decay Tank release will be concurrent with a Unit 1 VCT Purge/Release:

• YES /NO

Signature: __ ~----~-----__ Date ~SM/CRS)

2.0 SAMPLE POINT (Chemistry)

C \-\ 2. 1 PERFORM gaseous discharge process IA W SC.CH·TLZZ-0145(Q), Radioactive Gaseous Effluent Permits.

C_li 2.2 After completion ofSC.CH-TI.ZZ-0145(Q), COMPLETE Parts 3.1 through 3.4.

3.0 DOSE, VOLUME ESTIMATES AND APPROVAL (Chemistry)

3 .1 Instrumentation;

(.x1_ • INDICATE if the following instruments are in service for release:

INSTRUMENTATION IN SERVICE

Iodine Sampler :r:/5 c.~

Particulate Sampler :!{_s C" · Sampler Flow Rate Monitor I{.J Cl-\



S l .oP~SO.WG-OOlO(Q)


RELEASE NO.-----

3.0 DOSE, VOLUME ESTIMATES AND APPROVAL (continued)

3.2 Pressure:

Cl-\ +

3.3 Volume:

c~ •

COMPLETE the following required data for 13 GDT:

Isolated Pressure __ S_8_ (PSIG)

Estimated Final Pressure --7?~- (PSIG)

ESTIMATE total volume of Waste Gas to be released:

___ :Z_t3_l'3_. \ __ (CU FT)

3.4 Approval:

NOTE

Calculated maximum allowable release rate must be >32 SCFM. Tanks with a calculated maximum allowable release rate of ~32 SCFM cannot be released.

Cl.\ +

C \-\ +

Salem 1

Approval is granted to release 13 GDT at the Calculated Maximum Allowable Release Rate of 3 2- SCFM.

This Release is consistent with the Limits set forth in the Offsite Dose Calculation Manual.


s l .oP"so. WG-001 O(Q)



RELEASE NO. ___ _

3.0 DOSE, VOLUME ESTIMATES AND APPROVAL (continued)

NA + IF RMS Channel 1R41A or D is inoperable, THEN the following have been completed (IAW the ODCM):

A. At least two independent samples of 13 GDT contents have been analyzed.

B. Release rate calculations have been independently verified by at least two technically qualified members of the Facility Staff

NA C. Grab samples are being obtained at least once per 8 hours,

wA +

uA +

C \-\ +

Signature:

c~ •

Salem 1

AND analyzed for gaseous principal gamma emitters within 24 hours.

IF Iodine Sampler or Particulate Sampler is inoperable, THEN a continuous sample of the effluent release pathway is being collected with auxiliary sampling equipment IAW SC.CH-AB.ZZ-l 102(Q), Response to Inoperable Technical Specification Effluent Monitors and Equipment.

IF Sampler Flow Rate Monitor is inoperable, THEN flow rate is being estimated at least once per 4 hours IA W SC.CH-AB.ZZ-l 102(Q), Response to Inoperable Technical Specification Effluent Monitors and Equipment.

All Chemistry requirements for 13 GDT release to the Plant Vent are satisfied and authorization given.

~ Time 0'-1'30 Date fod«y ~istry /

FORWARD this Radioactive Gaseous Release Form to SM/CRS.


S l .oP-SO. WG-001 O(Q)



RELEASE NO.----

4.0 RELEASE REVIE\V AND APPROVAL (Operations)

4.1 Release Verification:

Po+ Calculated Maximum Allowable Release Rate from Section 3.4: '3'2- SCFM.

Calculated Maximum Allowable Release Rate is >32 SCFM.

4.2 Ventilation Configuration:

Total number of Auxiliary Total Number of Fuel Handling Pressure Relief Building Exhaust Fans Building Exhaust Fans In Service In Service In Service (Y1es/No)

2- I ,No

4.3 Radiation Monitor Release Data/Source Check/Channel Operable:

Time Date Radiation Monitor Source Check Monitor Prior to Release

z.02.5 7::,du--'{ 1R41A (O~INOP 1. 7'1 £.-·6 µCi/cc

-z.o -i..S (0 J <A~/ 1R41D NIA I '2-.5 µCi/sec , 4.4 Release Review

pLJ-o~ NCO

Time ?..oZ.6 Date (o J1 4.5 All requirements in Section 3.0 and subsections 4.1 thru 4.4 are met to authorize the release

of the tank.

Time ---- Date ___ _ SMICRS

I


S 1.0P-SO. WG-001 O(Q)



RELEASE NO. -----

5.0 RELEASE DATA(Operations)

5.1 fu Progress Release Data:

• Release sta1ted: Time Date --- ----+ Pressure downstream of 1WG38:

lll=====l=PL=8=67=8 ===~'I

_I PSIG* I_

* Shall be maintained :S8.0 psig to ensure GDT release rate :S32 SCFM. ·

+ PERFORM an Independent Verification of:

N

N

+ 1 WG38 pressure (1PL8678) :S8.0 psig.

• 1 W G4 l controller positioned :S 100% ( corresponds to a maximum gaseous release rate of :S 32 SCFM).

Time ___ _ Independent Verifier

5.2 Meteorological Data.

Salem 1

+ Meteorological conditions at time of Release. (El. 33' is preferred channel and should be used if available)

• +

Wind Speed ___ MPH at El.

Wind Direction ° at El. ---+ ~ T (_ 1

- 33,) -- C0

Page20 of 25 Rev. 31

S l .oP-SO.WG-OOlO(Q)



RELEASE NO.----

5.0 RELEASE DATA (continued)

5.3 Final Release Data:

Time Date Radiation Monitor Highest Reading during release 1PIS1038

I I I 1R41A : µCi/cc PSIG I 11

1R41D µCi/sec 11 + Plant Vent Flow during Release (average):

5 .4 13 GDT Radioactive Gaseous Release conducted under supervision of:

Date ----(SM/CRS)


S 1.0P-SO .WG-OOlO(Q)


13 GDT RELEASE RATE CALCULATION

Initial Pressure = ___ psig (1 PIS 1038) Time ---

Time (Min) GDT Pressure (psig) Average Release Rate 3 (psig/min) *

Salem 1

+10

+20

+30

+40

+50

+60

+70

+80

+90

+100

+110

+120

+130

+140

+150

+160

+170

+180

A R l R t Initial GDT Pressure-GDT Pressure verage e ease a e = ---~. ---'-· -------Time (Min)

Maintain Average Release Rate s; 1.0 psig/min by reducing 1 WG41 valve position. Average Release Rate at end of GDT release shall NOT exceed 1.0 psig/min (IA W the ODCM).



PLANT VENT FLOW RATE DISCHARGE ESTIMATION

1.0 ESTIMATEDFLOWRATE

NOTE

If Plant Vent Flow Rate Monitor is inoperable, Plant Vent Flow Rate shall be estimated at least once er four hours AW the ODC .

AUX BLDG EXHAUST # FHB EXHAUST PRESS RELIEF FANS IN SERVICE FANS IN SERVICE IN SERVICE

2 1 N

2 1 y

2 2 N

2 2 y

1.1 IF Plant Vent Flow Rate Monitor is inoperable, THEN RECORD estimated flow rate at least once every 4 hours.

S 1.0P-SO.WG-001 O(Q)

EST. PLANT VENT FLOW RATE

68,540 (SCFM)

70,940 (SCFM)

78,540 (SCFM)

80,940 (SCFM)

Time Date Estimated

Plant Vent Flow Rate

SCFM

SCFM

SCFM

SCFM

SCFM

SCFM


sl .OP-S0.WG-0010(Q)


COMPLETION SIGN-OFF SHEET

1.0 COMMENTS:

(Include procedure deficiencies and corrective actions.)


S 1.0P-SO. WG-001 O(Q)

ATTACHMENTS (Page 2 of 2)

COMPLETION SIGN-OFF SHEET

2.0 SIGNATURES:

Print Initials Signature Date

<[<, Ck (A."" <j<.. %~ Cht Ml s+rv C \..\ ~~ I

f/~~+ OfefL>-iv -po

/cJ J <A'(

1)£0 1- N'E.O j__ ~o~ I

INDEPENDENT VERIFICATION:

NGO Z.

3.0 SM/CRS FINAL REVIEW AND APPROVAL:

This procedure with Attachments 1-5 is reviewed for completeness and accuracy. All deficiencies, including corrective actions, are clearly recorded in the COMMENTS Section of this attachment.

Signature: __________________ _ Date: -----(SM/CRS)


STATION:

SYSTEM:

TASK:

TASK NUMBER:

JPM NUMBER:


SALEM


Classify an Event and Complete ICMF IAW EP-SA-111-101

1240020502

16-01 NRC SRO-A5

KIA NUMBER: G 2.4.41 ALTERNATE PATH: D ------------1 IMPORTANCE FACTOR:

APPLICABILITY:

EOD ROD STAD sRo[KJ

EVALUATION SETTING/METHOD: Classroom o I ~ "...G\'"''1

EP-SA-111-101, Rev. ~(checked 10-2-17) EP-SA-111-121, Rev 00

REFERENCES: EP-SA-111-F3, Rev 03

TOOLS AND EQUIPMENT: ECG Books

VALIDATED JPM COMPLETION TIME: 10 mins


Developed By: R. Chan f2J.J} cl,,._ lnstruc\'f; · c

Validated By: /l/lc-;rr_, rJ\ ~Ju i /Laf uJ!

SME or Instructor

Approved By: ~c-1:::_ LJA. f:t ~ Training Deg rtment, / ;1

Approved By: Pa.t\ N c -Av q"' ~ lief t O~r · ns Department



PERFORMED BY:




RO

15 mins

Date: 10-2-17

Date: •o ·-2 ·-17

Date:

Date: I o/ '-I/ t 7

DATE:

4.6 SRO

'---·----------------------------------' PSEG CONFIDENTIAL - Possession Requires Specific Permission from Nuclear Training

Page 1 of 11


JPM NUMBER: 16-01 NRC SRO-AS

Rev#

00

Date Description

10-2-17 Added revision history and simulator setup pages. Updated NI currents from Rev. 5 of REM dated 6/4/17. Editorial comments from IP 71111.11 FASA.


Validation Required

Yes

SYSTEM:

TASK:

TASK NUMBER:

SIMULATOR IC:





1240020502

N/A


OVERRIDES: N/A


• ENSURE copy of Attachment 3 (SAE).

• ENSURE copies of Attachments 2 (ALERT) and 4 (GE) ICMFs are available if requested. Note: these are the incorrect Attachments to use.

PSEG CONFIDENTIAL - Possession Requires Specific Permission from Nuclear Training Page3of11


NAME: ------------DATE:

SYSTEM: Emergency Plan - Administrative

TASK:

TASK NUMBER:


1240020502

INITIAL CONDITIONS:

• Salem 2 was manually tripped and Safety Injection Auto actuated due to a RCS lealc inside containment.

• The crew is implementing 2-EOP-TRIP-1.

• RCS pressure < 60 psig.

• RCS Subcooling is O degrees F.

• All ECCS pumps are running.

• Containment pressure is 35 psi and 21 Containment Spray pump failed to start. Attempts to start 21 CS pump from the control room are unsuccessful.

• 21 CFCU is C/T for cooler leak and 22 and 23 CFCUs failed to start in LOW SPEED. Attempts to start 22 and 23 CFCUs from the control room are unsuccessful.

• Meteorological data is as follows: Wind Direction: 180 degrees, Wind Speed: 5 mph

• 2R41 D, Plant Vent Release Rate, radiation monitor is NOT indicating elevated readings.

INITIATING CUE:


• CLASSIFY the event AND COMPLETE the ICMF JAW EP-SA-111-101 and appropriate EAL category flowcharts.

• THIS IS A TIME CRITICAL JPM.

• You will be giving 5 minutes to review the initial conditions. The time will stop when you have submitted the ICMF to the Lead Evaluator.








Task Standard for Successful Completion: 1. Classifies the event as Site Area Emergency (SAE) based on RB2.L and CB8.P. 2. Properly completes ICMF for the classified event.




Task: Classify an Event and Complete ICMF IAW EP-SA-111-101

cjrf:<'1:;t{,1:·.tsl2;,f;i11;) ,t?s"/:~::tt.~J~r::,:~{'1(,il\·:; \:' ·.::~·1t'«-:'.\ ::'~fr;,r : ·{+t' ....• c' ~;;r~~.l?~~q> 7:";':.;:".:;t :t0·1·/ .t(Shad~dar~a/denotes*Criti.caJ .•. step y~: ;;w ci, (Balded :are·a~identifi~s ;Task ,:;.'\ ';;c

'.1.'.e)J;yJ~jj~~!i~~f Jtfl1~~t\~~r~:~~r/:r::)l,; ·;·•·.·<:·.··.,• ... '··: ..• : ....• · .. •·••••; S!~naat~t)h'.:;:·t,rf •,<·it"··'··


• EP-SA-111-101,

• Salem 2 ECG books

CUE: I State to the Operator:

THIS IS A TIME CRITICAL JPM.

You will be giving 5 minutes to review the initial conditions. The time will stop when you have classified the event and submitted the ICMF to the Lead Evaluator.


START TIME: -------

Operator reviews initial conditions.

NAME: _________ _

DATE: _________ _





t~~i ttf tlMiiif ~f k fri;c:~1g:a?f f JOf ~f ;r:~1~~;: · <iLASSlFY'.'th~e~$n(/, I Operator classifies the event as Site

Area Emergency (SAE) based on Fission Product Barrier Table:

• RB2.L (5 pts) - Subcooling S 0 F (as a result of RCS leakage)

• CB8.P (2 pts) - Containment pressure> 15 psig AND EITHER of the following:

o One containment spray train in service AND < 3 CFCUs running in low speed.

• 7 points total for Site Area Emergency (SAE)

NAME:, __________ _

DATE: __________ _





CUE: I JPM is Complete.


STOP TIME: ------

.. ,/ .. •,,. ,S:rA~P~~p.,\. '..>:f'f ;(Balded . .area:,id~ntifi.es'Jaslt ....

•s.i .:"'. '.. st·' .. d ··'.· d·)·····t•.c;x;?" '.Yi• .. i• ..... ' an ar . : .. •·:· ·r , , .,, , ' :)c;:.::ft,,~>.\:,'.;',;,,~<,,.·~:~::.::j~;"';

Cue: Provide copy of EP-SA-111-F3, Attachment 3 (SAE) when requested.

Note: Attachments 2 (ALERT) and 4 (GE) ICMFs are available if requested.

Operator accurately and completely fills out the ICMF for Site Area Emergency IAW EP-SA-111-F3, Attachment 3.

See attached ANSWER KEY for complete and accurate ICMF.

Terminate JPM when operator submits the ICMF form.

NAME: ________ _

DATE: ---------


JPM #: 16-01 NRC SRO-AS




A- 1. Task description and number, JPM description and number are identified.

I Pft --j-- 2. Knowledge and Abilities (KIA) references are included.

-I!:-- 3. Performance location specified. (in-plant, control room, or simulator) +- 4. Initial setup conditions are identified.

+,- 5. Initiating and terminating Cues are properly identified .

• '/I~. n1 6. Task standards identified and verified by SME review.

- l\r\ --+-"-- 7. Critical steps meet the criteria for critical steps and are identified with an asterisk(*).

}i'ty 8. Verify the procedure referenced by this JPM matches the most current revision of ~ that procedure: Procedure Rev. ,3 Date I c /i. /1,

Iv~· 9. Pilot test the JPM: --r-- a. verify Cues both verbal and visual are free of conflict, and · b. ensure performance time is accurate.

_N_/P_1_ 10. If the JPM cannot be performed as written with proper responses, then revise the JPM.

fl.~.\

~ 11. When JPM is revalidated, SME or Instructor sign and date JPM cover page.

SME/lnstructor:~J.._/_?\afl __ _..,__,_~ ___

1

~tv1~,,:;\_~_\e=s_· _ Date: ---·---/0 .. "2-- - t --,

SME/lnstructor: Date: -------------- ------

SME/lnstructor: Date: -------------- ------


INITIAL CONDITIONS:

• Salem 2 was manually tripped and Safety Injection Auto actuated due to a RCS leak inside containment.

• The crew is implementing 2-EOP-TRIP-1.

• RCS pressure < 60 psig.

• RCS Subcooling is O degrees F.

• All ECCS pumps are running.

• Containment pressure is 35 psi and 21 Containment Spray pump failed to start. Attempts to start 21 CS pump from the control room are unsuccessful.

• 21 CFCU is C/T for cooler leak and 22 and 23 CFCUs failed to start in LOW SPEED. Attempts to start 22 and 23 CFCUs from the control room are unsuccessful.

• Meteorological data is as follows: Wind Direction: 180 degrees, Wind Speed: 5 mph

• 2R41 D, Plant Vent Release Rate, radiation monitor is NOT indicating elevated readings.

INITIATING CUE:


• CLASSIFY the event AND COMPLETE the ICMF IAW EP-SA-111-101 and appropriate EAL category flowcharts.

• THIS IS A TIME CRITICAL JPM.

• You will be giving 5 minutes to review the initial conditions. The time will stop when you have submitted the ICMF to the Lead Evaluator.


I.

INITIAL CONTACT MESSAGE FORM

EP-SA-111-F3 ATT3 Pg. 2 of 5

THIS IS , COMMUNICATOR IN THE~ CONTROL ROOM --------(NAME) 0 TSC

AT THE SALEM NUCLEAR GENERATING STATION, UNIT(s) No._2._

II. THIS IS NOTIFICATION OF AN SITE AREA EMERGENCY WHICH WAS

DECLARED AT N cW ON to Jo..'/ (Time - 24 HR CLOCK) (DATE) /

EAL# RS2. L css.P DESCRIPTIONOFEVENT: t-.~.ss of +k~ 'Re(lc+ov- Cso\~11\t-------~------------Sys+c.W\ 1s~v-v-1er, Po-f<-»f te\. ( £-c, SS of +I.H•_ Cen~fat~"'e.tf ts~r'V'l~Y'

Any release

0 THERE IS A RELEASE IN PROGRESS DUE TO THE EVENT } above normal, - attributable to the

k.f'THERE IS NO RELEASE IN PROGRESS DUE TO THE EVENT event. See Basis ~ - for examples .

111.

IV. 33 FT. LEVEL WIND DIRECTION (From): /BO WIND SPEED: .5 (From MET Computer /SPDS) (DEGREES) (MPH)

V. NO PROTECTIVE ACTIONS ARE RECOMMENDED AT THIS TIME

SGS

.SRO EC Initials:

(Approval to Transmit ICMF)

Rev. 03

STATION:

SYSTEM:

TASK:

TASK NUMBER:

JPM NUMBER:

ALTERNATE PATH:

SALEM


Control Rod Drive System (CRDS)

Respond to Loss of All Control Roci Drive Vent Fans IAW S2.0P-AR.ZZ-0011

0220040101

16-01 NRC Sim-a

K/ANUMBER: 001 A2.01 I X I ------------j IMPORTANCE FACTOR: 3.1

APPLICABILITY:

EoD ROCK] STAD SROCK]

EVALUATION SETTING/METHOD: Simulator/ Perform

REFERENCES: S2.0P-AR.ZZ-0011, Rev 60 (checked 9-10-17) S2.0P-SO.CBV-0001, Rev 33


VALIDATED JPM COMPLETION TIME:

Developed By:

Approved By:

~ q-18-ll 5 /jnin

Operations Department ~ _ ·Gt.--c. {f")? ~



PERFORMED BY:




RO

NIA

Date: 9-15-17

Date:

Date:

DATE:

PSEG CONFIDENTIAL- Possession Requires Specific Approval from Nuclear Training

3.7 SRO

JPM NUMBER:

Rev# Date

00 9-15-17


REVISION HISTORY

16-01 NRC Sim-a

Description

Added revision history and simulator setup pages. comments from IP 71111.11 FASA.

Validation Required

Editorial Yes



SYSTEM:



TASK:

TASK NUMBER:

Respond to Loss of All Control Rod Drive Vent Fans IAW S2.0P-AR.ZZ-0011

0220040101

SIMULATOR IC: IC-240

MALFUNCTIONS/ REMOTES:

1. Reset the simulator to IC-240 2. Ensure 21 and 22 CROM vent Fans are running. 3. Verify the following events on the Summary/ET Trigger Lists:

• RT-1 MALF: RD0316A CRD Vent Fan damper fails close.

• ET-1 KABOSPBR: Inserts MALF VC0316B: 22 CRD Fan Trip with 01:10 second delay; MALF VC0316C: 23 CRD Fan Trip with 01 :00 second delay.

4. These malfunctions will simulate the running CROM Vent Fan dampers closing resulting in air flow lo console alarm. IAW ARP, the standby fan will be started. Seconds later the standby fan trips followed by the last remaining running fan (no CROM Fans running). IAW ARP, the operator is required to TRIP the Reactor.

5. This completes the setup for this JPM.

OVERRIDES: None


• None.



NAME: ----------------DATE:

SYSTEM: Control Rod Drive System (CRDS)

TASK: Respond to Loss of All Control Rod Drive Vent Fans IAW S2.0P-AR.ZZ-0011.


INITIAL CONDITIONS:

• Unit 2 at 100% power.

• No equipment is out of service and no active Tech Specs are in effect.

INITIATING CUE:


• Respond to all alarms and indications.

Successful Completion Criteria: 1. All critical steps completed. 2. All sequential steps completed in order. 3. All time-critical steps completed within allotted time. 4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory


Task Standard for Successful Completion:

1. STARTS Standby CRDM Vent Fan IAW ARP based on abnormal console indications. 2. TRIPs the Reactor IAW ARP based on NO CRDM Vent Fans running.


SYSTEM:

TASK:

* STEP

# NO.

CUE

CUE

CUE


Control Rod Drive System (CRDS}

Respond to loss of All Control Rod Drive Vent Fans IAW S2.0P-AR.ZZ-0011

STEP STANDARD (Shaded area denotes Critical Step) (Bolded area identifies Task

(* Critical Steo) Standard)


START TIME:

Simulator Operator: INSERT RT-1 when the operator assumes the watch.

MALF: RD0361A 21 CRD Vent Fan Damper Failure

The following alarm and indication will come in Operator reports receipt of unexpected following RT-1 for 21 CRDM Vent Fan: console alarm on 21 CRD Vent Fan for

AIR FLOW LO and the SEQUENCE • AIR FLOW LO COMPLETE bezel extinguished. • SEQUENCE COMPLETE bezel

extinguished (NOT Illuminated) Operator refers to 2CC1 ARP.

Cue: IF operator reports to you as CRS the following alarms AND is waiting for direction; THEN state: CRS directs you to respond to alarms and indications !AW applicable Alarm Response Procedures.

The following steps are from Alarm Response Evaluator's Note: The operator may also Procedure (ARP) S2.0P-AR.ZZ-0011, refer to S2.0P-SO.CBV-0001, CONTROLCONS0LE2CC1 Containment Ventilation Operation,

section 5.4 for starting/stopping CRDM Vent Fans. However, this Qrocedure Qrovides NO direction for a loss of all CROM Vent Fans.

EVAL S/U



evaluation)

SYSTEM:

TASK:

* STEP

# NO.

2CC1 ARP pg 13

1.0

2.0

3.0 NOTE




STEP STANDARD (Shaded area denotes Critical Step) (Balded area identifies Task

(* Critical Steol Standard) CONTAINMENT VENTILATION SYSTEM Operator responds to console alarm for Rod Drive Vent Fans AIR FLOW LO and refers to 2CC1 ARP

S2.0P-AR.ZZ-0011 page 13. AIR FLOW LO

CAUSE(S): Operator reads the step and continues on.

Fan discharqe pressure < 2.0 INWC. AUTOMATIC ACTIONS: Operator reads the step and continues on.

None OPERATOR ACTIONS: Low flow alarm may result from erratic flow Operator reads the Note and continues on. during fan start. Illumination of control console SEQUENCE COMPLETE light indicates flow through fan outlet damper. Alarm should clear when fan is up to speed.

EVAL S/U

CAUTION Operating with less than two Rod Drive Vent Operator reads the Caution and Fans in service could degrade the Rod Drive determines this is not applicable at this Coils. An Operability Determination should be time, unless the standby fan does not performed when operating with one Rod Drive start. Vent Fan. Operating with more than two Rod Drive Vent Fans in service could damage the Operator continues on. fan blades.

Cue: IF operator informs CRS of Caution, THEN state: the CRS will review this Caution for potential Operability Determination requirements.



evaluation)

SYSTEM:

TASK:

* #

STEP NO.

3.1




STEP (Shaded area denotes Critical Step)

* Critical Ste IF Rod Drive Vent Fan has just been started, AND SEQUENCE COMPLETE indication is illuminated, THEN MONITOR both running Rod Drive Hdr Outlet temperatures.

Fan Comp Pt/ Alrm Description 21 T2602A / 160°F 21 Rod Drive Hdr Outlet Temp 22 T2603A / 160°F 22 Rod Drive Hdr Outlet Temp 23 T2604A / 160°F 23 Rod Drive Hdr Outlet Tern 1. F:SEpUE,NCE; COMPLETE indicatiO~Jor: ··. .. affected fan. is, extinguished TH EN· immediately

:'. sw1et<?:~pe' stahdby ~od.Drive.9ent.f:an/ . .

STANDARD (Bolded area identifies Task

Standard Operator reads the step and determines that a Vent Fan has NOT been started.

Marks step N/A and continues on.

Operator determines these steps are applicable based on the SEQUENCE COMPLETE indication bezel is extinguished.

Operator continues on and PERFORMs the applicable steps.

Evaluator's Note: It is acceptable for the operator to Stop and Start CRD Vent Fans usinq S2.0P-SO.CBV-0001. Operator depresses STOP PB for 21 Fan and verifies STOP bezel illuminates Green. Operator depresses ST ART PB for standby vent fan and verifies ST ART bezel illuminates RED. Operator reports SEQUENCE COMPLETE bezel is illuminated and AIR FLOW LO is extinCJuished as exeected.

EVAL SIU



evaluation

SYSTEM:

TASK:

* #

STEP NO.

CUE

3.2.C





* Critical Ste Simulator Operator: ENSURE ET-1 is TRUE when the standby fan is started. This will INSERT VC0316C and VC0316B to Trip the two (2) running Vent Fans after a time delay.

MALF VC0316C 23 CRD Fan Trip Delay= 01 :00 seconds MALF VC0316B 22 CRD Fan Trip Delay = 01: 10 seconds.

IF the standby fan can NOT be started, AND at least one Rod Drive Vent Fan is in operation, THEN PERFORM an Operability Determination to determine continued plant operation rsoo83830l. ALTERNATE PATH STARTS HERE:

:,if, there\are NO;Rod.bdve\JenFFansin \ ··operation.THEN~;

s-;.s•• '• • • 0 :, •.,~~••. ,•' .' t : > • ;• • ' • C )\' '


Standard

Operator marks step as N/A based on standby fan starting.

Operator initially marks this step as N/A based on standby fan starting.

This step will become applicable when the two (2) running vent fans trip shortly after.

Operator TRIPs the Reactor when NO Vent Fans are in operation.

Terminate the JPM when Rx is Tripped

Evaluator's Note: Performing EOPTRIP-1 immediate actions is not required to complete this JPM.

EVAL S/U



evaluation

SYSTEM:

TASK:

* STEP

# NO.

3.2.E

3.3

NOTE

3.3.A

3.3.B

3.4

3.5





(* Critical Step} Standard} IF at least one Rod Drive Vent Fan is in Operator determines this step is N/A and operation, THEN INITIATE a NOTF to continues on. determine and correct the cause of the low flow. SEND an operator to check the main and Cue: CRS will dispatch an operator to backup breakers closed for the affected fan. check the breaker positions for the main

and backup breakers for 21 CRD Vent Fan.

Main breakers are on 84', 460/230V Switchgear Operator reads the Note and continues on. Room IF a breaker is found tripped, Operator awaits report from field operator THEN INFORM the Unit 2 Control Room. and continues on.

21 Fan Main Bkr 2EX1AX5X Backup Bkr 2EX1AX5X-1 INITIATE a NOTF to determine and correct Operator awaits report from field operator cause of the breaker trip. and continues on. MONITOR running Rod Drive Hdr Outlet Operator monitors running Vent Fan Outlet tern perature( s). temperatures on the P250 computer.

Fan Comp Pt/ Alrm Description 21 T2602A / 160°F 21 Rod Drive Hdr Outlet Temp 22 T2603A / 160°F 22 Rod Drive Hdr Outlet Temp 23 T2604A / 160°F 23 Rod Drive Hdr Outlet Temp INITIATE a NOTF to determine and correct Operator informs CRS to initiate NOTF. cause of the of the low flow alarm

Cue: CRS will initiate the notification.

EVAL SIU



evaluation)

SYSTEM:

TASK:

* STEP

# NO.

CUE:





l* Critical Steo) Standard) JPM is complete when the task is complete Terminate the JPM when the operator

OR at the direction from the Lead TRIPs the Reactor.

Evaluator. Evaluator's Note: Operator performing immediate actions of EOP-TRIP-1 is not

RECORD the STOP TIME. required for this task.

STOP TIME:

EVAL S/U



evaluation)

JPM: 16-01 NRC Sim-a

OPERATIONS DEPARTMENT JOB PERFORMANCE MEASURE



~ 1. Task description and number, J PM description and number are identified.

~2. Knowledge and Abilities (KIA) references are included.

~ Performance location specified. (in-plant, control room, or simulator)

_...,,.....~-,,. Initial setup conditions are identified.

________ 5. Initiating and terminating Cues are properly identified.

~-Task standards identified and verified by SME review.

~~- Critical steps meet the criteria for critical steps and are identified with an asterisk(*).

~ 8. Verify the procedure referenced b~ ttA JPM matgrps the most current revision of /

1

/ that procedure: Procedure Rev. Cl Date J/1<'( / 1 }

v Y 9. Pilot test the JPM: ~ a. verify Cues both verbal and visual are free of conflict, and


TQ-AA-106-0303

t,,J / A

f\UA '

10@,e JPM cannot be performed as written with proper responses, then revise the JPM.

11. When JPM is revalidated, SME or Instructor sign and date JPM cover page.

rr~}t ~ SME/lnstructor:~~~_____,,..-----.,,=------4-~s~c...,.d.o--L-;_

SME/lnstructor:_~-------.2----1-_tl._V_.c4_,Jl"---'--

SME/lnstructor: -------------

Date:

Date: ------

Date: ------


INITIAL CONDITIONS:

• Unit 2 at 100% power.


• No equipment is out of service and no active Tech Specs are in effect.

INITIATING CUE:


• Respond to all alarms and indications.


s2.oP-AR.ZZ-0011 (Q)

SYSTEM CONTAINMENT VENTILATION SYSTEM Rod Drive Vent Fans

BEZEL 1-1 AIR FLOW

BEZEL 21 2E - 460V LO (22 2E - 460V) (23 2G - 460V)

21 Fan 22 Fan 23 Fan

DEVICES: 2FD-7662 2FD-7664 2FD-7666

SETPOINT: 2.0 INWC

1.0 CAUSE(S):

1.1 Fan discharge pressure < 2.0 INWC.

2.0 AUTOMATIC ACTIONS:

2.1 None

3.0 OPERATOR ACTIONS:

NOTE

Low flow alarm may result from erratic flow during fan start. Illumination of control console SEQUENCE COMPLETE light indicates flow through fan outlet damper. Alarm should clear when fan is up to speed.

CAUTION

Operating with less than two Rod Drive Vent Fans in service could degrade the Rod Drive Coils. An Operability Determination should be performed when operating with one Rod Drive Vent Fan. Operating with more than two Rod Drive Vent Fans in service could damaae the fan blades.

3.1 IF Rod Drive Vent Fan has just been started, AND SEQUENCE COMPLETE indication is illuminated, THEN MONITOR both running Rod Drive Hdr Outlet temperatures.

Fan Comp Pt / Alrm Description

21 T2602A I 160°F 21 Rod Drive Hdr Outlet Temp 22 T2603A I 160°F 22 Rod Drive Hdr Outlet Temp 23 T2604A I 160°F 23 Rod Drive Hdr Outlet Temp

(Continued) Page 1 of 2 1-1

Salem 2 Page 13 of 148 Rev.60

s2.oP-AR.ZZ-0011 (Q)

3.2 IF SEQUENCE COMPLETE indication for affected fan is extinguished THEN immediately SWAP to the standby Rod Drive Vent Fan,

A. PRESS STOP for affected Rod Drive Vent Fan

B. PRESS START for standby Rod Drive Vent Fan

C. IF the standby fan can NOT be started, AND at least one Rod Drive Vent Fan is in operation, THEN PERFORM an Operability Determination to determine continued plant operation [80083830).

D. lE there are NO Rod Drive Vent Fans in operation, THEN:

1. TRIP the Reactor

2. GO TO 2-EOP-TRIP-1, Reactor Trip or Safety Injection

E. IF at least one Rod Drive Vent Fan is in operation, THEN INITIATE a NOTF to determine and correct the cause of the low flow.

3.3 SEND an operator to check the main and backup breakers closed for the affected fan.

Main Bkr Backup Bkr

NOTE

Main breakers are on 84', 460/230V Switchgear Room.

21 Fan

2EX1AX5X 2EX1AX5X-1

22 Fan

2EX1AX14X 2EX1AX14X-1

23 Fan

2GX1AX5X 2GX1AX5X-1

A. lE a breaker is found tripped, THEN INFORM the Unit 2 Control Room.

B. INITIATE a NOTF to determine and correct cause of the breaker trip.

3.4 MONITOR running Rod Drive Hdr Outlet temperature(s).

Fan Comp Pt/ Alrm Description

21 T2602A I 160°F 21 Rod Drive Hdr Outlet Temp 22 T2603A I 160°F 22 Rod Drive Hdr Outlet Temp 23 T2604A I 160°F 23 Rod Drive Hdr Outlet Temp

3.5 INITIATE a NOTF to determine and correct cause of the of the low flow alarm. Page2of2 1-1

References: Dwg. 203591, 203592, 203593, 203594, 205338

Salem 2 Page 14 of 148 Rev.GO

STATION:

SYSTEM:

SALEM

OPERATOR TRAINING PROGRANI JOB PERFORi"'\1ANCE MEASURE

Chemical and Volume Control System (CVCS)

TASK: Perform Manual Makeup of the VCT !AW S2.0P-S0.CVC-0006

TASK NUMBER:

JPM NUMBER:

0040130101

16-01 NRC Sim-b

ALTERNATE PATH: K/A NUMBER: 004 A4.04 ----------1 MP ORT AN CE FACTOR: 3.2 3.6 APPLICABILITY:

EoC] RO[KJ STAC] SRO[KJ


REFERENCES: S2.0P-SO.CVC-0006, Rev. 25 (checked 8-24-17) S2.0P-AB.CVC-0001, Rev. 10 S2.RE-RA.ZZ-0012 Rev. 218



TIME PERIOD IDENTIFIED FOR TIME CRITDL s1T~P]j /) /)

Developed By: R. Chan ~~ ~<..,,-Instructor

Validated By: ~ ,r;2r p /AC(/lr!)fl/0 ~~~--c' ~M_E or Instructor 11 '

Approved By: No/\lt Rasse:.}J.J " If Training Department~ .... -/-i

Approved By: u~ Operations Department



PERFORMED BY:




RO SRO

N/A

Date: 9-8-17

Date:

Date:

Date:

DATE:


JPM NUMBER:

Rev# Date

00 9-8-17


REVISION HISTORY

16-01 NRG Sim-b

Description


Validation Required

Editorial Yes




SYSTEM: Chemical and Volume Control System (CVCS)

TASK: Perform Manual Makeup of the VCT IAW S2.0P-SO.CVC-0006



MALFUNCTIONS / REMOTES:

1. Reset the simulator to IC-241 2. The following malfunctions will be INSERTED when simulator is placed in RUN:

• RT-1 MALF CV0037 VCT LEVEL XMTR LT112 FAILS H/L, Final Value: 100.


OVERRIDES: None


• Drain down the VCT level to about 39%. • Make sure a marked up (partial procedure usage) of S2.0P-SO.CVC-0006 is available

for candidate. • Setup P250 on 2CC1 to CVCS system so operator can monitor VCT level using 2LT114.


OPERATOR TRAINING PROGRAM JOB PERFORl'1ANCE MEASURE

NAME: ----------------DATE: ----------------


TASK: Perform Manual Makeup of the VCT IAW S2.0P-SOCVC-0006.


INITIAL CONDITIONS:

• 100% power, MOL. RCS boron concentration is 900 ppm.

• The crew has entered S2.0P-AB.CVC-0001, Loss of Charging, due to VCT level channel 2L T112 failing high.

INITIATING CUE:


• The CRS has directed you to PERFORM a manual makeup of the VCT to RESTORE VCT level to 53% !AW S2.0P.SO.CVC-0006, Boron Concentration Control, Section 5.2, Manual Makeup Mode.

• All prerequisites are complete with no issues.

• P&Ls have NOT been reviewed.

• Boric Acid Storage Tank boron concentration is 6,700 ppm.




1. Initiates manual makeup to VCT and stops the makeup when directed.


SYSTEM:

TASK:

* STEP

# NO.

CUE:

CUE:

Pre-Reqs 2.0

P&Ls

5.2



Perform Manual Makeup of the VCT IAW S2.0P-SO.CVC-0006


(* Critical Step} Standard}

Provide the operator the initial conditions, marked up S2.0P-SO.CVC-0006, and initiating cue sheet.


START TIME:

PREREQUISITES 2.1 THRU 2.3 Cue: All prerequisites are completed SAT with no issues.

Precautions and Limitations 3.1 thru 3.22 Operator reviews all P&Ls.

MANUAL MAKEUP MODE N/A

EVAL S/U



evaluation}

SYSTEM:

TASK:

* STEP NO.





* Critical Ste OETERMINE;.BCJrfc>Acld Flov1:Setpoint from

· ,S2'.RE:--M:Zi~oq12: Figore(s);:1 OOA. 1QOC, :and. .}105'.a~ appUcable·;··ORaitalculatec(and'.verified ••

by the.CRS/STA, AND· RECORD Bbrit{Acid . . Fl,oi,vSetpoint>' < . . . ..·.


Standard Cue: If asked about Boric Acid Tank Boron concentration, state all required information given in Initiating Cue.

Cue:JE operator uses the current makeup boric acid flow setpoint as displayed on the control console, THEN CUE that the CRS directs you to perform Step 5.2.1 to verify the Boric Acid Flow setpoint is correct.

Evaluator's Note; Correct Figure to Use is 1 OOA for 62 gpm Primary Water Flow with BAST concentration at normal ppm. 1 DOC is wrong figure because it is for 9000 ppm boron which is not used during normal ops. Figure 105 is the correction factor for RCS temperatures less than 547, which is N/A at 100% power.

If operator uses the graph; then setpoint is about 10 gpm.

If operator calculates; then setpoint is 9.6 gpm.

Operator determines setpoint between 9-11 gpm.

Evaluator's Note: If operator performs calculation using 900 ppm in RCS and 6,700 ppm in BAST, result is 9.62 gpm. Boric Acid flow setter is in 1 gallon increments.

EVAL S/U

COMMENTS {Required for UNSAT

evaluation

SYSTEM:

TASK:

* #

STEP NO.

5.2.2




STEP {Shaded area denotes Critical Step)

* Critical Ste IF required, THEN RESET COUNT A on the Makeup Flow Registers to zero IAW Exhibit 1.

PRESS Makeup Control Mode SelectSTOP pllshblltt~n/' . .


Standard Resets COUNT A for Boric Acid and Primary Water flow IAW Exhibit 1.

Presses Makeup Control Mode Select STOP pushbutton and verifies bezel illuminates. Depresses 2CV179 MANUAL PB until bezel illuminates.

Depresses 2CV179 CLOSE PB until bezel illuminates. Depresses 2CV172 MANUAL PB until bezel illuminates.

Depresses 2CV172 CLOSE PB until bezel illuminates.

Operator reads and initials the Note.

Operator selects one (1) flowpath alignment by depressing the MANUAL PB until bezel illuminates, THEN the OPEN PB for 2CV185 or 2CV181 until OPEN bezel illuminates.

Evaluator's Note: The "NOTE" prior to Step 5.2.6 states that charging pump suction is the preferred path, (but not required) which is accomplished by opening the 2CV185. Opening either 2CV185 or 2CV181 is acceptable.

EVAL S/U



evaluation



TASK: Perform Manual Makeup of the VCT IAW S2.0P-SO.CVC-0006

* #

STEP NO.

STEP (Shaded area denotes Critical Step}

* Critical Ste CAUTION I Pump damage may occur while operating in a

parallel configuration IF both a Fast and Slow speed Boric Acid pump is aligned to the same header. PERF.ORM the following as required to sopport

· .. Currenfplanf conditions: ,::.:,:-,f'--:'~': ' ''.', :',>.>" '>>

~·,:·sr~~+;Prfrnary W~~~f P.~:;.~ : ·. · PLACE a BorlcAcid Pump in

MANUAL/FAST START


Standard Operator reads the Caution Note

Evaluator's Note: Normal configuration is ONE Boric acid pump running in AUTO SLOW, and NO Primary Water pumps running.

Operator depresses MANUAL PB for selected PW pump and verifies bezel illuminates.

Operator depresses ST ART PB for selected PW Pump and verifies bezel illuminates.

Operator depresses MANUAL PB for selected BAT pump and verifies bezel illuminates.

Operator depresses FAST START PB for selected BAT Pump and verifies bezel illuminates.

Adjusts Boric Acid Flow on Fl110A to the value recorded in Step 5.2.1 by depressing the 2CV172 OPEN PB to raise setpoint or 2CV172 CLOSE PB to lower setQoint.

EVAL S/U



evaluation

SYSTEM:

TASK:

* #

STEP NO.

5.2.9

5.2.11





* Critical Ste IF required Boric Acid flow is NOT achieved, THEN:

• CLOSE 21CV160, RECIRC VALVE • CLOSE 22CV160, RECIRC VALVE •

ManuaHy ADJUST 2CV179. Setpoint.to 62 gpm· ... . (or as. calculateq)to .obtain. the requiredflow as

indicated on FIH1A(Refer to step 3;12) "·' . --:' " .-, " ... ,, '"

ENSURE required Boric Acid AND Primary Water Flow are being maintained OR ADJUST 2CV1 72 and 2CV179 as required to obtain required flows.


Standard Determines closing of the CV160 valves will NOT be required.

Adjusts Primary Water flow on Fl111 A to 62 gpm (acceptable range 60-64 gpm) by depressing the 2CV179 OPEN PB to raise setpoint or 2CV179 CLOSE PB to lower setpoint.

Cue: Once makeup is in progress and operator is monitoring VCT level via LT-114 using the Plant Computer, inform operator that VCT level is now at 53%.

Monitors Boric Acid and Primary Water flows being maintained as required and adjusts 2CV172 and 2CV179 as required to obtain required flows.

EVAL S/U



evaluation

SYSTEM:

TASK:

* STEP NO.

CUE:



Perform Manual Makeup of the VCT IAW $2.0P-SO.CVC-0006


* Critical Ste :>When desired makeup ,is completed: ·

'"' , , '_., .,·". '"., >. • . ·- ' "' . '·· 'i ,,\·"··- . . ·. ' . . '

". .' ' ~- ;>, •,'( 'C· ,,v.'/. • • '.' ".· /! • ,• ··}· '

.. PLACEc'6oricl\t:id Purnp selectedJn :sLOY{,Speed , , ·;/ ;:, ·. ·· , · · ··

JPM is Complete.

RECORD STOP TIME

STOP TIME: ------


Standard

Depresses the CLOSE PBs for 2CV179 and 2CV172, and whichever of the 2CV185 or 2CV181 was opened in Step 5.2.6; verifies that the CLOSE PB bezels are illuminated.

Depresses STOP pushbutton for Primary Water Pump which was started.

Places the selected Boric Acid Pump in SLOW speed and verifies SLOW speed bezel illuminates.

Terminate the JPM once the selected Boric Acid Pump has been placed in SLOW s_eeed. Terminate the JPM when the Boric Acid Pump is in SLOW speed.

EVAL S/U



evaluation

JPM: 16-01 NRC Sim-b




-£. Task description and number, JPM description and number are identified.

_z 2. Knowledge and Abilities (KIA) references are included.

~ 3. Performance location specified. (in-plant, control room, or simulator)

-h 4. Initial setup conditions are identified.

-h- 5. Initiating and terminating Cues are properly identified.

~ 6. Task standards identified and verified by SME review.

?. Critical steps meet the criteria for critical steps and are identified with an asterisk(*).

8. Verify the procedure referenced b~tp.is JPM ma~,es re most current revision of that procedure: Procedure Rev. :J Date / a>q

. Pilot test the JPM: a. verify Cues both verbal and visual are free of conflict, and b. ensure performance time is accurate.

TQ-AA-106-0303

Ni A 10. If the JPM cannot be performed as written with proper responses, then revise the JPM.

/VJ ~ 11. When JPM is revalidated, SME or Instructor sign and date JPM cover page.

SME/lnstructor: ____________ _ Date: ------


INITIAL CONDITIONS:


• 100% power, MOL. RCS boron concentration is 900 ppm.

• The crew has entered S2.0P-AB.CVC-0001, Loss of Charging, due to VCT level channel 2L T112 failing high.

INITIATING CUE:


• The CRS has directed you to PERFORM a manual makeup of the VCT to RESTORE VCT level to 53% !AW S2.0P.SO.CVC-0006, Boron Concentration Control, Section 5.2, Manual Makeup Mode.

• All prerequisites are complete with no issues.

• P&Ls have NOT been reviewed.

• Boric Acid Storage Tank boron concentration is 6,700 ppm.


STATION:

SYSTEM:

TASK:

TASK NUMBER:

JPM NUMBER:

SALEM


Emergency Core Cooling System (ECCS)

Isolate the ECCS Accumulators IAW EOP-TRIP-6

1150070501

16-01 NRC Sim-c

ALTERNATE PATH: I X I K/A NUMBER: 006 A1.13 ------------! IMPORTANCE FACTOR: 3.5 3.7

APPLICABILITY:

EOLJ ROITJ STAD SRO[KJ


REFERENCES: 2-EOP-TRIP-6 Rev. 30 (checked 9-29-17)


VALIDATED JPM COMPLETION TIME: 8 Minutes


Developed By: R. Chan ~ ~ () / ~ Instructor

Validated By: \....Z) ( L b, M~ ~'j ~ 1,_/ ~ME or lnstrwc~ "Z;?10 Im /3ttc.; ~AJ fq'J ""--l ,-.:l r J7

Approved By: £, Training Department u M-ffl,,

Approved By: Operations Department



PERFORMED BY:




RO SRO

NIA

Date: 9-29-17

Date: 9/i.,/,,.

Date: i(i 3/1, Date:

i ij13/ 17

DATE:

PSEG CONFIDENTIAL-Possession Requires Specific Permission from Nuclear Training Page 1 of 9


REVISION HISTORY

JPM NUMBER: 16-01 NRC Sim-c

Rev#

00






SYSTEM: Emergency Core Cooling System (ECCS)

TASK: Isolate the ECCS Accumulators IAW EOP-TRIP-6




1. Reset the simulator to IC-242 (IC219 used as baseline) 2. Note: The following were used to setup plant conditions: MALFS RC0003A/B/C/D to trip all

RCPs. Performed EOP's to TRIP-6, Step 12, SI ACCUM ISOLATION.

OVERRIDES:

1. Ensure Override A303 B DI (KA3030CL): 24SJ54 Accumulator Outlet Close to Override OFF


1. ENSURE SPDS on Press/Temp Display 2. ENSURE RCS T-colds on trend on P250 on 2CC1. 3. Marked up copy of 2-EOP-TRIP-6 on center console.



NAME: ---------------DATE:

SYSTEM: Emergency Core Cooling System (ECCS)

TASK: Isolate the ECCS Accumulators IAW EOP-TRIP-6


INITIAL CONDITIONS:

• A reactor trip occurred when a 500 KV grid perturbation occurred, which also caused all RCPs to trip.

• The operating crew has progressed through the EOP's and is now in 2-EOP-TRIP-6, NATURAL CIRCULATION RAPID COOLDOWN WITH RVLIS.

• The RCPs will NOT be restarted.

INITIATING CUE:


• The CRS directs you to isolate the SI Accumulators IAW Step 12 of 2-EOP-TRIP-6, NATURAL CIRCULATION RAPID COOLDOWN WITH RVLIS.

• Notify the CRS when Step 12 is completed.

• Your evaluator will take care of all alarms not related to your task.

Successful Completion Criteria: 1. All critical steps completed. 2. All sequential steps completed in order. 3. All time-critical steps completed within allotted time. 4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is

being made.

Task Standard for Successful Completion: 1. Closes 21, 22, and 23 SJ54's. 2. Vents 24 SI Accumulator to atmospheric pressure.


SYSTEM:

TASK:

* #

STEP NO.

CUE:

12

12.1

12.1

Contd




(* Critical Step) t# ?_~guential Critic:aJ _St~J>}

2-EOP-TRIP-6 is open and marked up on console.



IS RCS PRESSURE <1000 PSIG

REMOVE LOCKOUT FROM 21-24SJ54 ACCUMULATOR OUTLET VALVES

ALTERNATE PATH STARTS HERE:

ARE 21 Thru 24 SJ54 CLOSED



STANDARD (Bolded area identifies Task Standard)

Reviews conditions and the marked up EOPTRIP-6 Natural Circ Cooldown With RVLIS

YES. Operator verifies RCS pressure is <1000 psig.

At 2RP4 Panel, operator selects VALVE OPERABLE on 21-24 SJ54 ACCUMULATOR OUTLET VALVES LOCKOUT Switch

Operator depresses CLOSE pushbuttons for 21 thru 24 SJ54s, ACCUMULATOR OUTLET VALVES and verifies each CLOSE bezel illuminates.

NO. Operator determines 24SJ54, ACCUMULATOR OUTLET VALVE, is OPEN. May re-check LOCKOUT Switch position or attempt to depress the Close PB again.

NAME:

DATE:

EVAL S/U


-----------


evaluation)

SYSTEM:

TASK:

* #

STEP NO.

12.2




(* Critical Step) f!!_ SeqLJ_ential Critical Step)

IF an accumulator cannot be isolated or vented, then consult the TSC to determine contingency actions

·•' VENTANY;'.AF,"FECTED 1ACCUMULATORS: :- ,,"

.MAtNT/.\IN RCSf:RESSU~E / ... GREATERTHAN ACCUMULATOR NITROGEN F?RESSURE · .



STANDARD (Balded area identifies Task Standard)

Cue: CRS will consult with TSC if needed.

Operator verifies RCS Pressure is > Accumulator pressure.

Operator depresses OPEN PB for 2NT35 (N2 HDR VALVE) until OPEN bezel illuminates.

Note: If 2NT35 is throtled opened, this may be acceptable so long as Accumulator pressure is sufficiently lowering in next step.

Operator depresses OPEN PB for 24SJ93 N2 SUPPLY VALVE until OPEN bezel illuminates and observes 24 Accumulator pressure lowering.

NAME:

DATE:

EVAL S/U


----------


evaluation)

SYSTEM:

TASK:

* #

STEP NO.




(* Critical Step) (# Sequential Critical Step)

· .• h' 1/VHEN '.ACCt.JM'CJtATORVENTING •:, COMPLETE, THEN'CLOSE/ .

" =;' A',,' '

JPM is Complete


STOP TIME: ------




When the operator checks that Accumulator pressure is lowering, THEN, provide the following cue:

Cue: 24 Accumulator has been completely vented and 24 Accumulator pressure is now reading ZERO.

Note: These valves can be closed in any order.

Operator depresses CLOSE PB for 2NT35 N2 HOR VALVE until bezel illuminates.

Operator depresses CLOSE PB for 24SJ93 N2 SUPPLY VAL VE until bezel illuminates.

Terminate JPM.

Terminate the JPM when the step 12.3 is complete.

NAME:

DATE:

EVAL S/U


----------


evaluation)


JPM#: 16-01 NRC Sim-c


~h tM bf'\ tM

DM tM DM ~h

1. Task description and number, JPM description and number are identified.

2. Knowledge and Abilities (KIA) references are included.

3. Performance location specified. (in-plant, control room, or simulator)

4. Initial setup conditions are identified.

5. Initiating and terminating cues are properly identified.

6. Task standards identified and verified by SME review.

7. Critical steps meet the criteria for critical steps and are identified with an asterisk(*).

8. Verify the procedure referenced by this JPM matches the most current revision of that procedure: Procedure Rev. 3D.___ Date 'th.1/ 1 "1

J)M 9. Pilot test the JPM: a. verify cues both verbal and visual are free of conflict, and

,. b. ensure performance time is accurate. I 'b,.., "'rzv, 1-

IJ IA ~ 10. If the JPM cannot be performed as written with proper responses, then revise the JPM.

tJ f & 11. When JPM is revalidated, SME or Instructor sign and date JPM cover page.

SME/lnstructor: Date: 0, /2f1/, t SM E/1 nstructor: Date: i':l,q-J)

Date: 1l i~d(7

PSEG CONFIDENTIAL-Possession Requires Specific Permission from Nuclear Training Page 8 of9

INITIAL CONDITIONS:

• A reactor trip occurred when a 500 KV grid perturbation occurred, which also caused all RCPs to trip.

• The operating crew has progressed through the EOP's and is now in 2-EOP-TRIP-6, NATURAL CIRCULATION RAPID COOLDOWN WITH RVLIS.

• The RCPs will NOT be restarted.

INITIATING CUE:


• The CRS directs you to isolate the SI Accumulators IAW Step 12 of 2-EOP-TRIP-6, NATURAL CIRCULATION RAPID COOLDOWN WITH RVLIS.

• Notify the CRS when Step 12 is completed.

• Your evaluator will take care of all alarms not related to your task.


STATION:

SYSTEM:

TASK:

TASK NUMBER:

JPM NUMBER:

ALTERNATE PATH:

SALEM


Reactor Coolant System

Initiate Feed and Bleed using Reactor Head Vents IAW EOP-FRHS-1

N1150290501

16-01 NRC Sim-d

K/ANUMBER: 002 A2.04 I X I ----------1 MP ORT AN CE FACTOR: 4.3 -----

APPLICABILITY: RO

EoO Rom STAD SRom

EVALUATION SETTING/METHOD: Simulator/ Perform 1'1 Jl-ll ... 17 17-

REFERENCES: 2-EOP-FRHS-1, Rev )8'(checked 11-8-17)



TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: ~

Developed By: R. Chan ~ NIA

Date: 11-8-17 Instructor

r:;· Qi.."-. Validated By: 1 ~it Date:

SME or Instructor

Approved By: ~ ff; T

. . D _/J( rammg epartment

Approved By: Date: Operations Department



PERFORMED BY:




PSEG CONFIDENTIAL- Possession Requires Specific Approval from Nuclear Training Page 1 of 9

4.6 SRO

STATION:

SYSTEM:

TASK:

TASK NUMBER:

JPM NUMBER:

ALTERNATE PATH:

SALEM




N1150290501

16-01 NRG Sim-d

K/ANUMBER: 002 A2.04 I X I _________ ___,

IMPORTANCE FACTOR: 4.3 APPLICABILITY:

EoO RO[Ll STAD SRO[Ll


REFERENCES: 2-EOP-FRHS-1, Rev 33 (checked 11-8-17)



TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS~

Developed By: R. Chan ~ Instructor

Validated By: SME or Instructor

Approved By: Training Department

Approved By: Operations Department



PERFORMED BY: GRADE: D SAT D UNSAT



-----RO

N/A

Date: 11-8-17

Date:

Date:

Date:

DATE: ti f-2{;1


4.6 SRO


JPM NUMBER:

REVISION HISTORY

16-01 NRC Sim-d

Rev#

00

01



11-13-17 Deleted malfunction for 2PR1 not opening in manual and Yes changed initial conditions that three (3) SG WR levels are less than 32% for Bleed and Feed criteria !AW new revision to 2-EOP-FRHS-1 (Rev. 34).




SYSTEM: Reactor Coolant System

TASK: Initiate Feed and Bleed using Reactor Head Vents IAW EOP-FRHS-1




1. Reset the simulator to IC-243 2. Verify the following events on the Summary/ET Trigger Lists:

• MALF: AF0181 B 22 AFW pump trip

• MALF: AF0183 23 AFW pump trip

• MALF: RP0247 False FW Isolation

• 21 AFW pump C/T.

3. Ensure three (3) SG WR levels are less than 32% to meet Bleed and Feed criteria.


OVERRIDES:

• 8202 E DI 2PR2 Open PB Override OFF


• ENSURE four ( 4) Reactor Head Vent keys are available for the evaluator. • Extra Instructor to respond to the alarms. • Consider leaving the Rx Head Vent Keys in the key switch to prevent damage.



NAME:

DATE:

SYSTEM: Reactor Coolant System

TASK: Initiate Feed and Bleed using Reactor Head Vents IAW EOP-FRHS-1


INITIAL CONDITIONS:

• Unit 2 was manually tripped at 90% power due to elevated main turbine vibrations IAW S2.0P-AB.TL-0001.

• An inadvertent feedwater isolation actuation occurred resulting in the loss of all main feedwater.

• Loss of all AFW flow occurred when all AFW pumps tripped.

• The crew has entered 2-EOP-FRHS-1 due to valid RED Path on Heat Sink CFST based on all SG NR levels < 9% and AFW flow< 22E4 lbm/hr.

• Plant conditions have continued to deteriorate and three (3) steam generator Wide Range levels are now less than 32%.

• The CRS is implementing the CAS action to Initiate Bleed and Feed.

INITIATING CUE:


• The CRS has directed you to Initiate Bleed and Feed starting at Step 21 IAW 2-EOP-FRHS-1, Response to Loss of Secondary Heat Sink.

• Your evaluator will respond to all alarms not related to your task.




1. OPENS 2RC40 thru 2RC43 Reactor Head Vents IAW 2-EOP-FRHS-1.


SYSTEM:

TASK:

* #

STEP NO.

CUE

CUE

Step 21

Step 21 Contd.

Step 23

Step 23.1

Step 23.1

Contd.





* Critical Ste


START TIME: -------The following are Steps from 2-EOP-FRHS-1, Response to Loss of Secondary Heat Sink.

CAUTION

To establish RCS Het Sink Removal by RCS Bleed and Feed , Steps 24 thru 29 Must Be Performed Quickly and Without Interruption.

STOP ALL RCPs

Are SI Valves in Safeguards Position

Is 21 or 22 Charging Pump Running

Is BIT Flow Established


Standard

Operator reads the Caution and continues on.

Operator verifies that all RCPs are already Stopped. (Step 7 of FRHS-1 stopped RCPs Operator initiates SI on both Trains by inserting key and turning switch clockwise until the SI Operate bezel illuminates and the SI Reset bezel extinguishes. Note: Operator only needs to initiate SI on one Train. YES. Operator checks that all SI valve bezels on 2RP4 are illuminated. YES. Operator reports that both Charging pumps are running as indicated by ST ART bezels illuminated Red. YES. Operator reports BIT flow is established by indication of flow on Charging flowmeter. (During validations flow was about 150-160 qpm

EVAL S/U



evaluation

SYSTEM:

TASK:

* STEP

# NO.

Step 23.2

Step 23.2

Contd.

Step 23.2

Contd. Step 24

Step 24

Contd.

Step 24.1





(* Critical Step) Standard) Is any SI Running YES. Operator reports that both SI pumps

are running by START PBs illuminated Red.

Are Valves in Table C Open for At Least One YES. Operator verifies that all valves are Running SI Pump OPEN in Table C for both running SI

pumps as indicated by valve OPEN bezels illuminated.

Are All Charging and SI Pumps Running And YES. Operator identifies that all Charging Aligned to Deliver Flow and SI Pumps are running and the valves

are in the safequards positions. Open Both PZR PORV Stop Valves Operator reports that both PZR PORV

Stop Valves are OPEN as indicated by 2PR6 and 2PR7 OPEN bezels illuminated.

[ALTERNATE PATH STARTS HERE:]

Open Both PZR PORVs Operator places both PZR PORVs in Manual and depresses OPEN PBs for 2PR1 and 2PR2.

Operator reports that 2PR2 will NOT OPEN.

Note: The PZR PORVS may be cycling during this time. The operator should determine that both PORVs are required to be fully open in Manual and not credit auto operation.

Are Both PZR PORV Stop Valves Open YES. Operator reports both 2PR6 and 2PR7 are open as indicated by OPEN bezels illuminated.

EVAL SIU

PSEG CONFIDENTIAL- Possession Requires Specific Approval from Nuclear Training Page 6 of9


evaluation)

SYSTEM:

TASK:

* #

STEP NO.

CUE:





* Critical Ste Are Both PZR PORVs Open

JPM is Complete


STOP TIME: _____ _


Standard NO. Operator reports that 2PR2 will NOT OPEN.

Cue: Lead Evaluator needs to provide the four ( 4) keys to the Operator.

At the 2RP2 backpanel, Operator obtains keys and inserts key into each keyswitch one at a time and turns clockwise until the OPEN bezel illuminates.

Terminate JPM when 2RC40 Thru 2RC43 are open.

Terminate the JPM when the operator OPENS 2RC40 Thru 2RC43.

EVAL S/U



evaluation


JPM: 16-01 NRC Sim-d



~ ______ 1. Task description and number, JPM description and number are identified.

/! 2. Knowledge and Abilities (KIA) references are included.

A 3. Performance location specified. (in-plant, control room, or simulator) T 4. Initial setup conditions are identified.

~ 5. Initiating and terminating Cues are properly identified.

1L 6. Task standards identified and verified by SME review.

A 7. Critical steps meet the criteria for critical steps and are identified with an asterisk(*).

~ 8. Verify the procedure referenced by this JPM matches the most current revision of r that procedure: Procedure Rev. __ Date

L 9. Pilot test the JPM: a. verify Cues both verbal and visual are free of conflict, and b. ensure performance time is accurate.

TQ-AA-106-0303

___ /_ 10. If the JPM cannot be performed as written with proper responses, then revise the JPM.

____ 11. When JPM is revalidated, SME or Instructor sign and date JPM cover page.

SME/lnstructor ~~ ~d ~Ll $ME/Instructor: Gusrll-.,vO OL_.<.,\ {M-,u·1-----·

Date: (llfz.o1t Date: __ I i_· _'3_·_:J.. _ _._,_T_



INITIAL CONDITIONS:


• Unit 2 was manually tripped at 90% power due to elevated main turbine vibrations IAW S2.0P-AB.TL-0001.

• An inadvertent feedwater isolation actuation occurred resulting in the loss of all main feedwater.

• Loss of all AFW flow occurred when all AFW pumps tripped.

• The crew has entered 2-EOP-FRHS-1 due to valid RED Path on Heat Sink CFST based on all SG NR levels < 9% and AFW flow < 22E4 lbm/hr.

• Plant conditions have continued to deteriorate and three (3) steam generator Wide Range levels are now less than 32%.

• The CRS is implementing the CAS action to Initiate Bleed and Feed.

INITIATING CUE:


• The CRS has directed you to Initiate Bleed and Feed starting at Step 21 IAW 2-EOP-FRHS-1, Response to Loss of Secondary Heat Sink.

• Your evaluator will respond to all alarms not related to your task.


STATION:

SYSTEM:

SALEM


Main Turbine Generator System

TASK: Synchronize the Main Generator IAW S2.0P-SO.TRB-0001.

TASK NUMBER:

JPM NUMBER:

N0450040101

16-01 NRC Sim-e

ALTERNATE PATH: K/A NUMBER: 045 A4.02 -------------1 IMPORTANCE FACTOR: 2.7 2.6


EOLJ RO[ZJ STALJ SRO[ZJ


REFERENCES: S2.0P-SO.TRB-0001, Rev 46 (checked 9-29-17)



TIME PERIOD IDENTIFIED FOR TIME CRl~AL 7Tf Pf ceu N/A

Developed By: R. Chan , j~ '- ~ate: -29-17

()_ sa Instructor "!). /'A-c--X e I~ Validated By: '-Ol'---0--. /r;t)C) 9-~q .... 17 ate: f /2"1/11-

SME or Instructor

Approved By: Training Department

Date: ,f 3 (r 7

Approved By: Date: Operations Department



PERFORMED BY: GRADE: D SAT D UNSAT





JPM NUMBER:

REVISION HISTORY

16-01 NRC Sim-e

Rev#

00






SYSTEM: Main Turbine Generator System

TASK: Synchronize the Main Generator IAW S2.0P-SO.TRB-0001




1. Reset the simulator to IC-244 2. No malfunctions inserted for this JPM. 3. Plant setup:

a. Turbine at 1800 rpm, Setter at 1801 b. Rx power at 16% c. Steam dumps in MS set about 960 psi d. Generator excitation completed IAW S2.0P-SO.TRB-0001, 4.4. VR set at 2092 amps

4. This setup will ensure that the turbine is rotating too slowly and INCOMING voltage is< 3 KV required to enable Synch Check relay.


OVERRIDES: None


• ENSURE sufficient copies of marked up procedure S2.0P-SO.TRB-0001. • At the Lead Evaluator's discretion; providing a marked up copy to the operator next in line

could save time by allowing time to read all the Precautions and Limitations and Section 4.5. • ENSURE Main Turbine and Generator parameter screens are open on P250 on 2CC2

console.



NAME: ----------------DATE: ----------------


TASK: Synchronize the Main Generator IAW S2.0P-SO.TRB-0001.


INITIAL CONDITIONS:

• Unit 2 is at 16% power starting up from a maintenance outage.

• The crew is performing power ascension activities IAW S2.0P-IO.ZZ-0003, Hot Standby to Minimum Load.

• The main turbine is at 1800 rpm with generator excitation applied.

INITIATING CUE:

• You are the Plant Operator.

• The CRS has directed you to synchronize the Generator IAW S2.0P-SO.TRB-0001, Turbine-Generator Startup Operations, Section 4.5, Synchronizing the Generator.

o All Prerequisites are completed SAT.

o Step 4.5.1 IVs are completed SAT.

o Synchronize the Generator starting at Step 4.5.2. The 500 KV 1-9 breaker will be closed first followed by the 500 KV 9-10 breaker.




1. Synchronizes the Generator to the electrical grid IAW S2.0P-SO.TRB-0001.


SYSTEM:

TASK:

* STEP

# NO.

CUE

4.5.2

4.5.3

4.5.4

4.5.5



Synchronize the Generator IAW S2.0P-SO.TRB-0001


(* Critical Step) Standard)


START TIME:

The following steps are from S2.0P-SO.TRB-0001, Turbine-Generator Startup Operations ENSURE 500 KV BUS SECT 9-10 (30X) Operator verifies 9-10 Breaker is Selected Breaker SELECTED to 9-10 to 9-10 LOCAL. LOCAL. At 2RP6, SELECT NO. 2 UNIT SCOPE Operator verifies that REGULAR SCOPE TRANSFER Switch to either is illuminated on 2PR6. REGULAR SCOPE or SPARE SCOPE position. MONITOR selected synchroscope while performing the following:

1. PRESS SCOPE TEST pushbutton on 500KV Operator depresses SCOPE TEST. BREAKER SECTIONS 1-9 (32X) Bezel.

2. ENSURE synchroscope hand indicates 12 Operator verifies synchroscope hand o'clock. indicates 12 o'clock.

3. ENSURE INCOM KV and RUN KV Operator verifies that the INCOM KV and Voltmeters both respond by moving upscale. RUN KV voltmeters move upscale.

4. RELEASE SCOPE TEST pushbutton. Operator releases SCOPE TEST PB.

ENSURE that MAIN GEN SYNC PERM Operator verifies MAIN GEN SYNCH BYPASS keylock switch is in the PERM BYPASS keylock switch is in the NORMAL position. NORMAL position.

EVAL S/U



evaluation)

SYSTEM:

TASK:

* STEP NO.

4.5.7





* Critical Ste IF 500KVBUS SECT.1-9 (32X)Breaker is ~vailable,THEN: .. . . .

. ·1. SELECT tim~ e·us 500KV BUS SECT..1-:9 . BREAKER 32X. .

a, ENSURE Mimic Bus pushbuttrin back light . is,yellqw.''i; . . ..

.. ,

, b .. ENSURE'.;,1~9 MIMIC BLJS'.INl"E~LOCK· .. . ;'.tC.&OS,E SELECTION bezel. back light i.~. lit.

2·. SELECT·1E9 SYNCH.POTON. ·

IF 500KV BUS SECT. 1-9 (32X) Breaker is NOT available, THEN:

1. SELECT Mimic Bus 500KV BUS SECT. 9-10 BREAKER 30X.

a. ENSURE Mimic Bus pushbutton back light is yellow.

b. ENSURE 9-10 (30X) bezel MIMIC BUS INTLK CLS SEL is lit.

2. SELECT 9-10 SYNCH POT ON.


Standard Operator determines that the 500 KV 1-9 breaker will be closed first from the Initiating Cue sheet.

Operator depresses 1-9 Mimic Bus PB and verifies the Mimic Bus PB illuminates yellow AND the console bezel for the MIMIC BUS 1-9 INTERLOCK CLOSE SELECTION is illuminated.

Operator depresses the 1-9 SYNCH POT ON and verifies bezel illuminates.

Operator determines Step is N/A since both 1-9 and 9-10 breakers are available and continues on.

EVAL S/U



evaluation



TASK: Synchronize the Generator IAW S2.0P-SO.TRB-0001

* STEP NO.

NOTE

CAUTION


* Critical Ste . ADJUST lNCO.M K\/ (Generator Output .voltage) to 3 -5KVgreater than, .... '.RUN KV (Line Voltage).;

NOTE 1. The following parameters should be closely monitored when closing the generator output breaker: Cl Steam Dump Valve Demand Cl Reactor Power IJ RCS Pressure 11 S/G Steam Flow

CAUTION The T-Error recorder on 2RP3 will be inaccurate during initial loading of the Turbine-Generator. Raising Turbine Inlet Pressure will cause Tref to rise from the NoLoad value of 547°F to the corresponding value for 40 - 60 MW, resulting in faster response of the T-Error pen. Only narrow range Tave should be monitored until a stable load is applied.


Standard Operator determines that INCOM KV is NOT 3-5 KV greater than RUN KV. (As Found; INCOM KV = 499, RUN KV = 498)

Operator adjust the Voltage Regulator to raise INCOM KV by:

At the EXCITATION, VOLTAGE REGULATOR, VREG CNTRL SETPT ADJ bezel; operator depresses the RAISE SETPT bezel until INCOM KV is 3-5 KV greater than RUN KV (at least 501 KV to meet Synch Permissive)

Operator reads the Note and continues on.

Operator reads the Caution and continues on.

EVAL S/U



evaluation

SYSTEM:

TASK:

* STEP

# NO.

4.5.9

4.5.10

4.5.11

4.5.12

NOTE





(* Critical Steo) Standard) REQUEST Electric System Operator permission Cue: The Electric System Operator grants to load Main Generator. permission to load main qenerator. NOTIFY the Hope Creek CRS/SM that Unit 2 Cue: Hope Creek CRS/SM is notified that Generator is to be synchronized to the grid. Unit 2 will be synchronized to the grid.

1 . RECORD contact in Control Room Narrative Cue: The extra NCO will record contact Loq. info in Narrative Loa. ADJUST RAMP RATES for the following to Operator adjusts the RAMP RATES using 10%/MIN: the DEHC HMI panel and verifies that LJ VL V POS CNTRL 10%/min is indicated on the HMI panel D VLV POS LIM screen. 11 TURB INLET PRESS CNTRL IF in OPERATOR MODE-AUTO, At the DEHC HMI panel, the operator THEN: determines that OPERATOR MODE is in

AUTO.

Operator performs steps in section 4.5.12 as applicable.

NOTE Operator reads Note and continues on. 1. MAIN GEN SYNC PERMISSIVE green indicating light will NOT light with any of the following: 11 MAIN GEN SYNC PERM BYPASS key lock switch in BYPASS position. IJ SYNCH POT OFF pushbutton selected. U INCOMING VOLTAGE less than RUNNING VOLTAGE n SYNCH SCOPE ROTATION is NOT every 25 - 30 seconds in the fast direction.

EVAL S/U



evaluation)

SYSTEM:

TASK:

* STEP NO.





* Critical Ste ·ADJUSTtutbine speed,as follows untilthe · \sy'nchfoscope'isJotatfnfSLOWLYJnthe.·FAST

directicm'af a rate of approximately f . revolution in every25.to.30seconds:


Standard Operator determines that adjustment to turbine speed is required.

Operator adjusts turbine speed using the DEHC HMI panel until synchroscope is rotating SLOWLY in the FAST direction. Note: the operator may use a stop watch or watch the clock.

Operator adjusts SETTER above REFERENCE AND ACTUAL SPEED displays. (As found SETTER = 1801) Operator should select 1-2 rpm increments when adjusting turbine speed.

Operator selects SETTER GO (illuminates Green) and verifies ACTUAL AND REFERENCE turbine speed adjusts to SETTER SPEED.

SETTER speed of 1802-1803 is acceptable to meet the Synch Permissive.

EVAL S/U



evaluation

SYSTEM:

TASK:

* STEP

# NO.

4.5.12.2





(* Critical Steo) Standard) IF MAIN GEN SYNC PERMISSIVE green Operator determines that the SYCNH indicating light is NOT lit each time the PERMISSIVE is operating properly and synchroscope indicator is near the 12 o'clock marks step N/A and continues on. position, OR is lit at any other synchroscope position, THEN: IF the MAIN GEN SYNC PERMISSIVE is

NOT lit as expected, THEN provide the following cue:

a. REQUEST permission from the CRS/SM to bypass the synchroscope interlock. Cue: CRS directs you to re-perform

Section 4.5. b. PLACE MAIN GEN SYNC PERM BYPASS key lock switch in BYPASS. Note: Not satisfying the Voltage and

turbine speed requirements in Steps 4.5.8

c. INITIATE a Notification to repair the circuit. and 4.5.12.1 would be the most likely cause for response not obtained.

CAUTION Operator reads Caution and continues on. Operator action is required upon Generator Output Breaker closure, if load is NOT automatically picked up within 15 seconds. [1 % REFERENCE change approximately 10 MW (NOT to exceed 4%)1

EVAL S/U



evaluation)

SYSTEM:

TASK:

* STEP NO.





* Critical Ste WHEN syochroscope is .. 1 to 2 minutes before

·12o'clod{ THEN CL0SE·theselected.500KV .. G.ROUP BUS·~BREAKER .

. SECTION: .. . n,1-9 (32X)'ti SOR ll9-1.0 (30X}; ·


Standard Operator depresses the CLOSE PB for 500 KV GROUP BUS - BREAKER Section 1-9 (32X) when the synchroscope is 1 to 2 minutes before 12 o'clock and verifies 1-9 CLOSE PB is illuminated.

Operator verifies load is rising on generator by monitoring either the MW indicator on 2RP3, MW Recorder on 2RP5, OR using the HMI panel GENERATOR LOAD lower left hand corner of screen. Note: the MW indicator on 2RP3 reads about 10 MW lower, so the operator may choose to raise load based on this indicator which is acceptable.

EVAL S/U



evaluation

SYSTEM:

TASK:

* STEP

# NO.

4.5.12.4

4.5.12.5

CUE:



Synchronize the Generator IAW $2.0P-SO.TRB-0001


(* Critical Steo) Standard) IF GENERATOR LOAD - MW does NOT raise Operator verifies that generator load rises to approximately 40 MW - 60 MW within 15 to 40 MW - 60 MW within 15 seconds and seconds, THEN: [C0431] marks this step as NIA and continues on.

Note: the MW indicator on 2RP3 reads a. RAISE SETTER - SETTER display less than about 10 MW lower, so the operator may or equal to 4% above the REFERENCE display choose to raise load based on this (approximately 1% for each 10 MW) AND indicator which is acceptable. SELECT SETTER - GO.

If raising load, THEN the Operator OR adjusts the SETTER to 1-3% above the

reference THEN selects GO. (Note: b. SELECT OPERATOR MODE- MANUAL during validations the SETTER is about

12%)

(1) SELECT RAISE until GENERATOR LOAD -MW are approximately 40 MW to 60 MW.

(2) SELECT OPERATOR MODE-AUTO.

SELECT SYNCH POT OFF for the selected Operator depresses the SYNCH POT OFF 500KV GROUP BUS -BREAKER SECTION: PB and verifies bezel illuminates. IJ 1-9 (32X) OR IJ 9-10 (30X)

JPM is Complete Terminate the JPM when the operator completes Step 4.5.12.5 or at Lead

RECORD the STOP TIME. Evaluators direction.

STOP TIME:

EVAL S/U



evaluation)

JPM: 16-01 NRG Sim-e




_/I' ___ 1. Task description and number, JPM description and number are identified.

-~/" __ 2. Knowledge and Abilities (KIA) references are included.

___../I': ___ 3. Performance location specified. (in-plant, control room, or simulator)

_fr ___ 4. Initial setup conditions are identified.

__ ft-__ 5. Initiating and terminating Cues are properly identified.

-~A __ 6. Task standards identified and verified by SME review.

-~f __ 7. Critical steps meet the criteria for critical steps and are identified with an asterisk(*).

__ fl __ 8. Verify the procedure referenced by this JPM matches the most current revision of that procedure: Procedure Rev.~ Date 1 /1.C\ / 1 -.:,,

__ I' __ 9. Pilot test the JPM: a. verify Cues both verbal and visual are free of conflict, and b. ensure performance time is accurate.

TQ-AA-106-0303

L 10. If the JPM cannot be performed as written with proper responses, then revise the JPM.

_AJ~/(f~_ 11. When JPM is revalidated, SME or Instructor sign and date JPM cover page.

SME/lnstructor <"?,( Sb ({:jL 8\---SME/lnstructor: -A;- &E.icr:,.J /iJ:::>~~ SME/lnstructor: b. M.wt t..,\f ~

I

Date: ~ 1"2.°I \~I Date: 2-,'cl.~-17

Date: 'f' /z 1/ I t


INITIAL CONDITIONS:


• Unit 2 is at 18% power starting up from a refueling outage.

• The crew is performing power ascension activities IAW S2.0P-IO.ZZ-0003, Hot Standby to Minimum Load.

• The main turbine is at 1800 rpm with generator excitation applied.

INITIATING CUE:


• The CRS has directed you to synchronize the Generator IAW S2.0P-SO.TRB-0001, Turbine-Generator Startup Operations, section 4.5, Synchronizing the Generator.

o All Prerequisites are completed SAT.

o Step 4.5.1 IVs are completed SAT.

o Synchronize the Generator starting at Step 4.5.2. The 500 KV 1-9 breaker will be closed first followed by the 500 KV 9-10 breaker.


STATION:

SYSTEM:

TASK:

TASK NUMBER:

JPM NUMBER:


SALEM

Containment Cooling System

Perform 22 CFCU Surveillance Test !AW S2.0P-ST.CBV-0003

N0220130201

16-01 NRC Sim-f

K./A NUMBER: 022 A1 .04 ALTERNATE PATH: ----------1 MP ORT AN CE FACTOR: 3.2

APPLICABILITY:

EOCJ ROITJ STAC] SROITJ


REFERENCES: S2.0P-ST.CBV-0003, Rev 19 (checked 9-10-17)


VALIDATED JPM COMPLETION TIME:

TIME PERIOD IDENTIFIED FOR TIME CRITI~ ST;Pt/ /"°'. /J Developed By: R. Chan /~ ~

Instructor

-----RO

N/A

Date: 9-18-17

Validated By: ~ /J<... tJ//At,,,o11JIJ Date: 9/11"/,-;

~~:1.~SJME ~~r1z;~d jJ .· ~ Approved ~ ~ ''!: , 1 ~""-- d h Date: /b Ir /17

f........l c.-'-- V\J rMning Department / pw "-Approved By: ]) 1 v1.. Mc 1-f v y \-\ _,4.c/J, ,1 { /1 Date: / c) ,.,,J 17

Operati~~~ !,__



PERFORMED BY:





3.3 SRO

JPM NUMBER:

Rev# Date

00 9-18-17


REVISION HISTORY

16-01 NRC Sim-f

Description


Validation Required

Editorial Yes




SYSTEM: Containment Cooling System

TASK: Perform 22 CFCU Surveillance Test IAW S2.0P-ST.CBV-0003




1. Reset the simulator to IC-245 2. Verify the following events on the Summary/ET Trigger Lists:

• ET-1: KAD06PBR, 22 CFCU LOW SPEED Start PB. INSERTS MALF: VL0570

• MALF: VL0570, 22 SW223, RAMP= 15 seconds, FINAL= 89 (SW flow 1786 +/- 5 gpm)

3. This malfunction will simulate an issue with the 22SW223 valve to properly obtain the required SW flow rate when in LOW SPEED. The malfunction attempts to have SW flow approx. 1786 gpm. This was chosen in case the operator chooses the incorrect Min Flow Rate of 1769 gpm for a SW DP at 105 psi.


OVERRIDES: None


• Provide operator marked up copy of S2.0P-ST.CBV-0003.



NAME: ----------------DATE:

SYSTEM: Containment Cooling System

TASK: Perform 22 CFCU Surveillance Test IAW S2.0P-ST.CBV-0003


INITIAL CONDITIONS:


• No major equipment out of service and no active Tech Specs are in effect.

INITIATING CUE:


• The CRS has directed you to PERFORM a scheduled surveillance test on 22 CFCU IAW S2.0P-ST.CBV-0003, Containment Systems - Cooling Systems.

• All Prerequisites are completed SAT and all required M&TE are installed in the field.

• A field NEO is standing by to provide SW header differential pressure when directed.


pro!=]ress is being made (and NRC concurrence is obtained).


1. PERFORMS surveillance test IAW S2.0P-ST.CBV-0003 and determines 22 CFCU Test Results is UNSAT.


SYSTEM:

TASK:

* STEP

# NO.

CUE

3.0

4.0

5.1

5.1.1

* • 5.1.1.A



Perform 22 CFCU Surveillance Test IAW S2.0P-ST.CBV-0003


(* Critical Step) Standard)


START TIME:

PRECAUTIONS AND LIMITATIONS Operator reads and initials all P&Ls.

3.4 After recording Differential Pressure (DP) Evaluator's Note: Understanding P&L reading, select corresponding minimum flow 3.4 is important to properly determining value specified in Exhibit 1 . which DP value to choose from Exhibit 1 .

• IF measured DP value is between DP values specified in Exhibit 1, THEN select minimum flow value for next higher DP value listed ( e.g., if measured DP is 101 psid, use minimum flow required at 105 psid).

EQUIPMENT/MATERIAL REQUIRED Cue: Completed SAT by l&C Technicians.

CFCU Operability and Service Water Flow Verification PERFORM test on each Containment Fan Coil Unit required to be tested IAW the following instructions:

. ENSU_RE .. C.FC_U being testedis iri LOW SPEED Operator places CFCU in LOW SPEED IAW S2.0P-SO.CBV-0001 (Q), Containment IAW S2.0P-SO.CBV-0001. Ventilation Operation: · ·· ·

. . ,>. . "'

Operator GOES TO $2.0P-SO.CBV-0001 .·

These next steps are from S2.0P-SO.CBV-0001, Containment Ventilation Operation.

EVAL S/U



evaluation)

SYSTEM:

TASK:

* #

*

STEP NO.

5.1.2

NOTE

5.1.2.B

5.1.2.D





* Critical Ste IF shifting CFCU(s) from High Speed to Low Speed, THEN for each CFCU to be shifted:

-·-------~--~-------~---·

.PRESS FAN HIGH SPEED STOP bezel. , ~- ' - . , ;- ' ·-

Steps 5.1.2B and 5.1.2C should be coordinated for 25 second delay prior to energizing slow speed windinqs. ENSURE FAN STOP bezel is illuminated.

···.When 25.second.s have.elapsedfrom pressing. 1-:IIGH.SPEED ·srOR bezel, PRESS FAN LOW

' · SPEED START bezel. . ,", ,''."

ENSURE following dampers are in indicated positions:

• ROUGH FL TR DAMPER CLOSED • HEPA INLET DAMPER OPEN • HEPA OUTLET DAMPER OPEN


Standard

Operator depresses HIGH SPEED STOP bezel for 22 CFCU and verifies STOP bezel illuminates. Operator reads the Note and continues on.

Operator verifies HIGH SPEED STOP bezel is illuminated. Operator waits 25 seconds from when HIGH SPEED STOP bezel was depressed.

Operator depresses LOW SPEED ST ART bezel for 22 CFCU and verifies ST ART bezel illuminates. Operator verifies the following for 22 CFCU:

• ROUGH FLT DAMPERCLOSED bezel extinguished.

• HEPA INLET DAMPER OPEN bezel illuminated.

• HEPA OUTLET DAMPER OPEN bezel illuminated.

EVAL S/U



evaluation

SYSTEM:

TASK:

* STEP

# NO.

5.1.2.E

5.1.2.F

5.1.1.B





(* Critical Steo) Standard) lE Service Water flow is less than 1465 gm, Operator determines that SW flow is > THEN: 1465 gpm and marks step N/A and

continues on. 1. STOP the CFCU 2. REFER to S2.0P-SO.SW-0005, SW

System Operability Guidelines

ENSURE Service Water flow greater than or Operator verifies that SW flow is > 1465 equal to 1465 qpm. gpm. Operator returns to S2.0P-ST.CBV-0003: Operator GOES TO S2.0P-ST.CBV-0003

RECORD Start Time in applicable Operator records ST ART time. Attachment(s), Section 3.0, for CFCU being tested.

EVAL S/U



evaluation)

SYSTEM:

TASK:

* STEP NO.





* Critical Ste .WHEN atleast15 niinwtes has elapsed; THEN· RECORD'thefoBowing in applic;able . ·Attachmeht; secti6n3.Q,; ·· .. . ..

· forcFclJ being·t~stect:'·;, /',/ ',:}/", ., .. ··· .·)/.:~~ ,i' • ., ''c '


Standard Cue: Inform operator that 15 minutes have elapsed.

Operator records STOP time.

Operator records SW flow on 22 CFCU (1786 +/- 5 gpm)

Cue: When field operator is contacted; report 21 SW Header DP is reading 106 2.§i

Operator contacts field NEO and Records SW header DP of 106 psi

Operator determines that 23, 24, and 25 CFCUs are not being tested.

Operator records Test Results as UNSAT. 22 CFCU is Inoperable based on Cooling Water Flow Rate is less than the Minimum Flow Rate (1811 gpm) required in Exhibit 1 selecting a SW DP of 110 psi (refer to P&L 3.4).

P&L 3.3 requires CFCU SW flow rate e:: 1465 gpm AND e:: Min Flow Rate specified in Exhibit 1 to be Operable.

See Answer Key for completed Attachment 2, Section 3.0

EVAL S/U



evaluation

SYSTEM:

TASK:

* STEP

# NO.

CUE:





(* Critical Sten) Standard) JPM is Complete. Terminate the JPM when the operator

Records Test Results as SAT or

RECORD the STOP TIME. UNSAT.

STOP TIME:

EVAL S/U



evaluation)

JPM: 16-01 NRG Sim-f





:p/l 2. Knowledge and Abilities (KIA) references are included.

---rj[. 3. Performance location specified. (in-plant, control room, or simulator)

l)2. 4. Initial setup conditions are identified.

:Di 5. Initiating and terminating Cues are properly identified.

:pl 6. Task standards identified and verified by SME review.

J.?1_7. Critical steps meet the criteria for critical steps and are identified with an asterisk(*).

~ 8. Verify the procedure referenced by this JPM matc)les tJ,e most current revision of that procedure: Procedure Rev. _jj_ Date 'i'(l't:/t7

=rrl.. 9. Pilot test the JPM: a. verify Cues both verbal and visual are free of conflict, and b. ensure performance time is accurate.

TQ-AA-106-0303

--~1..,..,&4'~ 10. If the JPM cannot be performed as written with proper responses, then revise the JPM.

-#11. When JPM is revalidated, SME or Instructor sign and date JPM cover page.

SME/lnstructor~o"-P ,

SME/lnstructor~s:5:ejJJ



INITIAL CONDITIONS:



• No major equipment out of service and no active Tech Specs are in effect.

INITIATING CUE:


• The CRS has directed you to PERFORM a scheduled surveillance test on 22 CFCU JAW S2.0P-ST.CBV-0003, Containment Systems - Cooling Systems.

• All Prerequisites are completed SAT and all required M&TE are installed in the field.

• A field NEO is standing by to provide SW header differential pressure when directed.


s2.oP-ST.CBV-0003(Q)

ATTACHMENT 2

22 CFCU DATA SHEET

1.0 Reason For Test

Post-Maintenance Operability Retest? I Yes I No X Date: 7odC\y SAP Order Number(s): So IC, 11, 3 L-/

2.0 Calibration Data

Instrument/Test Equipment Description Calibration

ID Number Initials Due Date

2FA5495 22 CFCU Outlet Water Flow Indicator S-/S,-/8 2 PA SY 't-5 I?-Model HQS-2 Sensor Module 0-2.00 psi 5-2q-1 <o Z.!c..1,'-{/ (2_

Model HOS-2 Sensor Module 0- 250 psi §<3/...- f i Z.,t I 6 SC, Q_

Model PTE-1 Hand Held Heise Pressure Calibrator Gauge 6' -22-1 S '2-l G 2-0 .J (2__

3.0 22 CFCU Performance Data

Test Results Component Test Data Acceptance Criteria

SAT UNSAT

Start Time

22 CFCU Stop Time

22 CFCU operated for at least

./ J78G 15 minutes in LOW SPEED 22SW58

Cooling Water at L 1465 gpm.

22SW72 Flow Rate .J,l S 9 f>W'\

22SW223

21 SW HDRL'.P 106 Cooling Water Flow Rate

(78' IPA - 21 SW Piping Room) is L the Minimum Flow Rate v"

Minimum Flow Rate I Bl\ obtained in Exhibit 1

(Exhibit 1) for 6P specified.

Salem 2 ..


STATION:

SYSTEM:


SALEM

A.C. Electrical Distribution

TASK:

TASK NUMBER:

Transfer 4KV Group Buses To The Alternate Power Supply (SPT to APT)

N0620110101

JPM NUMBER: 16-01 NRC Sim-g

ALTERNATE PATH: I X I KIA NUMBER: IMPORTANCE FACTOR:

APPLICABILITY: EO C:=J RO DO STA c=J SRO DO


REFERENCES: S2.0P-S0.4KV-0008, Rev. 12 (checked 9-29-17) S2.0P-AR.ZZ-0009, Rev 27




062 A2.04 3.1 3.4 RO SRO

Developed By: R Chan ~ clu"'-lnstructor ,,,..,,1 ""L /

~ b. ~-e, d~ ::::6 Validated By: (. C) '-- PAr {Yle,>l:t,.) ~ 0

SME or lnsfructor

Date: 9-29-17

q/7,<i_/11-Date: }JC,-' /1

Approved By:

Approved By:

~ Jl_ Date: Training Departmen U H

rµ-----~ Date: Operations Departme ~,._,~s



PERFORMED BY:

GRADE: SAT UNSAT




JPM NUMBER:

Rev# Date

00 9-29-17


REVISION HISTORY

16-01 NRC Sim-g

Description


Validation Required

Editorial Yes




SYSTEM: AC. Electrical Distribution

TASK: Transfer 4KV Group Buses To The Alternate Power Supply (SPT to APT)




1. Reset the simulator to IC-246 (IC-258 used as baseline) 2. Verify the following actions in the Summary/ET Trigger Lists:

a. ET-1: KC509PCO - 2BGGD 2G Group Bus Feeder Close, INSERT MALF: EL0142 -Loss of 2G 4160 V Group Bus.

3. This malfunction will simulate a loss of the 2G Group Bus only and result in the loss of one (1) RCP (24 RCP). Based on S2.0P-S0.4KV-0008, Precautions and Limitations 3.3, the crew should respond to OHA J-39 when it does NOT clear following bus transfer. The OHA ARP will direct you to J-38 to TRIP the Reactor and GO TO EOP-TRIP-1.

4. Check APT voltage the same as the Group bus voltage pre-req 2.3.3 5. This completes the setup for this JPM.

OVERRIDES: None


• Provide marked up hard copy of S2.0P-S0.4KV-0008 to candidate. • Setup to only deenergize one (1) Group Bus, THEN the operator will receive OHA J-39, 4KV

GRP BUS XFER FAIL. • The ARP for J-39 will direct operator J-38 for response. • OHA J-38 states: IF ANY RCP Trips THEN:

o TRIP Reactor o GO TO EOP-TRIP-1



NAME: --------------0 ATE: --------------

SYSTEM: A.C. Electrical Distribution



INITIAL CONDITIONS:

• 18% power, 160 MWe, BOL.

• The Main Generator was synchronized 10 minutes ago.

• Steam Dumps are in MS Pressure Mode-Auto set at 970 psig. • Rod Control is in Manual (D-147) until Group Buses are transferred.

• Group Buses are currently powered from the Station Power Transformers (SPT).

INITIATING CUE:

• You are the Plant Operator. • The CRS directs you to TRANSFER all 4KV Group Buses from their respective Station Power

Transformers (SPT) to the Aux Power Transformers (APT) IAW S2.0P-S0.4KV-0008, 4KV Group Buses Power Supply Transfer in the following order:

1. 2F IAW section 5.2 2. 2G IAW section 5.3 3. 2H IAW section 5.4 4. 2E IAW section 5.1

• All pre-requisites are completed SAT.


progress is being made.


1. Transfers 2F 4KV Group bus from SPT to APT. 2. Trips Reactor IAW ARP following de-energizing of 2G 4KV Group Bus






STEP STANDARD

* STEP (Shaded area denotes Critical Step)

(Bolded area identifies Task Standard) NO. (* Critical Step) #

(# Sequential Critical Step)

CUE: Fill in the JPM Start Time when the student acknowledges the Initiating Cue.

START TIME:

P&L Note: The operator may also review the Operator reviews Precautions and

OHA ARPs prior to starting the JPM. Limitations.

Evaluator's Note: P&L 3.3 will be applicable when the 2G 4KV Bus deenergizes:

When transferring a group Bus from SPT to APT, OHA J-39, GROUP BUS XFER FAIL, will illuminate then clear on bus transfer ( expected response). OHA J-39 annunciator response is applicable when the alarm does NOT clear following bus transfer.

5.2 Transferring 2F 4KV Group Bus from 22 SPT to 2 APT

5.2.1 ENSURE all Overhead Annunciators for Checks OHA Windows and determines all 2 APT are clear. Overhead Annunciators for 2 APT are

clear.

5.2.2 ENSURE 2A APT voltage is 4.22 - Checks 2A APT reading on 2CC3 and 4.36KV. ensures 2A APT voltage is 4.22 - 4.36KV.

Page 5 of 13

NAME: -----------DATE: ----------

COMMENTS EVAL (Required for UNSAT S/U evaluation)






* #

STEP NO.

5.2.3


(* Critical Step) (# Sequential Critical Step

lE Auxiliary Power Unit Isolation Transfer is tripped, THEN RESET Auxiliary Power Unit Isolation Transfer (UIT).

PRESS the Mimic Bus 2F GROUP BUS . INFEED2BFGD BREAKER pushbutton, AND.ENSURE console beiel 2BFGD Ml MIC BUS INTLKCLOSE SELECTION

,, illUminates ... ·

*PRESS control console 2BFGD CLOSE RUShl:>uttoh, .· · •.. ··

·:.AND ENSURE t~e following: . ,,',,\';' ' . i~i,/'':

A'.': *22FSD is OPEN.· . B. *2BFGD is CLOSEt:f

\G;;''*2FAKV·~roup BLlsVoltage.Js 4;22:- ·. ·. ,'. , . .4.~6.K\'t.', ... .· .. ,, . , r ..• ...... . .... · .•

.. D.,:Ccinsole' bezel2BF::GD'MIMIC BUS . \''.\r>·1NTCK,Cl))SE SELECTION•is~·; t'. '· .. ; : extihgui.st\ed. · · ·

,: J'" '.;;,., ,". <-'' \:2;:;,


Determines Auxiliary Power Unit Isolation Transfer is not tripped from control console indication.

Depresses Mimic Bus 2F GROUP BUS INFEED 2BFGD BREAKER pushbutton and verifies console bezel 2BFGD MIMIC BUS INTLK CLOSE SELECTION is Illuminated.

Depresses control console 2BFGD CLOSE pushbutton and verifies the following:

A. 22FSD OPEN bezel is illuminated. B. 2BFGD CLOSED bezel is illuminated. C. 2F 4KV Group Bus voltage is 4.22 -

4.36KV . D. Console bezel 2BFGD MIMIC BUS

INTLK CLOSE SELECTION is extinguished.

Page 6 of 13

NAME:

DATE:

EVAL S/U

--------------------


evaluation)





TASK: Transfer 4KV Group Buses To The Alternate Power Supply (SPT to APT) STEP STANDARD

* STEP (Shaded area denotes Critical Step) (Bolded area identifies Task Standard) NO. (* Critical Step)

# (# Sequential Critical Step)

5.3 Transferring 2G 4KV Group Bus from 22 SPT to 2 APT

5.3.1 ENSURE all Overhead Annunciators for Checks OHA Windows and determines all 2 APT are clear. Overhead Annunciators for 2 APT are

clear. 5.3.2 ENSURE 2A APT voltage is 4.22 - Checks 2A APT reading on 2CC3 and

4.36KV. ensures 2A APT voltage is 4.22 - 4.36KV.

5.3.3 IF Auxiliary Power Unit Isolation Transfer Determines Auxiliary Power Unit Isolation is tripped, THEN RESET Auxiliary Power Transfer is not tripped from control console Unit Isolation Transfer (UIT). indication.

* . 5.3:4 ·· PRESS Mimic Bus2G GROUP BUS Depresses Mimic Bus 2G GROUP BUS ' .. . . " IN FEED 2BGGD BREAKERp'Ostibutton, _ INFEED 2BGGD BREAKER pushbutton, . AND ENSURE console bezel 2BGGD ... AND verifies console bezel 2BGGD

' MIMICBUS INTLK CLOSE SELECTION MIMIC BUS INTLK CLOSE SELECTION illuminates; · , is illuminated.

" •· .


Page 7 of 13

NAME: ----------DATE: ----------




JOB PERFORMANCE MEASURE SYSTEM: A.C. Electrical Distribution

TASK:

* #

STEP NO.

Transfer 4KV Group Buses To The Alternate Power Supply (SPT to APT)


(* Critical Step) # Sequential Critical SteJ)_

*f>RESS controLconsole 2,BGGD. CLOSE pus,t:,button';"ANb ENSURE the'following:. ·

,,, '

*22GS0 is OPENi *2BGGo is ccosEo.> ...... ·. ..

C. ~2G 4KVGroup Bus voltage is t22 -.. •

0 436KV ·.·. ·· , · . . . [),. c'ons61~ bezel 2BGGD MIMIC al.ls· .....

·INTLKCLOSE SELECTIONis .. ,, ex:tinguished.


Operator determines 2G 4KV Group bus did not transfer and announces several unexpected OHA alarms.

The following OHA alarms are applicable to the loss of 2G 4KV bus and will provide the operator with the required actions:

J-8 (2G 4KV GRP BUS DIFF/OVRLD), J-38 (4KV GRP BUS UNDRVOLT), J-39 (4KV GRP BUS XFER FAIL), and 0-31 (24 RCP BKR OPEN/FLO LO).

Cue: If requested to dispatch an operator to inspect the 4KV group Bus, state; the CRS will send an operator to investigate.

Operator identifies that OHA ARPs for J-38 or 0-31 requires tripping the Reactor and going to EOP-TRIP-1 (OHA response are provided in next steps).

Cue: If operator informs CRS of action to trip the reactor, state; take actions per the alarm response procedure.

Operator TRIPs the Reactor.

Page 8 of 13

NAME:

DATE:

EVAL S/U

----------

----------


evaluation)






* #

STEP NO.

OHA ARP J-39


(* Critical Step) (# Sequential Critical Step

4KV GRP BUS XFER FAIL

3.0 OPERATOR ACTIONS

GO TO OHA J-38 response

4KV GRP BOS UNDRVOLT

A?: TRIPReactOr· . ···· .. ···•· .. . . B. GO TO 2:-EOP-TR.IP~1i


lE the operator refers to this ARP, THEN GOES TP ARP for J-38 for response.

lE the operator refers to this ARP, THEN the operator determines that Step 3.5 is applicable and performs the following:


Page 9 of 13

NAME:

DATE:

EVAL S/U

----------

----------


evaluation)






* #

STEP NO.


{* Critical Step) # Sequential Critical Step)

.24 RCP BKROPEN/FLO LO

·. io: OPERATORACTIONS: . : :;

> ,. "

3:51E Reactor Coolant System flow. · degradation exists;·· . THEN: ...

!Rllfthe ~eactor . . ST0.~324 8CP,,;. . ·. TF Rc'it;shutdown was du~: to ...... .

RC!? .. 'S1al Lea~off} e g'pm:/fHE~-f · ~imulJane9uslf'PERFORM the · f '·11 ·>::, . i":\ :/:.,:.· :<.: .. ·:· ::. : .. o owing,, . · ...• ·· ... ~;. , .· . ·. ·•· .•. 1/: .· '.~Jt' Be1WeJTii;3l5 rni'nyt~~

1~fter.

' stopping 24,RCF',/CLOSE,, 24CV104, SEAC; .. .

LEAKOFF. • GO T0,2-EdP-TRIP-1

. D~ . GO.TO 2-EOP-TRI P-1 ·

STANDARD {Bolded area identifies Task Standard)

!Ethe operator refers to this ARP, THEN the operator determines that Step 3.5 is applicable and performs the following:


Note: Stopping 24 RCP is not required due to the bus de-energizing .

Page 10 of 13

NAME:

DATE:

EVAL S/U

--------------------


evaluation)






STEP STANDARD

* STEP (Shaded area denotes Critical Step)

(Bolded area identifies Task Standard) #

NO. (* Critical Step) j# Sequential Critical Step)

CUE: JPM is Complete Terminate the JPM when the Rx trip has been initiated.


STOP TIME:

Page 11 of 13

NAME: ----------DATE: ----------




JPM #: 16-01 NRC Sim-g


---..~.-~ __ 1. Task description and number, JPM description and number are identified.

_t!l ___ 2. Knowledge and Abilities (KIA) references are included.

_f))~-- 3. Performance location specified. (in-plant, control room, or simulator)

__ W __ 4. Initial setup conditions are identified.

__ P.L> __ 5. Initiating and terminating Cues are properly identified.

____,F)......,...R'---- 6. Task standards identified and verified by SME review.

__ A_~-- 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).

_p~'k __ 8. Verify the procedure referenced by this JPM matches the most current revision of

P/1 that procedure: Procedure Rev. __ Date _____ _

9. Pilot test the JPM: ----a. verify Cues both verbal and visual are free of conflict, and b. ensure performance time is accurate.

ti I A 10. If the JPM cannot be performed as written with proper responses, then revise the JPM.

rJ /A 11. When JPM is revalidated, SME or Instructor sign and date JPM cover page.

SME/lnstructor: Date: 1--a~-17

Date: °I/lei,/, f

SME/lnstructor: Date: c, tici t ,1

Page 12 of 13 PSEG CONFIDENTIAL - Possession Requires Specific Permission from Nuclear Training

INITIAL CONDITIONS:

• 18% power, 160 MWe, BOL.

• The Main Generator was synchronized 10 minutes ago.

• Steam Dumps are in MS Pressure Mode-Auto set at 970 psig.

• Rod Control is in Manual (D-147) until Group Buses are transferred.

• Group Buses are currently powered from the Station Power Transformers (SPT).

INITIATING CUE:


• The CRS directs you to TRANSFER all 4KV Group Buses from their respective Station Power Transformers (SPT) to the Aux Power Transformers (APT) IAW S2.0P-S0.4KV-0008, 4KV Group Buses Power Supply Transfer in the following order:

1. 2F IAW section 5.2 2. 2G IAW section 5.3 3. 2H IAW section 5.4 4. 2E IAW section 5.1

• All pre-requisites are completed SAT.

Page 13 of 13 PSEG CONFIDENTIAL - Possession Requires Specific Permission from Nuclear Training

STATION:

SYSTEM:

TASK:

TASK NUMBER:

JPM NUMBER:

SALEM


Component Cooling Water System

Start A CCW Pump IAW 2-EOP-APPX-1 (23 CCW Pump)

N1150420501

16-01 NRC JPM Sim-h

KIA NUMBER: 008 A2.01 ALTERNATE PATH: I X I ------------1 IMPORTANCE FACTOR: 3.3

APPLI CASI LITY:

EoD R0[8J STAD SR0[8]


REFERENCES: 2-EOP-APPX-1 Rev. 25 (checked 9-29-17)




R. Chan'7)-~l-11

/ d~f•v Developed By: f<-· 1"-' () J ()\ u. l~c;orcX'~ ~

Validated By: l 27\ Lt'-- P1r, IJ.Ru cw /J,vbll.~ SME or Instructor

RO

N/A

Date: 9-29-17

°!/z 't./, 1 Date: Cf-~?-/7

Approved By: Training Department ~f1.,.

~ Date:

Approved By:

Operations Departmenr--)~ s~5 Date:



PERFORMED BY:





3.6 SRO


JPM NUMBER:

REVISION HISTORY

16-01 NRC Sim-h

Rev#

00


9-29-17 Added revision history and simulator setup pages. Editorial Yes comments from IP 71111.11 FASA. Incorporated changes to 2-EOP-APPX-1 Rev. 25.



SYSTEM:



TASK:

TASK NUMBER:


N1150420501



1. Reset the simulator to IC-247 (IC-239 used as baseline) 2. Ensure the following malfunction on the event summary:

a. RC0001 B: RCS rupture of RC loop 22 set to TRUE b. EL0134: Loss of 500 KV off-site power c. EL0145: Loss of 28 Vital Bus

OVERRIDES:

• A601 EDI: KA601PBM 21 CC PUMP-START. Final= Override OFF.


• ENSURE sufficient copies of 2-EOP-APPX-1. • Extra Instructor on the floor is recommended to respond to the numerous post-trip alarms that

may unnecessarily distract the candidate.



NAME: --------------DATE:

SYSTEM: Component Cooling Water System

TASK:

TASK NUMBER:


N1150420501

INITIAL CONDITIONS:

• The Unit 2 reactor was manually tripped and a SI initiated based on indications of a large break LOCA.

• A loss of off-site power occurred when the Main Generator breakers opened.

• 28 4KV Vital Bus is de-energized due to Bus Differential with its Diesel running.

• 2-EOP-TRIP-1 is in progress.

• NO CCW pumps are running (SEC Mode 3).

• 21 and 22 CCW pumps were in service prior to the trip and 23 CCW pump was in Auto.

INITIATING CUE:


• The CRS directs you to START ONE CCW pump IAW 2-EOP-APPX-1.

• Notify the CRS when one CCW pump is running.

Successful Completion Criteria: 1. All critical steps completed. 2. All sequential steps completed in order. 3. All time-critical steps completed within allotted time. 4. JPM completed within validated time. Completion time may exceed the validated time if

satisfactory progress is being made (and NRC concurrence is obtained).

Task Standard for Successful Completion: 1. STARTS 23 CCW pump IAW EOP-APPX-1.


NAME: -----------OPERATOR TRAINING PROGRAM

JOB PERFORMANCE MEASURE DATE: -----------


TASK: Start A CCW Pump IAW 2-EOP-APPX-1 (23 CCW Pump)

_:,r STEP No. - •

CUE:

cc - ;c: \\::.STEP/ :r~; , ,\, __ (Shadect'area denotes Critical Step)

· \' 'C* Critical Ste_,Q) --_ --- -~--·-······------~

Operator obtains 2-EOP-APPX-1



CHECK 4 KV vital bus status:

a. CHECK AT LEAST ONE vital bus ENERGIZED by station power transformers.

:'STANDARD i- -' (Bolded · area idehtifies Task

Standar'dJ_; -

Determines that NONE of the 4 KV vital buses are energized from the station power transformers. (2A and 2C are energized from EDGs, and 2B is deenergized).

RNO: GOES TO Step 2.

·EVAL S/U


"- COMMENTS ·'':'(Required for UNSAT

- Evaluation)


JOB PERFORMANCE MEASURE NAME:

DATE: SYSTEM: Component Cooling Water System


2

3

CHECK ECCS pump (CVC,SI, or RHR) and AFW pump status:

a. CHECK all ECCS pumps AND motor-driven AFW pumps running on energized vital buses.

b. CHECK one CCW pump running.

SELECT CCW pump start strategy (choose one (a, b, c, d)):

.• STANDARD. .. · ........ . (Bolded area· identifies]Task··

· · ·' Standard ·· ·

Checks running pumps and determines that f!!l_ECCS pumps AND motor driven AFW pumps running on energized vital buses (A and C}.

Checks CCW pump status and determines NO CCW Pumps are running.

RNO: GOES TO Ste2_ 3.

Selects 'C' CCW Pump Start strategy based on:

-De-energized 4KV Vital Bus = B. -CCW Pumps Available = 21 or 23 -GO TO Step No. 6.


-----------

<( C.OMMENTS · . . :• ·.(Required for. UN SAT

· · Evaluation·





·, [4KVVital Bus ''.B""De-energlzed]: . .. . '..i / CHECK 21 ccw Pump .... ·.

.. ··.. · .. AVAILABLE. ·.

. STANDARD ··. {Bolded area\identifies ;Task

. Standitrd\ ·.. ./.

Determines 21 CCW Pump is available (in service prior to Rx Trip) .

Rotates 2A SEC Block Switch to BLOCK and releases.

Depresses Emergency Loading Reset for 2A SEC on 2CC3 and verifies bezel illuminates.

Depresses the 21 CS STOP PB and verifies STOP bezel illuminates on 2CC1.

Depresses the 21 CCW ST ART PB and reports that 21 CCW Pump did NOT start.

RNO [step e]: 1. RESET Containment Spray 2. ST ART 21 CS Pump, as

necessary. 3. GO TO Step 6(h)

Note: Re-starting 21 CS pump is necessary when 22 CS is stopped later.

Cue: !Ethe operator does not re-start 21 CS pump, THEN state: CRS directs restartinq 21 CS pump.

NAME: ----------

DATE:-----------

.......... COMMENTS .. (Required for UNSAT/

Evaluation






STANDARD . ... (Boldecfare~ identifles''.r~sk

•·standard Determines 23 CCW Pump is available.

Rotates 2C SEC Block Switch to BLOCK and releases (2A selected to Block previously).

Depresses Emergency Loading Reset PBs for 2A and 2C SEC on 2CC3 and verifies bezel illuminates.

Depresses 22 CS STOP PB and verifies STOP bezel illuminates on 2CC1.

Depresses 23 CCW ST ART PB and verifies START bezel illuminates

Depresses Train A and B RESET SPRAY ACTUATION PBs and verifies RESET SPRAY ACTUATION bezel illuminates Green (Note: previously reset from Step 6.e).

Depresses 22CS2 CLOSE PB and verifies CLOSE bezel illuminates.

GOES TO Step 8

NAME:

DATE:


-----------

----------

'"' COMM .. l=NTS ... (Required for'UNSAT

· 'Evaluation·

SYSTEM:

TASK:





NAME: -----------DATE: ----------

SJAND~R,D:, ; 7 ,

(Boldedareif.identifiesJask ·•··· ..•.. ·•···.·. COMMENTS ..•

CUE: JPM is Complete.


STOP TIME: _____ _

·· Stan'd'~rd · Terminate JPM when operator completes GOES TO Step 8.


·· ·.(Required for LJNSAT .... ·. ···•·· .. Evaluation .



JPM#: 16-01 NRC Sim-h


_B\ ____ 1. Task description and number, JPM description and number are identified.

__.9}..<--__ 2. Knowledge and Abilities (KIA) references are included.

___,\1>~-- 3. Performance location specified. (in-plant, control room, or simulator)

-~-4---- 4. Initial setup conditions are identified.

~t11 ___ 5. Initiating and terminating Cues are properly identified.

'ill 6. Task standards identified and verified by SME review.

~ 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).

_m~-- 8. Verify the procedure referenced by this JPM matches the most current revision of that procedure: Procedure Rev. JS' Date 't-~/7

9. Pilot test the JPM: ----a. verify Cues both verbal and visual are free of conflict, and b. ensure performance time is accurate.

}//A 10. If the JPM cannot be performed as written with proper responses, then revise the JPM.

eJ I A 11. When JPM is revalidated, SME or Instructor sign and date JPM cover page.

SME/lnstructor: & &~.t t:zN &J ~ Date: 'f-o.. 9-r, -'------

SME/lnstructor: 't, /1a..:<fuf ~~~ SME/lnstructor: ~\... <; ~( l

Date: ----''f/_i._c_'?_/_1 t __

Date: ~1-1 "11_},__,-+-)_


INITIAL CONDITIONS:


• The Unit 2 reactor was manually tripped and a SI initiated based on indications of a large break LOCA.

• A loss of off-site power occurred when the Main Generator breakers opened.

• 28 4KV Vital Bus is de-energized due to Bus Differential with its Diesel running.

• 2-EOP-TRIP-1 is in progress.

• NO CCW pumps are running (SEC Mode 3).

• 21 and 22 CCW pumps were in service prior to the trip and 23 CCW pump was in Auto.

INITIATING CUE:


• The CRS directs you to START ONE CCW pump IAW 2-EOP-APPX-1.

• Notify the CRS when one CCW pump is running.

PSEG CONFIDENTIAL - Possession Requires Specific Permission from Nuclear Training Page11of11

STATION:

SYSTEM:

SALEM


Emergency Diesel Generator (ED/G) System

TASK:

TASK NUMBER:

Unload and shutdown 2C EOG IAW S2.0P-SO.DG-0003

N0645060104

JPM NUMBER: 16-01 NRC IP-i

ALTERNATE PATH: KIA NUMBER: 064 A2.04 -----------< IMPORTANCE FACTOR: 2.7 3.0

APPLICABILITY:

EOD RO[XJ STAD SRO[XJ

EVALUATION SETTING/METHOD: In Plant/ Simulate

REFERENCES: S2.0P-SO.DG-0003, Rev. 42 (checked 10-2-17)




Developed By:

Validated By:

RO SRO

N/A

10-2-17

}D-2--l'l

lo/1.Lf/ I 1 Approved By: 11Jf Date 1,f ?/,7

Approved By: Operations Departmen



PERFORMED BY:




l\ / f°b f 11

DATE:


JPM NUMBER:

Rev# Date

00 10-2-17

16-01 NRC IP-i


REVISION HISTORY

Description


Validation Required

Editorial Yes




SYSTEM: Emergency Diesel Generator (ED/G) System

TASK: Unload and shutdown 2C EOG IAW S2.0P-SO.EDG-0003


SIMULATOR IC: N/A


N/A

OVERRIDES: N/A


• This JPM is located inside the RCA.



NAME:

DATE: ---------------SYSTEM: Emergency Diesel Generator (ED/G) System



INITIAL CONDITIONS:

• 2C EOG was paralleled to the 2C 4KV Vital Bus IAW S2.0P-SO.DG-0003, 2C Diesel Generator Operation, Section 5.4, Diesel Generator Parallel Loading, following maintenance.

• The 2C EOG has been running loaded for 20 minutes at 2550 KW and 1500 KVAR OUT.

INITIATING CUE:

• You are the extra NCO.

• The CRS directs you to unload and shutdown the 2C EOG IAW S2.0P-SO.DG-0003, Sections 5.8 and 5.9.

I Successful Completion Criteria:




4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made (and NRC concurrence is obtained).

Task Standard for Successful Completion: 1. Lowers EOG load to 200 KW 2. Lowers EOG KVAR to between 50-100 KVAR 3. Opens EOG output breaker 4. Stops EDG and places GEN LOADING SW to AUTO (ISOCR)


I




TASK: Unload and shutdown 2C EDG IAW S2.0P-SO.EDG-0003

STEP STEP STANDARD * (Shaded area denotes Critical Step) (Bolded area identifies Task #

NO. (* Critical Steo) Standard)

Provide candidate with marked up procedure Give operator marked up copy of S2.0P-(partial procedure) S2.0P-SO.DG-0003, 2C SO.DG-0003, 2C Diesel Generator Diesel Generator Operation. Operation.


START TIME:

P&Ls Precaution and Limitations The Operator may wish to review all of the P&L's. Note: None of the P&Ls are applicable to this Task.

5.8 Diesel Generator Loading

NOTE The GENERATOR CIRCUIT BREAKER Operator reads the Note and continues on. SWITCH should be placed in the TRIP position as soon as EOG Load is reduced to 200 KW.

NAME: _________ _

DATE: _________ _







* STEP NO.

5.8.2


* Critical Ste .JF.2C EDG<is paraHeled.on 2C4KV Vital Bus,.

•· i. THEN coricurrenJly·PER.FPRIVI .the following: ;A.bJUSTSPEgbcoNTR.Ol.rSW ITCH (GS) t(),graduallylOWerfoadtb 200 .

·'KW: V

.ADJUSTVOLTAGECONTRQL.· .. ,.,'"·SWITCH (VCS) to graduallyJower

K)IARto b~tween 50~100 KVAR OUT.

IF 2C 4KV Vital Bus is isolated and energized from 2C EDG, THEN:


Standard At the 2C EDG Control Panel the operator performs the following:

Operator locates SPEED CONTROL SWITCH (GS) and VOLTAGE CONTROL SWITCH, and simulates rotating the switches to the LOWER position while monitoring Generator KW and KVAR.

Cue: When the operator simulates operating the switches to the LOWER position, THEN give operator the following readings: WATTMETER now reads 200 KW and VARMETER now reads 75 KVAR.

Cue: IF operator simulates going to RAISE on either switch, then CUE a reading that is HIGHER than last reading given until you achieve the desired final readings of 200 KW and 75 KVAR.

Marks step N/A.

NAME: ________ _

DATE: ________ _

EVAL SIU


evaluation




SYSTEM: Emergency Diesel Generator {ED/G) System


* #

STEP NO.

5.8.4

5.8.5

5.9

5.9.1


* Critical Ste OPEN 2C.DJESEL GENERATOR BREAKER by performing one bf the· following: •··

. . ... :OPEN 2CD1AX6D, 2C DIESEL .}GENERATORBl~EAKER: (64'

swgf Rm); or · ··

PR~~s' 2c BREAKER OPEN< pushbutton (2CC3); or PL.ACE2C~DF-GCP-3

.. GENERATOR CIRCUIT. BREAKER SWITCH(BCS); to·

.TRIP (2CD/GControlPanel). . .

ALLOW Diesel to run unloaded for~ 3 minutes prior to stopping the EOG.

lE diesel unloading was directed by Step 5.9.3F OR Step 5.10.4E, THEN RETURN to Step 5.9.4 OR Step 5.10.5.

Diesel Shutdown From Local Control Panel

IF Diesel Generator was operated without electrical load for <15 minutes, THEN ALLOW Diesel to run unloaded until total runtime is ~15 minutes OR for a period of time specified by a preplanned Maintenance activity,

rior to stoppinq Diesel.

STANDARD {Bolded area identifies Task

Standard Cue: IF operator asks which to perform, THEN state; CRS directs you to OPEN the DG Breaker at the 2C D/G Control Panel.

At the 2C D/G Control Panel the Operator performs the following:

Operator simulates rotating 2C-DFGCP-3 (BCS) to the TRIP position .

Cue: Green indicating light above switch is illuminated and the red light is extinguished. Generator KW and KVAR indicate 0.

Cue: 3 minutes has elapsed.

Marks step NIA

GOES TO Section 5.9

Marks step NIA

NAME: _________ _

DATE: _________ _

EVAL S/U


evaluation




SYSTEM: Emergency Diesel Generator {ED/G) System


STEP STEP STANDARD * {Shaded area denotes Critical Step) {Bolded area identifies Task #

NO. (* Critical Step) Standard)

5.9.2 !E Diesel Generator was operated without Marks step N/A electrical load for ~2 hours, AND the diesel is capable of loading, THEN: [C0300] A. Slowly LOAD Diesel, over 15 minutes, to 1500 KW at 1125 KVAR for minimum of 1 hour IAW Section 5.4 of this procedure. B. UNLOAD Diesel IAW Section 5.8 of this procedure.

5.9.3 !E Diesel Generator was operated without Marks step N/A electrical load for~ 2 hours ....

NAME: ----------DATE:----------

COMMENTS EVAL {Required for UNSAT S/U evaluation)






STEP STEP STANDARD

* (Shaded area denotes Critical Step) (Bolded area identifies Task #

NO. (* Critical Step) Standard)

5.9.4 !E 2C-DF-GCP-1 2C DIESEL GEN LOADING Note: 2C-DF-GCP-1, 2C DIESEL GEN SW is in MANUAL (DROOP), THEN: LOADING SW was placed in MANUAL

(DROOP) during Generator Paralleling in Section 5.4.

A. ADJUST Diesel Generator speed as necessary to achieve 900 rpm using Cue: DG speed indicates 900 rpm. SPEED CONTROL SWITCH (GS).

B. CHECK frequency indicated on 2CC3 Calls control room to check frequency. bezel is 58.94-60.36 Hz. Cue: frequency is 60.03 Hz.

C. ADJUST Generator terminal voltage Cue: Generator voltage is 4200 V. as necessary to achieve 4160 volts using VOLTAGE CONTROL SWITCH (VCS)

D. CHECK voltage indicated on 2CC3 is Operator simulates calling control room to 4.023-4.306 KV. check voltage on 2CC3 bezel.

Cue: Voltage is 4.160 KV.

Caution Placing the CMC switch in the stop position Operator reads the note. does not lock in a stop signal to the shutdown relays. The switch should be rotated to the stop position and held momentarily to facilitate engine shutdown. Do not hold the switch in the stop position for more than approximately 2-4 seconds in order to minimize deterioration of the shutdown relay coils.

NAME: ________ _

DATE: ________ _







* #

STEP NO.

5.9.6


* Critical Ste PLACE2C:-:DF~ss, 2CDG STOP/START SWITCH in STOP.

lE the Diesel Generator does not shutdown when the CMC switch is placed in the STOP position PERFORM the following:

A. OPEN the CB4 breaker (S2DG-2CDG-CB4) in the Control Panel.

B. PLACE CMC switch 2C-DF-SS, 2C DG START/STOP SWITCH to STOP

C. Once the engine shuts down, CLOSE the CB4 breaker (S2DG-2C-DG-CB4)

D. INITIATE a Notification to inspect Panel Alarm power supply and SR/SRS relays for stray voltage IAW SC.MD-PM.ZZ-0011.


Standard Operator simulates rotating 2C-DF-SS 2C DG STOP/ST ART SWITCH to STOP position.

Cue: Diesel is shut down.

Marks step N/A.

NAME: ---------DATE: ---------

EVAL S/U


evaluation






* #

STEP NO.

5,9.7

CUE:


* Critical Ste IF 2C-DF-.GCP~1. 2C.DIESEL. GEN LOADING SW is in MANUAL (DROOP), THEN PLACE 2C-DF-GCP-1 2C DIESEL GEN LOADING

.. SW in'AUTQ (ISOCR) ..

JPM is complete when the task is complete OR at the direction from the Lead Evaluator.


STOP TIME: _____ _


Standard Operator simulates rotating 2C-DFGCP-1 2C DIESEL GEN LOADING SW counter clockwise to AUTO position .

Cue: AUTO light is illuminated, MANUAL light is extinguished; GENERATOR LOADING IN DROOP MODE (B-9) panel alarm is now cleared.

JPM is Complete

Terminate the JPM when the operator completes Step 5.9.7.

NAME: ---------

DATE: -----------

EVAL S/U


evaluation


JPM #: 16-01 NRC IP-i





-?--2. Knowledge and Abilities (KIA) references are included.

~ 3. Performance location specified. (in-plant, control room, or simulator)

Vn 4. Initial setup conditions are identified.

~ 5. Initiating and terminating Cues are properly identified.

~~ 6. Task standards identified and verified by SME review.

7. Critical steps meet the criteria for critical steps an. d are identified with an asterisk (*).

8. Verify the procedure referenced by this JPM mat.ch~s the most current revision of that procedure: Procedure Rev. W..+ Date \0 / "&- l\l

~ 9. Pilot test the JPM: -t- a. verify Cues both verbal and visual are free of conflict, and b. ensure performance time is accurate.

_____._tJ-!/-'"'1

~'-- 10. If the JPM cannot be performed as written with proper responses, then revise the JPM.

~N ...... '(t~, __ 11. When JPM is revalidated, SME or Instructor sign and date JPM cover page.

Date: __ ! o__,/_:J-..~/ _n.,_____

Date: 10/zz.//17

Date: 10/~'"t/,7


INITIAL CONDITIONS:


• 2C EOG was paralleled to the 2C 4KV Vital Bus IAW S2.0P-SO.DG-0003, 2C Diesel Generator Operation, Section 5.4, Diesel Generator Parallel Loading, following maintenance.

• The 2C EOG has been running loaded for 20 minutes at 2550 KW and 1500 KVAR OUT.

INITIATING CUE:


• The CRS directs you to unload and shutdown the 2C EOG IAW S2.0P-SO.DG-0003, Sections 5.8 and 5.9.


STATION:

SYSTEM:


SALEM

Reactor Protection System (RPS)

TASK: Locally Open Reactor Trip Breakers and Control Charging Flow Following Control Room Evacuation IAW S2.0P-AB.CR-0001.


JPM NUMBER: 16-01 NRC IP-j

KIA NUMBER: 012 A4.06 ALTERNATE PATH:! .... _ _.I ----------, IMPORTANCE FACTOR: 4.3

APPLICABILITY: RO

EOCJ RO[KJ STAL] SRO[KJ


REFERENCES: S2.0P-AB.CR-0001, Rev. 23 (checked 9-20-17)

TOOLS AND EQUIPMENT: JAM Key



Developed By: R. Chan Date: 9-20-17

Validated By:

Approved By:

Approved By:

Instructor ff!.(;}../ ]yi /J \ti,,. 0 }M,~"-'\es ,J.l.Air70~~,e~ \O_-)-J.C ii

s~;;;~ructor~~ 101t'-1/17

~ ft/ Date: 11 ;; ) /,, Training Departmenlu-<1-t1L<- '/ ' /'

-b.--~ Date: ... 1,~jt) Operations Department~ )"1€,z..,S



PERFORMED BY:





4.3 SRO

JPM NUMBER:

Rev# Date

00 9-20-17


REVISION HISTORY

16-01 NRG IP-j - .

Description

Added revision history and simulator setup pages. Editorial comments from IP 71111.11 FASA. Incorporated comments from validation.

Validation Required

No




SYSTEM: Reactor Protection System (RPS)



SIMULATOR IC: N/A


OVERRIDES: N/A


• This JPM is located inside the RCA.

• Evaluator must have a JAM key to give to operator at start of JPM. Operators do not have individual JAM keys! Check out key #8 at Work Control Center.

• Notification to control room will be required when opening panel door in the charging valve alley.



NAME: ------------

DATE:




INITIAL CONDITIONS:

• The Control Room has been evacuated in accordance with S2.0P-AB.CR-0001, Control Room Evacuation.

• A reactor trip from 100% was initiated prior to evacuating the Control Room, but the reactor failed to trip from the control room.

INITIATING CUE:


• The CRS directs you to locally trip open the Reactor Trip Breakers and take local control of charging flow by PERFORMING Steps 1 thru 9 IAW Attachment 5 of S2.0P-AB.CR-0001, Control Room Evacuation.






Task Standard for Successful Completion: 1. Locally OPEN Reactor Trip and Bypass Breakers 2. Locally controls 2CV55 to maintain charging flow.





NAME: -------

DATE: -------

TASK: Locally Open Reactor Trip Breakers and Control Charging Flow Following Control Room Evacuation IAW S2.0P-AB.CR-00_01.

.. .. STEP·

· .. No·.·· ,,:#: .· 1 ... ' ,,. ; ':'

;. . . .. " .

CUE:

1.0

; . . , . . . 1 • SJEP . . .. .· > ·" . STANDARD ; >/,(Shadecfarea denotes Critical Step)> ,' <·

······,••.:t ·?(*Critica1Step)\s' :! . (Bolded area:identifies Task Standard) EVAL ., ."···:; ,··. '. ,<\:?.'' . . 't

'., S/U 1 • • ., h't SequentialCritical Step}/; . . . .;;i< .. 1:r:,:·' •· .. ,

Lead Evaluator provides blank copy of S2.0P-AB.CR-0001, Control Room Evacuation, Attachment 5, a JAM Key, and state: "You have a radio and all other required keys."


START TIME:

Operator reviews a copy of S2.0P-AB.CR-0001, Att. 5, and proceeds to El. 84 switchgear room (outside RCA).

OBTAIN the following: Cue: Operator has been provided all the • One copy of this procedure . required items. • One radio (located in Appendix "R"

Cabinet)

• Key ring set and tools (JA Master, Breaker Keyswitch, screwdriver and adjustable wrench).

• A Security Master Key from the Unit 1 CRS (located on the Unit 1 Security Key Rinq)


COMMENTS (RequiredJor

UNSAT evaluation)




NAME: -------DATE:

Locally Open Reactor Trip Breakers and Control Charging Flow Following Control Room Evacuation IAW S2.0P-AB.CR-TASK: OO_Oj~

3.0

4.0

- . .. ·· ·· STEP ' ' . <(shaded area denote~ criHcaFStep)

> ,-..-, , ::: i(*' Critical step··), :W. }?'}:?"" ---·

'<: (ifs,qGehtial Critica1istJ;~r1' PROCEED to Rod Drive MG Set Control. Pane.I (460V Vital Bus Room-El 84'),

· AND OPEN the:following breakers:

· Reactor Trip8reaker A

_ Reactor Trip Breaker B

Reactor Trip Bypass Breaker)\_ .·

·. Reactor Trip Bypass Breaker S:

CONFIRM with the Hot Shutdown Panel Operator (PO) that 21 or 22 Charging Pump is operating.

PROCEED to 2AX1AX7X, #23 Charging Pump breaker AND OPEN the breaker.

STAND:ARD . .. (Bo.lded area identifies Task Standard)'

Operator simulates opening each breaker by removing cover and depressing the TRIP pushbutton until the breaker flag indicates OPEN.

Cue: For each breaker that is simulated open, state: the breaker indicates OPEN.

Note: Operator only opens Reactor Trip Breakers that are currently racked in and closed. Typically the Reactor Bypass Trip Breakers are Open and racked out. So these breakers would be N/A.

Cue: 21 charging pump is operating.

Locates 2AX1AX7X, #23 Charging Pump breaker AND depresses the trip PB to open the breaker. [location: 84' EL. SGWR Room, 2A 460 V MCC]

Cue: The breaker indicates OPEN.

EVAL .. ·.stu


COMMENTS (Required for

_UNSAT evaluation}




NAME: -------DATE: -------

Locally Open Reactor Trip Breakers and Control Charging Flow Following Control Room Evacuation IAW S2.0P-AB.CR-TASK: 0_001.

5.0

6.0

7.0

: . STEP; <,, \ (Shaded are;ipenotes'Critical Step)

· ....• ,•. , {* c·riticatStepf ·· (# SeguerjJial',C'ritical Step)

PROCEED to 2C West Valve & Misc 230V Control Center-El 84', AND OPEN Breaker 2CY2AX41, 2CV175-Rapid Borate Stop Valve.

NOTIFY the CRS of the following: 6.1 The Reactor Trip and Bypass breakers

are OPEN 6.2 #23 Charging Pump Breaker is OPEN.

CONFIRM with NEO #1 that 2CV71, Chr Hdr PCV, is isolated (2CV70) and bypassed (2CV73) and that flow is being maintained to RCP seals at flowrate of 6 to 10 gpm to each seal.

. STAND.ARD. '(Boldedarea identifies:,Ta,sk Standard)

Locates 2C West Valve & Misc 230V Control Center-El 84', and opens Breaker 2CY2AX41, 2CV175-Rapid Borate Stop Valve, by rotating switch to OFF positon. [location: Inside RCA, 84' EL. Aux Bldg., across from AFW pumps)

Cue: The breaker is in OFF position.

Cue: CRS understands the Reactor Trip and Bypass breakers are open and #23 Charging Pump Breaker is open.

Contacts NEO #1 and confirms that 2CV71, Chr Hdr PCV, is isolated (2CV70) and bypassed (2CV73) and that flow is being maintained to RCP seals at flowrate of 6 to 10 gpm to each seal.

Cue: NEO #1 reports 2CV71, Chr Hdr PCV, is isolated (2CV70) and bypassed (2CV73), and that flow is being maintained to RCP seals at flowrate of 6 to 10 gpm to each seal, currently 8 gpm each.

EVAL 5/U


,, COMMENTS :· (Required for

./UNSAT evaluationf'




NAME: --------

DATE: -------

Locally Open Reactor Trip Breakers and Control Charging Flow Following Control Room Evacuation IAW S2.0P-AB.CR-T ASK: 0_0_0_1 --

' ' . > ······ ..... STEP ' ' . . \.': STANDARD·. I COM~ENTS. *, SJ:EP, (Sh~ded area de11otesCntical:Step) ..... • (B ld· .. d .' "d t'f' T k St ... d d)· EVAL · (Required for . . NO· · - , . · .( .. * c. 'f .. · .1 s.t.).' ·.-.,.,.·.···. ·.·.-·· . o e area I en 1 1es. as . an ar , 1_ • • • UNSAT # • .·.. .·. n 1ca ep • , • . ·. .... S/U

• .•. , •... • , , : 1 (#:Sequential Critical Step)S' ., , < ·:.· •.. evaluation)

Proceeds to Unit 2 Panel 216-1, Chg Pmps FL & PR Inst Pnl. (84' EL. Aux Bldg, Charging valve Alley)

Note: Panel 216-1 will alarm in the Control Room. The Control Room must be notified prior to opening this panel, and when it is secured.

NOTE The_ following indications_ and con~rols are Operator reads the Note and continues available for local operation at Unit 2 eve on. Chg Pmps FL & PR Inst Pnl, Panel 216-2:

Operator proceeds into the Aux Bldg • 2CV55 AUTO/MANUAL Selector 84' EL., Charging Pump Alley (RCA

Switch (2HC-128G No. 21 & 22 entry) Charging Pumps Flow to Regen HX) . . .

• 2CV55 Manual HAND/AIR Regulator Note: Use caution (s1tu_at1onal . Control awareness) when entering the Charging

• Ch i p Fl I d" t· 2FI- Valve Alley for hazards such as low arg ng ump ow n ica ion, hanging pipes and bump hazards near

128A . valve operators. • 21 and 22 Charging Pump Pressure

Indication, 2Pl-142B • VCT Level Indication 2LT-114.

8.0 TAKE control of 2CV55, Cent Chg Pmp Flow Cont Valve, by performing the following:

8.1 RECORD the charging flow as indicated on Records charging flow from 2Fl-128A, 2Fl-128A. Charging Pump Flow Indication. __ gpm indicated on 2Fl-128A





NAME: -------

DATE: -------

Locally Open Reactor Trip Breakers and Control Charging Flow Following Control Room Evacuation IAW S2.0P-AB.CR-T ASK: .0001~

Ye,'/, .a:·· ; STE;,P \'•. . .... . . .(Shaded area denotes Critical Step), · .... ;: >. (\Critical Step) .. · •... ·· · ·

(# Sequential Critical Step)::

. STANDARD . (Bolded area identifies Task Standard) EVAL

·· S/U

PLACE local.E/P Bypass Line Selector Valve ih Manual, . .· Locates local E/P Bypass Line

Selector Valve and simulates rotating valve clockwise to Manual position.

Cue: E/P Bypass Line Selector Valve is in the Manual position.


COMMENTS · (Required for

UNSAT evaluation}




NAME:

DATE: --------

-------

Locally Open Reactor Trip Breakers and Control Charging Flow Following Control Room Evacuation IAW S2.0P-AB.CR-T ASK: 0001_.

8.4

,, ... ··. . :,,ST~P .·· ··.·• 1 ....

•(Shaded area denotes. Critical.Step) .. . ... · .. •· * •"•'' •. '• ,,, )····· ,, : \ · ( Cntlca1Step · · ,, , (# SequentiaLCritical Step)

Using the MANUAL hand air operator, ENSURE that the flow rate as noted in Step 8;1 is being maintained with 2CV55.

' . - . · ..

OBSERVE local air pressure indicator to verify local control.

'.STANDARD (Bolded area identifies Task Standard).

Reads flowrate from 2Fl-128A, Charging Pump Flow Indication to ensure the flow rate is maintained with 2CV55.

Cue: Flow rate has LOWERED 10 gpm from flow rate recorded in Step 8.1.

Operator adjusts the Manual Hand Operator in the counter clockwise direction to LOWER air pressure to OPEN 2CV55 and RAISE charging flow.

Cue: Flow on 2Fl-128A reads the value recorded in Step 8.1. IF operator rotates the hand sender in the clockwise direction, THEN report flow reads 15 gpm LOWER than the flow rate noted in Step 8.1

Note: 2CV55, Cent Chg Pmp Flow Cont Valve is fail open valve; air to close.

Raises air pressure to lower flow or Lowers air pressure to raise flow.

Points out local air pressure indicator.

Cue: Air pressure on local air pressure indicator is 8 psig.


COMMENTS ·· (Req'l'.lired for

UNSAT evaluation}




NAME: -------DATE: -------

Locally Open Reactor Trip Breakers and Control Charging Flow Following Control Room Evacuation IAW S2.0P-AB.CR-TASK: 0_0_01.

9.0

CUE:

<f .. : ·STEP ·.... . • (Shaded ,area denotes Critical Step)

. (* Critical Step) . ·· {#Se_<:1uential Critical Step)

NOTIFY the CRS and STA that Steps 1 through 8 of Attachment 5 are completed.

JPM is Complete


STOP TIME: ------

,,·:. x·,· '

· .. . STANDARD . :/ ·· . (Balded areaidentifi~s Task Standard) · 1 EVALt.

·:.s,u

Cue: CRS and STA understand that steps 1 thru 8 of Attachment 5 are complete.

Terminate JPM when operator completes Step 9.0.


COMMENTS (Required for . UNSAT .· evaluation)


JPM#: 16-01 NRC IP-j


fA1 /Vv"' 1. Task description and number, JPM description and number are identified. l ~ 2. Knowledge and Abilities (KIA) references are included.

· ~\k 3. Performance location specified. (in-plant, control room, or simulator)

~ 4. Initial setup conditions are identified.

· Ws 5. Initiating and terminating Cues are properly identified. I ~ 6. Task standards identified and verified by SME review.

7. Critical steps meet the criteria for critical steps and are identified with an asterisk(*).

8. Verify the procedure referenced by this JPM matches the most current revision of that procedure: Procedure Rev. __dj_ Date 10 I '.J-1 \I

~I\~ 9. Pilot test the JPM: ~ a. verify Cues both verbal and visual are free of conflict, and

· b. ensure performance time is accurate.

rJ )J,, 10. If the JPM cannot be performed as written with proper responses, then revise the JPM.

NIA. 11. When JPM is revalidated, SME or Instructor sign and date JPM cover page. )

Date: l o / 'J.- / t l ------

Date: --'-I _o -I-"/ a.'--''1_,_/ _, 1<--

Date: ~lo_,_/_t.•1'-+-· /-+17_

PSEG CONFIDENTIAL - Possession Requires Specific Permission from Nuclear Training Page 12 of 13 Rev. O

INITIAL CONDITIONS:

• The Control Room has been evacuated in accordance with S2.0P-AB.CR-0001, Control Room Evacuation.

• A reactor trip from 100% was initiated prior to evacuating the Control Room, but the reactor failed to trip from the control room.

INITIATING CUE:


• The CRS directs you to locally trip open the Reactor Trip Breakers and take local control of charging flow by PERFORMING Steps 1 thru 9 IAW Attachment 5 of S2.0P-AB.CR-0001, Control Room Evacuation.

PSEG CONFIDENTIAL - Possession Requires Specific Permission from Nuclear Training Page 13 of 13 Rev. 0

STATION:

SYSTEM:

SALEM


Liquid Radwaste System

TASK: Perform a Radioactive Liquid Release and TCAF High Radiation Monitor Alarm during release IAW S2.0P-SO.WL-0001


JPM NUMBER: 16-01 NRC IP-k

ALTERNATE PATH: KIA NUMBER: IMPORTANCE FACTOR:

APPLICABILITY:

EOD RO[ZJ STAD sRo[ZJ


REFERENCES: S2.0P-SO.WL-0001, Rev. 28 (checked 10-2-17) S2.0P-TM.ZZ-0002, Rev. 8

TOOLS AND EQUIPMENT: S2.0P-TM.ZZ-0002 Tank Capacity Data



Developed By:

Validated By:

Approved By:

Approved By: Operations Departmen



PERFORMED BY:




068 A2.04 -----------! 3.3 3.3 RO SRO

N/A

DATE:


JPM NUMBER:

Rev# Date

00 10-2-17


REVISION HISTORY

16-01 NRC IP-k

Description


Validation Required

Editorial Yes




SYSTEM: Liquid Radwaste System



SIMULATOR IC: N/A


N/A

OVERRIDES: N/A


• This JPM is located inside the RCA. • ENSURE Lead Evaluator has a copy of S2.0P-TM.ZZ-0002, Tank Capacity Data, to provide

to Operator when requested. Note: Field Copy does exist at the Radwaste Operator desk by the 104 Panel.



NAME:

DATE: ----------------SYSTEM: Liquid Radwaste System



INITIAL CONDITIONS:

• Preparations for a release of 21 CVCS Monitor Tank via Unit 2 SW system to Unit 1 CW system is in progress !AW S2.0P-SO.WL-0001, RELEASE OF RADIOACTIVE LIQUID WASTE FROM 21 eves MONITOR TANK.

• Chemistry has granted permission to release 21 CVCS MT at a Maximum Release Rate of 45 gpm due to the high curie content of the tank.

• 2R18 and 2FR1064 Flow Recorder are both OPERABLE.

• All Unit 1 CW pumps are in service.

INITIATING CUE:


• The CRS directs you to release 21 eves MT !AW Section 5.5 of S2.0P-SO.WL-0001.

I Successful Completion Criteria:




4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made (and NRC concurrence is obtained).

Task Standard for Successful Completion: 1. Controls the discharge of 21 CVCS MT to less than the Maximum Release rate. 2. Takes required action to terminate the release when 2R18 is in Alarm.


I

1 ·.;;


JOB PERFORMANCE MEASURE NAME: _________ _

DATE: _________ _ SYSTEM: Liquid Radwaste System


STEP STEP STANDARD COMMENTS * (Shaded area denotes Critical Step) (Bolded area identifies Task EVAL (Required for UNSAT #

NO. (* Critical Step) Standard) S/U evaluation)

Provide candidate with marked up procedure Give operator marked up copy of S2.0P-(partial procedure) S2.0P-SO.WL-0001, SO.WL-0001. RELEASE OF RADIOACTIVE LIQUID WASTE FROM 21 eves MONITOR TANK.


START TIME:

5.5 Release of 21 eves MT via SW System to CW System

5.5.1 IF 2FR1064, RADWASTE OVERBOARD Marks step N/A; 2FR1064 is OPERABLE. DISCH FLOW RECORDER is INOPERABLE, THEN INITIATE Attachment 4, Section 4.0 .

.•.. .. 5.5.2 ..• · DIRECf Unif2 NCO to OPEN2WL51, LIQUID. Operator simulates using the plant page or *·· ... RELEASE STOP VALVE . ··· phone to call control room.

Operator DIRECTS Unit 2 NCO to OPEN 2WL51 .

. ,. Cue: Unit 2 NCO reports 2WL51 is OPEN .

.

5.5.3 DIRECT second Operator to PERFORM Independent Verification of 2WL51, LIQUID Cue: IV has been performed. RELEASE STOP VALVE, position in Attachment 2, Step 4.1.2 OR 4.2.2, as applicable (ODCM).





DATE: _________ _


* #

*

STEP NO.

5.5.5

Caution


* Critical Ste . THROTTLE OPEN 2WR59, MT PMPS OB ·

, 'STOP VAL VE; to obtain less than or equal to Max1rrium .Release Rate recorded in · Atta9hment 2! Step 2.2,2 ...•.

DIRECT second Operator to PERFORM Independent Verification of 2WR59, MT PMPS OB STOP VALVE, position in Attachment 2, Step 4.1.3 OR 4.2.3, as applicable (ODCM ,. Completely closing 21WR53 will NOT provide sufficient recirculation to protect the pump should 2WL51 isolate due to high radiation alarm.


Standard Operator locates 2WR59 and simulates opening valve by turning valve hand wheel in the counterclockwise direction. [location: Gas Stripper Feed Pump Room, 64' El. Aux Bldg.]

Cue: The 2WR59 is full open.

Cue: When operator checks the 2FR1064 flow recorder on the 104 panel, THEN report; flow is reading 5 gpm.

Cue: IV has been performed.

Operator reads Caution and continues on.

EVAL S/U



evaluation




DATE: _________ _


* #

STEP NO.

5.5.7

5.5.8


* Critical Ste IF Ma:ximum Release.Rate recorded in Attachment 2, Step 2.2.2, NOT obtained with 2WR59, MT PMPS OB STOP VALVE,

. fully'open/THEN THROTTLE 21WR53, MT RECI RC}v, to obtain less than or equal to Maximum Release Rate recorded in · · Attachment 2,.Step2.2.2 ...

IF 2FR1064 flow monitor is OPERABLE, THEN RECORD time, date, and tank identification on recorder. COMPLETE Attachment 2, Section 5.1

21 eves MT Release Initial Data:


Standard Operator locates 21WR53 and simulates throttling valve CLOSED by turning the hand wheel in the clockwise direction to raise flow. [location: eves MT Room, 64' EL Aux Bldg. 21WR53 is about 7 feet above the floor]

Cue: When operator checks the 2FR1064 flow recorder on the104 panel after going in the CLOSED direction, THEN report; flow is 50 gpm.

When flow is > 45 gpm, the operator lowers flow by OPENING 21WR53 in the counterclockwise direction until flow is less than 45 gpm.

Cue: When the operator adjusts the 21 WR53 in the OPEN direction, THEN report that flow is reading 40 gpm.

Note: During actual releases, the best flow achieved during this evolution is about 50

m. Operator simulates annotating recorder with time, date and tank.

Operator Records data IAW with the provide information below.

EVAL S/U



evaluation

;vsTEM: Liquid Radwaste System


JOB PERFORMANCE MEASURE NAME: __________ _

DATE: _________ _

"ASK: Perform a Radioactive Liquid Release and TCAF High Radiation Monitor Alarm during release IAW S2.0P-SO.WL-0001

STEP STEP STANDARD COMMENTS * (Shaded area denotes Critical Step) (Bolded area identifies Task EVAL (Required for UNSAT #

NO. (* Critical Steo) Standard) S/U evaluation)

• 21 CVCS MT Level (2LIS180) Cue: When operator reads 21 eves Monitor Tank Level on the 104 panel, state; 2LIS-180 indicates 90%.

• 21 CVCS MT Volume (1) Cue: When operator reports the need to obtain S2.0P-TM.ZZ-0002, Tank Capacity

(1) Obtain tank volume from S2.0P-TM.ZZ- Data (Note 1 ), THEN provide the data 0002(0), Tank Capacity Data. sheet for eves Monitor Tank.

Operator uses provided data sheet and determines a tank volume of 19,500 gallons (acceptable range between 19,200 to 19,800 gallons).

. Dilution Flow Rate Cue: Chemistry paperwork indicates dilution water flowrate is 200,000 gpm.

Records Dilution Water Flowrate of 200,000 gpm. Initial conditions stated all circulators were in service. 2 Circulators used x 100,000 = 200,000.

. Discharge Flow Rate (3) (2FR1064) Records 40 gpm for Discharge Flow Rate.

Cue: 2FR1064 reads 40 gpm.




JOB PERFORMANCE MEASURE NAME: -----·-----DATE: _________ _


* #

STEP NO.

CUE:


* Critical Ste • 2R18 Monitor Reading (5)


IF any,of .the following'occur-during release, . JHEN DIRECT'NCO to.CLOSE 2WL51, . LIQUID REl:.EASESTOPVALVE: ..

~ ' '

•!• L0SS'of dilutionwaterflo~-- · ''•v ,',

+· 2FR1064 becom~s inoperable

. · •!• · 2R1 i3 M~nit~/ALARMS

•!• <MTPump press(JreJallsbelowMDP alloWecflAW Attachment4 ..

,. . \1"

JPM is complete when the task is complete OR at the direction from the Lead Evaluator.


STOP TIME: _____ _


Standard Cue: When operator reads the 2R18 on the 104 panel state; 2R18 reads 105

counts per minute and the 2R18 High Radiation light is illuminated.

Operator simulates calling the main control room to report that the 2R18 is in ALARM and DIRECTS the NCO to CLOSE 2WL51.

Cue: Unit 2 NCO reports that the 2WL51 is CLOSED .

Terminate the JPM when the Control Room reports that 2WL51 is CLOSED.

EVAL S/U



evaluation


JPM #: 16-01 NRG IP-k



/IPA 1. Task description and number, JPM description and number are identified.

J ~Ah-~ 2. Knowledge and Abilities (KIA) references are included.

kv\ 3. Performance location specified. (in-plant, control room, or simulator)

I JVA ~ --+-~_LA __ 4. Initial setup conditions are identified.

M~\ 5. Initiating and terminating Cues are properly identified.

I ~ 6. Task standards identified and verified by SME review.

_·,....Jt~k __ 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*). !

--+'/L'--1,A~'-. _ 8. Verify the procedure referenced by this JPM matches the most current revision of / 4> that procedure: Procedure Rev. 1/+-~ Date /0--J.-~l,

/l/lft 9. Pilot test the JPM: ~ a. verify Cues both verbal and visual are free of conflict, and

· b. ensure performance time is accurate.

tJ IA 10. If the JPM cannot be performed as written with proper responses, then revise the JPM.

N/A 11. When JPM is revalidated, SME or Instructor sign and date JPM cover page.

SME/lnstructor: Date: tc-:z.-11

SME/lnstructor: Date: /o / Z'I [I?

SME/lnstructor: Date: IV ta-4. l, 1


INITIAL CONDITIONS:


• Preparations for a release of 21 CVCS Monitor Tank via Unit 2 SW system to Unit 1 CW system is in progress IAW S2.0P-SO.WL-0001, RELEASE OF RADIOACTIVE LIQUID WASTE FROM 21 CVCS MONITOR TANK.

• Chemistry has granted permission to release 21 CVCS MT at a Maximum Release Rate of 45 gpm due to the high curie content of the tank.

• 2R18 and 2FR1064 Flow Recorder are both OPERABLE.

• All Unit 1 CW pumps are in service.

INITIATING CUE:


• The CRS directs you to release 21 eves MT IAW Section 5.5 of S2.0P-SO.WL-0001.


S2.0P-TM.ZZ-0002(Q)

CHEMICAL & VOLUME CONTROL MONITOR TANK

100 ~: - ---==·-.:--·~~~~~-----_-:·~-:~ -[-T-Ll-r-·-=--·:·: -OVERFLOW -- :11~----~J~~:=

- >-. -- _j__f--.

f-+--l-+-l-f---1-1-f-!-I- -~~- - - .I I- --L f-- I I/

1 1 1 l I v lf--'-1 I I I - --~~ -·- ,_,_,_ j '

90 - - --+-l--+--+-+-+-+-•-1-~;- -+-+--+-1--i . HIGH ALARM I- -I (~~"---t--+-++-+-+-+-+-+-+-+-+-I-H-1-1 ,• I

1--t--1"---t--+-++-+-+-+-+--+--+-- ~e- -- . - . . = --, -~ :_ t+-1-,-+--+!---+-t-t-J·,+j--+-,f--+-+-1-1-+-+-+-+-I +-. -

-A-,-+-+--+-+--+-r-+--+-< -- - t- -

so -- __ . V I .

_i_ --:++ I- ..•. I ---rt~,~----- ---- -+ T I i r- f .T ··'- - ... -- ·- -r -1--,-,-l--+-+-+--l-h'-'-+-+-l-l-+-+-!-f-1-1-~'-l-l-+-I

-----1 1 7-- r--.. --····-----

70 · - - ·- - - ·- -1---- ·rr- ---1- ·----1

--- ·· 11;_ _J_r_1 ____ L _____ - ---I ~ -+-1 I 1 --1--I-!- '1 .,... -f--.1f--.

; 60 --- + - +~-=--=- 1/ - I (

~ :: IL~-v 1L1 I IJ : -~r11 ~= ~ 50 ·+-+I _ _, ......,_,__1--f--_,_r + f --- ·- rl- -v · ---+-f--. 1

: : i l ~ -~ .1 1 111 r- -- -h--rr~ ~-- ---- --,- ~ f--.

@ -T 1 :-lt+ :-----~~~ : 11 JI < 40 . I I ' -I/ -1 i I i I ~ -~ I - f7 - -- -f- +1--L--+-1-1-: -+-+-l-+-1-f---1-1---1-+-+-+--1-+-+--

~ , : - V~ . r-r- . I I ! n1=----r---r-··---··:_:_:~~ -/- -. -~-I::: I- - .. +·---T I J __ _

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i _ _11

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, 1l~ - ~==~~:=·t= :::::::~:::: _ ~= 10 :~- --+-~~I LOWAc.;~L-'ti·~~ -- -· -· · -------·->-->---,-----

,., ·- .. - ·-i- - -, . t - -- -i-+-!-+--+-+-+-!-+-f--+-+-!--1-1-·-~~ -~--!·- -- -T --u.i/ LEVEL ~);::I r r---- =----H- <l

0 - '--- - ·-·- .. - _f-L-L._.!......l......!.........C..-1----l-..L.....l.....-'-'-.LJ....J'......!......j.....L....L....J_j_-L....L...LJ.....--'-f--..1.....l......L.....L...L....l.......~

0 5000 10000 15000 20000 25000

CONTAINED VOLUME IN GALLONS

Salem Unit 2 Page 8 of34 Rev. 8

SIMULATOR

TQ-AA-106-0204 Page 1 of 39

EXAMINATION SCENARIO GUIDE

SCENARIO TITLE:

SCENARIO NUMBER:

EFFECTIVE DATE:

EXPECTED DURATION:

REVISION NUMBER:

PROGRAM:

Revision Summary:

16-01 ESG-1 [AB.PZR-1, AB.SW-3, AB.RCP-1, TRIP-1, TRIP-2, SGTR-1] 16-01 ESG-1

See Approval Dates

70 minutes

00

~-~I LO. REQUAL

X I INITIAL UCENSE

~-~jSTA

~-~' OTHER

New issue for 16-01 ILOT NRC exam

PREPARED BY: R. Chan 8-18-17 Lead Regulatory Exam Author Date

APPROVED BY: (rt :P

APPROVED BY: ' Date


TQ-AA-106-0204 Page 2 of 39

TQ-AA-106-0204 Page 3 of 39

A. Given the order or indications of a pressurizer control system malfunction, perform actions as the nuclear control operator to RESPOND to the malfunction in accordance with S1/S2.0PS2.0P-AB.PZR-0001.

B. Given indication of a pressurizer control system malfunction, DIRECT the response to the malfunction in accordance with S2.0P-AB.PZR-0001.

C. Given the order or indications of a SW Bay leak, perform actions as the nuclear control operator to RESPOND to the malfunction, IAW approved station procedures.

D. Given the order or indications of a SW Bay leak, DIRECT the response to the malfunction IAW approved station procedures.

E. Given the failure of affecting a Reactor Coolant Pump, perform actions as the nuclear control operator to RESPOND to the failure IAW S1/S2.0P-AB.RCP-0001.

F. Given the failure of affecting a Reactor Coolant Pump, DIRECT the response to the failure IAW S1/S2.0P-AB.RCP-0001.

G. Given the order or indications of a reactor trip, perform actions as the nuclear control operator to RESPOND to the reactor trip in accordance with 2-EOP-TRIP-1.

H. Given indication of a reactor trip, DIRECT the response to the reactor trip in accordance with 2-EOP-TRIP-1.

I. Given the order or indications of a safety injection, perform actions as the nuclear control operator to RESPOND to the safety injection in accordance with the approved station procedures.

J. Given indication of a safety injection, DIRECT the response to the safety injection in accordance with the approved station procedures.

K. Given the order or indications of a steam generator tube rupture, perform actions as the nuclear control operator to RESPOND to the tube rupture in accordance with the approved station procedures.

L. Given the order or indications of a steam generator tube rupture, DIRECT the response to the tube rupture in accordance with the approved station procedures.


A Power Ascension

B. Controlling PZR Pressure Channel fails high

C. #2 SW bay leak

D. 22 RCP #1 seal degradation and seal failure

E. 24 SG Tube Rupture

TQ-AA-106-0204 Page 4 of 39

A The crew will take the watch with the unit stable at 3% reactor power during a plant startup, BOL. 21 SGFP is in service and 22 SGFP is 0/S. Steam dumps are in Main Steam Pressure Control, Automatic, set at 1000 psig. 23 Charging pump is CIT to troubleshoot flow oscillations with the fluid drive. The crew will be instructed to raise power to 10% and enter Mode 1.

B. The crew will initiate power ascension to 10%, and enter Mode 1, using Main Steam Dumps and control rods IAW S2.0P-IO.ZZ-0003, Hot Standby to Minmum Load and S2.0P-SO.MS-0002, Steam Dump System Operation, Attachments 3 or 4.

C. After the crew enters Mode 1 (about 6% Rx power), the controlling PZR Pressure channel will fail high, deenergizing PZR heaters and causing both PZR Spray valves to fully open. The crew will respond IAW S2.0P-AB.PZR-0001, Pressurizer Pressure Malfunction, to establish manual control of PZR pressure control and restore pressure to normal, transfer to an operable channel, and remove the failed channel from service. The CRS will evaluate Tech Specs. [Tech Specs exercised]

D. After the Pressurizer Pressure channel failure has been addressed, a service water (SW) leak in #2 SW bay will occur. The crew will respond IAW S2.0P-AB.SW-0003, Service Water Bay Leak. The crew will split the SW headers, stop all SW pumps in #2 Bay and isolate the leak. The CRS will evaluate Tech Specs. [Tech Specs exercised]

E. After the SW Bay leak is addressed, 22 RCP #1 seal will degrade indicated by an increase seal leak-off flow. The crew will respond IAW S2.0P-AB.RCP-0001, Reactor Coolant Pump Abnormality. The crew will evaluate the seal degradation and determine a course of action which could include an orderly unit shutdown.

F. After the crew determines a course of action to address the seal degradation, the #1 seal will fail resulting in the crew initiating the CAS of S2.0P-AB.RCP-0001 and Attachment 2 for stopping RCPs. The crew will trip the Rx, confirm the trip, stop 22 RCP, and then within 3-5 minutes close 22CV104 [CT#1].

G. The crew will perform immediate actions in EOP-TRIP-1, Reactor Trip or Safety Injection, and then transition to EOP-TRIP-2, Reactor Trip Response, based on no SI required.

H. Shortly after transition to EOP-TRIP-2, 24 SG will rupture (650 gpm) and the crew will manually initiate SI and return to EOP-TRIP-1. While in EOP-TRIP-1, the crew will identify that a FW isolation valve (24BF13), did not close on SI / Phase A signal and will take manual actions to close 24BF13 from the control room.


TQ-AA-106-0204 Page 5 of 39

I. The crew will identify that 24 SG has a tube rupture based on SG narrow range levels rising, and several radiation montors in alarm, and transition to EOP-SGTR-1, Steam Generator Tube Rupture.

J. While in EOP-SGTR-1, the crew will isolate feed and steam flow to the ruptured 24 SG and initiate a RCS cooldown using steam dumps to the target temperature IAW Table B, Required RCS Cooldown Temeprature. The crew will stop the cooldown when the hottest CETs are less than the required RCS cooldown temperature [CT#2]. Note: the crew may have initiated MSLI while in EOP-TRIP-2 based on RCS temperatures not being controlled. If so, the crew will cooldown the RCS using intact MS1 O's.

K. The scenario will be terminated after the hottest CETs are less than the RCS cooldown temperature and the cooldown is stopped.


IC-233

Initial I Description

1 VC1 and VC4 CIT

2 RCPs (SELF CHECK)

_ 3 RTBs (SELF CHECK)

_ 4 MS167s (SELF CHECK)

_ 5 500 KV SWYD (SELF CHECK)

_ 6 SGFP Trip (SELF CHECK)

_ 7 23 CV PP (SELF CHECK)

8 21 SGFP is in service

__ 9 23 Charging pump is CIT

TQ-AA-106-0204 Page 6 of 39

10 IOP-3 open and complete up to step 4.3.19, Power Operation. Attachment 4 is marked up.

11 Steam Dumps are in MS Pressure Mode and Auto, and S2.0P-SO.MS-0002 is open and marked up to step 5.4.B

12 Rod control in manual.

13 Complete Attachment 2 "Simulator Ready-for-Training/Examination Checklist."

Note: Tables with blue headings may be populated by external program, do not change column name without consulting Simulator Support group


TQ-AA-106-0204 Page 7 of 39

,'A~/ ,:~:~,\~fr,~1:::_?tt&\i:;.·:·Y'··· ,)-'. -~;;:\~ ,,:>~<:

II 1niti_~ ET# _Descriptio~~~-~----~----~~----------~--~-~-~------ ~-------~---~~ -~- ___ -~ _________ Jj

EVENT ACTION: KBN12TCY //24BF13 FW INLET STOP VALVE CLOSE

1

SELF-CHECK

01

02

03

04

05

COMMAND: DMF VL0026

PURPOSE: <update as needed>

Description

PR0016A PZR PRESS CH I PT455) FAILS H/L

SW0216A 21 SW HOR LEAK IN SW STRUCTURE

RC007B 22 RC PUMP - #1 SEAL FAILS - w/ DEGRADATION

SG0078D 24 STEAM GENERATOR TUBE RUPTURE

VL0026 24BF13 Fails to Position 0-100%

,, (?:;J{f'.'J7f.~ ,;,,/<,;p,:, r;f:~r V

i]: :,REMOTE ./\,:;,l\i,:"'. '. :r ,'~itZ ',At,;

SELF- Description CHECK

01 RC05A RCS SYSTEM , BORON CONC RESET

02 AF01 D 23 AUX FP TRIP RESET

03 CV52D 23 CHG PUMP BKR CONTROL POWER

04 CV53D 23 CHG PUMP RACK OUT

05 PR34D PORV STOP VALVE 2PR6 TAGGED

06 SW23D 21 SW PUMP BKR CONTROL POWER



09 MT03D MAIN TURB TURNING GEAR START PUSHBUTTON

10 MT02D MAIN TURB TURNING GEAR ENGAGE

SELF- Description CHECK

01 Cl11 EDI KCl11PB2 TURNING GEAR-STARTED

02 Cl 11 C LO QCl11 HR2 TURNING GEAR-ENGAGED

03 Cl11 FLO QCl11TG2 TURNING GEAR-STOPPED

04 Cl11 E LO QCl11PR2TURNING GEAR-STARTED

05 Cl 11 D LO QC! 11 LG2 TURNING GEAR-DISENGAGED

Delay Initial Ramp Time Value Time

N!A NIA N!A

N!A 0 00:03:00

NIA 0 00:01 :00

NIA NIA. NIA

NIA N/A N/A


N/A NIA NIA

N/A NIA l'JiA

N/A N/A N/A

N/A NIA N/A

N/A WA NIA

N/A NIA NIA

00:00:10 N!A N/A

00:00:20 N/,A, NIA

N/A NIA N/A

NIA NIA l'l/A


N/A NIA Nil,

N/A N/A NIA

N/A NIA NiA

NIA N/A N/A

NI;\ N!A N/r'1

Trigger Severity

RT-1 2500

RT-2 8000

RT-3 0.75

RT-4 650

NIA 100

Trigger Condition

NIA 1827

N/A RESET

r,J/A OFF

N/A TAGGED

RT-10 TAGGED

RT-11 OFF

RT-11 OFF

RT-11 OFF

NIA DEPRESS

PB

NIA ENGAGE

Trigger Condition/ Severity

NIA ON

N/A ON

NIA OFF

NIA ON

NIA OFF


Description

1. None

TQ-AA-106-0204 Page 8 of 39


A. State shift job assignments.

TQ-AA-106-0204 Page 9 of 39

B. Hold a shift briefing, detailing instruction to the shift: (provide crew members a copy of the shift turnover sheet).

C. Inform the crew "The simulator is running. You may commence panel walkdowns at this time. CRS please inform me when your crew is ready to assume the shift".

D. Allow sufficient time for panel walk-downs. When informed by the CRS that the crew is ready to assume the shift, ensure the simulator is cleared of unauthorized personnel.


TQ-AA-106-0204 Page 10 of 39

~ ; '•9 <,•• •'••'j <•• "/,-S>., <• :,>' •••:,~ ," ,_' •• ,'W,'' { n • ; 0 0 >. ~ ' ~ ),s { ' ';~ " S S /~-.'" '9' ) S,«" ~J:~ f '''':-. •))"CC ,,·,,<%->.•,:.•o,0'."•:•, ,,{ i>Yc'.'3 "'~,-,..,_,~\,!:'.,''.•>'' .".N',;f.':~,~'J.'./i~~r',/:,->'"\

c .. yJ,=yaJuator/ltistrucfor,Actiyity, :1'' , •· .,,' Expected Plant/Student·RespoJise· · '· ·~ · .. S.I3T·:·; ,u" ·". :/: j;:1: PomrtJ,lit'.tt ;:,>'s; .

1. Power Ascension

·Evaluator's Not~: fhecrewwill .,.·be'dsing'.'.Sg:p~-10:cZZ'-0,003,'.:Hot.·.,,:, •..

. ~l!liil{ltiilif i( ', Durn ·· s O\w,s2:op .. so:Ms:.:0002: ,'~ }· ... p " .. ; , .. ,,. '"· .. ·' ., . ' ..... ,,,,. \Tne!crew''cart useAttachmerifa'3 of, ' '',.:[ofiS2tOP2SO:f\A$~d002, t()dperate ;

1ii!iiii!i~:~:~' .:,Eya]:lJijf°'r;~,Nq~~:59abs9fe:aJarf!i ; .. ·•· 'Rc·roops· :r· · .. '"'·T·'',f . ;'' .•·"

'. ,. ,, ,;,'"':-,. .. ;' r'' ,\ .a~g>:'l:1 f'jl ;;., '.(,)l , DEVIATIO~,wiH bein;·~t·.;th~Jimet:;

;,tne~rew;it~~f/s4fle lf.rafct,.)t1:he, ····· ... • :cte'tv.J.,iJi1o~·,t>r~~ici~a.R1st}ucuptJs.v, i.di:itjr1g:f4rripve~''foafy~tificatioh.of,.l.

-r '\/{ 1 ,· 41" 4 'n .·· +. 1'r . ' T >f .. . ' .::11a g,1s15 .. ~i:::.,o, ce,pe.,30Jn nu es: ;: .. ypfi1.,~1srm,J~ft~~~fit,)"¢~ptc~1~~~8onvf. '.':N.arratiVeilt'qgJ$b,eingp.erfotrned,;1t: .. f , · i;;;,y·· ···the·· ,,·e· x•·t·r·a·'xNc"o· ·\ .·i\;,, • '/">.,J;,,., ,-U " .. ,· .. ,, . _, .-· , _.. , , ,~" /1.: , ,,".J,)":" ";' "''

,' ;<,. ·i"'.'

This·atarmWiil ci;ir'd~~r11§'fhe : .. . ewer. ascension into Mode J.


. · .. . ,Evaluafor/lnstructor:Activity' .,~.~,·,):<::~\;~:· ,,3 • }i;.: :;;~,::~··.·,~· .. ~ .•:~/~.;~:~ >);·· >'~'.~\ ,"; ' •. ,.. •V' ' ,,~

Evalua.torfs·.J\lote:The'CR$will · ... ·. airect the crew in the order ir:i \A/hich to· raiSt3.RX ppwer bywithHrawing,. ·•·· c'oritrolrods or raisfng· sfeam'dump

'deniand'firsi: . . ...

,<E."'aluat(fr's No.te: Program Tavg :at.JO'.% gx poweri§iabput5,49 .. Fi.i.

, Dq~i~~f'~irii~fatbrr~~s:1'1;;·~ ... · . Durnp Rressure setfing .• was •abotit .982 psig.fora Rx Power of.5.4% ..

Simulator Qperator: When Rx B.c,wer)s abo1.1f6%,'THEN; .··· ·.·· . continue fo,nexf event by direction' from Lead evaluator. '; .

TQ-AA-106-0204 11 of 39

j~:$.7@t~,~:~.'~f :g~~~e:ij~·~:~~Z~:~:~;:ir:t;;,'.'.!"~:,;;·I~::.:2g~\r1?:'~*:,:;:.,~5";:::t·· " CRS directs power ascension using Main Steam Dumps in MS Pressure Control and control rods.

PO raises steam dump demand IAW S2.0PSO.MS-0002, section 5.4 using Attachments 3 or 4.

RO withdraws control rods at the specified increments to maintain Tave on proqram.

RO announces when NIS indicates 5% Reactor Power and RECORDs time of Mode 1 entrv in Control Room Narrative Log.

PSEG CONFIDENTIAL • Possession Requires Specific Permission from Nuclear Training

, ''>E'; ,,.,·< ,,,,, ·\ ·,· · "'" · , · · "·, ,; "' , \' ·.- ,,,. ·. , ,, •. · ·· ''.;. ·: ,. , .,. · ',.; ,,,,,,. R'· · ,., .,.,.i., · · 'ii:' ·,. ..· s···,·s· ·,. ,,.," ,Js·,,""'"0' ,;,< va.lJatorJnstructor Act1v1ty.11,;,, :>\·''r. :1Expec;ted, Pant/Student· f3Sponse:xr;,w;:< '1:'~'l:,J, ,·.· ,:c,.;:,,;.,:;;.,: ,·"'

2. Controlling PZR pressure channel fails HIGH

,,CSimUlato(Operator:·'lhserf.RT-t;><' i,oii · ctirecti6ri'tr6nfte~'8'~Evafuatqr) ,: ·:

.'1,IV1AL;E:YMALF;.,PROOi6A"PZR),'.f : '. ,,':.pr~ssJ:;F1;;1;(F\fi4ss),fai'ts,ii1t,·,• .. ·, . r:·i=inaiVa1uJfr2soo oc,·

RO announces unexpected OHA alarms D-8 RC Press HI, and E-42 2PR1 ~ Trip.

RO determines actual pressure is not high and reports spray valves open and recommends placing Master Pressure Controller in manual.

CRS directs RO to place Master Pressure Controller in manual.

RO takes manual control of Master Pressure Controller and lowers demand (increase pressure) to close sgray valves.

CRS enters S2.0P-AB.PZR-0001, Pressurizer Pressure Malfunction.

At anytime the CRS may direct the power ascension to be placed on hold.

CRS directs initiation of AB.PZR-0001 CAS.


TQ-AA-106-0204 12 of 39

f Y : EyaluatBrJi nstructor.Activity:: ):::;( ·;.,; .. ~Eicpected·Plant/Sfuaenf:Respons~:" ''·:Jt:;.y:;::';:?j:;;, :~I:.,,f:";:~·)\'w;;,,;;; ;~2z;1~~:;t~!,,:(;,;.z:t.',\~i:::~{;',:;~;;(;~f:fi.1Ift~1~.}:~ :~·.·t:; f • '.~., t11:;;:::••· :t ~? •·· :~t: .t )*:'"¥¥'.:J ... "."'. ,,;'4,,. tlf,;,-~.~ .• ··.·.

Evaluator's Note: The '·· <. ,'.requirement to plose PZR PORV.::{' .,:@.1.99~Y~ty~: t2e~6,t~r,iP;f~rnoye ·: ··• :.cootrqr·pow~r:is.requited,to'.be"'··· . per,fortned within.onehc5ur'fo 'Jfolnf>lY __ V\l!tlfJS;3I4. 5 act/Oh b: , .. : ··

.. S!~~latp(c,per~t.~~=)?5s~rt~T.:1o • . 2fl)mutes·after·bemg drrected to•

·: r~foo~E(powe'rfrom.2PR6t'?·;:.······· 'REMOTE:,PR34D ~ORVSfop Valve2PR6faaaed . .

CRS qives band for control of PZR pressure.

RO identifies PZR Pressure Channel I failed hiqh.

CRS verifies that Master Pressure Controller MPC) is in Manual.

RO adjusts MPC demand signal to be consistent with Attachment 2 to restore

ressure to proqram.

RO selects Channel Ill for control.

RO matches MPC demand to current pressure and returns MPC to AUTO.

RO closes 2PR6 and places 2PR1 in Manual.

CRS directs WCC to remove control power from 2PR6 .

PSEG CONFIDENTIAL · Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 13 of 39

Evaluator:s'Note:Crew.·mayw~it. fo~;)&,C:sµP,pott'5~fore'.' perfc;,rn:iing; .. ·aQy; act1ohs;J,!i. S2; OP2S.O:R,PS:-..

:'.0003;J.1:fl{e,..steps~peovjdt3d below·

:l!t!!{~?;!i~,!~ff "CRS; the'c•rest:[1eedfl&C:sUpQQrt. •··

Steps from S2.0P-SO.RPS-0003, Placing PZR Pressure Channel in Tripped Condition:

Proceed to next event after CRS evaluates Tech Specs or by

CRS directs PO to initiate removing failed channel from service and contact l&C for support IAW S2.0P-SO.RPS-0003.

PO checks that tripping associated bistables will NOT result in an ESF or RPS actuation.

PO verifies that Channel Ill is selected for Master Pressure Control.

PO selects PZR Pressure recorder to channel II (111) (IV).

PO selects Reactor Coolant Temperature, Differential Temeprature Recorder to Loop 22 (23) (24).

CRS enters TSAS; 3.3.1.1 action 6, 3.3.2.1.b action 19, 3.4.5 action b, and 3.2.5 {DNB).

TQ-AA-106-0204 Page 14 of 39

.·"'"·;·~;E~·1~f K''S:"·


i:~!r1!.\~F~,:~tf ~t?it1:1~f f :·t~J.i;i~t? -. · · ·i:':~tr:E!~~:;r;!!~t!!udt'~±;~:f ,~.f t!.(f0

tI:::/:::'.?~t1;~€d1'.t ... · direction from Lead Evaluator.

3. #2 SW Bay Leak

Sirnulatgr Operaior':.fnseft RTL2os· :, ori <lire:Cficih · from Eead Evaluator:,• I ~;~} .·:. \j, ;lt~f!'., \{)\(t i <;, ~.' •. )t::;~\ . , . . ··••·.MALF:;;$~0216A1;2.tSW L:EAKIN ,: 1tf~\TJ~?1·~(~.1::'.*t;f,·,l;::!J, ./ .,, .. » F'inar,Vcrlue ·~ ~1000

Evaluator'sNote:, ThefirstOAA' :i.yilJ ~f1riuoci.~f(;'.;~f minute ~ft~f the .. %

lea~ is inserted ..

RO announces unexpected OHA alarm B-29, followed shortjy by OHA B-13 and B-14.

OHA B-29, 22-23 SW PMP SUMP AREA LVL HI, directs entry into S2.0P-AB.SW-0003, IF OHA B-13, 21 SW HOR PRESS LO, is alarm in~.

Crew dispatches NEO to investigate leak in SW bay.

RO either starts a SW pump based on lowering SW header pressure, or announces the auto start of 25 SW pump when it occurs, and the clearing of the low SW header pressures alarms.


TQ-AA-106-0204 Page 15 of 39

·m~rt. ::0t,:J{h; ..

'1rttt'~f I!.ilt·r~}~I~~ti~{]Y,; tJ.~:'i1::,r;~~~f ~~81~!?:~01~~!~ae~t,:~~~ij~,":·r~t?S~.:~:<?,tg~,:·

. Ev,al,u~t!?i::s J'1otE3?. OHA ~-29 ARP als9, dire:c~s::.ipitia.t~on.ot:S~:01?~ •>, «\;•.

?\~i:??7:qopgr·f199,qing\::1:~~ .. q139\ ··. ·. qaQ'.;ipitiatett~fsproceduref.aftet)he · 'swYsayleaK".is'..aadressed·int,. :·'.;' · •.. f..s:"swioo63~,.,. .. · ·.· , ... , .. ,, .. ,

Role Play: .. Heportthe{ollowing· <after?~tep~\o./ip~r{t!i,e,;TJE};~~lves\·· ' 'J~\/Y?3,'.s);~r~89'h:ielet,¢}repoJ~;as·: '.' .. . NEOcthatthere:1s~,a::1argeleak'Jn:#2c'

::$vy(6a·y~ly9k8a.rfti8,~rtri("Yf"\e'r~Jt .,, · .. is.:c;xjmirig;Jror11 \c:Jtf(fto,ttje }3,riray'. : < The\vafer;Jevel ln)he''bay·ls.•·•·,"·'

5approx{2f5:.ft. ahd:rfsing slowly. ··{~~B.JmJ1,ii~:cori.~ider1d:.·,",~· ······.

disat>led at2ft: in the ·say.per' ·Amzz:0002 Attach7f'. · . .

. .,. .,,,,,,,·,

CRS enters S2.0P-AB.SW-0003, SW Bay Leak, per ARP direction or enters S2.0PAB.SW-001, Loss of SW Header Pressure, which directs transition to S2.0P-AB.SW-003.

PO initiates the CAS of AB.SW-0003.

RO reports both SW Bays are in service and dispatches NEO to investigate #2 SW Bay alarms.

PO monitors Main Turbine and SGFP temps on SPDS and Plant Computer per CAS.

TQ-AA-106-0204 Page 16 of 39

··t\·;,~?~~~ry,fr;'.;::~': :rr;:;t''' ',1, ~-0-<--,, ,, . c, '


'E.va'lu~toBl'nstructot"Acftvity """\\(:····;: , ,···)

·.Simulator Operator: 2.:minutes. ·. after being. directed Jo ci.e;E3Qefgize;, .~ghtrbl,p9.":Ver.to:.2f.23~SWpuh)ps,

.'call ·fdr:a',f irst Check) theriinsert \ ·, iRT't.11:;; j"'., ·•:. /t J ... o'./f\

.. REMOTES/SW23D .SW27D·".< ,'·'. ' •. ,·> .•. ·. ;>.>'·.,-· >-i' ·,,._:- ., __ >:.·,, .. · >)._, ·:> . SW32Dfor.;21.~.}22. arid 23 sw ... ,

''.. .',' ,, C ' ' ''. '''.,·' .: J', .'. \·'·' ... ::_" '.. >t;

·•'puhJp;.;BKR9ontrofRower''With·•·. · ·,

\\~.~1a·:~'.f ,~,;it:f {r1tt1~!0::~r~:~~11:

.• Call controrroon1¥aftef last'reh1ote .·. is''~ctiye·anct repbftl6fiffol'·powf3r:.··· breakers have:been\.openedfor:21, 22 and 23 SW pumps). · ·

~~:;\}\:7~,~~~i:~:t~f ~i~!!~~=~} .. R~:~.f ~t3e{fi1t::~t:;;?~}:~~~:,::: Crew splits SW Bays by opening nuclear header cross over MOVs 21SW23 and 22SW23, and closing SW bay cross connect valves 21SW17 and 22SW17.

Crew determines the SW leak is in #2 Ba

RO/PO starts all available Bay 4 pumps (24, 25, 26).

RO/PO sto

Crew sends NEO to open control power bkrs for 21-23 SW pumps.

Crew isolates 2 SW Bay by closing 21SW22 and 21SW20.

PO reports that SW is available to the Diesel Generators throuqh 22SW21, DG COOLERS.

TQ-AA-106-0204 Page 17 of 39

.,?~~c· - ·,~,,,.F<:<*t',··:;/:-T;~) ;r\:,\_::;:- ,,,~ ,. -- , ommen . , ., ;p,• ,. . ·:,,q;,;:&'.y·_\_~-;<.,;,:;·<:':, ,:;f\ ,.-;':,.·, - .


:;s,;1~'~?i!f,~!,~,~!1~~!t~~!,~f:~~!1!)~\.

,,1Rolef>lay::,.Once:2 SVVBayis Sc,i;':'· ;,iiplateq:tNE,O{if(qc,ntactaq)'cep"orfs.; . tn 't;t'i.;<':r ,, '. ·R''i/ • , > ,, .. ,V .• ;;t· .. Ji;;t' ,·"'t,t,\.{~\,.'., . · .. a r,,e:,ea ,9'ppec:1rs. o, •. ;1.,a~.e., ... ,,.,1,./

't~lttti'.i~~~1~,~~:~J~ti,~;rt1t.::e !;,,'AZ~t~rvev;el;ffHEN;.:teporrtliat:ithe, ,?· , wijt,eril.~vet:is >.:Z.'f7e~farld·lowelngi slowrv:\\,.f.,,",1, i/<<t:·.• ,, :;::,p,'',v6 '

Proceed to next event after Tech Spec has been evaluated or by direction from Lead Evaluator.

Evalautor's Note:. Flooding procedure may not be e·ntered due to pace of scenario. · · ·

. ~~~~'!lT~t:~~~~~e:·,;x:t;: PO reports that SW is being supplied through 23SW20, TURB AREA.

PO reports the leak is isolated.

CRS evlautes Tech Specs and ECG.

CRS enters TS 3.7.4 due to having only one operable SW loop.

PO initiates action to remove one CCHX from service IAW CAS item 4.0.

CRS contacts maintenance to assist in leak


TQ-AA-106-0204 Page 18 of 39

· CT#1;(Site>Specific):,St<>p 22 . R'CP.anatcl()se:22cv104'withir13;, . :5' minutesiattel~tpp.phui 22 RCP }~r\r f t'dl:A:'~, ~{ ·

CRS determines 22 RCP seal leakoff flow >6 gpm meets the Attachment 1 CAS and initiates Attachment 2, Stopping Reactor Coolant Pumps.

CRS briefs Rx trip actions to be performed.

CRS identifies the requirement to close 22CV104 within 3-5 minutes after stopping 22 RCP and assiqns to RO.

RO trips the Rx.

RO confirms the Rx Tri

RO stops 22 RCP and starts the timer for closina 22CV104. rCT#1]

RO performs immediate actions of EOP-TRIP-


TQ-AA-106-0204 Page 21 of 39

{~~,;:,:· .. ..

5. 24 SG Tube Rupture

,Simdlatof:Operafor: , lnserfR;t.:4· · ·; •. fqr"2A;.$<3it96erRuptUr~"of,6oO;::f ··.·,

::,:111 il1I~1!f ~ll; RO reports unexpected OHA A-6, RMS TRBL, and reports 2R53D and 2R15 in alarm, followed later b__y 2R41 and 2R19D in alarm.

RO reports rapidly lowering RCS pressure and/or level.

CRS directs RO to initiate SI and return to EOP-TRIP-1.

RO initiates SI and performs immediate actions of EOP-TRIP-1

CRS re-enters EOP-TRIP-1.

CRS performs immediate actions of EOPTRIP-1.

CRS directs RO and PO to implement the CAS.

RO reports that SEC loading is NOT complete for energized vital buses.


TQ-AA-106-0204 Paae 24 of 39

TQ-AA-106-0204 25 of 39

Evaluafor11n'strfictodAcfivityJ :;::Sifxn~s{ed'p1arit/Stu9~11t·Response/d1i;Ifli!t::Issf": .. ····· .... .i:OGt,>

RO reports that NO available equipment failed to start.

PO reports that 21 and 22 AFW pumps are runnin .

If the ruptured SG is known at this point, the PO may request to close the 24AF21 and 24AF11 to isolate feed flow to the ruptured SG.

RO reports that not all valve groups are in safeguards positions. Reports that 24BF13 failed to close .

. . Simulator ,Op~rator: Ensure. ET-1 is TR~Ewhen operator depresses the close PB for 24BF13;

PO closes 24BF13 from console.

RO reports that containment pressure has remained less than 15 si .

PO reports that 2RP4 does NOT indicate high steam flow coincident with low steam pressure or low-low Tav .

PO re arts all 4KV vital buses are ener ized.

RO reports control room ventilation is in Accident Pressurized mode.

RO reports 2 switchgear supply and 1 exhaust fan are runnin .


.... :.}''Eva1aatoiWostructor·'.A:ctfvityi<· ~~~~,,;,<t':/~\'.+Jf:{·~?~-\\i?J \;~f('·\·,.?''.· ',, _,:~><.:t,_},,<;:," --~'~?~;,,,

Expected Plant/Student R .. 0''c

RO reports 2 CCW pumps running.

RO reports ECCS flow as expected for current RCS pressure.

PO maintains total AFW flow greater than 22E4 lbm/hr until at least one SG NR level is >9%, then maintains SG NR level 19-33%.

RO reports 21, 23, 24 RCPs are running.

RO reports RCS Tcolds are stable or tending to 547 F.

RO reports both RTBs are open.

RO reports both PZR PORVs are closed.

RO reports 2PR6 is closed (power removed due to instrument failure) and 2PR7 is open.

RO reports 21, 23, 24 RCPs are running (22 RCP stopped previously).

RO reports both PZR spray valves are closed.

RO reports that RCS pressure is > 1350 psig.

RO maintains seal injection flow to all RCPs.

PO reports NO SG pressures are dropping in an uncontrolled manner or completely depressurized.

.·<~1SBT

TQ-AA-106-0204 Page 26 of 39

·•\:~ '\t::·~0;:!?°''.~~t:~;~ib'.?'.::;: • . .. c


2t~~iilBi1:?tan~!rH~Jo~·;~?tiv~Jf ·~'i•: "c• • f i~;~cfe~ .Pl.ant/Stiident Respon~1;:·~~-w~ nz ·-~, '~BT: i. /,,. ·'£1tI:\ . ·\~\);.ft(,,.~, .. - :i~(::,:.,, ..... ;~\\$?<t· .c\,,:;t,,J;_:, " ,: ~ , , ~,, " , , /·<\, ~ / g st'~ itt "'e/ :~COG

~valuator:s Note: After~Jopping ,.22i;RC.1?,irNR:JevelsJn,22;SG.may. [b$j,~lso .~lsi'ng}ffh,~3:pr-eV¥. sh.<5,yld. ':~}.

reqog17i,z;~,~toc:1tthjs'.{is• <:l9.~.;~9.:1bss,:pf, ;··· ,;torc:~d :'cifcul.atiorf inJhaf RGJ()opt( .... ····' antflreduce&sfoaming effe(::t?in that.,

SG; . . .c/' .. /',(;/ . . .

RO reports that NR level in 24 SG is rising in an uncontrolled manner.

CRS transitions to EOP-SGTR-1, Steam Generator Tube Rueture.

PO reQorts NR levels rising in 24 SG.

PO reports 24MS10 is set to 1045 psig and closed.

PO closes 24MS167, 24MS18, 24MS7, and 24GB4.

PO reports 24MS167, 24MS18, and 24MS7 are closed.

PO reports that 21 or 23 SGs are NOT ru12_tured.

CRS dispatches operator to close 24SG 2SS339.

PO closes 24AF21 and 24AF11 valves.

CRS dispatches operator to shift gland sealing

TQ-AA-106-0204 Page 27 of 39

. , .... ~1!ii:i:~ti:f~~~;pi~:~;:/ :i}, ...


. ,:':, 'evatlia:t&r-11Hsfrhctor ~ctivity"2z:::o\, ,,_ cV, .:i Expectea etant/Student Re·ijionsehh',•=··-· :· _ _ts,,'. SST· w· , * ... it;·'\.?:'..~·:;:;~~~<;~r:~~;:.:~:.:::::>-~::, /; \: ({<, >:'. :·;"!)/'\''._ J:\?t ,' \}, {.~~,·, _,,'\" ~\, ?;~rv:;- /~;;,~t,.t <"~,;:~-!?;~::-" ~~"\"'_\;:-~>',~.,~\:1.i : ~a_:,h,·}/' .~i\·f,/I*f\,i;tv-~\~ ·,):LOG!"'''.;),, "t<r;r;_·

. Ey~1uator\N.~t~V.Q.epen-ding pn• . ,the'pa'5e,pttli~'.qre~.dur.irig';:~bP:, -J:R.1Ri2;'·tn'eJ;rew ¢a\,'.;li'ave::i{L >:, ..

\( a~ter,rnire4 }t:iati,~ts::fo.rnp~ra.iufot1ii •.,

0

W§},.:r1pfbeing,q2dtroJ!ed,)1~at,~:::; .• ;;: •. ~,i ·,·ipihated}MS0t'e:I F--tnis:w~if'' -. · '" ·· ::ri~to+p,~'1,';:rR~N;}bElc,r~~~ilL ... , i/eportthatNQ steam:cdumps·arE(

l~!19~j~~~!5?f :J\!:i~~~'.'<, purJng/validation:using rv1Sj o·s,·it .·

. took ,about;6 mfrisJi:l reai:HtCET. of~':. '503 F.> .. ' . . .. .. .

CT~2 (CT-t9}:,co.ntrolinitial RCS: . . co,9ldOWQ so;tha,t transmonJr~m . . EOP-SGTR-1 'does notoccur/':

steam to alternate source IAW S2.0P-SO.GS-0001.

CRS determines RCS target temperature using Table B (SG press at >1000 psig = 503 F CETs) .

PO reports steam dumps are available.

PO places steam dumps in manual, adjust demand to 0%, and then place in MS Pressure Control.


TQ-AA-106-0204 28 of 39

... .Sim0

ulator:Operator;:, IF rE:)quested by:cre'I{; DELETE,.Reh1ote: PR34D.

:to restore powert62Pij9'.. Notify,) 1 CRSwhen completed:· · · ·/ ·

PO initiates RCS cooldown by adjusting MS Pressure Control to 25% to open steam dumps OR dump steam at maximum rate using intact MS10's. [CT#2]

CRS continues on in EOP-SGTR-1.

RO reports hottest CETs are not less than RCS cooldown target temp.

PO maintains AFW flow > 22E4 lbm/hr until one SG NR level is > 9%, then maintain between 19% and 33%.

RO reports power is not available to both PZR PORV stop valves (2PR6 power removed due to instrument failure) .

CRS may direct WCC to restore power to 2PR6 at this point or wait until directed later in the 12.rocedure.


RO opens 2PR6 stop valve, if power restored.

RO resets SI, Phase A, and Phase B isolation.

RO opens 21 and 22 CA330s.


TQ-AA-106-0204 Page 29 of 39

' Eval tfatorli'r11structdr').Activ1tyctt::{. ~. fvJ.:: (r)i\ ':'.\.i.,;,/ •' .. );~AX .. , .,J'(·,,,,:',i;)#{{ ,·~ 1r:;';ff:> ..

Terminate the scenario when the RCS cooldown is stopped or by direction from Lead Evaluator.

Following steps are for the RCS depressurization with normal PZR spray:

J;;.(iil~!ft~.~:•;:1t~t'~!~~:~r:R~~.~{,·:I:'~>;:;;~~:~:ll~)tg~·:*;::'.·· PO resets each SEC and associated control centers.

RO reports RHR suction is aligned to the RWST.

RO sto[)s both RHR pumps.

RO reports hottest CETs are not less than RCS tarqet temp.

Crew waits until hottest CETs are less than RCS target cooldown temp.

RO reports hottest CETs less than RCS target cooldown temp.

PO stops the cooldown by closing the steam dumps and then placing MS Pressure Control in Auto OR closing intact MS10's and placing in Auto. [CT#2]

CRS directs PO to dump steam to maintain CET temp. less than required.

PO reports ruptured SG pressure is stable or rising.

TQ-AA-106-0204 Page 30 of 39

;i':t:J{t~~~;;;rt:::,~?t~:~(/\;.·.


::E\~J~,i\~t1f?,~!ru~!<>~i~~ti,~t!~{,'.':?\J:l'Iiii}Ef1ij::~\td'';~~~2~:~~~~.en(:iRe:~PJl~~~1t;;;;,,t2:%

RO reports RCS subcooling is greater than 20 F.

RO reports normal PZR sgray is available.

CRS reviews depressurization termination criteria IAW Table D.

RO fully opens both PZR spray valves.

RO reports PZR spray is reducing RCS ressure.

RO reports when depressurization termination criteria is met IAW Table D.

RO closes both PZR spray valves.


TQ-AA-106-0204 31 of 39

A. Alarm Response Procedures (Various)

B. Technical Specifications

C. Emergency Plan (ECG)

D. OP-AA-101-111-1003, Use of Procedures

E. S2.0P-IO.ZZ-0003, Hot Standby to Minimum Load

F. S2.0P-AB.PZR-0001, Pressurizer Pressure Malfunction

G. S2.0P-SO.MS-0002, Steam Dump System Operation

H. S2.0P-AB.SW-0003, Service bay Leak

I. S2.0P-AB.RCP-0001, Reactor Coolant Pump Abnormality

J. 2-EOP-TRIP-1, Reactor Trip or Safety Injection

K. 2-EOP-TRIP-2, Reactor Trip Response

L. 2-EOP-SGTR-1, Steam Generator Tube Rupture

TQ-AA-106-0204 Page 32 of 39


'.; ''··', .

ATTACHMENT 1 . UNIT TWO PLANT STATUS

TODAY' . .

MODE: 2 POWER: 3% RCS BORON:

SHUTDOWN SAFETY SYSTEM STATUS (5, 6 & DEFUELED):

N/A REACTIVITY PARAMETERS

• Control Bank D at 130 steps. • Core burnup 500 EFPH.

1648

TQ-AA-106-0204 Page 33 of 39

MWe 0

• Reactor Engineering directs use of control rods and steam dumps to raise power to 10%. No Fuel Conditioning Limits are imposed until 50%.

MOST LIMITING LCO AND DATE/TIME OF EXPIRATION: None

EVOLUTIONS/PROCEDURES/SURVEILLANCES IN PROGRESS: • S2.0P-IO.ZZ-0003, Hot Standby to Minimum Load complete up to Section 4.3, step

4.3.19. • S2.0P-SO.MS-0002, Steam Dump System Operation • Monitoring Tavg > 541 F oncer per 30 minutes due to RC Loop Tavg - Tref Deviaton

console alarm in (extra NCO to log). • Power ascension to 10% using control rods and steam dumps, and enter Mode 1. • Reactor Engineering is standing by to support power ascension.

ABNORMAL PLANT CONFIGURATIONS:

CONTROL ROOM:

Unit 1 and Hope Creek at 100% power.

PRIMARY: • 21 Charging pump in service due to 23 Charging pump CIT for troubleshooting of

flow oscillations with fluid drive.

SECONDARY: • On main feedwater using 21 SGFP; 22 SGFP 0/S in standby

RADWASTE:

No discharges in progress

CIRCULATING WATER/SERVICE WATER:


ATTACHMENT 2

S1MULAT6~READYFORTRAIN1NG;CHECKLIST ' , ' • '. ' • • ,.~ ','.- "<;:"" ';·,., ~."' ; ,_,,: ,

1. Verify simulator is in "TRAIN" Load

2. Simulator is in RUN

3. Overhead Annunciator Horns ON

4. All required computer terminals in operation

5. Simulator clocks synchronized

6. All tagged equipment properly secured and documented

7. TSAS Status Board up-to-date

8. Shift manning sheet available

9. Procedures in progress open and signed-off to proper step

TQ-AA-106-0204 Page 34 of 39

10. All OHA lamps operating (OHA Test) and burned out lamps replaced

11. Required chart recorders advanced and ON (proper paper installed)

12. All printers have adequate paper AND functional ribbon

13. Required procedures clean

14. Multiple color procedure pens available

15. Required keys available

16. Simulator cleared of unauthorized material/personnel

17. All charts advanced to clean traces and chart recorders are on.

18. Rod step counters correct ( channel check) and reset as necessary

19. Exam security set for simulator

20. Ensure a current RCS Leak Rate Worksheet is placed by Aux Alarm Typewriter

with Baseline Data filled out

21. Shift logs available if required

22. Recording Media available (if applicable)

23. Ensure ECG classification is correct

24. Reference verification performed with required documents available

25. Verify phones disconnected from plant after drill.

26. Verify EGC paperwork is marked "Training Use Only" and is current revision.

27. Ensure sufficient copies of ECG paperwork are available.


ATTACHMENT 3 . ., .. •. .

. CRITICAL TASK METHODOLOGY .

TQ-AA-106-0204 Page 35 of 39

In reviewing each proposed CT, the examination team assesses the task to ensure, that it is essential to safety. A task is essential to safety if, in the judgment of the examination team, the improper performance or omission of this task by a licensee will result in direct adverse consequences or in significant degradation in the mitigative capability of the plant. The examination team determines if an automatically actuated plant system would have been required to mitigate the consequences of an individual's incorrect performance. If incorrect performance of a task by an individual necessitates the crew taking compensatory action that would complicate the event mitigation strategy, the task is safety significant.

I. Examples of CTs involving essential safety actions include those for which operation or correct performance prevents ...

• degradation of any barrier to fission product release

• degraded emergency core cooling system (ECCS) or emergency power capacity

• a violation of a safety limit

• a violation of the facility license condition

• incorrect reactivity control (such as failure to initiate Emergency Boration or Standby Liquid Control, or manually insert control rods)

• a significant reduction of safety margin beyond that irreparably introduced by the scenario

II. Examples of CTs involving essential safety actions include those for which a crew demonstrates the ability to ...

• effectively direct or manipulate engineered safety feature (ESF) controls that would prevent any condition described in the previous paragraph.

• recognize a failure or an incorrect automatic actuation of an ESF system or component.

• take one or more actions that would prevent a challenge to plant safety.

• prevent inappropriate actions that create a challenge to plant safety (such as an unintentional Reactor Protection System (RPS) or ESF actuation.


TQ-AA-106-0204 Page 36 of 39

SCENARIO IDENTIFIER: 16-01 ESG-1 REVIEWER:

Initials

Qc) /J )c) 1. ' ~ 2.

1P 3. jj-v 4.

Qualitative Attributes

The scenario has clearly stated objectives in the scenario. The initial conditions are realistic, in that some equipment and/or instrumentation may be out of service, but it does not cue crew into expected events. The scenario consists mostly of related events. Each event description consists of: • the point in the scenario when it is to be initiated • the malfunction( s) that are entered to initiate the event • the symptoms/cues that will be visible to the crew • the expected operator actions (by shift position) • the event termination point No more than one non-mechanistic failure (e.g., pipe break) is incorporated into the scenario without a credible preceding incident such as a seismic event. The events are valid with regard to physics and thermodynamics. Sequencing/timing of events is reasonable, and allows for the examination team to obtain complete evaluation results commensurate with the scenario objectives. The simulator modeling is not altered. All crew competencies can be evaluated. The scenario has been validated. If the sampling plan indicates that the scenario was used for training during the requalification cycle, evaluate the need to modify or replace the scenario. ESG-PSA Evaluation Form is completed for the scenario at the applicable facility.


Minimum Quantitative Attributes (NU REG 1021, R11, Form ES-301-4)

Malfunction Total Malfunctions

Abnormal Major EOPs ID Malfunctions

After EOP Events Transient used

entry

PR0016A 1 1

SW0216A 1 1 TRIP-1

RC007B 1 1 1 TRIP-2 SGTR-1

SG0078D 1 1

VL0026 1 1

Total Number of 5 2 3 1 3

Events Min Number

5 1-2 2-4 1-2 1-2 of Events

Verified By

Comments: See NRC-3 for Contigency EOP used (FRSM-1)

Critical Task

2

2

~2

TQ-AA-106-0204 Page 37 of 39

Tech Specs Continge

exercised ncy

EOPs

Yes

Yes

No

2 0

2 per set 1 per set


16-01 ESG-1

TQ-AA-106-0204 Page 38 of 39

CT-1 (Site Specific): Stop 22 RCP and close 22CV104 within 3-5 minutes after stopping 22 RCP in EOPTRIP-1.

• Safety Significance:

Failure to close the seal leakoff flow valve (CV104) when required could result in damage to the backup #2 seal and loss of RCS inventory. When seal leakoff is greater than 6 gpm the operator must close the associated CV104 within 3-5 minutes. The 3 minutes allows for the RCP to coastdown and enable static conditions for the #2 seal to perform its backup function. The 5 minutes minimizes RCS leakage from the damaged seal to maintain RCS inventory.

• Initiating Cues:

Seal leakoff flow indication or console alarm

• Measurable Performance Standard:

Seal leakoff valve (CV104) position indicates closed RCP breaker position indicates open

• Performance Feedback:

Report from operator that affected RCP is stopped and seal leakoff is isolated.

CT-2 (CT-19): Control initial RCS cooldown so that transition from EOP-SGTR-1 does not occur.

Note to Evaluator: CT numbers in parentheses are the corresponding Westinghouse ERG Rev. 2- based Critical Tasks procedure WCAP-17711-NP


'.. . .· ATTACHMENT 6

TQ-AA-106-0204 Page 39 of 39

E~cl-PRA RELA~,o~~HIP EVALUATIC>N <:

EVENTS LEADING TO CORE DAMAGE

Y/N Event Y/N Event

N TRANSIENTS with PCS Unavailable N Loss of Service Water

y Steam Generator Tube Rupture N Loss of CCW

N Loss of Offsite Power N Loss of Control Air

N Loss of Switchgear and Pen Area Ventilation N Station Black Out

N LOCA

COMPONENT/TRAIN/SYSTEM UNAVAILABILITY THAT INCREASES CORE DAMAGE FREQUENCY

Y/N COMPONENT, SYSTEM, OR TRAIN Y/N COMPONENT.SYSTEM.OR TDll.lf\1

N Containment Sump Strainers N Gas Turbine

N SSWS Valves to Turbine Generator Area N Any Diesel Generator

N RHR Suction Line valves from Hot Leg N Auxiliary Feed Pump

N eves Letdown line Control and Isolation Valves N SBO Air Compressor

OPERATOR ACTIONS IMPORTANT IN PREVENTING CORE DAMAGE

Y/N OPERATOR ACTION

N Restore AC power during SBO

N Connect to gas turbine

N Trip Reactor and RCPs after loss of component cooling system

N Re-align RHR system for re-circulation

N Un-isolate the available CCW Heat Exchanger

N Isolate the eves letdown path and transfer charging suction to RWST

N Cooldown the RCS and depressurize the system

Y Isolate the affected Steam Generator that has the tube rupture(s)

N Early depressurize the RCS

N Initiate feed and bleed

Complete this evaluation form for each ESG.

SIMULATOR

TQ-AA-106-0204 Page 1 of 36

EXAMINATION SCENARIO GUIDE

SCENARIO TITLE:

SCENARIO NUMBER:

EFFECTIVE DATE:

EXPECTED DURATION:

REVISION NUMBER:

PROGRAM:

Revision Summary:

16-01 ESG-2 [AB.RC-1, AB.LOAD-1, TRIP-1, LOCA-1, LOCA-3] 16-01 ESG-2

See Approval Dates

80 minutes

00

.____ _ __.I LO. REQUAL

I . X \ INITIAL LICENSE

._______.I ST A

I OTHER ~-~

New issue for 16-01 ILOT NRC exam. Incorporated editorial comments from validation.

PREPARED BY: R. Chan 9-15-17 Lead Regulatory Exam Author Date

APPROVED BY: M _,ff~ R

APPROVED BY:


TQ-AA-106-0204 Page 2 of 36

A. Given the indications of a reactor coolant system (RCS) malfunction or leak, perform actions as the nuclear control operator to RESPOND to the malfunctioning accordance with S2.0PAB.RC-0001.

B. Given the indications of a reactor coolant system (RCS) malfunction or leak, DIRECT the response to the malfunction in accordance with S2.0P-AB.RC-0001.

C. Given the order or indications of a reactor trip, perform actions as the nuclear control operator to RESPOND to the reactor trip in accordance with 2-EOP-TRIP-1.

D. Given indication of a reactor trip, DIRECT the response to the reactor trip in accordance with 2-EOP-TRIP-1.

E. Given the order or indications of a safety injection, perform actions as the nuclear control operator to RESPOND to the safety injection in accordance with the approved station procedures.

F. Given indication of a safety injection, DIRECT the response to the safety injection in accordance with the approved station procedures.

G. Given a safety injection has occurred and equipment has failed to start, START equipment that has failed to automatically start in accordance with station procedures

H. Given the order or indications of a loss of coolant accident (LOCA), complete actions as the nuclear control operator to PERFORM the immediate response to the LOCA in accordance with the approved station procedures.

I. Given indication of a loss of coolant accident (LOCA), DIRECT the immediate response to the LOCA in accordance with the approved station procedures.

J. Given the order or a loss of coolant accident (LOCA) and plant conditions to support cold leg recirculation, perform actions as the nuclear control operator to TRANSFER to cold leg recirculation in accordance with the approved station procedures.


A. 21 MS167 drifts from full open position

B. 22 CFCU trips

C. RCS leak inside Containment (35 gpm)

D. Large Break LOCA (LBLOCA)

E. Both trains of SI fail to auto actuate and one keyswitch fails to operate

F. 2B SEC fails to actuate on SI signal

SCENARIO SUMMARY 011,1

TQ-AA-106-0204 Page 3 of 36

A. The crew will take the watch with the unit at 40% power, BOL. 23 condensate pump and all heater drain pumps are out of service due to plant power level. 22 SW pump CIT for pump packing replacement; 238 CW pump is CIT for traveling screen repair; 2A EOG is CIT for governor inspection and output breaker swap.

B. After the crew assumes the watch, 21MS167 will drift from the full open position and respond to OHA G-34; 21-24 MS167 VALVES NOT FULL OPEN. The crew will take actions IAW OHA ARP S2.0P-AR.ZZ-0007, and re-opens 21MS167.

C. After 21MS167 has been addressed, 22 CFCU will trip. The crew may review S2.0P-SO.SW-0005, Attachment 2, SW System Operability Guidelines, to determine course of action. The crew will evaluate Tech Specs and take actions to remove control power to the high and low speed breakers to comply with the one hour TS action for 3.6.1.1, containment integrity. The crew may also start the standby CFCU (25 CFCU) to maintain containment pressure and temperatures. [Tech Specs exercised]

D. After the 22 CFCU trip has been addressed, a 35 gpm RCS leak inside containment will occur. The crew will enter S2.0P-AB.RC-0001, Reactor Coolant System Leak, and diagnose the leak. The crew will transfer to a centrifugal charging pump, reduce letdown to a 45 gpm orifice, and estimate the leak rate. The CRS will evaluate Tech Specs. [Tech Specs exercised]

E. The CRS will determine a unit shutdown is required based on the RCS leak exceeding Tech Spec limits. The crew will initiate an orderly unit shutdown.

F. After the orderly unit shutdown has commenced, the RCS leak will worsen to a large break LOCA. The crew will diagnose deteriorating primary conditions. When it is determined that PZR level will be unable to be maintained >17% or leak exceeds makeup capability, the crew will take the CAS action in S2.0P-AB.RC-0001 to trip the reactor, confirm the trip, and initiate Safety Injection.

G. During performance of initiating Safety Injection (SI); the operator will be unable to manually actuate one train of SI using the keyswitch; the other train keyswitch will function and allow manual actuation of both trains of SI. [CT#1]

H. The crew will perform plant stabilization and diagnostics in EOP-TRIP-1, Reactor Trip or Safety Injection. While in EOP-TRIP-1, the 28 SEC will fail to actuate following SI actuation. The crew will manually start safeguards loads for 28 bus using Table A.


TQ-AA-106-0204 Page 4 of 36

I. The crew will transition to EOP-LOCA-1, Loss of Reactor Coolant, when directed in EOP-TRIP-1.

J. The crew will perform actions in EOP-LOCA-1 until the RWST level low alarm actuates at 15.2 feet; then transition to EOP-LOCA-3 to transfer to cold leg recirculation. [CT#2]

K. The scenario will be terminated when the transfer to cold leg recirculation is completed in EOPLOCA-3.


IC-231

Initial I Description

1 VC1 and VC4 CIT

2 RCPs (SELF CHECK)

_ 3 RTBs (SELF CHECK)

_ 4 MS167s (SELF CHECK)

_ 5 500 KV SWYD (SELF CHECK)

_ 6 SGFP Trip (SELF CHECK)

_ 7 23 CV PP (SELF CHECK)

_ 8 22 SW Pump CIT

_ 9 238 CW pump CIT

10 2A EOG CIT

11 Complete Attachment 2 "Simulator Ready-for-Training/Examination Checklist."

TQ-AA-106-0204 Page 5 of 36

Note: Tables with blue headings may be populated by external program, do not change column name without consulting Simulator Support group


TQ-AA-106-0204 6 of 36

--- --------- ------- ·--- -------·-------

EVENT ACTION: kbd12an1 //21 MS167 HYDRAULIC OPEN

1 COMMAND: DMF VL0420

PURPOSE: <update as needed> ----· -------- ··----- -- -· - ---

EVENT ACTION: HWKA501 DOA //W Var bind for ZDIPANEL(1615)

2 COMMAND: DOR ka701doa

PURPOSE: <update as needed> ---------- ------- ----------------- --·-- --· -------~~------ -----------

EVENT ACTION: HWKA701 DOA //W Var bind for ZDIPANEL(1669)

3 COMMAND: DOR ka501 doa

PURPOSE: <update as needed> ---------- .. ------ ----·-- ----~- __ ,. _____ ----- ···--------~

EVENT ACTION: MONP254 <10. //CONTROL BANK C GROUP POSITION

4 COMMAND:

PURPOSE: <update as needed>

SELF- Description Delay Initial Ramp Trigger Severity CHECK Time Value Time

01 VC0173B 22 CNTMT FAN COIL UNIT TRIP NIA N/A NIA RT-2

02 RC0002 RCS LEAK INTO CONTAINMENT ( equiv to 0-

NIA 0 00:02:00 RT-3 35 4inches

03 RC0001D RCS RUPTURE OF RC LOOP 24 N!A NIA NiA RT-4

04 RP0274A AUTO SI FAILS TO ACT, TRNA N!A NIA t-J/A l'-J/A

05 RP0274B AUTO SI FAILS TO ACT, TRN B NIA NIA N/A NIA

06 VL0420 21MS167 Fails to Position ( 0-100%) NIA NIA N/A RT-1 95

SELF- Description Delay Initial Ramp Trigger Condition CHECK Time Value Time

01 DG02D DEENERGIZE "B" SEC CABINET NIA NIA N/A ET-4 YES

02 SW27D 22 SW PUMP BKR CONTROL POWER NIA NIA NIA NIA OFF

03 SW28D 22 SW PUMP RACK OUT NIA N!A NIA N/A TAGGED

04 CW03B 238 CIRC WATER PUMP CONTROL PWR NIA N/A N/A N/A OFF BKR2CW5BD

05 DG1 OD 2A DIESEL GEN LOCKED OUT NIA NIA N/A N/A YES

06 DG11 D 2A DG BKR CONTROL POWER N/A NIA N/A NIA OFF

07 DG12D 2A DG BKR RACK OUT N/A N/A N/A N/A TAGGED

08 CT192-1 D 22 CFCU BKR #1 Hi h S eed 125VDC NIA N/A NIA RT-10 OFF

09 CT192-2D 22 CFCU BKR #2 Hi h Speed 125VDC 00:00:10 N/A NiA RT-10 OFF

10 CT192-3D 22 CFCU BKR #3 Low S eed 125VDC 00:00:20 NiA NIA RT-10 OFF


TQ-AA-106-0204 Page 7 of 36

9ilBR1PI~~=' i,,'' •,:'/,\,I.',_..:.........=· ··L' .:c_·. '---LL'---LL'---'---'---"'--'---='---........c____c~c..__-~~LLLL'---~~==~=~=-.--LLLL--'-__.;

SELFCHECK

01

02

1.

Description

A701 B DI KA701DOA TRAIN 'B' - SJ OPERATE KEYSWJTCH

A501 B DI KA501DOA TRAIN 'A' - SI OPERATE KEYSWJTCH

Description

Delay Initial Time Value

r,.,11)\ < <o:r\ N/A

NIP\ NiA

Ramp Trigger Condition/ Time Severity

NIA N/A OFF

N/A N/A OFF


A. State shift job assignments.

TQ-AA-106-0204 Page 8 of 36

B. Hold a shift briefing, detailing instruction to the shift: (provide crew members a copy of the shift turnover sheet).

C. Inform the crew "The simulator is running. You may commence panel walkdowns at this time. CRS please inform me when your crew is ready to assume the shift".

D. Allow sufficient time for panel walk-downs. When informed by the CRS that the crew is ready to assume the shift, ensure the simulator is cleared of unauthorized personnel.


1. 21M5167 drifts from full open position

1,Sif11'.ulatorOperator:Jns'ertRT~1// . . '6ri;directt8n::ffom7~ea'd:.E\)a]Uator; ·: ...•.•. /t: ::liJ1:,:~:i.t1:,t :!!f,:',z: ·/;~:.:~·:::t· . { ;iMAl:iE:rVL!:.0420 '21' l'JIS167rtailsto,zf,

"~r;~ti~i~~'.~I~~~~::~~ ·,1: Jr,~ ?J;; 1

, evatu~tor'{Notef'A~tsoan •. a,'sl, .. · ·· rn~lfunction, is ent~red,:OAA'd;34. , overhead alarm wilfcOme'in.; ,,,,i

Sifo-ulc;ltorpperator:iEnsure .. ET~1.·.·· .CisTRlJ~Vv6en?ff0~-i9fdpepPB··· is aepr,essed; :Tt,is deletes MAL;F

,\/L.0420); : ·. . . . .. .

PO announces unexpected OHA G-34, 21-24 MS167 VALVES NOT FULL OPEN, and refers to ARP.

PO reports CRT and board indication of 21MS167 not being full open.

CRS directs PO to open 21MS167 per OHA ARP.

PO depresses open PB and reports 21MS167 has fully opened.

CRS directs initiation of notification to


TQ-AA-106-0204 Page 9 of 36

.; Ev~lu.atqr/Jn~truct4r A;ctiy,ty 1'1'. .. ':\:;::,;,F1\ Exi:ie]tict;l'lantTStud~nt .Respqri~!t , ,. , ,. {::~:{f ~· ;:~ ;·' . >··:~>':<,r-:;./?Jr~: ·;~};tAt:"~:~ii);'. ., ~~:1· · -,,. :;ft :: · ~ ~ i!X~-. ·.\ -~J, ~ •• :/;t~:~\~ti~,:: ·r~:-,<\;~1:.:~~ ~'7JK/+ .::::~:)~:,: ,, /}! ~5;:;\. -1,,~1:~;

Evaluator's Not!: Tech.Spec .: . . }.·k\.t5/9fMsJVbpera~ilify. i§:r10t ;·

.. . . 1· bl .. 'MS.I' rd ·tt· .. ····· ·t .,·· 0 ·•• '.app \x.a . e:{ / , N . (I . ,ls,no 1:'':; 2 r;it >

·sun,cbrrimon,·a'n~ tjeclaring::{the MSMX'r .··fnbperabre .. ]s;,n'ot'.\varrantea.Jhe . opera,bfjityjcqo·cit~,woulp· ti~!;\:,::·

rel.atE:1dfo)fs)1ot befnitable ·to fast 'close(stearh'assisf). 's\

2. 22 CFCU Trip

··sifu~lator:tOperator:.)nsertcRT-2 "ofi directiori:from Lea·c.tEvaluator.:<

1Mit~t,~~~i1;·ai;i J:Nr,Mt,·f~\N .·. c611:::uN1r·rR1R ,, •0 ,,,)i,.

. • Role f>lay: 2 ltliriutes after being dispatched/report as 'the NEO that. · bqth high speedbreakers'tor:22 CFCU are,open arid 'there.is an , over,current fndi6ation(whiteJ1agY lhat1s,up. You'dor:i'(smell anything . near;the .breakets. . . .. ' ... 'location: B 460 V Bus 84' SWGR

investiqate and correct cause of the alarm.

RO identifies that 22 CFCU has tripped.

PO refers to ARP S2.0P-AR.ZZ-0011 (Q), for Low Air Flow console alarm.

CRS dispatches NEO to investigate the cause for 22 CFCU trippinq .

TQ-AA-106-0204 Page 10 of 36 .. co;,~~~:r .:·l;!~·f":0.


Rm)

. Evaluator's.Note: S2.QR,.SO.SVV,0005r'Att: 2/se.rvice.VVatef sYstein .. ' \ Ope,:abnity··csui9elines7;pag'e·s~l IF treqtlires;'eritfylinto·JSAS:3.6:fif for :

~. '.·.· ·,.· .. ·.'' •.••.•.•.· ·1.· .\.··· •• ·.t.· .. ". 'rt.·· •. •.·. · .... • ... ·.···.'.', .·.·• .• '.· ·. . .··'"(.'.''.d ...... ·'¥'.'t' ',.·.· /;·····. . 1a1 ure. o s a ;ir,,, ow ~pee .• un 1 ••:i'' Ahe:CfG.1J;ii~f'el19ctricallyf s'olat&d ;~~ It.,

,r. do~s:1;0Edirecf'ei11tf¥,fot: high speed

iJ!t~!i~!1YJ~fitff '.Oearlng'fai,lt.fre)that WOl)lo prevent· :~farting in l()v,i ~peed,,thet1\eptry/ ji,tfr3'.6.'1fJ may be made. /" · .. ·

Crew may refer to S2.0P-SO.SW-0005, Attachment 2, for SW System Operability Guidelines.

CRS enters Tech Spec 3.6.2.3 action a and 3.6.1.1 until electrically isolated. TS 3.8.1.1 action b is still active due to 2A EOG CIT; action b.2 would require 21 CFCU to be declared inoperable if 22 CFCU is not restored to operable status after 4 hours ( crew may refer to S2.0P-SO.DG-0005, Preparation for Removing A Diesel Generator From Service for additional guidance).

CRS directs opening of control power breakers for 22 CFCU high and low speed breakers within one hour to comply with TS 3.6.1.1.

TQ-AA-106-0204 Page 11 of 36

''''commehtl!'~:;?•·+ ··


~imulatorJ:>petator: ,, / . ' ... , lnserV:Remote,:RT-10.,:This will >;,~,:

, insMth~ following .Re~otes t8 .

'/! f i\ilf t!1~!:t~ ,1crf92;;20, ·'."! ':::c-._,_::/~1 • t · r~<:,· er. s2 30,,, ;;; , , .

c • ' ~" '.~','.\ '• •::,?' 1 ·'."'' ," ,;:,•(!• ' •:' • '""'{!/ ,'•, C

.;Final Value = OFF.·

Proceed to next event once Tech Specs has been evaluated or at Lead Evaluators direction.

3. RCS Leak Inside Containment

<Simulator Operator: losertRT-31/. ori' directi6n,froml:ea&Evaluatcr' .

··:"+il ::;,1t;;::'?.·::.;}::w )\;;:~~:mt'/'.: ·· ,·M:AliF:\RC0002, RC$il:.Eiak•·into . ·' con(~JtirAE:fr1~:,l· il> •.. :\'~Fi'.,>,,,i'i

FinatValue::35 (30~35 gpm) R~mp == 2 minutes~ .\1 '

Crew may choose to start the standby CFCU in high speed if containment temperature or

ressure is risinq.

RO reports that charging flow is rising and PZR level is lowerinq slowlv.

Crew reports reading on 2R11A containment radiation monitor is risinq or in warninq/alarm.


TQ-AA-106-0204 12 of 36

TQ-AA-106-0204 13 of 36

:~{{~?Y\~{t~Jf ff ';f ~~.r~~i1~r,;iitJ~J~y<:: .... i~!:i ··••:;~·E·x~1~~t7'cf~l!~"![Sty~i~! Resp1>:~~]~1k' ' • .· SB"f'.' 101~:' . LOG'*::' '., .... . .. . .. ...•.. ...

/0-?Wt ':"', '?t*P~-

RO reports unexpected OHA C-2, CNTMT SUMP PMP START, when it occurs.

CRS enters S2.0P-AB.RC-0001, Reactor Coolant System Leak.

CRS directs initiation of Attachment 1 CAS.

RO reports RCS temperature> 350°F and the Unit is in Mode 1.

RO reports PZR level is lowerina.

CRS enters S2.0P-AB.RAD-0001, Abnormal Radiation after OHA A-6 unexpected annunciation.

RO reports that NO centrifugal charging pumps are runninq.

RO transfers to a centrifugal charging pump IAW Step 3.14, and raises charging flow to stabilize PZR level.

PO reduces letdown flow to minimum by opening 2CV3, maintaining letdown pressure -300 psig with 2CV18 in manual, then closing the open 75 gpm orifice and returning 2CV18 to auto.

RO stabilizes PZR level and estimates leak rate.

CRS initiates S2.0P-ST.RC-0008, Reactor Coolant System Water Inventory Balance.


·· Role, Play: If Rad Pro/is contacted ·aboU(ci=cl.fs;istafe Bad PrO, 'i\' ····

'.• rebomrn.~nds'.pfodrigv2 :cECLJ's·Jn ·.·LoW§.peed~rfd:2,CFCO's.in:l,igh',,'.\:

... sp¢~d~·~ ~~ ... ·. . ''" ·· ·· :,, · ..

4. Orderly Unit Shutdown due to RCS leak exceeding Tech Spec

Role Play: After RCS Jeakage ., .. · . sTeCt\S,P~Sh'asb~enidentined,,1.F; I\ G~S,dOEl~i:nqtJrtiti~tEl)a,ipoWer/ ;\:•r > ..•

·.r,~~UGti9°tj 1tO: 6ttn~ftllE3·un[t off-linEl, · · .... :cal.t:Gdntrot Roomias . .Operati6ns·.·c . Direct6rand.i11sfrucMhe;GRSrto: Jnitiate:a· 3Qo/ci pechooi:'JoacC): .,· .· . reduction to')O°lo)n preparati6nfor

taking. Unit 2. offline to ihvesfigate and repair the RCS leak. . .

Lead Evaluator may proceed to

CRS contacts Rad Pro for recommendation on CFCU operation.

PO places 2 CFCU's in Low Speed and 2 CFCU's in Hig~Speed.

CRS initiates actions to locate and isolate the leak IAW Attachment 2.

CRS enters TSAS 3.4.7.2.b action b for RCS leakage and 3.6.1.4 for containment .e_ressure (if it has reached 0.3 psig).


TQ-AA-106-0204 Page 14 of 36

,, · .. ·<:·.·e· " ·f ·:·'1·.··,·.x··· ,: ·:,:,. ·.·.,· ,,, 'f·:. ..('A'<.: "''".·.·JI. ;cw. ··.·.·,: •. ~ .• ,,. '''.·.''.'',."'.·':,·cc.ti,:, ·'. ·."<e· .'C:.'•. ·.'.'''"'."'':a.·. ··e·.·.·. ·1·'.'d····' .... "' ·,s·'".· ·. ';a'' ·.·t' •: .... R .. : .... ·:A+ .• , •. •• ~ ... ·, •. " . .AF,····.''. .... · ... \.;.'tF.f+•. ···.:.:·.·s··. ·a· ''>"::t ya ua~q~ l.n~tructor,,nctlv1W;;,;,;6}0 r,::ii:£:r,1 xpecte\.l< .·.• .ant tµ\.len .:. espopse,y~~,t:1ccr:",::it , _ .:,:.~,~;.'.·~.: .. ::~~~~~,.:-,·_:.<:;~·.:~)~~~.'.::~;>/;·f .A:;\;,~;, ... ~)~:~.S<>Y~; ·'.~~;~:<.: ... tS-~~'.;~~-~,·' ·~ :3·: ,, · ,:~ :~\: ' · ~-·,-.. · '.< :_ ·~~::'.; : ~~:" ~. · .'.i:>, ~·-- I3.,;·::~::_:'.· ·:,,· :"::~: · ,, ·;;J; <~ ·.: >.,r·<.:: '.~:~~> .. ·. · · :>;~ :~ .. ~-~: ·<~~~ :·:·~.'.·> ... :>:;,;~'.::~:.~~":· , ,..A;+ <:-;.:·~. ·~;.~ji:i;. EPG

n ext event (LBLOCA) if observing unit shutdown is not necessary.

Proceed to next event once the unit shutdown has commenced or at direction from Lead Evaluator.

5. Large Break LOCA

,Sirriulator;Opel'..aftlr: lrfo~rVRT-4 I at direction from lleaa Evaluator. . . , .. ·, .~< ,·<. . ., .... :< -',.· 0,.';\;_Y.' "~·"''. c '.:,.·• '-').;":t'·.('<': <:<:: .~:;~;,;,"

'MALF: RC~001D•RCSLQOP, .. . RUPTURE 0

0F RCl.00P'24

SimulatQ~ Operator: Ensure ET-3 is TRUE if Train BSI keyswitch is operated OR ET .;2 TRUE if Train A

1 kevswitch is operated. This deletes

CRS determines that an orderly unit shutdown is required based on RCS leak exceeding TS limits.

CRS enters S2.0P-AB.LOAD-0001 (crew may also use S2.0P-IO.ZZ-0004).

RO develops reactivity plan for shutdown and initiates boration.

PO initiates turbine load reduction to 20% at specified rate from CRS.

RO reports rapidly lowering PZR level and 12.ressure.


TQ-AA-106-0204 15 of 36

.. ·.;~I:;'1'1%K:\:i~f ef.P1!~:~.;r:1,~,~t!~1~.dettY~.~::~~P.~t

:>Sir,nulator Oper.ator,:.En~1.1re ET .;4 ... ,:'istJRlJE followi0fJ R~.'T~fp:;i·his . ·:inserts'REMOTE.bG02Dto .,,: . :deebertfize •. the2BiSEC c'abineL •.

6. SI fails to auto actuate and one train keyswitch fails to manually actuate.

(?f#f:(cf .. ]}:;·Manually· i_n itiate, SI", l:iefore transition, to' EOPs •t.:.ocA- • . .. . . . . ; . /·, .· . . .·• ,.. . . .

· -.1· ; FRTS-1 or TRIP-2 "'$:..·F ,, •' " c• ·' • •• • •. •'""<'.• ,,;t•

;UNSA~>

CRS directs Rx Trip and Safety Injection

RO trips the reactor and confirms the reactor trio.

RO reports that SI failed to auto actuate and manually initiates Safety Injection using keyswitch. RO reports that one train of SI failed to manually initiate and goes to other train keyswitch to initiate SI. RO reports SI initiated on both trains. [CT#1]

RO continues Immediate Actions of EOPTRIP-1;

Trips the Main Turbine


TQ-AA-106-0204 Page 16 of 36

.··. tJEv~lu'atcirllrf$,tr.:ict6riActi,dF; ::::{:\ti/}~~~:,/:,:/'.{ \r<· :\,{: ·\\\~:<;;: ~t,'*:::~::~::J 1

,";Ji~'

TQ-AA-106-0204 Page 17 of 36

"\·: '" J Expected.Plantl$tuaent Response·v t . :.,"~·s·s;r, ,. :··, ··"· ·t*t. ' ~d'tcomment~/ ·1;0f7:<·:.•• .. ·t•; ,''' ' :, "\, ,4:' ,', ; , '~ ',, '* ,:: .. ' ., # fi '"' -· :: f:L '\ 3 ·w~~ ••. • {(OG ,.: ,~. ~·:~: • '.· "' , :::L:i .. ,; ;d;';\ ::~t;,,;'::1 •• ::,;;;f~,ft·.::.c .. ::'.~,?·,,w

7. 2B SEC fails to actuate

RoleJ>lay: ,,fhe•CRS may dispatch .· •·. N.!;,O to locally ,ch~ckJhe breaker .••..

f6(~B SEC ~nd'tnen dfrecfthe;0 .. ··•······ ., .. . b'fei?l<er; tel be opened toehsurethe . SECJs.deenergizedr: IF cbntacted\ THEN,,report.backafter,1/tnin"Cite as·the NEO.th'arthe instrument'·. bower breakerfor the 2B SEC is in

Reports at least one 4KV Vital bus energized. Reports SI initiated.

CRS enters EOP-TRIP-1.

CRS and RO perform immediate actions of EOP-TRIP-1.

CRS directs RO and PO to implement the CAS.

PO requests permission to throttle AFW flow to no less than 22E4 lbm/hr.

RO reports that SEC loading is NOT complete for energized vital buses.

RO reports that available equipment on 2B bus failed to start.

RO blocks 2B SEC.

RO resets 2B SEC.


~fj1;)~ti~,~~t!1:zt!{f :~!,~~~l!l~!iff ~~1:i;~\>~te~~}~f 'tr:~~2~!!~t~:~~~fR~~~~t~t( , ...... " ___ .. . thc:itripped·condition. andJheSEC looks to be. deenergized:: e_ '1 ...

CRS directs RO/PO in starting safeguards loads for 28 bus usinQ Table A.

PO reports that 21 and 22 AFW pumps are runnina.

RO reports that NOT all valve groups in Table B are in safeguards positions. PO reQ.orts that 2SW26 is NOT closed.

PO manually closes 2SW26.

PO reports that 21 and 22 CA330's are closed.

RO reports that containment pressure has NOT remained less than 15 2_sL.,.

CRS directs initiation of Phase B and Spray actuation, if not already auto initiated.

RO reports that both CS pumps started.

RO initiates Main Steam Isolation, if not already auto intiated. (Note: During validations MSLI Auto initiated post-tri

RO stops all RCPs.

RO reports that all valve groups in Table D are in the safequards positions.

PO reports that 2RP4 does NOT indicate hiqh


TQ-AA-106-0204

t~vafoatof11nstructor;'Activity1: 'l·"'',,--,i">>t,;.\'·{:'': :>::f- .,L)t";t''. f '~)/.it?'-' ~,;

>·,,.,,,,.-. '·A·w-·,,.

Expebt~cl"P!':1.ht/Stud~nf~e~p'o'ns·e:t"w>'.' . ,ixifS'.Bt1f . ' .... •m• '

,,·,, , .... ,~, ,· .·F ,,~, ''<:;0 _. •. OT'·'',, ___ ,

steam flow coincident with low steam pressure or low-low Tavg. MSLI previously initiated.

PO reports all 4KV vital buses are enerqized.

RO reports control room ventilation is in Accident Pressurized mode.

RO reports 2 switchgear supply and 1 exhaust fan are runninq.

RO reports 2 CCW pumps runninq.

CRS reads CAS to RO to notify CRS when RWST level lo alarm actuates at 15.2 feet.

RO reports RHR is NOT aligned for Cold Leg Recirc

RO reports charqinq flow is > 100 qpm.

RO reports that RCS pressure is < 1540 psig ( 1660 psiq adverse)

Per the GAS, IF RCS 1500 psig and BIT flow is established at this point, the RO closes the charqinq pump minflow valves.

RO reports that SI flow is> 100 qpm.

RO reports RCS pressure is < 300 psig ( 420 psiq adverse).

RO reports that RHR flow is at least 300 aom.

>•

TQ-AA-106-0204 Page 19 of 36

;~·:co'ffimentt'."''. ,r ;c •·

'""t, , ·, . .' {J*1ft'L ,, ,', /,,--, , }\1?,t~( > : ,.,,,. <i.J;··. ,,,,i;,)'


'.::'.':Eval'Uatorlfr1sfructor'AcJivify : ,:, ,!,< ->>i!-J):(; · · , ,;,, i J ).;,(.,_:/,,"--,;.\;:\> -t~ . , <'-''"---t·:::;: r .. ;. :""> >\~: · ·;;;)~~e~~~~~,,:~,,~~t/Studeht .. ~8,,S~(j'~~~iJrf ;.:,:}i,:?ft. ~~l}

.. .. , .... .. ' ,;,,..,,,_..,...,..


RO reports NO RCPs are runninq.

RO reports RCS Tcolds are NOT stable or tendin!J to 547 F.

RO reports that RCS Temperature is NOT> 547 F.

CRS directs PO to stop dumping steam.


RO reports that RCS temperature is NOT being controlled and that MSLI actuation has been previously initiated.

RO reports both RTBs are open.


RO reports both PZR PORV stop valves are open.

RO reports NO RCPs are runninq.

RO maintains seal injection flow to all RCPs.

TQ-AA-106-0204 Page 20 of 36 ···rcom~nti;:WB• '·'"' '?'f

c;:i;*1~~J'~~~::~; ~~: i~~;:1·:~,


TQ-AA-106-0204

.. ~J~!stJW· Page 21 of 36

· ;;'.;jiji1fi 7,·:r~~~r:';~t:)~~r ':s;~s., · · •· :.Evalil~torlinsttJ1ctorc::Acfiyjly';:1;; t:':; ri\Expectaa· Plarifl$tu~ent ~esphn*se' '~'-f\ .. :<F{:i<·: __ ·;·t:trf.·i ,\/:'. ;.,:.,t: .. ·._:·1{:< :· :·'·:%\:<\i,::----~·<*'" ....... , .. · ,_ ··" ·· .. , .... ~... "· ... -."~-.. ·-- ........ ,, · .~ ..... , , .. ,· -·

'' •··


RO reports that NO SG NR levels are rising in an uncontrolled manner.

RO reports that 2R15, 2R19A-D, and 2R46A-D are NOT in warning or alarm.

RO/PO reports ALL channels in Table F are in alarm or risinq.

CRS transitions to EOP-LOCA-1, Loss of Reactor Coolant.

STA beqins monitorinq CFSTs.

ST A reports RED path for Thermal Shock.

CRS transitions to 2-EOP-FRTS-1.

FRTS-1 actions start here:

RO reports RCS pressure NOT greater than 300 psig ( 420 psig adverse).

RO reports that RHR flow is at least 300 gpm on 21 or 22 SJ49 cold leq injection meters.

Crew returns to procedure in effect which was EOP-LOCA-1.

LOCA-1 actions start here:


Evaluator's Note: During validations, around .. this time the··. crew receivedthe,RWST Low

CRS directs RO to maintain seal injection flow to all RCPs.


CRS directs PO to maintain AFW feed flow> 22E4 lbm/hr unitl one SG NR level is > 9% (15% adverse), then maintain NR levels between 19% and 33%.

RO reports that NO SG NR levels are rising in an uncontrolled manner.

RO reports that 2R15, 2R19A-D, and 2R46AD are NOT in warning or alarm.

RO resets SI, Phase A and Phase B Isolation.

RO 0_2.ens 21 and 22 CA330s.

PO resets each SECs and reports 2A and 2C SECs reset and 2B SEC is deenerg_ized.

RO resets SGBD Sample Isolation Bypass and opens 21-24SS94s.

CRS directs chemistry to sample 21-24SGs for boron and activity.

TQ-AA-106-0204 Page 22 of 36

. :5:ct:1~,~1~~eijtt~f;:r!f ':i'.1(1r?i.:?~l7'.


:~~valtiator11 nsWCfofor·Activ1ty -,, t ?::·, ') ,~~ : 1t: Jt' :t,:\L~f ~~-\,,:\ pijf }:" ;' jji?r-2 :'.)~;;~'4 -?\ ::\;~,\~;;;:~~\l,h.

'LevelAlannand transitionedto· .·

, ,,·~?,~t?;f /3::i'•.,\:t,0:··;:t)i " .... M~f~'Ji,M.~:~~~Jlow L~x,et

. Alarm actuatectifor CT#2:::'.:i) ..

,[~1tl~,:;~i]/1)'./~'1~z'i'~'+\~ ..

Role Play: Atthis tifne,only 2C ·· )Ept3Js·forin(~g},,1Fcortta,ct~<t''6Y ''.:···· :<;cr~w U(qi~pa,tc;.~tN E.9 W'EDG·s t6)~~:.: ··•••· reset each DG:r therj: call back','after . •·f ~Jrute'.'.ar1d;(epOri'w6en}:'QU're ...... . . ready to ~top:,tbEfdiesel,J;HEI\I wait 1 rnihUte c3ndreportthat;the .. §hutclown ~EDG:is:reset.. · "'

i ·r1!i~:~xpe~\r~·d,~·l~f ~!'8,t~:1e,jf ~~·sgoj:~0~J?E ,;{Piri/:~g~/)';r,:

RO reports both PZR PORVs are closed and Block Valves open.

RO reports RCS subcoolinq is NOT > 0°F.

RO reports both RHR pumps are NOT aligned to cold leq recirculation ..

RO reports that RHR flow is> 300 QQm.

PO reports that all vital buses are energized from offsite power.

PO stops all EDGs one at a time until the DG is verified to be reset prior to stopping the next DG.


TQ-AA-106-0204 23 of 36

,;-\l>'''E"'.' .·~'<,':\'',~'""-'".·· ··,\tW,¥,.;;<, .. ·,,, ·"r<;,._::;:::,, .. , .. , ... ,;.;J,;.·· ... i'·,\,,, """"'-· .. ,_, i:-:e· , .... , W}\'.' .. ,,~,;-1'·'. P , .. h,.~;,:,'.' ': -'"~~··· .... R "'>', '"~-Z,.,,·f'?'r.-:~"' ,,,·,D\T·'.·,:,~,,...,,,.:·,;~ ... ~ ...... ,,.,"'''"7''.~,·.://<''.":(\ ·, ··p:A.,-,;µ..,'lR'"' . 11\ vatuator/lnstructot:fAct1v1tyi,,,,/, ,J"tr .,, xpected lant .Student esponse::t;::r:.:,,,; 1!C: ,bi SBT ./ ,,, :, •\i1tf';;:':, v,.

Use.of:S2p1?-SO.DG-Q0'01f0002, ·an~: 0:003 .sectidff 5.11 ):uJese1 ,

... Ge'n;eritor shutdowti:Checks is . ~sed•fo'aligfi"f?r}lUtorstarf.····

Evaluator's Note: Depending on · the pace,ofthe crew, they may.; reach step 19 with the RWST low

RO reports both RHR pumps and SJ44s available.

PO reports that there are NO Aux Bldg radiation detectors in Table C in warning or alarm.

CRS consults with TSC about obtaining required RCS, SG and Cntmt samples and equipment availability to assist in long term recovery.

CRS dispatch operators to close 2CC37 and 2CC48.

PO reports 23 AFW pump is NOT needed and trips and stops 23 AFW pump.

CRS dispatches NEO to reset the 2MS52 trip valve when the 23 AFW pump auto start siqnals are cleared.

RO reports both RHR pumps are injecting to RCS and RCS pressure < 300 psig ( 420 psig adverse).

TQ-AA-106-0204 Page 24 of 36

:· s~~~~~~:;0·:};~~~·,;~\ .


leveLalarnlnot actuated and return . : fo; step: 16, . .

EOP-LOCA-3 actions start here:

.Eyaluato(mark.timeJ>f R\1\/ST} .'lo"'tlevel alarm: .. ·.·

Time:.'"

CJ#? (CJ:-36): J:ran.sfer;to·c.61.d't ... · ie9 'rec,.rq.u1ati<>n before RWSJ · · 1evel drops/below 1 ;2'.feet.:, ...

, .. ';:; .: .. ·' ', ,, .', : . <J'(;".

Evaluator'.s Note: This CT is broken' down into three(3) parts.

" ' ' ' ~

RO reports that RWST level lo alarm has actuated

CRS transitions to EOP-LOCA-3 to transfer to Cold LeQ Recircualtion.

CRS does not implement any FRPs during LOCA-3 performance until step 16 is reached.

RO reports containment sump >62% lights lit and depresses open sump auto arm PBs for 21 and 22 SJ44.

PO removes lockouts for 2SJ67, 2SJ68, and 2SJ69.


TQ-AA-106-0204 Page 25 of 36

'·:~'\. ,;'., ,.,. •ss. ,-,~·y;.,.,.,,r

l.ji,i1!=f ttut:,tt'lg'ilpc~§~~f ~li;tt,r'}it?\[~}~;ti\,E,tf ~:~i~,;'~1:,~t/~tu.~erif~!~~1~,r .....

CJ#2(Part ~) ..,.. I nitiate:cl.ose·:orf .2SJ69 ,fn <3~ 7. mim.itei' of RWSTcs,; .

. il!lf ~f f 1~i~1!t~~; ')}:t\·\~~~

CT!2 (Part 2)-::Stop:one . ·!' ..• (;~~ta!rrnent spray purripJr:a,.~5.5~·

1E~t?0~r9~;~Vf'· SAT .-----,

RO reports 21 and 22 SJ44s are open.

RO reports that both RHR pumps are runnin

RO closes 2SJ69. [CT#2-Part 1

PO reports SI and each SECs are reset.

RO reports that both CS pumps are runnin...,.


TQ-AA-106-0204 26 of 36

RO stops 22 CS pump. [CT#2-Part 2]

RO closes 21 and 22RH19s.

RO stops 23 Charging pum2.

Using Table B, Crew selects flowpath for all 4KV vital buses are energized and goes to Step 11 for Recirc Alignment.

PO reports that there are NO vital buses energized by the DGs.

RO reports at least 3 SW pumps running, both CCHXs in service, and at least 2 CCW pumps running.

RO reports 21 and 22gc16s_are_Q_f)_en.

RO closes 2SJ67 and 2SJ68, and reports 2RH1 and 2RH2 are closed.

RO reports that 22 RHR is running.

RO opens 22SJ45.

RO reports that 21 RHR is runnin_g_.

RO opens 21 SJ45.

RO re2orts 21 and 22SJ113s are open.

RO reports 21 and 22 charging pumps runnin~d 21 and 22~S~m~unning.

TQ-AA-106-0204

,~t~l!):=t~{f t~~ of 36


:~i?1:172~~~r:(l,n~,r~.c~~*€~'{:\;~l~~!lt~,1·;:;'t:.:~::1t»' •. ''""! ... . "J;(gJPf;:tt .

· CT#2;(Parf3)--\COnlRlete , ;,t, , .. ,. ~fram,f~(to, eold)!9 recirq!(LOCA- . :r~tep:15 isJc~njplete> ih·.51t2;;; mif1utes·'frbmSRW$J;<lovitlevel ; '

. J?rt:<·i};ii:/1\l~}t~;1t:~:i~r·, '~:~. ':; ~\st

Terminate scenario when CT#2 has been evaluated QI at Lead Evaluators direction.

PO removes lockout from 2SJ30.

RO closes 2SJ30, 2SJ1, and 2SJ2.

RO places 21 RH29 and 22RH29 in manual and ensures closed (Step 15j._JCT#2-Part 3

TQ-AA-106-0204 Page 28 of 36

•

1r::c~;~:¢~'1jr.;<~Lt},~L~ ' .


A. Alarm Response Procedures (Various)

B. Technical Specifications

C. Emergency Plan (ECG)

D. OP-AA-101-111-1003, Use of Procedures

E. S2.0P-IO.ZZ-0004, Power Operation

F. S2.0P-SO.SW-0005, Service Water System Operation

TQ-AA-106-0204 Page 29 of 36

G. S2.0P-SO.DG-0005, Preparation for Removing a Diesel Generator from Service

H. S2.0P-AB.RC-0001, Reactor Coolant System Leak

I. S2.0P-AB.LOAD-0001, Rapid Load Reduction

J. S2.0P-IO.ZZ-0004, Power Operation

K. 2-EOP-TRIP-1, Reactor Trip or Safety Injection

L. 2-EOP-LOCA-1, Loss of Reactor Coolant

M. 2-EOP-LOCA-3, Transfer to Cold Leg Recirculation


MODE: 1

ATTACHMENT 1 UNIT,TWO PLANT STATUS

'TODAY

POWER: 40% RCS BORON: 1348

SHUTDOWN SAFETY SYSTEM STATUS (5, 6 & DEFUELED):

NA REACTIVITY PARAMETERS

MOST LIMITING LCO AND DATE/TIME OF EXPIRATION: • 3.8.1.1.b, action b, for 2A EOG, expires in 60 hours.

EVOLUTIONS/PROCEDURES/SURVEILLANCES IN PROGRESS:

TQ-AA-106-0204 Page 30 of 36

MWe 410

• Power ascension on hold due to Main Turbine Valve Testing issues.

ABNORMAL PLANT CONFIGURATIONS:

CONTROL ROOM:

• Unit 1 and Hope Creek at 100% power. • No penalty minutes in the last 24 hrs.

PRIMARY: • 2A EOG CIT for governor inspection and output breaker swap.

SECONDARY: • Polisher in service at 35K aligned to flash tank/23 condenser • 23 CN pump and all Heater Drain pumps out of service.

RADWASTE:

No discharges in progress

CIRCULATING WATER/SERVICE WATER: • 22 SW pump CIT for pump packing replacement. • 238 CW pump CIT for traveling screen repair.


ATTACHMENT 2

SIMULATOR READY°FORTRAINING CHEC~LIST

1. Verify simulator is in "TRAIN" Load

2. Simulator is in RUN

3. Overhead Annunciator Horns ON

4. All required computer terminals in operation

5. Simulator clocks synchronized

6. All tagged equipment properly secured and documented

7. TSAS Status Board up-to-date

8. Shift manning sheet available

9. Procedures in progress open and signed-off to proper step

TQ-AA-106-0204 Page 31 of 36

10. All OHA lamps operating (OHA Test) and burned out lamps replaced

11. Required chart recorders advanced and ON (proper paper installed)

12. All printers have adequate paper AND functional ribbon

13. Required procedures clean

14. Multiple color procedure pens available

15. Required keys available

16. Simulator cleared of unauthorized material/personnel

17. All charts advanced to clean traces and chart recorders are on.

18. Rod step counters correct ( channel check) and reset as necessary

19. Exam security set for simulator

20. Ensure a current RCS Leak Rate Worksheet is placed by Aux Alarm Typewriter

with Baseline Data filled out

21. Shift logs available if required

22. Recording Media available (if applicable)

23. Ensure ECG classification is correct

24. Reference verification performed with required documents available

25. Verify phones disconnected from plant after drill.

26. Verify EGC paperwork is marked "Training Use Only" and is current revision.

27. Ensure sufficient copies of ECG paperwork are available.


ATTACHMENT 3 . . .

CRITICAL TASK.METHODOLOGY

TQ-AA-106-0204 Page 32 of 36

In reviewing each proposed CT, the examination team assesses the task to ensure, that it is essential to safety. A task is essential to safety if, in the judgment of the examination team, the improper performance or omission of this task by a licensee will result in direct adverse consequences or in significant degradation in the mitigative capability of the plant. The examination team determines if an automatically actuated plant system would have been required to mitigate the consequences of an individual's incorrect performance. If incorrect performance of a task by an individual necessitates the crew taking compensatory action that would complicate the event mitigation strategy, the task is safety significant.

I. Examples of CTs involving essential safety actions include those for which operation or correct performance prevents ...

• degradation of any barrier to fission product release

• degraded emergency core cooling system (ECCS) or emergency power capacity

• a violation of a safety limit

• a violation of the facility license condition

• incorrect reactivity control (such as failure to initiate Emergency Boration or Standby Liquid Control, or manually insert control rods)

• a significant reduction of safety margin beyond that irreparably introduced by the scenario

II. Examples of CTs involving essential safety actions include those for which a crew demonstrates the ability to ...

• effectively direct or manipulate engineered safety feature (ESF) controls that would prevent any condition described in the previous paragraph.

• recognize a failure or an incorrect automatic actuation of an ESF system or component.

• take one or more actions that would prevent a challenge to plant safety.

• prevent inappropriate actions that create a challenge to plant safety (such as an unintentional Reactor Protection System (RPS) or ESF actuation.


TQ-AA-106-0204 Page 33 of 36

SCENARIO IDENTIFIER: 16-01 ESG-2 REVIEWER:

Initials

]>Os. "i:) 6 i$u 7.

le.) 8. W 9. c.J 10.

\-J/A-11.

iu 12.

Qualitative Attributes

The scenario has clearly stated objectives in the scenario. The initial conditions are realistic, in that some equipment and/or instrumentation may be out of service, but it does not cue crew into expected events. The scenario consists mostly of related events. Each event description consists of: • the point in the scenario when it is to be initiated • the malfunction( s) that are entered to initiate the event • the symptoms/cues that will be visible to the crew • the expected operator actions (by shift position) • the event termination point No more than one non-mechanistic failure (e.g., pipe break) is incorporated into the scenario without a credible preceding incident such as a seismic event. The events are valid with regard to physics and thermodynamics. Sequencing/timing of events is reasonable, and allows for the examination team to obtain complete evaluation results commensurate with the scenario objectives. The simulator modeling is not altered. All crew competencies can be evaluated. The scenario has been validated. If the sampling plan indicates that the scenario was used for training during the requalification cycle, evaluate the need to modify or replace the scenario. ESG-PSA Evaluation Form is completed for the scenario at the applicable facility.


Minimum Quantitative Attributes (NU REG 1021, R11, Form ES-301-4)

Malfunction Total Malfunctions Abnormal Major EOPs

ID Malfunctions After EOP

Events Transient used entry VL0420 1 1

VC0173B 1 1

RC0002 1 1

RC00010 1 1 TRIP-1 LOCA-1

RP0274A LOCA-3

RP0274B 1 1

A701 A501

DG02D 1 1

Total Number of 6 2 3 1 3

Events Min Number

5 1-2 2-4 1-2 1-2 of Events

Verified By

Comments: See NRC-3 for Contigency EOP used (FRSM-1)

Critical Task

2

2

~2

TQ-AA-106-0204 Page 34 of 36

Tech Specs Continge

exercised ncy EOPs

Yes

Yes

No

2 0

2 per set 1 per set


16-01 ESG-2

TQ-AA-106-0204 Page 35 of 36

CT#1 {CT-2): Manually actuate SI before transition to EOPs; LOCA-1, FRTS-1, or TRIP-2

CT#2 {CT-36}: Transfer to cold leg recirculation before RWST level drops below 1.2 feet.

Note to Evaluators: CT numbers in parentheses are the corresponding Westinghouse ERG Rev. 2- based Critical Task procedure WCAP-17711-NP


TQ-AA-106-0204 Page 36 of 36

. A.TTACHMENTt.

esG:PRA RELAr10Ns'1-1lPiji;_uArloN, ·

EVENTS LEADING TO CORE DAMAGE

YIN Event YIN Event

N TRANSIENTS with PCS Unavailable N Loss of Service Water

N Steam Generator Tube Rupture N Loss of CCW

N Loss of Offsite Power N Loss of Control Air

N Loss of Switchgear and Pen Area Ventilation N Station Black Out

y LOCA

COMPONENT/TRAIN/SYSTEM UNAVAILABILITY THAT INCREASES CORE DAMAGE FREQUENCY

YIN COMPONENT, SYSTEM, OR TRAIN YIN COMPONENT.SYSTEM.OR TDt.11\1

N Containment Sump Strainers N Gas Turbine

N SSWS Valves to Turbine Generator Area y Any Diesel Generator

N RHR Suction Line valves from Hot Leg N Auxiliary Feed Pump

N eves Letdown line Control and Isolation Valves N SBO Air Compressor

OPERATOR ACTIONS IMPORTANT IN PREVENTING CORE DAMAGE

YIN OPERATOR ACTION

N Restore AC power during SBO

N Connect to gas turbine

N Trip Reactor and RCPs after loss of component cooling system

Y Re-align RHR system for re-circulation

N Un-isolate the available CCW Heat Exchanger

N Isolate the CVCS letdown path and transfer charging suction to RWST

N Cooldown the RCS and depressurize the system

N Isolate the affected Steam Generator that has the tube rupture(s)

N Early depressurize the RCS

N Initiate feed and bleed

Complete this evaluation form for each ESG.

Salem Generating Station - Nuclear Regulatory Commission

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