. ACCELERATED 1>1WRIBUT306 DEMONSTRATION SY~Eg

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:8909200241 DOC.DATE: 89/09/13 NOTARIZED: NO DOCKET gFACIL:50-250 Turkey Point Plant, Unit 3, Florida Power and Light C 05000250

50-251 Turkey Point Plant, Unit 4, Florida Power and Light C 05000251AUTH.NAME AUTHOR AFFILIATION

WOODY,C.O. Florida Power & Light Co.RECIP.NAME RECIPIENT AFFILIATION

CASTO,C.W. Region 2, Ofc of the DirectorSUBJECT: Advises that ref matl re operator exam scheduled for wk of

891106 shipped to listed address,per NRC 890831 request.

DTSTRTBUTTON CODE: IE42D COPTES RECETVED:LTR i ENCL ~ STSE: RkTITLE: Operator Licensing Examination Reports

NOTES:

RECIPIENTID CODE/NAME

PD2-2 PD

INTERNAL: AEOD/DSP/TPABNRR/DLPQ/HFB 10NUDOCS-ABSTRACTRGN2 FILE 01

EXTERNAL: LPDRNSIC

COPIESLTTR ENCL

1 1

1 11 11 11 1

1 11 . 1

RECIPIENTID CODE/NAME

EDISON,G

NRR SHANKMAN,S/DLQQ/OLB 10

REG FILE 02

NRC PDR

COPIESLTTR ENCL

1 1

1 11 11 1

1 1

NOIR ZO ALL t RZKSlt RZCZPIIÃIS

PURSE HELP US I0 REDUCE HASTE'. 02KACI', 'IHE DOCUMEPZ CONTROL DESKSRXN Pl-37 (EXT. 20079) TO EIiZMIIRXBYOUR NAME HKH DIPHKSOTICNLISTS P5R DOCQKMIS RÃJ DOMPT NEED)

TOTAL NUMBER OF COPIES REQUIRED: LTTR 12 ENCL 12

P.O. Box14000, Juno Beach, FL 33408-0420

SEPTEQBER i 3 1989

L-89-33410 CFR 55

Mr. Charles W. Casto, Acting ChiefOperator Licensing Section, Region IIU. S. Nuclear Regulatory Commission101 Marietta Street, N. W., Suite 2900Atlanta, GA 30323

Dear Mr. Casto:

Re: Turkey Point Units 3 and 4Docket Nos. 50-250 and 50-251Operator License ExaminationsScheduled for Week of November 6 1989

Florida Power & Light Company (FPL) has shipped the referencematerial requested by an NRC letter dated August 31, 1989 to theexaminers and addresses listed below:

Attn: Dim MormanU. S. Nuclear Regulatory Commission, Region II101 Marietta Street, N. W., Suite 2900Atlanta, Georgia 30323

Attn: Bob GrulBattele Pacific N. W. LabsSigma 3 Building 13000 Area3160 George Washington WayRichland, WA 99352

The reference material was shipped by Federal Express to NRC RegionII and Battele Pacific N.W. Labs on September 6, 1989, from theTurkey Point Plant. An index of the reference material is attachedfor your information.

The examiners are requested to return the reference material to theTurkey Point Plant Training Staff, after the exam, so it can bemaintained current for the next exam cycle.

890920024i 8909i8PDR ADOCK 05000250V PDC

an FPL Group company

L-89-334Page 2

Should you require any additional information, please contact Mr.Paul J. Baum at (305) 246-1300.

Very truly yours,

C. 0. WoodyActing Senior Vice President — Nuclear

COW/JRH/cm

Attachment

cc: Stewart D. Ebneter, Regional Administrator, Region II, USNRCBob Grul, Battele Pacific N. W. LabsDocument Control Desk, USNRC

Page 1

SUMMARY OF REFERENCE MATERIAL

7echnical Specifications and 0-ADM-021 Technical Specificationcomplementation Procedure

Unit 3 Plant Curve Book

Precautions, Limitations, and Setpoints Document

Special Enstructions Book

Radiation Protection Manual and RWP Procedure

Transient and Accident Analysis Text

Mitigating Core Damage Text

*System Descriptions

+Siaulator Training MaterialsLesson Plans

SystemsPxoceduresTransient and Accident AnalysisMitigating Core Damage

Question Bank

SysteasProceduresTransient and Accident AnalysisMiti;gating Core Damage

*JPM's

Plant Dra~ings

Primary SystemsSecondary SystemsLogicsControls

Page 2

Original and Upgrade Procedure Index

+Original Administrative Procedures*Original Operating Procedures*Original Off-Normal Procedures*Upgrade Administrative Procedures*Upgrade Unit 3 and Common Operating Procedures>Upgrade Unit 3 General Operating Procedures+Upgrade Unit 3 and Common Off-Normal Operating Procedures*Fuel Handling Procedures*Annunciator Procedures*Emergency Plan Implementing Procedures*Unit 3 Emergency Operating Procedures*Unit 3 Emergency Operating Procedures Basis Documents

* - Detailed Lists included on subsequent pages

TVRK POINT NVCLEARTRAINING APARTMENTSY5TEIVI-OESCRIPTION5

50No.

2

3

45

6

7

8

911

13

21

2528

40

63

6890

102

104105112117123127130132

137139140144

153

155165166170

176

Rev. No.

2

45

3

3

2

43

3

5

5

3

3

3

3

42

2

4

.3410

3

2

5

3

42

2

3

48

6

43

3

FinalApproval

Date

01/07/8911/22/8806/20/8906/14/8907/12/8912/14/8801/06/8906/02/8911/16/8808/11/8802/28/8906/20/8905/16/89

02/28/8910/03/8808/22/8808/24/8812/07/8808/15/8809/29/8812/14/8806/17/8806/23/8906/14/8910/10/8802/17/8902/27/8902/28/8910/10/8811/22/8810/12/8802/28/8907/17/8908/21/8906/14/8910/18/8802/23/89

TITLE

Reactor. Vessel and InternalsIncore InstrumentationExcore Nuclear InstrumentationFull Length Rod ControlRod Position Indication SystemReactor Coolant SystemReactor Coolant PumpsPressurizer and Relief SystemSteam GeneratorChemical & Volume Control SystemEmergency Core Cooling SystemContainment SprayContainment Post Accident Monitoring & Post AccidentSampling SystemComponent Cooling WaterFuel Handling SystemReactor Protection and Safeguards Actuation SystemRadiation Monitoring and ProtectionElectrical Heat Tracing SystemSteam Generator Blowdown SystemMain and Extraction Steam SystemSteam Dump SystemCondensate and Feedwater SystemsAuxiliaryFeedwater SystemCondenser and Circulating Water SystemMain Turbine ControlTurbine, Turbine Oil, and Gland Seal SystemsTurbine Plant Cooling Water SystemEmergency Diesel Generator and AuxiliariesMain Generator and ControlsMain Power Distribution120 VAC & 125 VDC Distribution SystemFire and Service WaterPlant AirSystemsIntake Cooling WaterVentilation System and AirConditioningEmergency Load Sequencer/Bus StrippingFire Protection'and Alarm System

INITIAL COND IT IONS 1

SPECIFIC FAILURE CAPAB I LIT IES 2

CAUSE AND EFFECTS 3

TURKEY POINT SIMULATOR

TRAINING MATERIALS

'GENERIC FAILURE CAPABILITIES 4

FAILURE ACTIVATION METHODS 5

TABLE OF CONTENTSMODELING PROBLEMS 6

PERFORMANCE TEST DISCREPANCIES

SIMULATOR . PLANT DIFFERENCES

DEGRADED PRESSURE CONTROL Cc HEAT REMOVAL SCENARIOS

SIMULATOR INSTRUCTOR MANUAL 10

SIMULATOR TRAINING SCENARIOS 11

SIMULATOR EVhLUhTION SCENARIOS 12

JOB PERFORMANCE MEASURES (JPM)

1005018100- TRANSFER FROM AUXILIARYTRANSFORMER TO STARTUP TRANSFORMER

1005020300 POWER "C" 4 KV BUS FROM CRANKXNG DIESELS

1005021300 POWER "C" 4 KV BUS FROM OPPOSITE UNXT'S TRANSFORMER

1005023300

10050241001023014500

1023015500

1028002100

POWER A OR B BUS FROM CRANKING DXESELS VIA C BUS

TRANSFER FROM THE STARTUP TRANSFORMER TO THE AUXILIARYTRANSE

MANAGE DIESEL LOADING BASED ON ONE EDG FAILURE CONCUEGKNT WI'I

RECOVER FROM AN EMERGENCY DIESEL GENERATOR AUTO START FAILURE

PERFORM AN E.C P.

1028004100 DETERMINE SHUTDOWN MARGIN

1028006100 DAMPEN XENON OSCILLATION

1028007200 INDUCE XENON OSCILLATION

1028009500 RESPOND TO ATWS

1028010300 PERFORM A DROPPED ROD RECOVERY

1028014300 RESET BANK OVERLAP

1028016300

1028022100

RECOVER MXSALIGNED CONTROL RODIf

CONDUCT A 1/M PLOT

1028023300 INVESTIGATE ROD CONTROL SYSTEM URGENT FAILURE

1028025300

1028026300

1028030300

1028032200

1041004100

RESPOND TO CONTINUOUS ROD WITHDRAWAL

RESPOND TO CONTINUOUS ROD INSERTXON

RESPOND TO IMMOVABLE RCC

BYPASS REACTOR TRIP BRPJOKRS

COOL DOWN THE PRESSURIZER

1041005100 PURGE THE PRT (FEED AND BLEED)

1041006100 ADJUST PRESSURIZER PRESSURE SETPOZNT

1041007200 PERFORM RCS OVERPRESSURE TEST

1041010100 EQUALIZE RCS/PER BORON CONCENTRATIONS

1041011100 DRAIN DOWN PRESSURIZER RELIEF TANK

1041012100 REDUCE PRT TEMPERATURE

VENT THE PRT1041021100

1041023100

1041063100

1041064300

VERIFY PROPER SPRAY VALVE ACTUATION

PURGE THE PRT (MAJOR GAS VOLUME)

VERIFY NATKULL CIRCULATION FROM THE ALTERNATE SHUTDOWN PM Lf

JOB PERFORMANCE MEASURES (JPM)

1046003100 RECIRCULATE BORIC ACID STORAGE TANKS

1046006100 BLEND TO THE RWST

1046007100 BORATE THE RCS VZA THE BLENDER

1046008300 EMERGENCY BORATE THE RCS (MOV 350)

1046010100 MANUALLYMA.'KEUP To THE RCS

1046013100 DILUTE THE REACTOR COOLANT SYSTEM BORON CONCENTRATION

1Q46029100 SET UP BLENDER FOR AUTOMATIC OPERATION

1046049300 RECOVER FROM FAXLURE OF FCV-113A AND/OR BLENDER STATXON

1046054300 DIRECT PERFORMANCE OF POST ACCIDENT RCS CHEMICAL INJECTION

1049001200 TEST REACTOR PROTECTION SYSTEM

1049002300

1050004300TRIP A FAILED INSTRUMENT BISTABLE MANUALLY

RESPOND TO LOSS OF RHR SYSTEM WITH RCP'S AVAILABLE (MODE

1050005500 ALXGN RHR FOR COLD LEG RECXRCULATION

1050007300 RESPOND TO LOSS OF RHR SYSTEM W/0 RCP'S (MODE 3 TO MODE 5 TK

1050008300 RESPOND To LOSS OF RHR SYSTEM - RCS DRAINED AND OPEN

1051018300 MANUALLY CLOSE INSTRUMENT AXR BLEED VALVE

1053001100 SHUTDOWN CONTAINMENT PURGE SYSTEM

10530021QO INITIATE (AUTHORIZE) CONTAINMENT PURGE

1059003100 ADJUST HIGH FLUX AT SHUTDOWN ALARM

1059005200 PERFORM A MANUAL CALIBRATION OF THE NIS

1059007100 REMOVE A SOURCE RANGE CHANNEL FROM SERVXCE

1059017200

1059024300

TEST SOURCE RANGE NZS CHANNEL (REACTOR SHUTDOWN)

RESPOND TO LOSS OF INTERMEDIATE RANGE INSTRUMENTATION

1059025300 RESPOND To LOSS OF SOURCE RANGE INSTRUMENTATION

1059029300

1062012500

RESPOND To A SOURCE RANGE NZS MALF'UNCTION (MODE 6)

ALIGN SAFETY INJECTION FOR HOT LEG RECIRC

1062013500 ALZGN SAFETY INJECTION FOR COLD LEG RECZRC

1063008500 VERIFY SAFETY XNJECTZON OPERATION

1064002100

1064003100

1064004100

1064005100

FILL THE ACCUMULATORS

DRAXN THE ACCUMULATORS

XNCREASE ACCUMULATOR PRESSURE (HXGH PRESSURE SOURCE)

REDUCE ACCUMULATOR PRESSURE

JOB PERFORMANCE MEASURES (JPM)1064010200 PERFORM ACCUMULATOR BACKLEAKAQE TEST

1071013500 XSOLATE STEAM GENERATOR SLOWDOWN

107403650010750023001094001500

1200001500

CLOSE FEEDWATER CONTROL AND BYPASS VALVESCONTROL STEAM GENERATOR LEVEL LOCALLY WITH AUXILIARYFEEDWATEPLACE POST ACCIDENT HYDROGEN MONITOR ZN SERVICE

RESPOND TO UNIT TRIP1200022500 DX'AGNOSE CAUSE OF SAFEGUARDS ACTUATION

1200060500

2001011400

2001012400

2001013400

20160074002201019400

PERFORM POST ACCXDENT CONTAINMENT VENTING

REPORT SIGNIFICANT EVENTS

MAKE PROTECTIVE ACTION RECOMMENDATIONS

MAKE EMERGENCY NOTIFICATIONS

RESPOND TO A PLANT FIRECLASSIFY PLANT EMERGENCY

2201022400 RESPOND TO A MEDICAL EMERGENCY

3028023300

3028039300

14002009500

14003008100

.14003009100

14003012100

ZNVESTXGATE ROD CONTROL SYSTEM URGENT FAILUREINVESTIGATE ROD CONTROL SYSTEM NON-URGENT FAILURETRIP THE GENERATOR FROM THE SWZTCHYARD

PLACE A DEENERGIZED BATTERY CHARGER ZN STANDBY

DEENERGIZE A STANDBY BATTERY CHARGER

PLACE A VZTAL INVERTER ZN STANDBY

14003013100 DEENERGIZE A STANDBY VITAL INVEIGLER

14003014100 PLACE A NON-VITAL INSTRUMENT ZWTERTER ZN SERVXCE

14003015100 REMOVE A NON-VITAL INSTRUMENT XNVERTER FROM SERVXC

14003016100 TRANSFER VITAL LOAD BETWEEN ZNVERTERS

14003017100

14003018100

14003023500

TRANSFER INSTRUMENT BUS FROM INVERTER TO CVT

TRANSFER INSTRUMENT BUS FROM CVT TO I&PERTER (INTERNAL TRANSF:PERFORM 125 VDC BUS SHEDDXNG(BLACKOUT IN PROGRESS)

14003024100 'SHXFT BATTERY CHARGERS

14003025100 TRANSFER INSTRUMENT BUS LOAD FROM CVT TO SPARE INV

1400302610014005009100

14005010100

TRANSFER INSTRUMENT BUS LOAD FROM CVT TO NORMAL XNVERTER

RACK-ZN C BUS 4KV BREAKERS

RACKET C BUS 4KV BREAlG5%

JOB PERFORMANCE MEASURES (JPM)

14005011100

14005012100

14005019100

14005020300

1400502330014006008100

1400600910014007004300

14007008300

14008028500

1401301610014023003100

14028003 100

RACK-ZN A/B BUS 4KV BREAKERS

RACK-OUT A/B BUS 4KV BEKMERS

OPERATE 4 KV BRFMZR LOCALLY

POWER C 4KV BUS FROM CRANKING DZESELS

POWER A OR B BUS FROM CRANKING DIESELS VIA C BUS

RACK-IN 480 VOLT LOAD CENTER BREAKER

RACK-OUT 480 VOLT LOAD CENTER BRFAKEKMANUALLY INITIATE TELEMAND TRANSFER

MANUALLY INITIATE TELEMAND TRANSFER (OPERATION OF MANUAL BR

ISOLATE CV-2201 (SI WITH ONE OPERATING ZCW PUMP)

STARTUP DIESEL INSTRUMENT AZR COMPRESSOR

START AND SYNCHRONIZE THE EDG LOCALLY

STARTUP A ROD DRIVE MOTOR GENERATOR SET

14028009500 RESPOND TO ATWS

14028018100 SHUTDOWN A ROD DRIVE MOTOR GENERATOR SET

14028020100 PARALLEL MOTOR GENEEUkTOR SETS

14028028100 RACK-IN REACTOR TRIP,BREAKERS

14028029100

14071013500

RACK-OUT REACTOR TRIP BRKQCERS

LOCALLY ISOLATE BLOWDOWN

14074036500 CLOSE MAIN FEEDWATER CONTROL AND BYPASS VALVES LOCALLY14075011100 RESET AUX FW PUMP OVERSPEED TRIP LATCH

14200056500 RE ENERGIZE BACKUP HEATERS ON EMERGENCY DIESEL GENERATOR

24006008100 RACK ZN FRG 480V LOAD CENTER BREAKS

2400600910024041065300

RACK OUT FOG 480V LOAD CENTER BKUQKRLOCALLY ISOLATE RCP SEAL COOLING

24046039300 MANUALLY EMERGENCY BORATE (356)

24046052500 PERFORM POST ACCIDENT R C S CHEMICAL INJECTION

,2405101830024062019100

LOCALLY CLOSE THE CONTAINMENT INSTRUMENT AZR BLEED VALVE CV.

CLOSE SIT INLET ISOLATION VALVES

24094001500 PLACE POST-ACCIDENT HYDROGEN MONITOR IN SERVICE

24200056500 REENERGIZE BACKUP HEATERS ON THE EMERGENCY DIESEL GENERATOR

24200060500 PERFORM POST ACCIDENT CONTAINMENT VENTING

ORIGINALADMINISTRATIVEPROCEDURES

0103.40103.120103.360103.410109.30109.6

'7/2(/893/31/893/10/8712/11/863/29/898/4/87

In Plant Equi~t Clearance OrdersNotification of Significant, Events to NRCControl of Operator Aids and Temporary Information tagsCaution Tag Clearance ProcedureOn the Spot Chcmges to ProceduresTemporary Procedures

ORIGINALOPERATING PROCEDURES

0204.21009.11009.31009.45163.

2'/27/898/24/884/19/895/28/885/19/89

OP 5523.1 5/30/89

OP 14004.8 6/14/8S

Periodic Tests, Checks> and Operating EvoluticasEcted Critical'aaditicaaSbutdc~ Margin CalculatiaaQyec'aticea Within Flux Differecme Target BandNaate Diapcaal S~tcm - Caetrelled Licyxid RelecLse

thMatte DiaZaeal Syataa - Gas Decuma Tank, CcatrollecBebmae to AtaceykmreUse of the CgP56 - Ermdeymte Core Cooling Hector

ORIGINALOFF-NORMALOPERATING PROt EDURES

CtKPCMPCMPONOPONOPONOP

ONOPONOPONOPONOPONOPONOPONOPONOPONOPONOP

0208.14

1108.11208.1

1568.1

2608.23108.23208.13308.13408.1340&.2

5168.55508.27308.1&608.19108.19208.19308.1930&.29408.19408.2

9408.39608.1960&o210308.1

11108.1

11208.1

12308.2

15608.216708.1

5/12/89

5/16/897/27/89

4/7/88

5/26/885/16/893/30/890/30/895/1&/891/24/&9

8/10/894/7/873/24/894/9/877/28/8610/30/864/6/894/9/872/10/886/30/88

4/6/893/24/898/17/884/28/89

5/24/89

5/28/87

10/22/87

3/2/897/24/88

Deviation or Failure of Reactor Protection andSafety ReLated Began Inatx~itation CmaaelsReactor Coolant Rap Off-Norjaal CoExkf.ticeaPressurizer Power Operated Relief Systea " (Reliefs azKV's) - HalfmctionSeccedary Chmisi ~ - Operator Actices in tbe Event cDeviation frca L'tsCVCS - Halfmetim ~~ Barm Ceacentratim Cantrol SysteaHigh hctivity in Caegxma& Cooling RaterMalfunction of Reaickal Heat 1 «aeval SystemTurbine Plant Cooling Water MalfunctionIntake Cooling Water - MalfunctionIntake Cooling Water - Failure Due to Transport of HeavLoadsWaste Holdup Tank-Pump Back SystemWDS - Off Normal Operation, Gaseous Waste Disposal SysteHalfunction of the Auxiliary Feedwater SystewGenerator Radio Prequel~ Honitor (Unit 4 Only)Hain Transformer - HalfunctionAuxiliary Transforaar - MalfunctionStartup former - Malfunction"C" Bus Transformer - MalfunctionLoss of "A" or "B" 4KV Bus.Energizing 4KV Buses Using the Cratdcing Diesels Bus YiLines or'Startup Transformer fraa the Opposite UnitLoss of Voltage to "C" 4160 Volt Bus125 V DC Systee - Location of GroundsAuxiliary 125V DC Systea - Location of GroundsControl Building Heating Ventilation and Air CoaditionirqSystea (HVAC)Process RacBatim Monitor - Off-Normal CceQtice Opera-tionArea Radiation Monitoring Systea (ARCS) OffWeruaiOperationPcs)er Range Nuclear Instrummtatim Verification ofUpper) Lever) and Cannel ~riation Ala~Inst+,ment Air Dryer MalfunctionSpent Peel Cask 3M~pmmy Cooling

UPGRADE ADMINISTRATIVEPROCEDURES

O-AD.'l-0310-ADA-2000-ADA-2010-ADM-202 ~

0-ADA-203O-ARf-204,0-ADH-207

0-ADH-o03

8/31/88~i/28/893/10/894/17/897/13/89ti3/899/30/88

5/20/89

Independent VerificationConduct of OperationsUpgrade Operations Procedure UsageShift Relief and TurnoverShift Operating PracticesOperations Varrative LogbooksOperations Instructions in the Event of a Situation riotAddressed by Procedure

. Control and Use of Temporary System Alterations

UPGRADE UNIT3 ANDCOMMONOPERATING PROCEDURES

0~003.10~003. 2~003. 3O~M03.43WEM053~&05. 13~0063~073~083~133~190~&230~253~303~38.233~041.13~~1.23~41. 33~~1o43~~1. 73~-041.83~-041.90~-0463WP-047.OW-0483~500~&51. 20~&533~&553-OP-0573WP&61. 33~~23~643~673~M683~713~&723~730~074. 13~753~873~893~94

4/4/894/26/894/4/894/26/895/22/895/22/896/1/894/27/887/13/895/30/8$8/3/897/20/&93/22/8$4/28/899/24/874/4/894/4/894/5/884/6/893/24/897/27/896/14/897/11/896/23/894/12/893/24/897/18/874/ll/894/26/896/16/8912/2/884/4/894/13/895/12/892/2/894/6/894/28/893/24/895/12/893/24/894/6/897/13/893/24/89

125V Vital DC Syatea125V Auxiliary DC Syatea120V Vital Instrument AC SyateaAmgQisry 120V AC Syat~4160 Volt Busea A and B4160 Volt Bua C480 Volt Srktchgcar Syatca480 Volt Hotar Control CentersTurbine Plant Coolie WaterInstruct Air SyateaIntake Cooling Water SyatcaE~isacy Diesel QacmcatarCentral Raaa Ventilation SyateaCcQg~lt Cooling Water SyatemFuel Transfer Syatea - Narasl OperaticeRector Coolant ~Pressurimer ~aaticmE rsseuriser Relict Tank0 IEttC ~Drafting the Reactor Coagulant SyateaFilling and Venting the Reactor Coolant SystemReduced Inventory'perationsCVCS - Boron Concentration ControlCVCS - Charging and LetdownHeat Tracing SystemResidual Heat Removal SystemPost Accident Containment Vent SystemContainment Purge SystemBnergency Containmcnt Cooling and Filtering SystemContaimmnt Normal Ventilation and Cooling SystemReactor Coolant Drain TankSafety InjectionSafety Injection AccuaaQatarsProcess Radiation Hanitoring SystemCantaimlent Spray SyateaStcam Gerwrator Blowdown Recovery SysteeHain Stcaa SystemCondensate SystcaStmxSy S/Q Fcedmtcr SystemAuxiliary Fcechatcr SyateaTurbine Lube Oil SyatcaHain TurbineCantai~nt Past Accident Hanitaring Systems

UPGRADE UNIT3 GgNERAI OPERATING PROCEDURES

3~-1033~-3013~P-3053~-503

7/20/89I /13/898/15/897/20/89

r

Power Operation to Hot StandbyHot Stmxiby to Power OperationHot Standby to Cold ShutdownCold Shutdown to Hot Standby

3~-003.4'~-003.5

3~-003.63~P-003.73~-003.83~-003.93~-0043~-004.1

Loss of DC Bus 3D01 (3A)Loss of DC Bus 4D23 (3B)Loss of DC Bus 3D01 (4D01)Loss of 120V Vital Instrunent Panel 3P06Loss of 120V Vital Instrument Panel 3P07Loss of 120V Vital Instnamnt Panel 3P08Loss of 120V Vital Instrument Panel 3P09Loss of Offsite PowerRestoration of Electrical Systems Following the Recover.of Offsite Power4KV Bus 3A or 3B GrocsxiLoss of Instr~st AirMain'ondec~r Loss of VacuxaaResponse to Spurious Actuation of a Fire/Isolation DamperScreen Wash Zhergency Makeup to the Fire Protectior.SystemResponse to a Fire/Smoke Detection System AlarmResponse to a Reported Fire in the Charging PumpRoaa, HCC B Rooa, Cable SpreacUing Room or ControlRoaaBaergency Diesel GeneratorLoss of Control Roca Ventilation System (CPS)Air ConditioiningReactor Control System HalfunctionRCC MisaligmmntRCC Position Indication MalfunctionDropped RCCLoss of CcmpcNMNst Cooling WaterSpent Fuel Pit (SFP) Cooling System MalfunctionRefueling Cavity Seal FailureAccidents Involving New or Spent FuelFuel Transfer System Manual/Emergency OperationExcessive Reactor Coolant System LeakageExcessive Reactor Coolant System ActivityPressurizer Pressure Control HalfunctionPressurizer Level Control HalfunctionEmergency BorationLoss of Boration

Flowpath(s)'oss

of Charging Flow in Modes 1 'Ihrough 3Off-Normal Critical Heat Tracing System TemperatureR~mrgizing Safeguard Racks After Loss of Single PowerSupplyLoss of RHRLoss of Containaant IntegrityExcessive dacial Flux Differecx:eSource Range Nuclear Instnematation HalfunctianBackup NIS (Gamm Hetrics) MalfurmtionIntermcU.ate Range Nuclear Instrumatatica MalfunctionPower Range Nuclear Instrumatation MalfunctionXzmctvertent Release of Radioactive GasInadvertent Release of Radioactive LiquidGteaa Generator ~i LeakStandby Steam Gcamrator Feedwater System Operation WithLoss of Offsite Power and Loss of Amciliary FeedwaterTUrbine RuabackAl % hdMcaktoringFast Load ReductimControl Roaa Evacamtica

3~-005.40~-0133~&140~-016.20~&16. 7

1/22/884/6/895/31/896/9/898/10/89

o/6/896/14/89

0~-016.83~-016.9

OWNQP-023. 20~-025.2

7/13/899/1/88

3 WHOP-0283~~28. 13WHOP-028. 23~OP-028. 33WHOP-0303&NXM33.13~-033.23~P-033.33~P-038.13~P-041.33~P-041.43~&41.53~&41. 63~-046.10~-046.33~-047 F 10~-0483~-049

8/8/892/15/894/io/8910/26/88

'5/16/892/11/883/24/898/10/899/15/877/27/896/29/898/10/897/27/897/6/897/12/88o/24/894/12/89o/20/88

3/30/895/31/896/30/892/25/885/11/881/9/899/21/885/16/895/30/897/6/897/27/89

3~-0503~-0533~-059.43~&59. 53~QP-059. 63EMP59. 73~&59.83~W670~-067.2"~P-0710~-074.13~~893~~4 10/20/88

4/26/89

7/20/897/13/89

3~OP-100O~KP-105

UPGRADE UNIT3 ANDCOMMONOFF-NORMALOPERATING P ROCEDURES

o/8/895/8/898/10/898/10/891/12/888/10/895/24/893/18/86

~ ~FUEL HANDLINGPROCEDURES

QP 16000.1 4/7/89 Lfaitaticas and Preoauticxm for Handling Fuel AsscablicsQP 16200 lg/3/St Manipu1atcc Craz» - Operating Instrc~icxm

ANNUNCIATORPROCEDURES

CHEAP 0208. 3QNP 0208. 4QNQP 0208. 5

(MP 0208.6CMP 0208. 7C5CP 0208. 8CAP 0208. 9CNCP 0208. 10

CMP 0208.11CNCP 0208. 12CNP 0208.13CAP 0208,15CtKP 0208.16QKP 0208 '8C5CP 0208.19

8/22/8911/25/888/22/89

8/22/898/22/898/22/898/22/898/22/89

8/22/898/22/894/26/896/14/898/22/893/24/898/22/84

AnnunciatorAnnunciatorAnnxumiatorTripsAnnunciatorAnnunciatorAnnunciatorAnnunciatorAtnunciatorAuxiliaryAnzRQx'.iatorAnamciatorAmmmciatorAnnmmiatorAnmnciatarAcaxnciatorAuamciator

List - Panel A - Reactor CoolantList - Panel B - Reactor PanelList - Panel C - Steaa Generator and Reacto:

List - Panel D - Condensate and FeecheaterList - Panel E - Turbine GeneratorList - Panel F - ElectricalList - Panel 6 - MiscellmmousList - Panel H - Safety Injection an

List - Panel. I - Station ServiceList - Panel X - CceaaList - %ate/Borca Panels- GeIMralList - Panel J - Aaaciliary Electrical Pc~List - Caadmsate Poliskdag Systea PanelList - Process Caatrol Panel&-46

EPIP 20101EPIP 20102

IP 20104EPIP 20105EPIP 20106EPIP 20107EPIP 20109EPIP 20110

EPIP 20111EPIP 20112EPIP 20125EPIP 20126

5/5/899/2//88

11/2/885/11/885/25/893/24/8910/11/886/19/89

11/2/884/17/8911/19/884/4/89

Duties of Emergency CoordinatorDuties ef an Individual Who Discovers an EmergencyConditionDuty Call Notifications/Staff AugmentationEmergency Respcese FacilitiesNatural EmergenciesFire/Explosion EmergenciesCriteria For, and Conduct of Local EvacuationsCriteria For > and Cotxiuct of Owner Controlled AreaEvacuation

RetryCcaxaa6cations NetworkQn-Site Emergency QrganinationOff-Site Dose Calculations

UNIT3 EMERGENCY OPERATING'PROCEDURES3-EOP-E-03-EDP-E-13-EOP-E-23-EOP-E-33-EOP-ECA-0.03-EDP-ECA-0. 1

3-EOP-EGA-0. 23-EDP-ECA-1. 13-EOP-ECA-1 ~ 23-EOP-ECA-2.13-EOP-ECA-3.1

3-EOP-ECA-3. 2

3-HP-ECA-3.33-EDP"ES-O.O3-EDP-ES-0.13-HP-ES-O, 23-HP-ES-O. 3

3-EOP-ES-0. 4

3-EOP-ES-1 ~ 13-HP-ES-1. 23-EOP-ES-1. 33-K)P-ES-1. 43-EOP-ES-3» 13-EDP-Ei-3. 23-EOP-ES-3. 33-HP-F-03-HP-FRW» 13-HP-FR%. 23-EDP-FRW» 33-HP-FRW» 13"EOP-FRW. 23-HP-FRW. 33-EOP-FR-H» 43-HP-FR-H» 53-EDP-FR-I. 13-EOP-FR-I. 23-EOP-FR-I. 33 "EOP-FR"P . 1

3-EOP-FR-P.2

3-EOP-FR-S.13-EOP-FR"S.23-HP-FR-Z. 13-EOP-FR-Z. 23-EOP-FR-Z. 3

ZC/Zf/ZC:wf/ZC/ZCZC/ZC/ZCZC/ZC/ZCZC/.CC/ZCZC/ZC/ZCZC/ZC/ZCZC/ZC/ZCZC/XX/ZCZf/ZC/ZCZQ'ZQ'XX

ZC/ZC/ZC

ZC/3K/ZCZC/KQZCZC/XX/ZC

'X/XX/XXZC/ZC/!K

!QC/ZC/!KXX/XX/ZCXX/XX/XXXX/ZC/XXZC/!K/ZCXX/XX/XXZC/!K/ZCZC/ZC/!KZNQNKZf/X&KZC/!QC/ZCZf/ZNK!QC/)QC/ZC!QNQf/ZCZC/XX/ZCXX/ZNKZf/Zf/ZC:G/ZC/ZC

ZC/ZC/ZC

ZC/ZQ'ZC

ZC/ZC/ZCZC/ZC/ZC

Reactor Trip or Safety InjectionLoss of Reactor or Secondary CoolantFaulted Steam Generator IsolationSteam Generator Tube RuptureLoss of All AC PowerLoss of All AC Power Recovery Without SI RequiredLoss of All AC Power Recovery With SI RequiredLoss of Emergency Coolant RecirculationLOCA Outside ContainmentUncontrolled Depremrurization of All Steam GeneratorsSCIL With Loss of Reactor Coolant-Subcooled RecoveryDesiredSGTR With Loss of Reactor Coolant-Saturated RecoveryDesiredSGTR Without Pressurizer Pressure ControlRediagnosisReactor Trip ResponseNatural Circulation CooldownNatural Circulaticm Cooldowa With Steaa Void in WithRVLHS (QSPDS)natural Circulaticm Cooldown With Steaa Void in Vessel(Without RVIAS)SI TerminationPost UXA Cooldown and DepressurizationTrmmfer to Cold Leg RecirculationTnmsfer to Hot Leg RecirculationPost-SGIR Cooldown Using BackfillPost-SGIR Cooldown Using BlowdownPost-SGTR Cooldown Using Steaa DumpCritical Safety Function Status TreesReeganse to Inadecymte Core CoolingRespcc~e to Degraded Core CoolingResponse to Saturated Core CoolingResponse to Loss of Seccedary Heat SMr,Rnq~e to S~Gemretar 0verprer ~Resgxmae to Steaa. Generator High LevelResponse to Loss of No~1 Steea Release CapabilitiesBespoke to Steaa Gamrator Low LevelResponse to High Pressurizer LevelResponse to Low Pressurizer LevelResponse to Voids in Reactor VesselResponse to Imu.nent Pressurizer Thermal Shock ConditionResponse to Anticipated Pressurized Theraal ShockConditionResponse to Nuclear Power Generation/ATWSResponse to Loss of Core ShutdownResponse to High Containment PressureResponse to Containaant Flooding,Response to High Containment Radiation Level

UNIT3 MERGENCY OPERATING PROCEDURES. BASIS DOCUMENTS

3-BD-EOP-E-03-BD-EOP-E-13-BD-EOP-E-23-BD-EOP-E-33-BD-EOP-ECA-0.03-BD-EOP-ECA-0.13-BD-KP-ECA-0.23-BD-EOP-ECA-F 13-BD-EOP-ECA-1.23-BD-EOP-ECA-2.1

3-BD-KIP-ECA-3.1

3-BD-BDP-ECA-3. 2

3-BD-KP-ECA-3. 33-BD-83P-ES-0. 03-BD-KP-M-0,13-BD-KP-ESW. 23-BD-KjP-ES-0. 3

3-BD-KP-ES"0. 4

3-BD-KP-FS-1. 13-BD-KP-ES-1. 23-BD-KP-ES-1. 33"BD-KP-ES-1. 43-BD-KP-ES-3. 13-BD-KP-ES-3. 23-BD-KP-ES-3, 33-BD-KP-F<3-BD-KP-FRW o 13-BD-KP-FRW. 23-BD-83P-FRW. 33-BD-KP-FRW. 13-BD-KP-FR-H. 23-BD-KjP-FR"H.33-BD-KP-FR-Ho 4

3"BD-KP-FR-Ho 53-BD-KP-FR-I. 13-BD"KP-FR"I.23-BD-KP-FR-I.33-BD-KP-FR-P. 1

3-BD-KP-FR-P. 2

3-BD-KP-FR-S. 13"BD-KP-FR-S. 23-BD-KP-FR-Z. 13 BD-KP-FR-Z.23-BD-KP-FR Ze 3

4C/'CC/XXZC/ZC/XX<C/XC/XXZC/ZC/XXXC/ZC/MC:aVhC/XXXC/.'K/3|XZC/ZC/MZC/.'GC/XXZC/3Z/ZC

ZC/XC/XX

XX/XVXX

XX/XX/XK3GC/XG~XX/XC/XXXVX2KCCXX/XX/XX

XX/ZC/XX!GNQKGCXX/ZC/XXXX/AC/XXXX/XX/XXXK/Zf/PGCXX/XX/XXZKQVXCXX/XNGCXÃGfjKKXX/XK/XKXX/XKKZNQZKXX/XNGCZNG4QK

ZNGKGCXX/:le GC

XXfXWCKXNCXnCKZNGVXK

Reactor Trip or Safety InjectionLoss of Reactor or Secoadax~ CoolantFaulted Steam Generator IsolationSteam Generator Tube RuptureLoss of All AC PowerLoss of All AC Power Recovery Without SI RequiredLoss of All AC Power Recovery With SI RequiredLoss of Emergency Coolant RecirculationLOCA Outside ContainmentUncontrolled Depressurization of All Steam Genera-torsSGTR With Loss of Reactor Coolant-SubcooledRecoverySGTR With Loss of Reactor Coolant-SaturatedRecovery DesiredSGTR Without Premsurizer Pressure ControlRediagnoeisReactor Trip RespecxseNatural Circulation CooldownNatural Circulation Cooldown With Steam Void inVessel With RVIAS (QiPGS)Natural Circulation Cooldown With Steam Void inVessel (Without RVlAS)SI TerminationPost QXA Cooldawa and DepressurizationTransfer to Cold Leg RecMmlationTransfer to Hot Leg RecirculationPost-SOIR Cooldawn Using BackfillPost-~ Cooldawn Using BlowctawnPost-SGIR Cooldawn Using Steaa DuapCriticaL Safety Function Statue ~~Re~rezw. to Iaahsquate Care CoolingResp~ to Degrade Core CoojLh+Respaaee to Saturated Care Cooling~ause to Lose of Secondary Seat Sink

Resume to Steaa Generator High LevelRespaaee to Lace of Naraal Steaa Release Capabili-tiesResponse to Steea Gsaerator Lur LevelRespaaee to High Preeeuriser LevelRespaElse to Loll Pressuriser IAhh$1Reepanee to Voids ha Reach'eaeelReslxese to ~hue Preesurixer 'Hernial ShockCcixkiticaa

.Respaa~ to hnticipatsd Pressurized '1henaal Bxcak'clxiitica'eepacme to Nuel~ E&ar Generation/hIWS

Respaclse to Loss of ~ ~doll»HUh~ iRespcime to Caatai wmt Plooding

RUh~ Mlt ti