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U.S. NUCLEAR REGULATORY COMMISSION

REGION III i

Report No. 50-331/0LS-87-01(DRS)

Docket No. 50-331 Licenses No. DPR-49.

Licensee: Iowa Electric Light and Power Company .

I.E. Towers. P. O. Box 351'

Cedar Rapids, IA 52406i

Facility Name: Duane Arnold Energy Center

Examination Administered At: Duane Arnold Energy Center

Examination Conductp4L July 15-16,1987' .

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Date|nln'

Examiners: Q Lhriksbur %

03 a Ob t, /& 7.. rcDate'

Approved By: dick, Chief 8h/D.

Operating Licensing Section Date

Examination Summary

Examination administered on July 15-16, 1987 (Report No. 50-331/0LS-87-01(DRS))Written and oral examinations were administered to two Senior Reactor Operator(SRO) candidates.Results: Both SR0 candidates passed the written and oral examinations.

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8708200371 870818PDR ADOCK 05000331V PDR

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REPORT DETAILS,

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|1. Examinerst

R. D. Lanksbury, Chief ExaminerE. A. Hare

2. Exit Meeting! .

!,.At the conclusion of the examinations, an exit meeting was conducted.The following personnel attended this exit meeting.

Facility Representatives ,

C.-R. Mick, Operations SupervisorD. Wilson, Training SuperintendentM. Meyer, Senior Instructor

| R. J. Bucker, Acting Training Supervisor, Operations

NRC Representatives

R. D. Lanksbury, Operating. Licensing ExaminerE. A. Hare, 0perating Licensing Examiner

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J. S. Wiebe, Duane Arnold Senior Resident Inspector

The following items were requested from the licensee:

a. A copy of Technical Specifications Interpretations,

b. Ensure complete and up to date material is sent to examiners,especially Technical Specifications. Reference material shouldnot be sent too early (i.e., significantly before the required60 days,unlesssorequested).

During the scenario walkthrough, the examiner noted a discrepancy inreferenced Operating Instructions (01) procedure numbers in the EmergencyOperating Procedure (EOP) and the currently used 01 numbers. The E0Psreferenced the.old two digit procedure numbering system. A new operatinginstruction numbering' system was implemented which changed the numbersystem to three or four digit codes. The E0P's have not been updatedto reference the proper 01 number. The examiner requested the facility

L to review their E0P and correct all reference material. This item wasturned over to the Resident Inspectors for followup,,

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3. Examination Reviewl

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Specific facility comments concerning written examination questions,'c followed by the NRC responses, are enumerated in the attachment.

The examiners noted that significant portions of the. facility suppliedreference material were out of date at the time of the examination. Thismaterial ranged. from the' Technical Specifications themselves-(which wereoutdated by several amendments) to the Operating Instructions-(which in

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'one case was outdated by.two' revisions).- Investigation.into.the matter| revealed that the changes had been issued as must as four months priorl to'the~ examination. The facility was requested to ensure that in the

future reference materials were up to date.

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ATTACHMENT-

5.04Et

Facility Comment: We agree with the' answer key, however, we feel the questionwas misleading since "several hours" was not quantified.Also, this question required the candidate to make anassumption that is beyond the scope of his classroom1

training. The' assumption he'had to make was that theburnout of Xenon at that power level is less tha'n the

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buildup of-Xenon due-to I-135 decay. ,

In operating the plant during a startup, he is trained |^

to correlate rod movement at constant pawers due to Xenon 1concentration changes. The Xenon concentration' amounts, i

changes, and when they occur is more a function of theReactor Engineer.

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i'The training conducted on Xenon Equilibrium is based

on conceptual. knowledge of:

1. The Xenon production and removal terms.

2. Operational transient effects of Xenonconcentration.

3. Relative changes in Xenon Reactivities for reactorstartup, shutdown, and poweE operation.

We feel the question would have been clearer if "severalhours" would have been quantified and a phrase explainingthat Xenon burnout is insignificant.

Also, Answer "b" is vague so we feel it could beinterpreted as the correct answer for the followingreasons.

1. The phrase " rapidly insert" is meaningless because~

there is only one rod speed. The operator has no wayto increase rod. insertion other than to' reduce thetime between rod selection.

2. The phrase "high rate of Xenon burnout" is vague andhe is not required to quantify Xenon burnout with apower level. He does not Pnow whether it is a highrate of burnout nor..is h6 ad to know when the.wburnout rate is high. Al* , v- n the different halflives of Iodine and Xeno< ^ lours for Iodine and i9.2 hours for Xenon) t.re 't into play it becomes '

very difficult to evalua* a phrase as beingincorrect.

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ATTACHMENT 2

We request that credit be given for Letter a or b.

NRC Resolution: Disagree with comment. The facility reference materialdid not substantiate that b would also be an appropriateanswer. In addition, " rapidly insert" rods is a genericindustry term not related to rod speed, but rather to how |quickly the operator performs the rod insertions. Sufficient '

information was provided to indicate to a knowledgeableoperator that Answer 'b' would not be correct (i.e. , Rxjust critical means low neutron flux levels which implieslow burnout of Xenon). To state in the question.that Xenonburnout was minimal would make 'b' an obvious wrong answerand not worth using. It should be also noted that thecandidates were briefed prior to the start of theexamination that if any question was not clear theyshould ask the examiner for clarification. The questionwill be reviewed for any necessary revisions for clarity.

5.06 B

Facility Comment: We agree with the answer key for 5.06 B, but we also |

feel that there are additional acceptable responsesas stated in the reference used.

Several of the major sources of hydrogen are longterm sources such as:

Radiolysis of Water iCorrosion of Zinc based paintAluminum corrosion i

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Since the question did not specify the time period, we |request the answer key be modified to accept any of the !

major sources of hydrogen listed below: {

Steam: Zirconium,

Steam: Steel '

Core: ConcreteRadiolysis of WaterCorrosion of Zinc based paint i

Corrosion of Aluminum {!

NRC Resolution: Disagree with comment. The question asked for the !principal source of hydrogen in containment following )a LOCA. A Steam: Zirconium reaction is the major |producer of Hydrogen as shown in MCD Page 6-22, 1

Figure 6-F. The answer key will not be changed. |

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ATTACHMENT 3

5.06 C

Facility Comment: Technical Specification Section 3.7 list a limit of.4%for Oxygen in the Primary Containment. The bases forTechnical Specification 3.7 lists two values, 4% and 5%.System Description E-12 states that the alarm is setfor 4%.

We realize that the Technical Specification bases and the 4

alarm setting are set conservatively low to ensure thatthe flammability limit stated in Mitigating Core Damageis not exceeded. However, we believe it is more importantfor the operator to be trained using the Technical.Specifications 4% limit since it is a licensed document.

The bases for Technical Specifications also implies there t

is more than one flammability limit, the 5% limit and theAEC (now NRC) recommendation of 4%.

The question also did not state the document that theoperator should reference for the Oxygen limit. Sincewe believe it is absolutely imperative that the SR0 isfamiliar with Technical Specifications and complies withTechnical Specifications at all times, we feel an Oxygenlimit of 4% is also a correct answer.

We request that full credit be given for stating thatthe Oxygen limit is 4%.

INRC Resolution: Disagree with comment. The candidates were specifically '

asked for the maximum flammable concentrations of hydrogenand oxygen in the containment following an LOCA. Thequestion was for LOCA conditions - not normal operations |

as stated in your Technical Specification reference. !The answer key has not be changed. |

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5.10|

Facility Comment: We believe there is a math error in the answer key.!

EOL period calculation is incorrect and should be !45 seconds. )

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This will also change the final answer to 17 seconds. |

62 - 45 = 17|

We request the answer key be changed to reflect an E0L )| period of 45 seconds, and a change of 17 seconds. l

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NRC Resolution: Agree.with comments. The correct answer will be changedto BOL = 62, E0L = 45, Change = 62 - 45 = 17 seconds.

5 11 A i

Facility Comment: The question did not ask for the reason or mechanism bywhich enhanced operation using barrier fuel is obtained.The question asked for the difference between barrierfuel and other fuels. |

The answer key includes the difference in the firstsentence. The second part of the answer key includesthe mechanism by which cracking is inhibited.

We request that the second sentence of the answer for'

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5.11 A be deleted and full credit be given for statingthat a layer of zirconium is bonded to inner surface.

NRC Resolution: Agree with comment. The second sentence will notbe required for full credit. The answer key willreflect this change.

5.11 B

Facility Comment: Iowa Electric may or may not eliminate PCIOMR restraints.It is true that Preconditioning can be eliminated by use '

of barrier fuel. However, from an operational standpointthe main significance of barrier fuel is the ability ofthe fuel to accommodate large power changes withoutpellet-clad interaction failures. The operator has v

been informed that PCIOMR may still be followed inan abbreviated manner to provide additional iconservatism. '

The use of the term " target exposures" is more of a !

( Reactor Engineer term than an operator term. The operatoris more familiar with the term power level and we feel thetwo terms are synonymous. '

We request full credit for answering in terms of allowinglarge power changes without fuel damage. We also requestthat no points be taken off if the operator does not statethat preconditioning can be eliminated.

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NRC Resolution: Partially agree with comment. The answer key specificallystates either answer would be acceptable for full credit.Therefore, the candidate does not need to state that.preconditioning can be eliminated to receive full credit. i

. However, the examiner does not agree' that power level and '

target exposures are synonymous terms.- One aspect of. a .target exposure'is power level. The other aspect is theamount of time at a given power level. Therefore, the twoare not synonymous, but are related,

5.13

Facility Comment: This question involves a conversion from psig topsia, determination of the saturation temperature iand a subtraction calculation to determine the '

number of degrees subcooled or superheated.

Any single mistake in this calculation such as improperor no conversion from psig to psia or a reading error on

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Table 2 could result in an incorrect response for bothanswers in the answer key.

We request that any single error in the calculationnot be carried forward when grading the question.,

NRC Resolution: Agree with comment. It is not NRC policy to doublejeopardize a candidate when a question of this typeis asked. A candidate would not lose full credit fora single error in his calculation.

5.15 B

Facility Comment: We agree with the answer key. We also feel thereare alternate answers that are just as correct.

As per the attached reference (System Description C1Page 47) we feel the below' listed responses shouldalso be given full credit:

1. Pump minimum flow ' valves

2. Pump minimum flow valves which open on lowflow (400 gpm)

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We request the answer key be modified and full credit be Igiven for the above mentioned items or similar responses. I

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ATTACHMENT 6

NRC Resolution: Agree with co;.1 ment. Will also accept " Pump minimum.flow valves" or " Pump minimum flow valves which openon low flow (<400 gpm).

6.01 A

Facility Comment: We agree that Technical Specifications list the fiveitems listed in the answer key, but the list is forthe second items and not the actual rod blocks. Seeattached Technical Specification Bases.

The attached System Description (I-8) and Figure ofrefueling rod blocks describe the refueling rod blocksin greater detail.

We feel that a better answer to the question would beto list four conditions that result in a rod block.

We request the answer key be modified to accept anyfour of the below list:

MODE switch in REFUEL and:

1. Trolley mounted hoist loaded with platform overor near core.

2. Frame mounted hoist loaded with platform overor near core.

3. Fuel grapple loaded with platform over ornear core.

4. Fuel grapple no full up with platform overor near core.

f5. Not all rods in and selection of a second.

6. Service platform hoist loaded.

MODE switch in STARTUP and:

7. Refueling platform over or near core.

8. Service platform hoist loaded.

NRC i lution: Agree with comment. Will also accept the abovementioned list as answers.

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6.02 A

Facility Comment: We agree with the answer key for each condition, however,we do not feel it is absolutely necessary for the operatorto answer the question using terms such as " level error,level set, steam flow / feed flow error" in order to

demonstrate understanding of the feedwater controlsystem.

We feel the format of this question could be improvedby separating the questions from the initial conditionstatement. It is very difficult for an operator todetermine the question he is being asked if the questionsare all written as one sentence next to the initialcondition. It is also difficult for the operator tocheck his answers following a lengthy exam if thequestions are not readily identifiable.

The answer key for the last 0.5 points states that the"feedwater control valves will open to match new higherlevel." This statement is confusing and we do not agreewith this answer. If the "A" level detector fails low,then the feedwater control system will see a large levelerror signal no matter how far level increases. Reactorlevel will increase until the feedwater pumps trip at211". (See attached System Description 0-15, Page 11.)

We request full credit be given if the explanationincludes a final resolution of the event, i.e., " levelincreases until feed pump trip" because we feel thisshows understanding of feedwater control.

NRC Resolution: Disagree with comment. The question asked how thereactor level will initially respond (immediatelyfollowing the failure). Therefore, feedwater pumptrip at 211" is the final response due to increasingreactor water level. The answer key will not be changed.The candidate need not use the exact terminology used inthe answer key to receive credit. The question will bereviewed for any changes necessary to enhance clarity.

6.02 C

Facility Comment: We request full credit be given if the explanationincludes final resolution of the event, i.e., "Feedwater |valves close due to Feed flow / Steam flow error until !

level drops enough for level error to counteract the |flow error. j

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ATTACHMENT 8i

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NRC Resolution: Agree in part with comment. The candidate need nothave exact wording as the answer key to get full credit.Each candidate's res.ponse~will be reviewed for itsindividual content.

6.03 8

Facility Comment: We do not agree with the answer key (prevent lockout)and feel it.is more correct to answer that the dieselwould fail to start.

01 324 states that to prevent an inadvertent lockout, astart signal should not be initiated within one minute i

of resetting an engine trip. This precaution implies thatdiesel generator lockout may occur. It will not occur ifa start signal occurs before the one minute time delay. ;

We feel this precaution is in error and have sent a '

procedure change request to our Procedure DevelopmentGroup.

The System Description for the Diesel Generator statesthat "to ensure there is not a failure to start, a startsignal should not be initiated within 60 seconds ofresetting a trip."

We feel this is the more correct answer based on reviewof the DAEC start circuitry and breaker control circuitry.

A short explanation of this circuitry follows:

A diesel generator trip will energize the SDR whichseals in and energizes Relay "5" which shuts downthe diesel generator fuel racks and prevents a restart.

Once the SDR is reset by clearing the " trip" condition i

and resetting PB4. The "5" relay is deenergized with !

a 60 second time delay before it drops out.

Until the "5" relay drops out, the diesel cannot bestarted because the air start solenoids will remaindeenergized. The only way we feel a lockout could occurwould be if the operator attempted to close the dieselgenerator output breaker without having the diesel runningand a failure of the Sync check relay. (Sync check - 25, i

prevents breaker closure if both sources are not inphase.)

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ATTACHMENT 9

Since this entails a procedure violation and equipmentfailure, we feel this to be unlikely.

We request the answer key be changed to read thefollowing.

The Diesel Generator will not start.

NRC Resolution: Agree with comment. Answer key will be changed toread as.follows, "The Diesel Generator will not start."

6.05

Facili ty . comment: .The lower limit to the Standby Liquid Control BoronInjection Rate is no longer applicable, and no longerin our Technical Specifications. The ATWS changes

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(10 CFR 50.62) required both pumps to start on S8LC ;

initiation via one. Attached is a copy of TechnicalSpecification bases which includes the lower limit.Our' System Description (C-4 SBLC) which was thereference for the exam question will be revised.

NRC Resolution: Agree with comment. The answer key will be changed toreflect the deletion of the lower limit. Full creditwill be given to a candidate that states the lower limitno longer exists.

" 6.07 8

Facility Comment: We believe the correct answer for 6.07 B is thatthe Recirc Drive Motor breaker will trip.

The Drive Motor breaker must be closed in order to startthe sequence. If the field breaker has not closed within15 seconds of the Drive Motor breaker closing, then theincomplete-sequence timer will trip the Drive Motorbreaker.

We request the answer key be changed to state that "TheRecirc Drive motor breaker will trip."

NRC Resolution: Agree with comment. The answer key will be changedto read as follows, "The recirc drive motor breaker |will trip."

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.6.08 A

Facility Comment: The valves listed in Question 6.08 A were.not correct~

in that-these valve numbers were for the Head SprayValves.

The answer key is also confusing for this question. |'

because two requirements are included'in one statement(2/3 core coverage and LOCA signal). As stated in System i

Description C-1, Page 37 and Figure 17 (see attached). ;

There are four (4) (not three) conditions that must besatisfied in order to open.the containment spray valvesafter a LOCA.

.iThese conditions are.

1. Drywe11' pressure greater than 2.psig and

2. Reactor vessel level is above -39 inches (2/3 corecoverage) and

3. LPCI initiation signal present and

4 .- Containment Spray Valve Control Switch to MANUAL

: We request the answer key be modified so that full creditis given for any three (3) of the above listed four (4)items.

We also recommend that M0 numbers not be used in future j

questions unless necessary, in order to avoid confusion.

NRC Resolution: Agree with comment. The question will be changed :requiring three out of four conditions. The answer !

key will be changed to include " Containment Spray ValveControl Switch in Manual." The examiners prefer toinclude valve numbers in case the candidate does not

!recognize the valve by name.

6.08 B

Facility Comment: As stated in System Description C-1, Page 37 and1

Figure 17, the Containment Spray Valve Control Keylockswitch bypasses the -2/3 core coverage and the LPCI

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initiation signal,'

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As stated, this design allows the operator to open the| containment spray valves 'following a LOCA if either:

1. Level is below -39 inches'

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'2. LPCI' initiation signal is not present.

We request the answer key be changed to accepteither of the conditions listed above.

NRC Resolution: Agree with comment. The answer' key will be changed-to state as follows, "It allows opening of containmentspray valves by bypassing the requirements for 2/3 corecoverage (-39 inches) or LPCI Initiation signal present."Either answer will be given full credit.

6.10 D

Facility Comment: This part of Question 6.10 is not defined in enoughdetail to ensure there is only one correct answer.

APRM.B upscale is insufficient because the APRM Upscalealarm is a rod block. The APRM Upscale Trip is-an RPStrip.

The operator could interpret the APRM upscale to beeither the rod block or the scram.

'It sh'ould be noted that upon checking the references usedfor this' exam question, inconsistencies in terminology forthe APRM upscale Trip and Alarm were found. Change formshave been promulgated to Material Development to correctthese deficiencies.

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We request the answer key be modified for Question 6.10 0to accept either " rod block" or "1/2 scram" as correctanswers.

NRC Resolution: Agree with comment. The answer key has been modifiedto accept either answer. The question will be reviewedfor necessary changes so that only one answer will beacceptable.

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6.12+

Facility Comment: OI 388 precaution No. 3 states that the batterycharger cannot supply emergency power by itselfand would trip under this condition.

The question does not state that emergency loads arebeing supplied by the 250 VDC system when the battery-is disconnected.

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If emergency loads are not being carried and the battery-is . disconnected, the charger would probably not trip.System Description G-5 Page 14 also states the chargercannot supply current under all load conditions, meaningthat the charger can supply loads under certain -conditions.

As per Technical Specifications Section 3.8.8.2.C HPCImust be considered inoperable and requirements of 3.5must be met. The question did not ask for a procedural '

response, therefore, we feel the candidates should not be'held responsible for mentioning Technical Specifications.

We request the answer key be modified and full credit,

be given for any of the following response:

1. HPCI inoperable or

2. Charger will carry the system as long as Emergencyloads are not started.

NRC Resolution: Agree in part with comment. The candidate was not askedthe status of the HPCI system. The candidates were notheld responsible for meeting DAEC Technical Specificationssince that was not the nature of the question. Therefore,the answer "HPCI inoperable" will not be accepted. Theanswer key will be changed to add "or the charger willcarry the system as long as Emergency loads are notstarted." Full credit will be given for this answer.

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!Facility Comment: We agree with the answer key, but we feel the bases forHCTL curve as stated in NEDC 30796 (see attached)_ statesthe same answers as Answer No. 2. We feel it is alsocorrect to state that the pressure or energy contained

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Iin the reactor is low enough so that a LOCA or SRVblowdown will still be adequately amdensed by waterin the torus.

We request that full credit be given if above answer i

is used for Answer No. 2. j

NRC Resolution: Agree in part with comment. The candidate need not have.the exact wording as the answer key to get full credit.Each candidate's response will be reviewed for itsindiridual content.

.7.02 *

Facility Comment: We feel th'at the question is a good question to ask onan oral or simulator exam, but is inappropriate to ask i

on a written exam for the following reasons:

Iowa Electric's accredited SR0 training program does*

not require the operator to memorize the E0P's. Theoperator must demonstrate the ability to use theE0P's at the simulator.

The question is a complex problem requiring the*

operator to enter several E0P procedures. We believea question of this nature would be appropriate for awritten exam only if accompanied by the E0P's.

ES402 states that the operator must have a complete*

understanding of immediate actions. We feel thequestion addresses those actions that are notimmediate actions that the operator would takewithout a procedure.

Recommend Question 7.02 be deleted because it is beyondthe scope of the SRO. If Question 7.02 is not deleted,then recommend the following changes,

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1. Allow credit in each section based upon thecandidate's assumptions and subsequent. actions.

2. The answer key for Part A should take into accountthat the initial conditions stated that BoronInjection is not required, but the answer requires {Boron Injection to be explained. This could be ;

confusing to the candidate.

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ATTACHMENT 14

3. The answer key for Part B does not mention that MARFPalso takes into account the minimum flow stagnationpower level (8%) for no natural circulation.Maintaining pressure constant ensures that the RPVis being properly flooded. (Reference NED0-30796Page 8-149.)

4. The answer to Part C should also include operationalconsiderations such as if Boron Injection is beingused, or the Rx is shutdown. Again due to the natureof the question (i.e., written vs oral) it isdifficult to assume that only some things arechanging.

5. The answer to Part D should also include a discussionof the " quality" content of the water, (i.e., Rxwater vs river water) and credit given accordingly.

NRC Resolution: Disagree with comment. This question does not requirememorization of the E0Ps. It simply describes particularplant conditions and corresponding actions taken in theE0Ps and then asks why these actions are taken. Since thecandidate is actually told what the E0PS require, the E0Psdo not need to accompany the question for it to be answered.It is not unreasonable to expect an SR0 to understsod why i

he is taking particular actions in an emergency procedure.10 CFR 55.43(b) prescribes emergency operating proceduresas a basis for questions on the written exam. In addition,

the question is supported with knowledge and ability ratingsthat are extremely high. This question is appropriate fora written exain in that its objective is not to see if the

' candidate has memorized the E0Ps, but instead to determineif he really understands them. Requiring an SRO to know thebasis of the emergency procedure is consistent with industrypractice and guidance provided to NRC examiners. If as thisfacility comment implies, the SR0s at DAEC do not understand jthe emergency procedures, then this would certainly cast idoubt on their ability to understand and control emergency ]conditions. Since the facility received a satisfactory jrequalification evaluation in December 1986, it is assumed |

| that SR0s at DEAC do understand emergency procedures and I| that this comment was inappropriate.

1. All assumptions indicated by the candidates willbe evaluated on a case-by-case basis. However, allassumptions needed to answer the question correctlywere given in the initial conditions.

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ATTACHMENT 15

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2. Although in this instance boron injection is notrequired, the procedure does address this systemwhether or not it is required at that point. Thisquestion specifically provides further clarificationthat boron infection must be addressed in the answerto receive full credit.

3. The answer given in the facility comment for whyRPV pressure is kept above MARFP is the same as thatgiven in the answer key, but stated a little morespecifically. The more specific answer given in the |

facility comment is not required for full credit, butwould certainly be considered an appropriate answer.

4. These operational considerations are given in theinitial conditions such as to arrive at the correctansvers.

5. The quality content of the water is not listed in thareferences on the answer key. This facility commentwas not accompanied by any further references tosubstantiate this. Therefore, the additional answergiven in the facility comment is not acceptable.

In summary, both the question and the answer areconsidered entirely appropriate and remain in theexam as is.

7.03 A

Facility Comment: The answer key references Page 25 of IP0I-2, but onlylists four conditions as stated at the top of the page.In actuality, the page lists other requirements such asDrywell Deinerted, Oxygen concentration greater than 19.5%by volume, and IP01-7 (Special Instructions). The questionimplies there are only four (4) conditions, but procedurallythere are many more conditions that must be met. Werequest that full credit be given for any four (4)conditions that are stated per IPOI-7.

NRC Resolution: Agree with comment. Full credit will be given for anyfour (4) conditions required prior to Drywell entry that '

are stated in IP01-7. The answer key is changed to includethe following, "S. Drywell is deinerted, 6. Oxygenconcentration is greater than 19.5% by volume, 7. Ensurerequirements of Plant Radiation Protection Manual arefollowed for Drywell/ Steam Tunnel Inspection. 8. Verifycontainment air purge in progress. 9. Verify at leastone CAD 0 analyzer recalibrates for high 0 . 10. Verify

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ATTACHMENT 16

that the TIP detectors are in their shields and the drivesdeenergized. 11. Have Health Physics perform necessarysurveys."

7.05 C

Facility Comment: Per EPIP 2.5, the OSS functions as the EmergencyCoordinator until relieved.

EPIP 1.1 also directs the OSS to make the plantnotifications per EPIP 1.2.

We believe that if the overall responsibilities of theOSS are evaluated using the entire Emergency Plan insteadof one procedure it is true that the OSS acts as theEmergency Coordinator until relieved.

Iowa Electric's SR0 candidates are trained to functionas the Emergency Coordinator until relieved. If an eventoccurred that was classified as an alert or higher andthe Emergency Coordinator has not relieved the OSS,then the OSS should maintain contact with the NRC.

We request full credit be given for a "true" answer inPart C and we also recommend this question be modifiedso there is only one correct answer.

hitC Resolution: Agree with comment. Since under varied circumstancesthe answer could be either True or False, this portionof the question has been deleted and the overall pointvalue of the question modified accordingly.

7.06

Facility Comment: The question asks for specific items as addressed in |only one part of the EPIP's. We believe that since the |candidates are trained on all phases of the EPIP's and log i

entries into the OSS logbook are done in accordance with lACP 1410.3, Operating Logs, that credit be given for ]

I additional items that could be part of any log entry jl made by an OSS when dealing with emergencies. This

would include additional items such as:

L 1. Time of log entry

2. Changes in plant operating status '

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ATTACHMENT 17

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3. Other entries. These might include, DeviationReport numbers, 10 CFR 50.72 or 50.73 reportsmace.

We request the answer key be modified to include otherlogged items during an emergency per ACP 1410.3.

NRC Resolution: Disagree with comment. The candidates were specificallyasked.about the log entries required upon declaring anemergency classification of an event. The log entriescalled out in ACP 1410.3 are entries made during eachshift. It is not stated that these entries are requiredto be logged during an emergency. The answer key willnot be changed.

7.08 8

Facility Comment: The answer key lists reasons why the minimum speed settingmust be correct, yet the question does not ask why theminimum speed setting is correct. The question is askingfor the consequence of improper minimum speed setting,namely that the pump would not start. If more ofan answer was desired, than an " explain why" phraseshould have been added to the question.

Given the wording of the question we request full creditbe given for Part B, by stating that the pump would notstart.

NRC Resolution: Agree with comment. The answer key will be changedto state that "the RWCU pump would not start."

7.08 C

Facility Comment: The answer key states that the pump will trip, but nomention is given for the actions that would possiblyoccur to the rest of the reactor water cleanup system(i.e., DEMIN BEDS going into HOLD). See attached.We request credit be given for answers pertainingto other parts of the system such as DEMIN BEDSgoing into HOLD.

NRC Resolution: Disagree with comment. The root cause of the reduced flowto the point where the Demin Beds go into hold is the pumphaving tripped (as stated in the answer key). If the

candidate states additional items such as stated in the

______ ._____________ ___ _ - -

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ATTACHMENT 18

r

comment, they will be accepted, but for full credit thecandidate will have to state that the pump. trips. The' answer key will not be changed.

7.09-

Facility Comment: We do not.see how candidate No. 3 can be acceptedeven though he exceeds 5(N-18).

_Even though 10 CFR 20.101 technically allowsexceeding 5(N-18), we do not advocate exceedingof this limit nor do we believe any other agencywouldadvocateexceeding5(N-18). '

- Both the National Council for Radiation Protection(NCRP) and the International Council for Radiation- '!Protection (ICRP) reconmend that 5(N-18) not beexceeded.

!

Duane Arnold's Radiation Protection Training-

advocates conservatism for personnel exposure.

We request that full credit be given for. rejectingcandidate No. 3 based on exceeding 5(N-18).

NRC. Resolution: Disagree with comment. You are correct in the fact that10 CFR-20.101 technically allows an individual to exceed5(N-18). More importantly, the individual is allowed to

,

legally exceed this in the particular question. The jdocument you referenced is not a legal document and i

can only recommend guidance. The-10 CFR is a binding I

document. Since no administrative limits are in placepreventing an individual from exceeding 5(N-18) and anindividual is legally able to receive up to 1.25 Rem /qtr.regardless of 5(N-18) the answer key will not be changed.

7.10

Ei Facility Conrnent: The question as written leaves off the part of tryingl' to first shutdown the reactor by the normal method.

This could be misleading to the candidate as he wouldbe also looking at the operational conditions that wouldnormally be followed prior to shutting down the reactor

|- protection systein. We believe credit should be givenfor answers that utilize those operating conditions.

t

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ATTACHMENT 19

We also request that full credit be given for stating thatRPS should be reset so that the CRD system can provideadequate cooling to the CRD's (see attached).

NRC Resolution: Disagree with comment. The question asked, "What is thereason for this," not "what should be done" as was implied !

should be correct answer. No evidence was providedindicating that in the shutdown conditions that normallywould exist when the RPS system is shutdown that CRDcooling is a concern. The only concern that is documentedis that listed in the answer key. The answer key will notbe changed.

7.11 A

Facilit.y Comment: We agree with your answer, but we also feel that creditshould be given for other operational concerns createdby a H/X low level.

* A low level could also result in cavitationof the RCIC pumps due to reduced NPSH.

RCIC Turbine Trip - Turbine trips at 15" Hg abs.*

suction pressure. >

We also feel credit should be given for stating theprecaution is based on draining the H/X dry since thethermal shock is due to RHR-SW flow through the tubesof a hot dry H/X.

We request the answer key be modified to give fullcredit for any of the following, j

1. Minimize thermal shock to H/X- 2. Prevent cavitation of RCIC pump i

3. Prevent RCIC Turbine trip |

4. Prevent draining H/X dry

NRC Resolution: Disagree with comment. The material that was referenceddoes not substantiate that low level in the heat exchangerwould directly cause a RCIC Turbine Trip. DAEC SystemDescription C-1 RHR Page 43 states the following. ;

"The RCIC pump suction is also supplied from theCondensate Storage Tanks so that if the pressurefrom the RHR heat exchanger drops below the Condensate j

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ATTACHMENT 1 20

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Storage Tank pressure, a check valve opens to supplywater from that. source so that the RCIC pump is notin danger of losing. suction pressure."

1

The. facility answers requested to be added to the answerkey are not correct. Prevent Draining the H/X dry wasnot accompanied by any'further references to substantiatethis would in fact happen. Therefore, the additional-answer given in. the facility comment is. not acceptable.

'The answer key will'not be changed.

7.11 B

Facility Comment: The caution in 0I 149 is not based on a loss of inventoryto the Torus. Step (2) of Section 5.3 has the minimum flowvalve closed and the breaker tagged open. Also, the caution r

directs the H/X. Bypass Valve be throttled open instead ofthe LPCI outboard throttle. valve. A note in Section 2.0specifically warns against using the outboard throttle-valve.

Failure to open the Bypass Valve within ten seconds will. result in the RHR pump operating at shutoff head. Thiswill result in inadequate minimum flow.

We request the answer key be modified and full credit.

be given for either of the following: {

Provide adequate minimum flow*,iPrevent operation at shutoff head*

NRC Resolution: Agree with comment. The answer key will be changed toread as follows, " Provide adequate minimum flow for the. )pump or prevent operation at shutoff head." ']

The examiner would like to note that the 10 referencedin the test was 10 149 Rev. O dated July 24, 1986. Thelicensee supplied reference was 10 149 Rev. 2 datedApril 30, 1987, to support this comment. The NRCquestion was correct from the information suppliedby the licensee.

7.13 A.I

Facility Comment: The question as written could be confusing because ofthe use of the word " basis." This word could implythe Technical Specifications bases and could cause the

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-ATTACHMENT: 21i

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candidate to' utilize ti,em'in developing-his answer. .|We believe credit should be.given as appropriate ^'

'(i.e.,use~" reason").!

We also request credit be given for other operational !

' concerns that are generic.for' pumps operating at shutoffhead such as:

1. Overheating of Pump2. : Seal Damage i

j!, ,- 3. Cavitation

NRC Resolution: Disagree with. comment. This. facility comment was jnot accompanied by any references to substantiate 1

it. Therefore, the additional. answers given in thefacility comment are not acceptable for full credit.

l

7.14'|

Facility Comment: The answer key referen:es E0?-6, but the question is |worded such.that other~means of shutting down the reactor jcan be.used, other than E0P-6.i We request credit be given '

to: reflect-other operatiot al means, of scramming thereactor to include the below listed and any other n ansidentified by the candidate. '

s .

,

11. Locally trip the' turbine (power above 30%) '

2. DeenergizeRPSMGSetsbYopening.breakerat '

1832 and 1842. s

3. Vent the scram air header.

NRC Resolution: Agree with comment. The answer key will be changed toinclude the following. "c, Locally trip turbine (power iabove 30%) at Turbine front standard on operating deck;. |d. Deenergize RPS MG Sets by opening breakers at 1832 and !

1842 located in the 1A3 and 1A4 switchgear room." Ventthe scram header was not included since it was already j,

| discussed in 7.14b of the answer key.2

' '

8.03

Facility Comment: The question is extremely long and multipart in nature. |ES-202-E.12 states that mulitpart questions should be jbroken down into logical sequential parts. As currentlywritten, we believe that the question is not clear in j

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4ATTACHNENT 22

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stating the requiremppts expected of the-:andidate.The-question containD both the long initial conditionssection and the actuaP two part requirement of thecandidate.

'We agree with the answer!kdy in part,'however, We believe ;

- that credit should be given for actions taken that would - n

check for the actual systems ~taken'out of service and the ' "

operability. requirements since TechnicalSpecifications 3.13C and 3.13E states that only certain. ' - -

'

deluge, sprinkler systems, and hose stations are requiredto be operable. The information provided in the questionis not complete, and would require the OSS to check on dP&IO exactly what systems were taken out of service.

i

NRC Resolution: Disagree with comment. The Region does not consider thisto be an example of a multipart question as stated in the ,

' comment. An example of a multipart question would be i

. Question 8.04 with two distinct points. This questionsimply listed a situation and then asked what action was

_

q required and how scon. Other similar questions, such as8.11, were not commented on in this context. The questionas stated says that a Technical Specification problem exists..

9 Therefore the candidate does not need to know which specificj4 portion of the deluge and sprinkler system or which hose 1

' station is inoperable since the required actions are the'

same and the'LC0 foR that system is entered as stated inthe answer. As far ab;what was requested of the candidate, i

it is clearly stated in the final retence of the paragraph. |

The answer key will not be changed.4

3

8.0hj4 it ,

Faciljty,, Comment: The question does not follow the Examiner Standards 202 '4

.L in the following ways:g .s

u

1. ES-202 2 12 states that multipart questions shou 16 ,

be broken down into logical sequential parts, t iJ3,

2. ES-202 E.16 states that "if a specific number of s .

responses are required, the question should clearly . , ,

4 state that expectation . . . ." :

"3. ES-202 E.20 states that diagrams or sketches should

be used as attachments to written examinations. Itw. further states that the use of these attachment <,'j's

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ATTACHMENT 23

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provide an effective and easily interpretable way i

for the candidate to demonstrate his knowledge ofthe topic / concept.

As written, the question could be understood by thecandidate as one question with three listed conditions ,

together and answered accordingly. The answer key, aswritten, assumes that credit should be given to the ,

candidate based upon his ability to correctly analyze |the situation using all three of the conditions together. -

Furthermore, since a core map was not provided as an;

attachment, credit should be given to the candidate for i

stating the requirements that would be followed if this '

operational situation were to arise.

Finally, the answer key for condition No. I states that}this situation would have no effect on plant operations.3

However, the two rods that are inoperable are in separate !

RSCS groups. (10-07 in Group A2 and 10-27 in Group B3), l

Since the original scenario has the candidate makingpreparations to start up the reactor, having these twocontrol rods inoperable and in separate RSCS groups would .

place a very large operation restraint upon the plant. I

Technical Specification 3.3.A.2.f.(2) clearly states thatall rods within a notch group containing an inoperable 4

control rod shall be positioned within one notch of theinoperable control rod whenever the rod sequence control

)system is required to operable. We believe that credit 4

should be given to the candidate for stating the |p0ssibility of this constraint, seeing as how a jcore map was not provided, and we do not require i

the candidates to memorize RSCS groups.

NRC Resolution: Partially agree with comment. This question, as written,is consistent with other Region III examinations. Eachquestion undergoes an independent QA review by a person ;

other than the author to ensure it meets with the Examiner |Standards. The number of responses depends on how the |candidate interprets DAEC Technical Specification (also see |response to Comment 8.03 and 8.08). The candidate should jbe familiar enough with a full core display / control rod

|positions without needing a diagram to assist him. As !

far as how credit will be given, each candidate will be |individually graded for his ability to assess the situation. i

The question was not intended to require the candidates !to have the RSCS groups memorized. The examiner will |review all assumptions made at arriving at his answer. >

The answer for the first condition given will be changed |to reflect the operational constraint imposed on the plant Ias noted in the comment, j

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ATTACHMENT 24 '

8.08'

Facility Comment: The question is stated, does not follow the ExaminerStandards. ES-202 E.16 states that,."If a specificnumber of responses are required, the question shouldclearly state that expectation so the candidate willknow when the answer is complete."

-The answer key for Question 8.08, list five overtimeguidelines that are violated, but there are seven totalviolations. We believe full credit should be given tothe candidate for stating the general guidelines thatare violated,.rather than being specific and listingthem individually.

NRC Resolution: Agree in part with ccmment. The question is not"open-ended" or " vague." The intent of this questionis to see how well the candidate can evaluate a givensituation and apply his' understanding / knowledge of theovertime guidelines. Therefore, the number of responsesare determined by his interpretation of AP 1410.1. Sincethe question by implication asked for all. violations,.thisin effect.is the same as asking "How many criteria havebeen violated." Credit will be given'for the candidatestating the general guidelines violated as well (the-specific answers in. parenthesis were for the gradersuse only and are not intended to be required). ;

8.09 B;

Facility Comment: The answer key for Question 8.09 B is directly derived ,

from Section 6.3.2 of ACP 1406.3, revision of Proceduresand Instructions. However, there are other places'inACP 1406.3 that describe situations that would utilizetemporary procedure revisions. In addition, Figure 2

'of ACP 1406.3, shows the temporary document change form,which contains a " temporary change information reviews"block that describes reasons for temporary changes. Webelieve full credit should be given for answers basedupon these situations.

NRC Resolution: Agree with comment. After a review of the referencematerial, the following list will be added to the answer

l' key. "5. When it's impractical to accomplish permanentrevision to approved procedure. 6. Editorial.7. Improvement. 8. New Procedure. 9. Inactivation .

or Reactivation. 10. Change of Safety Intent or |

Function. I

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, ATTACHMENT' 250

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8.11 I

Facility Comment: We agree with the answer key as written, however, we |''

believe that full credit should be given to the candidate..,;,

for describing the concerns about providing an isolablevolume (i.e., 2/3 core coverage), as described in theSystem Description A-2, Reacto'r Recirculation System, 1

when dealing with Jet Pump Operability.

NRC Resolutiom Agree with comment. Will also accept "providesan isolable volume capable of being flooded aftera recirculation line break (2/3 core coverage)"as alternative answer.

,>

8.12 Aj

Facility' Comment: The question is based upon a new Technical Specification ,

change that is currently having a letter of. interpretationwritten to clearly define the facilities stand on the issue.We believe that the question as written does not provide {enough information for the candidate to fully answer thequestion. The candidate must spend time in developing anassumption of the scheduled due date of the surveillance-to ensure the correctness of his answer.

We believe that credit should be given for answers'thatare correct when based upon the candidates assumptionsand utilizing Technical Specifications 1.0, DefinitionNo 26, Surveillance Frequency. Also, per ACP 1407.5, !

Surveillance Program, it is the surveillance performancecoordinator's responsibility in setting up.the due dateson the surveillance test procedures and not the OSS.

Using Definition No. 26, Surveillance Frequency,as stated in Technical Specifications the followinginformation could be used in developing the candidatesanswer.

Technical Specifications quarterly (92 days) i 25% =23 days prior to the scheduled due date, or 23 days jafter the scheduled due date. !

Combined time interval for any three consecutivesurveillance intervals shall noc exceed 3.25.92 days x 3.25 = 299 days. l

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p.}1[;i.O

' ATTACHMENT. 26

Assuming January 1,1987, is the earliest the 0SS couldrun a Schedule Surveillance, places the due date at 24-January 1987. Using.that due date the following applies.

RUN "A" 3 October 1986 (90 days prior to 1 January 1987)RUN "8" 1 January 1987 (Given)RUN "C" 16 April 1987 (Given)

Combined time. interval A, B, C = 197 days (.

RUN NO. 1 1 January 1987 (23 days prior to 24 January 1987due date)

RUN NO. 2 16 April 1987 (10 days prior to 26 April 1987 j

due date) ;

RUN NO. 3 19 August 1987 (Absolutely last possible date to i

RUN with 27 July 1986 due date) i

l

Combined time interval 1, 2, 3 = 230 days

NRC Resolution: Disagree with comment. It is obvious from this commentthat the facility does not understand the new Tech. Spec.regarding surveillance frequency. The facility proposed.answer of August 19, 1987, is.in violation of Tech. Specs. !

in two respects.- The maximum allowable extension cannot |'

exceed 25% of a surveillance interval. The time intervalbetween April 16, and August 19, 1987 is greater than 25%(or 115 days maximum). Therefore, the date of August 19, i

1987, is not correct. The combined interval between three ;

consecutive surveillance cannot exceed 3.25 of the |

specified: interval, 92 days in this case, or 299 days fora quarterly surveillance. The combined intervals for thesurveillance from October 3, 1986 to August 19, 1987 is321 days or 22 days longer than allowed by Tech. Specs. jTherefore, the date of August 19, 1987, is again not ;

correct. The facility is apparently keying in on dates 4

and due dates for surveillance rather than intervals asspecified in the Tech. Specs. This is obvious from theircalculation of 230 days for the three surveillance )conducted on January 1, April 16 and August 19, 1987 to i

show that they met the 3.25 requirement. This constitutesonly two intervals vice the three required by Tech. Specs.,but did comprise three dates. The answer key will not bechanged.

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U. 9. UUCLFAR REGULATGFY COMMISSIONRENINR R E t. C T O R OPEPATOR LICENSE EXAMINATION

F AC)! ]I Y : DUAM ARNOLD

REACTOR 1YPr : _DWR_.GE_4___________ _____. . . _

DATE ADMINISTERED + 0. 7 _/ 0 7_ _/. _1 0 _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _._ _ _

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EXAhTNER: H_ARE,._F_._A _ __ __ __.____ __ _ .

CANDIDATF.__ ________ _.__ __. ____ .

I n s _i rm_ C .T _J _n u e T o c A N ra f: ATF!. _ . .. _ _ _ _ _ _ _ _ _ . , _ _ . _ _

une Separate p a ra r for the -nruers. Write anwers on one side only.'

3tep je c;u e x t i c n s. h e e t on top of the ensoer theets. Point-i- for each..g ie .t i o n ar" i m.j ! c : l e d in parenthe n s f' t e r the o.uestion. The c, n c <. i n c

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d> r e .,v i r m r+ leent 70: in each c a t e a., o r v, :< r. d c final e t c e' e of at. .. i .;. .w

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Nr:C RULES AND CUTDELINES FOR LICENSE EXAMINATIONS-

:During the adkinar,tration of this exsnination the following rules apply:

1. Cheating on'the ewaniination n.eens an automatic denial of your applicationand cavid result in n. o r e severe penalties. -|

2.,'Restroom trips are to be lin,ited and only one candidate at.a time.mayleeve. . You must avoid all contacts with enyone outside the examinataanroom to woid even-the appearance .o r possibility of cheating.

13 . th e blaciJirk or dark penc'il 901'; to facilitste legible reproductions.

4 .- Print 'your name'in the blant provided on the cover sheet of thee;;aminaLion.

6

5. Fill in the date on the cover sheet of the exenination (if necessary).

!-6.. Use.only the peper provided for answers.

.7.- Print your nan,e in the upper right-hand corner of the first page of e g(n -section of the ensuer sheet.

'

C,- Conercutfively number each answer cheet, utite 'End of Cate. gory _' en'

appropriece, start each c e teeot y on e nee prae, write.oniv on en* J i r' oor the peper. ond ur Le "Last Page' on the Irst a n ::v e r sheet.

9 Ph u ur each sosuer t. n to cctegory tod nun ber . for cuamplee 1.4r 6,3.

' 10 . Osip (t least t h r o i- line, between ench ancuct.

, 11, 9epar :Le enroer sheets fror, pad and place finiched answer sheets frecdown on your deel or tcble. !

l

it. Us -hbreviations only if they cre commonly used in facility 111gE512LE.

13. The point value for each quection is indicated in parentheses cfte- thequestion and can be used as a evide for the depth of ensuer required-

Show 'l c a l c u l t '. i o n t . c. e b h n d c - or resunplioni used to obtcin en Incuer.i-

*. O rp g t F. p n a l ( e f } } ,0 0 ' , e la u;ielh>1 1ridi(e. led ife t h s,.; quention o r' not.

15 Psrijal cred.L- niay be given. Theref or e. ANSLER ALL P/RTP OF THED.rCTION AND FC NOT LEA'E WY ANSWFP DLAM.

16. If p a r t e. of 'he e eninction ere not ej =r as to intent., ask quv.t;on' of.

the o $ s. in n e i _i ! ] ,> 4

174 Y Of f th u % i 01 j f- D ie i I. f' I 6 ' o f. n I ) tIID (? O V e f % Isee$ t |ll. b ind1Cateb t'3 E k '

e not recoaved or bear- given c,sistmae irwork it you. out vid you hir b n;-- l e ! : n g ''o n P o lim t i or. H nm L 'm.: dont efter the examin; on hc: i

h h e r. e n ly F l 3 i I (? ij ,

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as, When you complet e your examination, you shsil:

a, A Aerable.your examination es follows:

(1) E n a n, questions or, top.

(2. Eacn rida - figure - t.t b l e s , etc.

'7) Antur psges including figures which are par t of the cnsurr.

!> , Turn in your copy of the examination cod ell pages used to answerth. e;eminction questions.

-c l ui n in all serap paper t= n d the balence of the paper ths+ you dit'not use for snitJering the questions,

d. Lenve the e m m :; n e t i o n creo. as defined by the e n a n. i n e r . If efter |

1eaving, you tre found in thir, ere- while the entmination ic s: t i l li T. pr090e55 YOU! liCen%C (b E y be. den $ed Or r9VOhed.

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6_ _. _ _ T H R .O R. Y _. O F _ _N U C L F _A _'i P O W E R_ _ P.. L_ _A N_ _T _ O P E R A. T T 0_ tJ _,_ F L U I_ D_ S_.,A_ N_ D_ PAGE 2__. ._ ._ _ _ . _ . ____. _ __.

T H_ _F P. M O D_ Y N _A r.i. T C_ S.._ ._ __ .

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OUEST3ON G.01 (1.00's

Uhi ch on*> of the following s t. a t e rn e n t s in true r og a r di rig i ntrinsic neiit t oncourcen in e shutdowr, recrtor?

c. Practice 11y 11 tha noorce neutrons f r o rn spontaneous fiscionc a ra e f r o r., U-235.

u. The alphr-ne utr on 'ource c oie s iton the a l p h r, d e c :n y of U-238, !

U-239, snd Flutonium which interact with 0-10 in the moderzter toyaeld neon ond i neutron.

c. The n ,; o r corsentt9 tion of source neutrons comes from spontaneousfission of U-238.

d. The phot o- inutr on tout ce is lec,s significant at BOL than EUL.

DUESTIori D,02 (2.00i

TP'ir or FALSE

ror a constent reactor pe: iod, il taken the RAME AMOUNT OF llME T D CHMMreactor power f r ort li to t' et it doer to chmnge it from 10'4 to 505 *

FXPL All' YOUP At!SWE R F ULi.Y . MHOW THE CALCULA1 TON YOU L' 0 U L D U S 'i inV F P1 r 's YOUR M'9WEP.

D U U' T I D N 5,03 (1.00)

Which one of .he falloutng s t a t e ni e n t s, it NOT trur iesarding the LHUP()inver heet g r n .f r e t i o n r,te) thetu-] l i n. I t ?.

13.l; LL'ft for both BnB and P0xBG f- |.Thn _MG' rH ,1 g n l a tn i t =.

7700b. The 1 i ro i i is beren on maintaining peak c l w'i is t e m p r r : L u r e =

deg er 7

C, II e LHGP spo i. I' : t F i ~t ori 'ir e that i'e L. H O P .i I i a n ',> 1 c t' i jet ',

thf de ' g r- V'lun even if fue3 pel 3 i 1 |nnti facc! ion 1L p o ':: 4.. ' ' ] R t P i

.r.ejedy ii o s i l i.- T- p ., t.i l t in f :iO ] e16d c r i c. I i i . ,,, i' i.'d. 'f 't. ? ) 4 1.1 p i t i. c

| tr : .ch tr or ,

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---- NUC.IEAP.PnU.FR- . .- - - l Mi t OPFRATION. FLU 1DG- MJD PAGE 3ftF --.- . P ..------ YT H F O T:%. ------------------------

THERnnoyNon)en

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OUES110H "'i . 0 0 (1.00)

The reacter tript fron, fn11 power, estnlibriun. xenon conditions. Four ( c 't

hour. Jcter the reactor it brought er itical and power level is n, c i n i a ) r a d

on rene.> D of th. IRM9 for ;evorc] hours. Which of the rollowings t a t e m e n t s, it COPfECT concernine contro) rod motion during this period?

L. Pcris will h: se to ti e wit heir a un due to venon build-i..

b. Rods will have T. o b e rapidly inser ted ';i n c e the critical r-nc t orwi;l cause a high rata of eenan burnout.

c. Pnds vill have to be Inserted since Menon wall closely follou'. ta, n o r nia l decay rate. .

c' . R o W., ul)1 appr oxin.atel y r emai n as ic as the xenon establisheritt equilibr ion value for this power 3evel.

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40EPTTOM .05 (*.no)'

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The ' c: -'or is critaccl at 106 eps WI!ICH of t, h e following best,

deter iber the behavio- of neutron power following a p r o n.p t intertion ofnu p tiv- ie ctivity. (Assume that not enough negative resetivity is anded

| to shuldm: the reactor)|

Noutron powee tirops imn:ediately to ' bets" (delayed neutron fraction) ;

times the neutron pouer prior to the pr ompt insertion of negative '

reat iivity.

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h. Neut.ron ;s o u e r decreasec linestly with time siter the initan] pint.ptH ri r o f .

c, A f *. t r lhe initial pron pt drop. netett on poWCr deC r E RSU 4 On a C o n s.t E n 'negcl1Ve perin#I the it.6 g n i t u d e of the period determined by the c o. n u n icr neptin r ei n c t i v ; t y inserted. ,

t

| - d. Cercose only delpyed neutrons ar e left immed]ately Efter a negr ti ureactivity .inwttion, neutron powor decreases on an 80-second p o:r i o d1 e g i: r d 3 e c. ta of tho s1:e of the noe. jve reactivit insertion.

( 'J 3 x:.w 's CATICD?Y O '.i C 0 r1 T I N' t r l+ ON HFXT P'iGF *ttuti

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E _. _ _ T H_ E_ _n R Y _ O F _ _N U_ C I F A R _ P O_ U F_ R _ P t_ A N T _ O_ _P F R_ _A T I. O N .,. _ F L. U_ T_ D_ f_4_,AND PAGE a |_ __ . _ .____ _ _ . _ ___ _ _. . _. ___

1 H. F R_ _M O .D..Yr.1 6 _M T C_ P. . _ - . . _ _ _,

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QUESTION 5.06 (3.50)

The Ovene ArnoJd containment atmospheres are inerted with nitrogen tolimit the post LOCA oxygen content,

e. What is the princi Pal source o f' oxygen in containment follouins aLOCA9

ti , Phet ie the pri_ncipal source of hydrogen i rl conLctnment followingLOCA?

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c. What are the m a n i nc u m permissible concentrations ( 1 1 ni i t of f l a m mi; b l e i

regioni of hydrogen and oxygen (in volume percent) in containmerefollowing a LOCA9

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OUESTION D.07 (2.50) i

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Assume that t h e- eactor i t, being started up from Cold Shutdown and rtd,

drop aceident occurr early in the stattup. Of the void, doppler, rnd |t e n p e r a t t.' r e coefficients, uhich vill act first, second, and third tolimit the irpid power rise? EXPLAIN YOUP ANSWER.

QUESTION 5.00 (2.00) 2i

The reactivity worth of a s i n g:l e control rod will (For e :h !________.s t a t e rn e n t below, indiccte INCREASE or DECREASE.) f

a. If the voad content around the rod INCREASES.,_______

b< If the moder etor temper nture DECREACES._ _ _ , _ _

_____ _r, If cn 3 r: j a c e n t contr ol rod is WITHDRAWN 4 ;

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,__f ___

d. If xe-135 concenttstion :>round the rod DECRE/MF;.

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DilESTION 5.V (: . io ) ]"

H O 'd dr+ * o r i .? i conrr n Lr - ti en afI'FCI p 'r> r i p h e r a 3 rod Warth following : <;r-

f t on hi h poemr and WHY don thi occur os

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|(***t3 AT'~CORY % CnNTINUED O! N C ):T PAGE *****?| i

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M_ _. _ _1_ I_t _t r: p y_ _ _ _ .n. F _' N ll_C L. C_' A R. _ P O _W E R_ _ P L A.N.. T_ _ O_ _P E_ .P A T_ T O_ N_ _,_ F_ L_0_3_ D ci _. _ A_ N D_ PAGE.~ S

TH_r_-P..M0_pv_N_A__*1_C8_

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JUES73 0R 5.10 (1.50)

- Suppose 'Beff over core life decreases from 0.0072 to 0.0055. With:equc1'-insertiont- of 0.001 dK/K of, positive rcettivity

.n. Pilchlate the cbange in reactor period over core 'lifb. (1.0)

'b. ' 'W h a t -i s the cause for this change.in Deff? '(0.5)~

hlJEST10N 5 11- (1.50)

a. Explairi how barrier fuel di f f ers f ron,' the pr evious types of fuel'

loedvd'into.the core. (.75)

Lv.- How uil] thist affect of. change power operation.at your'fecility with !''

.s furj core lorded wi th: tvr r i er fue17 (.75)i||

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O t.!p B T 10 N 5 . M' ''(2.50) H

'Re9c7 d.i ng MCPR (Mininam Cnitical Power Retio);l

a., What PHENOMENON 00llLD.snist in a fuel bundle if it were operat+dht an MCPR LES5 THAN ONE (<1 0) and WHAT is the concern if thisphennwr on' uas to occur? :( 1 . 0 )

b ., . W h y. nn.i n t t h e T e c h n i c a l Specification MCPR lin.it'anclude a M facter ,

when' core #10w i, LESR THAN RATED? (1.0) j:|

.e. HOW d o r. CP.TTIC POWEP -chenge (INCREASES, DECPEASES, OR REMAT;K7HE GAME.) u52n ici subcoeli ng inct ear ei (core inlet water getrcDOlerl' sO.5

Dtl5 N T) OM 5'.15 f1.00)

r. &nd < B '.; pttg. J1 it mbennled or siip m h' i t . c: j"

.A # 1 m i c' La at 400 degreenFrsd b y . h 0 0 0Phy'dOgrPD 7

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~ THEORY O .t Hitrt F ARL,C. -------------------- -- LUIDS.---------AND PAGE 6OPERATION, F----..------ r-------- POWER Pt. ANT

.ldESU991dfl.01EUl

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QUFSTION S.14 (1.50)

-' The att6ched F:gure 2 shoun a T-S di ag r an, for 6 stean. cycle.

;; 3. Whst phenomenon is taking place between points 1 and 2?

b. How does.'this procetas benefii plant operetion'

.e. What i <s. the divedvsnteae a.tocitted with this process?

.

00ESTIDh- 5.1D (3,00)

a , .- What'is " shut-off head' for a pump and why is it undesirable for 6. pomp to run in this condition? (2.0)

b. How doen the'RHR system protect its pumps from operating at n' shut-off head' condition? '(1.0)

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(*Wo* Ds0 OF C/4TECDFY 05 A u t" '

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& __5LOUI.li!2IE00_DESI00:_GOUIBOL1_800_IUSIEUdEUI61 IOU ' PACE- 7 !

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QUESi10ff 6.01; (2.00) i

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List FOUR ~ (4)' rod biceks anot,i ated with ref ueling equipnient.. (2.0).

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.00ESTION 6 02 (4'.00Y

Acwrm the f e e. d w e t. e r '. l e v e l control systr+ is being operated in.3-element

e n n't r o ] using. reactor level detector channel 'A'. Reactor. power it.Et.EM r4,t+sdy state. T;or each of the instrument or control signal failureslisted below, state how reactor. level. wil] initially' respond (increcse,.

decreace, or v e nic i n constant) and briefly explain why, in tarnis of what it !

.heppening in the L evel Control Systen. .and ' Feedwater Systen. . immedicielyfollowing the fcilure. j

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fiOTE' A block disgram of'the feedwater level control svstem is attrehed.. ,

(figure 21 |.

a.- -Channel 'A' - r eactor' flevel detector signal fails low.

b. I ocn of signal to *P' feedwater control valve-M/A tran:fer stction.I

c.. "E" foortwater ] ins flow cignal fnils high..

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OUFSTION 6.03 (2.00)

The follauing question: concern the starting of the Emergency Diesel :|Generators. j

a. Explain the concerns on why a diesel generator should not be runi u n l o a d e rt . (1.0)

b. 1he r e s.c t or operator just reset c gener ator trip. If an a Lienptwee nade to restsrt the diesel before the ono n,inute tine lap::e. ;

whet would he the strtuc of the d i e s e l '? (1.0)|

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(**rr* ColEGORY 06 C 0 t! T I t W E D O!! t! EXT PAGr rwtrr3. _ . _- -

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6: _ _ E L 69 I _ S I S1E d 9_ D E S I O h _009 I S O L .t _680_ I t! E I E u d E U I 61100 PAGE B

QUESTTON' 6.04 (2 50)

e, Driefly enpinin WHY it is i n.p e r t a nt to closely monitor ~RWCU s'/ sten.f3ourste/tepiperature when operating in-the blowdown mode.~(NegiecL

!. of f eet on vessel level.) ..(1 0)|

t.<. State t h e. purpose of the RWCU Dlowdown mode.end state when this. n. e G e ' i t ' u s e d . (0.5)

c, Fo t s t. e . t h e T 'r' O L ( 2 ) datometic. closure signals for RWCU CV 2729(;;

.

-ithe Clean Up.-Drain Header Contral Uslve)-while operating in theblowdown mode add explain the bssis.of each. (1.0)

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20UEDTION 6.05~ (2.00) ;

L The Staridliy Liqui d Contr ol System (SDLC) injects sodium pentaborateL solo' tion into the reactor coo 1Ent. The punip discharge was desisned to

l i n. i t the ba r on_ i n j ec t i on '. r ate . Why (i. err whet is the basis) are-there lin.itt at.which the solutien mu:,.t be injiated-(both upper end lowerlimite.cnost be discussed for fu]] credit)? (2.0)

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' 6 __EL6EI DYSIEtjE_QEDIGU2 COMIS961_6UD_IUEIBUt!EU161190 PAGE 9

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QUES 110rl 6.06 (2.00)

The followins relant c o n d i t i o r.s eulst:

= 3 psid IJet Pumps 1 - 53 Differential Preawt e ' Meter)

o - 16 Differential Pressur e (Meter)= 15 pnidJet Pumpt

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Pecirt Syctem A On]p In Seivite (Annunciator) Off=

Ia. Th; TOTAL CORE FLOW Recotder would calculate enre flow by which

of the followind methods'; (1 0) ;

(;) Loop A Jet Punip Flow + Loop B Jet P i i n. p Flow j'I

.

(2) Loop A Jet Pump Flou - Loop B Jet Piimp Flow

(3) Loop E Jet P u m :.. Flov Only

,' 'd) Loop A Jet Pump flow Onlyi

b. After 5 r,rinutes, the operrtor o p e n ts the Dischst se W1ve of Recirc

| Dump D to maintain th+ E: Loop temperature. The T01AL CORE FLOWi Retorder would ce;culete core f1ow by which one of the fo3louine

wethodt? (1.01 ;

(1) Loop A Jet Pump F]ov + Loop D Jet Purap F low|

| (2) Loop A Jet Pump Flow - Loop D Jet Pump Flow !!

(3) Loop D Jet P u r,. p F l o w Onlyi

f4) Lcop A Jet Piine Flow Onlyi

O D E b l $.O r! 6.07 (1.50)

a. Wh:t wil) cause RECIPC PYSTEM A ( D '> Sl ARluP SEQUENCE IUC0tU' .f TE.

v. n o u n r i s t o r w h t- n etsiting E recircu]ction pump? (1 01

'b . Ul< a l " t L ori OLCur! 'I 'n InZOmp)Ote start G e qu e ric ** 15 Ci c t e c t e ri .. ,

(0,ns

t

(wwwn CATECDPY 06 Corn ItT' D ON NFMT PrGi r m s)t- ,

r___ _ _ . _ . _ _ _ _ _ . . . _ _ - - _ _ _ _ . _ . - - - - - --- - .__ -.

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f., PLANT SYST E MR DESIGN. C0fJTR01. . AND INSTPUMFNTATTON PM;E 10 ,

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(1.50) actc/LAOUEDTION 6.08 e\

7'c. List Mm THREE.(3)0 conditions that n,u s t be met in order t'o open

the, Conteinnient Spray Uc1ves (MO : '' ' C ,-1H+) after a LOCA. ( 1. 0 ) . jv

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h. . . What is the purpose'of the 'Centainn.ent Spriy Vrlve Control Reylock :

Switch"? (0.5)

9UEElION 6.0? (1,00),

The main turbine is at 1800 r p ra in preparation for synchronizing the ncingenerator to the grid. -|

What will heppen if the "all valves closed' pushbutton is depressed?(Choose the correct answer from the following.)

Nothing.will happen since the synchronous speed select signal is- j:.'sealed in.

b. The turbine control valves and mein stop valves vill close, but theintercept VElves will t e ni c a n open.

c. A]1 of the control valves (TCVs and IVs) and u.ain stop valve.; (h0Vs)uil) e]ote.

d. T h r- contrel valves (TCVs and IVs) will close, but the main stop !

volves will ren sin open. ii

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lGUE0 TION 6 10 (2.50) '

For EACP of the follouing conditions, state whether a scran, half-scrcm,rod block, or no action it generated. -For c o n d i t i o n s, thet p r oduc e nior e

than one n e t :i o n . 5 !.a t a the mote severe action (i.e. half-scram is st r i e ;

sever e ther, a red block). Consider logic only.

o. t ot of one RPS MG set

b. Turbine t.t i p et 20% pouer

c. thin stean lines D and D 1solate, Mode suitch in RUN

d. APRM B ups. calc Mode % itch in R,UN

)e. S c r a ni discharge volume level is at 60 g a l '. e n c , Mede r. witch in i

STARTUP I1

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( n t:0 CATECORY 06 C O N T IN L' E D O t! NEXT FACE antx) ji

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' 6 .1 1. (3.00) .QUESTION

I 'An automatic RCIC initiation,has occurred. Subsequently, RCIC-injectionwas aulcrastical terminated'due to high reactor water level.

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e.' What con:pon nt in the RCIC. sys t,em f unctioned as a. result of the 1Lsysten. logic'to autonistically terminste the injection? (0,5)

b.' Assumins no operator action. how will RCIC respond to a-subsequentcontinuously decrec;s.ing water level? (1.0)

cc -If a.RCIC 'Turbfne Test.' had been in progress wheri the initial

L seotomal.ic initiation pignal had been received,-how would thesystem have - responded? (1.0)

d . If, following the initietione the RCIC .tur bine had tripped on 'I

overspeed. (125% of rated). could RCIC injection be restartedfron, the Control Roon? EXPLAIN.- (0 5)

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QUE51 TOM 6 12 (1 00).

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W h o.l- w i l l happen to the 250 V battery system if the 200 volt b a t t e r ', -i sdisconnected and only the charger is sup,tlying bus voltage?

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r i _ _t E D G E D U B fi S _ : _ U D S t! 6 L t. 6000 B b 66 : _ E t! E E E E U C 1_600 PAGE 12 lS69106901G66_G9UIS96

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QUESTION 7.01 (1.00)'

'Enplein why,.froni the attached Heat Ccpacity Temperature Limit (llCTL)Curve (figure 31' fro'm EOP-2, Primary Containment Control, the shaded etee !

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does not include' values.less thcn 135 psis. -(TWO reasons required) ( 1. 0 ) -.

oOUESTION 7k07 '(3.b0)-'

A transientDhas.oecurred w|ith 'a resulting reactor s c r a n, . Howevery- several j

rods-tencin stuck out-beyond posiLion 02. (Doron irijection 'is not !

: required.) At the same tinie,.al] Reactor Pressure. Vessel (RPV). water1ebel-indication'is lost and thus RC/F 'RPV Flooding" (Contingency 461 is

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; entered.a RC/P-0, ' Enier genc y Depr e ssur iza tion' (Contingency 42) .is be:ng

|. -performed concurrently,i

: a '. 'Euplain why, 'under these circumstances, the flooding procedure firstrequ2res.thet all injection into the RPV be. terminated and preventediscept .that :from Doron ;1njection and CRD. (Full exp.lanation require $rees:oij uhy injection termineted and why Boron Injection and CRDJem eaceptions.) (3.0)

.

' b' . 'Fuplein why, efter injection is fin; cortr.enced under these; circumstances, the floodin>; procer equires that RPV pressurep 'be'ncintained e bt v e the Minin um native RPV Flooding PressureL (MARFP) but as low as practical. Anust explain both for full|' tredit.) (1.0) Il. [

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c. Euplain what a suddenly decreasing RPV pressure would indicate i'

following comnientement of injection'and establishnient of theMARFP, (0,5)

d. E::pl ai n why the prefer red systems fo* injection i r, this P r o c e d u r -- ute ;uCondenuste/Feedwater, RHR, and CPD. (TWO renons required.) (1.0) |

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'90EDTION 7.03 (P.SO)I

c' I P 01 - 74 n'm tup, requires that :e n .nspection of the drywell :,c sten },

tunnel be per f or med.- List the FOUR (4) conditions that must be netpi ior t r. drywe]] entt y. ('24 01

4

b, I' an emergency entry beyond these restrictions is required, who nu-'i

j, eppt'OVe Ihis type of enlty? (0,6)t-

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L __EEDGt:0UBEE __UOBb6L1_6SUDEb6L1_EUEEEEUGl_6UD PAGE 13

E6010LO91066_00dIBOL

Q UE S110 tJ 7.04 (1.50)

L13t the THREE (3) reasons why an oFerator would went cooldown rater, sbove100 deerees F/hr durins Emersency OperaLing Procedur e usege? (1.5)

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DUf.STION 7.05 ( 1.j50 ) |

I r' eccordance with EFIP 1.2, Notification, the following are theresponsibilities of t' h e Operctions Shift Supervisor (answer each as eitherTRilF or FALSE):

a, Advice the Security and Support Supervisor upon completion of all jte.:;uired notifications and appraise hini of problems encountered. '

b. Verify that the NRC is contacted within 1 hour of initialdoelaration.

-e. -4.-a.11..c v en tw e l - % i r i ad--we r n L F P T - tir-tagrirr , v er rf y--t ha.t.

Cont 3 Duct'" 'c O m m o r t i c h< t i o n" h?Vr bron cst ?bli 5he d-tei th the -NRC . ' f1

QUE"il.ON 7;06 /1.50)

.In necordenc e with EPIP 1.1, Determination of the Emergency Action Level,what THREE (0) i t e n, s are required to be logged in the Shift Supervisor'sLo3 upon declar ing the emergency classifiestion of an eventr {

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l' 'GUELTION 7.07 (1.50)

luo e6119 of the 250 volt DC batter y sis ta, are found to have e fin ~svolt gie 2 e xt than ihe required 2.13 volts. Ones this rffeet theoverisbi1ity of this mysten, and other plant synteme? Enplnin your answer.

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(nvra CATFGORY 07 CONTINtG NN NTYT PACE * * *u ) i

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7.00 (2.50F-00ESTION.

LWith. respect to Opereting Instruction No. 261, Resctor Water Cleanup |S y t, t e nr ;

.a' State .the raininoan'sp eed at : which the RWCU pump speed.

.euntro)lers shoold be set during pump startuP. (0.51

b. Wh'at would heppen if.they'were set at a lower setting? (1.0)'

c. What'would happen'if the RWCU pump is not secured prior to- q

transferring between local and r emote operations? (1.0)

QUESTION 7.09 (1.50)-

A.co.ndition arises that requires the entry of an operator into a HIGH-

RADIATION AREA. The operator will receive an estimated whole body dose.of50 mren.c You.have tho following data svailcble about the three (3)candidates for~the-job:

Candidate 1 2 3'Age 2- 30 24Exposure:

Wee! 15 mrem 35 meen 5-rtiremDucrter 2954 m r e n. ?G7 n r e r., 16 ner e m j

Life 10000 m r e n. 45720 mrem 29995 mrer.,

Rem #rkr!NRC Forni 4 on File Y E. C YES NO, Authorized 5000 mrem /yr 1000 mrem /qtr 150 mrem / day

F,sch candidcte is techniccily competent and physically cepsble ofp e r f c, r m i r.g t h e t asl . Emer gency limitt do not apply and time conttreintsdo not permit authorinction f o r- an administrative exponore limit jnerease.

EXPLAIN the reasons l' o r ececpting or ocjecting each condidate.

|a

GUESTION 7.10 (1.00)

Oporeting Instruction No. 350, Peactor Protection-System, notes that in {the event that both RPS Dusse rw s t be shut down, a]1 errort shov:d be nd.to restore at l e a s t, one PPS Dos to oper st r on and recet the s c r a i- n,

80 p D F, b i b l e . Whet is the ietson for thle?I

( n y :n CATECDPY 07 CON 1: Nuth DN NLXT PAGF n tx v );

1

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~E1__C89CE998EE'_~_U98d6LI_bCUO80bk1_EUE89EUC1.6UD PAGE 15P_ A_ D I G_ l. n G_7_ C_ A_ ! _ C O tJ T R_ O_ L___ _ _ .

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OUESTI0tt 7.11 (2.001

With resti d to'the RHR Systen, and Opercting Instruction No. 1497 Reuidual| ' Hect Renion1 Systeni;

c .- DI 149 eautions the operator to slowly lower HX shell side waterlevel during initiating of the Steen, Condensing Mode. WHY?

b. DJ 149 cautions the operstor t, h a t the LPCI Dutboard Throttle velve

should be throttled open within 10 seconds after starting _en RHR p u nipfor t. h e S h u t d o w r's Cooling Mode. What is the concern if this is notdone?

.

QUESTION 7.12 (1.50)

The ECCS Opercting Instruction Procedures caution you NOT to secure OR i

override en ECCS Systen: initittion unless certain criteria are ni e t . Whatrt ? O iheLe e i' i i, e r i O ?

QU E F) 10 t! 7.13 (2.50)

With veetrd to Operating Instruction No. 264, Reactor RecirculationSysten.'

!

i

n. 01 264 cautions the operator to open the discharge va.!ve as a rm n t-

.possible after etcrting recire. punp. Whrt is the basis of this-

pt ecau ti on? (1.0)

h. 01 T6C a ] s- n caut.Jons the oper ator that the recirc. punip shoit: d not beopereted with the p u ru p dischstge valve closed, e ::c e p t when st cling

;hull |lte dOWh N ptim; . Other than your answer to psrt E.-lip of t

a b r: v e , wha * is the beuis for this precaution? FULLY e. plain your i

cn,yer, A c; ,q. e i ,yi e (tid ! tiig p '' e n t, [5 f ri R U fJ Mode and that the otherr .~ e t t e , p u u.p is runnin. n o t ni a l '1 y . (1.5)c

o t't P I n n c.1c (2.00)

Durins apietions at 100L ,suwer, en exp nsion pnd mubsequent tii e in tho jc o ri t r e '. r o o m less required immediate evacuction prior to any po:sibleO p e l C t 01- LC jpp. N A M E t w c, (g) D l t e r r. c f., e mcthodi to achieve a r e ts c t u it

seren ent DIVE their locations. (Panel tJ c. . not r+ouired) 'T.0)'i!

i

( * * :r a r E" >'| i.:. '.] F , E l i.:C. O N. Y 07 * 't * " t |

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h - _6 C U I U I SI B o II V E _ E B 90 E 0 !J E E h _ G 0001II O U h _ o u 0_ L I U II o II O U S PAGE 1.6

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OUEST10tf 0.01 (2.00)

F o r . +.h e following refueling occurrences,' choose the correct action.I

Recurrences

1. . Dr opped f ue 3 e s sen bly wit.hi n -- the rezctor vessel.

E' D anaged 'f uel assenibly with evidence of fission ges releece.

(buhliles)..

3.- ' Loss of Water' Level Situation. .

1

A.. Unexpected Suberitical Multiplication.

Actionc i

|

-a. Stoppsge of core component movement only.

1b. Evacuation of refueling floor, i

i

c. Evecuetion of refueling ricor and drywea.1.

d. Evaevetion of refueling floor, drywell, torus, and torus ares. r

l.1

!

I

GUESTION C'02 (1 50).

|TRUE or FALSE?|

a. A Juroper and Lifted Lead Clearance Form shall only be completed ptior .jto . r enioving Jumper or Lifted Lead Tags.

"

b.- For Lifted Lead r e nt o v a l , return of the Lifted Lead Tag is sufficient .iverification that they have been reconnected. I

c. Durin3 not m31 surveillance testing, Jumper end Relay Block ,

ins,tallation verification is not required; however, final Jumper and |

R e l e y R ?. o r-k r e m o v a l v e r i f i c:a t i o n by qualified personnel is r e gin i e d .

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(wrtrr CATEGORY 08 C0tMINUr0 DN t'E K1 PAGE rrrtr)_____ -_-___

,

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h ._ _ 6 D D I U l E I E 6 1 1 E _ E B O C E D U E E h _ C O U D I I I O U h _ 6 U O _ L I d I I 6 1 I O U D PAGE 17

outsT1oN a.03 (2 00)

1he reactor is at 100% power and the Fire Protection System Ring HesderFluth it in progreu when you take the shift is the Shift Engineer.

j Duririg your revine of the w o r t. In progrecs. you note that, per procedore.| 2 vi ' vet have been closed to allow flushing of the cociing tower looE. M

| the time t, h i s occutred, 2 other post indicating valves on the main heedetenre airerdy closed to allow installation of 2 eiew fare hydrants. Thisituation r ewl tod in isolaLing a section of the deluge, c., p r 1 rs 1 e r , hace.

e red f .i t " ru e. i n n g s t e n.t for the las.t five hour . F r o ta c Technice]

Opeetf' cal 1on sLandpotnt, thit ereates a problt+. For the abovet)tuntion. d e s c r i t, e dhat actions should have been taken et the time the 2

valvec were closed to iso] ate the cooling tower loop and in what timeframe (si per your technical spoeifications.

GUEE110N C.04 (2.00)

Concerning reactor coolant c h e ra i c t r y :

DAFC Technical Specificttione r e q u i. r e that the iodire c o n c e r.t r : t i c n,.

in the t v. s c t o r cool mit shall not exceed uCi/gm of doce equisalent''

'J - 131 far the 48 hours rollowing power transient, If this l j rn . t in

e<ceeded, what TWO (2) act:on a the Technical Specificationsiequire the operator io t al ei

b uhen in the shutdown or refueling node and with steaning rate: 1eret h r. r. 100,000 lbc /hr . conductivity shall rio t e :eeed 5 umho/cm a r. dchlor i<le not exceed 0.1 ppn, per the Technical Specifiestions. Witheterming r4Les greater thEn or e e;o a l to 100,000 } t, /hr, conductisil.ybhn31 not PAceed 10 umho/en, said chlorides not (mceed 0.5 ppm. Whyate the l i ra i ta. for conductivity sod chloride al] owed to p u ;- ., hen

.

I s t e s i. i n g ratee ere above 100,000 lbs/hr? !

00"9T10N 0.05 (1.50)

'T h e lechnical Opecificcilori ntato ih follow:n3 "The ten dieselg * f n e f' a l o r : Lh,li be operab]r prir4 't h e r e :ha]1 he m j t i ; p t i il of 10e000<

g 513.,o - er ri i o . e ' fool an th- die ..] t iie ] oil tent."..

I

umt a. uw Teenr w spec;c m : tion ru c c f o , thu mount?

( :41 ?" *4 7 r'AT[CDOY O f) C ''I N I I ['' : [ if+ n2' N[yl P A f' f 11WYWl

4. .-

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Si_ 6DdIf.! ISIS $112E_ES9GE9UBEE1_COUDIIIDUSt_6BR_LIdII61100g Pact is

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i

' QUESTION 8'.06 (2.50)

Yod ace making preparatiorfs to start up the reactor the reactor ;is ir;the Stertup. Mode. The f ollouiing cenditions ar e reported *

.

l

1. Control rods;10-07 and 1.0-27 have inoperable accumulators. i!

(2. The scram time,to rod position 46 from full out for control rodN-23 was 0.370 sec.; for control rod 26-19, the time was 0.372 sec.;-for contr ol . rod 22-19. the time was 0.371 sec.1 and for control rod22-23,<the time was 0.368 sec. |

J

i

3 '. Control rod 26-07 cannot be roved with control rod drive pressure. q\

In accordance with DAEC Technical Specifications, what actions must.be iItaken,in this situation and how does this effect plant operctions?

s

. NOTE: Use the attach'd sections of Tech Specs to answer this ques 11on'.eFULLY reference all applicable sections of Tech. Specs.that you useto develop your answer.

QUESTION C.07 (1.50)

While playind softb511 on Sunday afternoon, you severely sprain yourE n F. ] e . Crutches ar e needed to repor t to worl< on Monday as the ShiftSupervisof.

a. Can you ' legally assume the shift? (0.5) Why or Why not? (0,5)iI

b. Mutt a report be sent to the NRC? (0,5)

)

. Qllr.CTION 0,06 (2.00)

D.ue ,o vacations and r equir ed tr aining, you have been esked to unrF the+

in) lowing schedule neNt week. Review the schedule end identify theovertine guldelines o* DAEC Adminis!.rt+ive Procedure 1410.1, Shift

Di wanin s wn * Oper,. tion fnd Tur nove r , that ynn would be violeting.CN01F; Mi tiae e;cludo 9h.ift turnover t : n, e . ) Assune that the pl so' it

npc1eting at 100?. pouer, j

Sunday 0700 - 1900Mondq 0709 - 1800Tuesdsy 0700 - 2400Wednesdby 0700 - 1600Thuisday 0733 - 2000 '

Friday 0700 - 2000Saturday 0700 - 1900

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(rr m C A T E r:n n Y CO CONTINUED Oi' ITXT PACF m ir)_ _ _ _ _ _ _

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_M _. _ _ .A D M _I N 1 S .T R _A _T T _u F _ P R O_ _C _E _D U R E_ S _. _ C _O N_ D_ _T T I O _N G_ _,_ A_ _N D_ _ L_ I M I T A _T I_ O_ N. S__ PAGE 17_ ___ _ _ _ _ __ _ _ _ . _ _____

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OUES110N B.07 (2.50) |i

e. In accordance with DAEC Ado:inistrative-Procedure 1406.3, Revision of-Procedures and Iristructions, who shall cpprove'all temportry changera.(1,0)

b. Give THDEE (3) REASONS (not enamples) why a temporary procedure ;

revision would be issued. (1 5)'

GUESTION B.0 (4,00)

With .r egar d to DAEC Administrative Control P'rocedure 1410,5, TescutProcedure: ,

a. What is c " SAFETY SYSTEM?' (1.0)

b. What are the required actions if a necessery Hold Card is foundto be missing? (1.5)

L. la the event that the person whose name is on a Hold Card is notonsite and cannot be r esched, WHO can authorire a relearse of the4 a l ci '; E r d and WHM r e e,o i r e m e n t '. 't.u s t be n.et be f 'ai e gr ant in 3 the

relene? (1.5)

I

GL'EDTIOd 8.11 (1.50)

1 r c hn i c i:1 Specifications require that all jet punips mus t be opertble or be !

ir et least hoi shutdown within 12 hours. LIST two (2) chect- for(portbilitv of the jei p u n. p s and CIVE the reason WHY jet p u r. p o p e r , $ 1 ityi t- E centern. (1,5)

CIII Cl 3 OI C,37 (2,n

A Techn c11 Spcc.ftratior, Docr t ei 'y 9^ days) survy 11ance un< pr r f t ted4

on the L:ay, Pre _,1v e Cut e Injectior s y d e n. oci mmri , 1907, or,o'

to J cnuct y - 1907, was c c,.. p i e t #A ,, r 1 | 16, * "' C ? Tir u a / c . 1 a r. m pr:. ,,

r .i n e t y (o: hc before J; nuar y 3r 1 '' P 7 i

_rtvoly surveillancep': AT thr , si MONTM and DAY the nc "':

,

e sa r - lit perfarted ;n'

h, m,-! S e n; -s n qi m n c c of '' ,: i l i n .; tr 7erfarn m'r c ill ence '

t II( .: p e C 1 30d i 1 11 . 0 'l n t E5 T V 01 ''#

i f' Cs ' C i t.: l i d . ( a t.t C C lie d ,

lot u u m m :w n a oc n e ;

. x i s vrv rrn ett FND Or EKAM]NAT70p rrrx t rm ni nix ' ]

EQUATION SHEET

f d ma v a s/t Cycle efficiency o (Networkout)/(Energyin)

. w = mg s = Vot + 5 atg.

E = mc2,

KE = 5 mv2 a = (Vf - Vo)/t A = AN A = A e-Atg

|PE = mgh

Vf = Vo + at w = e/t A = in2/tg = 0.693/tg

W-6 tgeff a [(tg) (t )]b

[(tg) + (t )3 fb'1

AE = 931 Am y , j e-zx' *

Q = mCpat

6 = UAat I = lo ~" *e

Pwr = Wrah I = Io 10- M'

TVL = 1.3/p

10 ur(t) HVL = -0.693/psP = PoP = P et/To

SUR = 26.06/T SCR = S/(1 - Keff) f

CRx = S/(1 - Keffx) |

SUR = 26p/t* + ( e- p )T CR) (1 - Kef f j ) = CR (1 - keff2)2

T = (t*/p) + [(a - p) 'Ip] M = 1/(1 - Keff) = CR /CRo1

T = 1/(p 's) M = (1 - Keffo)/(1 - Keff1)

. T = (B - p)/(Ap) SDM = (1 - Keff)/Keff,

t* = 10-5 secondsp = (Keff-1)/Keff = aKeff/Keffi = 0.1 seconds-1

p = [(1 /(T Keff)] + [Seff/(1 + IT)) ,

'Ijdj = 1 d222

P = (rev)/(3 x 1010) lidt 2=1d222R/hr = (0.5 CE)/d (meters)z=N

R/hr = 6 CE/d2 (feet)Miscellaneous ConversionsWater Parameters1 curie = 3.7 x 1010dps

| 1 gal. = 8.345 lbm.| 1 gal. = 3.78 liters 1 kg = 2.21 lbm

!3 Btu /hr| 1 ft3 = 7.48 gali 1 hp = 2.54 x 10

1 mw = 3.41 x 106 Btu /hrDensity = 62.4 lbm/ft!

l' Density = 1 gm/cm3 1 in = 2.54 cm ;<

Heat of vaporization = 970 Btu /1bm *F = 9/5*C + 32Heat of fusion = 144 Btu /1bm *C = 5/9 (*F-32)1 Atm = 14.7 psi = 29.9 in. Hg. 1 BTU = 778 ft-1bf ;

1 ft H O = 0.433 Ibf/in22

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# NollW diagram S.,) for steam.

- - - - - - - - - - - - - - _ _ _ _ _ _ _ _ _ _

- - - - - _ _ _ _ _ - _ _ _ .

DAEC-1

- -

LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT |.

3.3 REACTIVITY CONTROL 4.3 REACTIVITY CONTROL

Applicability:Applicability:

Applies to the operational Applies to the surveillancestatus of the control rod requirements of the control rodsystem. system.

Objective: Objective:j

To assure the ability of the To verify the ability of thecontrol rod system to control control rod system to controlreactivity. reactivity.

Specification: Specification:

1 A. Reactivity Limitations A. Reactivity Limitations

1. Reactivity margin - core 1. Reactivity margin - core loading.

loadingSufficient control rods shall be

A sufficient number of control withdrawn following a refueling"rods shall be operable so that outage when core alterations werethe core could be made performed to demonstrate with a

subcritical in the most margin of 0.38 ak/k that the corereactive condition durina the can be made suberitical at any

time in the subsequent fuel cycleoperating cycle with the with the analytically determinedstrongest control rod fullywithdrawn and all.other strongest operable control rodoperable control rods fully fully withdrawn and all other

operable rods fully inserted.inserted,

2. Control Rod Exercise 2. Control Rod Exercise

Control rods which cannot be a. Each partially or fully withdrawna.moved with control rod drive operable control rod shril bepressure shall be considered exercised one notch at least onceinocerable. If a partially or each week when operating above

30% power. This test shall befully withdrawn control rod performed at least once per 24drive cannot be moved withdrive or scram pressure, the hours in the event power

reactor shall be brought to a operation is continuing above 30%shutdown condition within 48 power with two or more inoperablehours unless investigation control rods or in the eventdemonstrates that the cause of power operation is continuingthe failure is not due to a above 30% power with one fully orfailed control rod drive partially withdrawn rod whichmechanism collet housing. cannot be moved and for which

control rod drive mechanismdamage has not been ruled out.The surveillance need not becompleted within 24 hours if thenumber of inoperable rods hasbeen reduced to less than two andif it has been demonstrated that

' control rod drive mechanismcollet housina failure is not thecause of an immovable control rod.

,

Amendment No. 19 3.3 1 3/76

-__ -_ - _ _ - _ _ - _ _ _ _ _ _ _ _ _ _ - - _ _ _ _ _ . _

,7-

LIMITING CONDITION FOR OPERAT10N SURVEILLANCE REQUIREMENT-

b. The control rod directional b. A second licensed operator~

control valves for inoperable shall verify the confonnance tr.control rods shall be disanned Specification 3.3. A.2d before aelectrically and the control rod raay oe bypassed in the Rodrods shall,,be in such position Sequence Control System,that Specification 3.3. A.1 ismet.

c. Control rods with inoperable c. Once per week when the plant isaccumulators or those whose in operation, check status ofposition cannot be positively pressure and level alarms fordetermined shall be considered each CR0 accumulator,

inoperable,

d. Control rods with a f ailed d. Once per quarter verify that:" Full-in" or " Full-out" ]position swi.tch may be (1) the Scram Discharge Volune i

bypassed in the Rod Sequence (50V) vent and drain valvesControl System and considered close within 30 secondsoperable if the actual rod after receipt of a closeposition is known. These rods signal, and .

'

must be moved in sequence totheir correct positions (full- (2) after removal of the close .

in on insertion or full-out on signal, that the 50V ventand drain valves are open.wi thd rawal) , Once per month verify thatthe 50V vent and drainvalve position indicating i

lights located in thecontrol roan indicate thatthe valves are open,

e. Control rods with scram times e. Once per operating cycle verify j

greater than those pennitted that:

by Specification 3.3.C.3 are(1) the SOV vent and draininoperable, but if they can be

inserted with control rod valves close within 30drive pressure they need not seconds after receipt of abe disarmed electrically. signal for the control rods

-

to scram, and'

(2) open when the scram signalis reset,'

f. Inoperable control rods shallbe positioned such thatSpecification 3.3. A.1 is met.

(1

I05/87Aaendnent No. 143 3.3-2

l

. _ _ _ _ _ _ _. .)

DAEC-1

LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT*

.

In addition, whenever the| 1)reactor is in the startup or

run mode elo more than onecontrol rod in any 5 x 5 arraymay be irfoperable (at least 4operable control rod', mustseparate any 2 inoperableones). If this Specificationcannot be. met, the reactorshall not be started, or if at

|power, the reactor shall bebrought to a cold shutdowncondition within 24 hours.

2) All rods within a notch groupcontaining On inoperable rodwill be positioned within 1(one) notch of the inoperable

|rod whenever the Rod Sequence|Control System is required. .!

g. During reactor power operation ,

the number of inoperablecontrol rods shall not exceed-8. Specification 3.3.A.1 mustbe met at all times.

B. Control Rods B. Control Rods ;

1. Each control rod shall be 1. The coupling integrity shall becoupled to its drive and have verified for each withdrawn !

rod position. indication control rod as'follows:available for the " full in"and " full out" position or a. When a rod is withdrawn thecompletely inserted and the first time af ter each refuelinocontrol rod directional outage or after maintenance, ,

control valves disarmed observe discernible response of |

the nuclear instrumentation and |electrically. This i

requirement does not apply in rod position indication for the" full in" and " full out"the refuel condition when the

reactor is v.ented. Two position. However, for initialrods when response is not ,

control rod' drives may beremoved as long as discernible, subsequent !

exercising of these rods af terSpecification 3.3. A.1 is met. the reactor is above 30% powershall be performed to verify,

instrumentation response. {

b. When the rod is fully withdrawnthe first time after eachrefueling outage or after CR0maintenance, observe that thedrive does not go to theovertravel position.

03/76Amendment No. 19 3.3-3

\ _-_ - _____-_ -

(-__ _ - _ . _ _ _ . _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _

OAEC-1

LIMITINGCONDITIdNFOROPERATION SURVEILLANCE REQUIREMENT,

.

c. During each REFUELING OUTAGE |t

observe that any drive which*

; . has been uncoupled frain and' subsequently recoupled to its

control rod does not go to the*

overtravel position. !

,

| 2. The control rod' drive housing 2. The control rod drive housingsupport system shall be in support system shall be

i place during REACTOR POWER inspected af ter reassembly andOPERATION or when the reactor the results of the inspection

'

. coolant system is pressurized recorded.I above atmospheric pressure

with fuel in.the reactor '-

vessel, unless all controlrods are fully inserted andSpecification 3.3. A.1 is met.

3.a Whenever the reactor is in 3.a. Prior to the start of controlthe STARTUP,or RUN mode below rod withdrawal towards 1

30% RATED POWER, and the criticality and prior to, control rod movement is within attaining 30% RATED POWERthe group notch mode af ter during rod insertion at50% of the control rods have shutdown, the capability of the

the Rod Rod Sequence Control Systen tobeen withdrawn,l System (RSCS) properly fulfill its function

._Sequence Controshall be OPERABLE. If the shall be verified by the -

<'system is determined to be following check:

inoperable in accordance withchecks in Specification Group Notch - Test the six4.3.3.3, power may be comparator circuits. Coincreased above 30% RATED throu- each comparator n!P' ~R by increasing core flow. inhit initiate test, ify '|

erre j reset. Afterb. aver the reactor is in comp checks initia. test.

STARTUP or RUN modes and /e completion of cyclet aw 30% RATED POWER the indi . by illumination of

Rwa Worth-Minimizer (RWM) test alete light.shall be OPERABLE or a second 1

Reactor Operator shall verify b. Pric ] the start of controlthat the Reactor Operator at rod aithdrawal towards criti-the reactor console is cality and prior to attainingfollowing the control rod 30% RATED POWER during rodprogram, insertion at shutdown, the i

Icapability (of the Rod WorthMinimizer RWM) shall be 1c. If either Specifications

3.3.B.3.a or .b cannot be met, verified by the followingthe reactor shall not be checks:started, or jf the reactor isin the RUN ce STARTUP modes at 1) The correctness of the Reducedless than 30% RATED POWER. Notch Worth Procedure sequencecontrol rod moveraent shall not input to the RWM computer shallbe permitted, except by a be verified.scram. Limited control rod |

imovement is permitted for thepurpose of determining RSCS orRWM OPERABILITY and shall beverified by a 'second ReactorOperator.

| Amen'dment 142 3.3-4 05/87

.

- - - - _ . - _ _ _ _

DAEC-1'

' '

LIMIT!NG CON 0lT10N FOR OPERATf0N SURVEILLANCE REQUIREMENT.

J

2) The RWM computer on line-

diagnostic test shall be.

successfully performed..

3) Proper annunciation of theselection ' error of at least oneout-of-sequence control rod in )each fully-inserted group shall ]be verified. )

, .-

4) The _ rod block function of tneRWM shall be verified bywithdrawing the first rod as an jout-of-sequence control rod nomore than to the block point.

.

|

4. Control rods shall not be 4 Prior to control rod withdrawalwithdrawn .in STARTUP or ' in STARTUP or REFUEL modes,

REFUEL modes' unless at least verify that at least two Source . q

two Source Range Monitor Range Monitor Channels have an |,.

Channels have an observed observed count rate of at .least !

count rate equal to or greater three counts per second.than three counts per second.

-

5. During operation with Limiting 5. When a Limiting Control Rod~

j

i

Control Rod Patterns, either: Pattern exists, an Instrunent

Functional Test of the RBMa. Both RBM channels shall be shall be performed prior to

| OPERABLE, or withdrawal of the designatedrod (s).

b.- With one RBM channel inoper-able, control rod' withdrawal '|

Shall be blocked within 24| hours, unless OPERABILITY-is

restored within this time. period, or

;

c. With both RBM channels inoper-able, control rod withdrawal !

!

shall be blocked until| OPERABILITY of at least one

,

channel is restored.p

k

i

. .

'

Amendment 142 3.3-5 05/87 |

..

- _. ._. _ _

. . '|

L LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT.-

|

| C. Scram Insertion Times C. Scram Insertion Times |

'1. The average scram insertion 1. After each refueling outage alltime, base on the de- OPERABLE rods shall be scram '|

energization of the sera time tested from the fully

pilot va'Ive at time zero, of withdrawn position to the

| all OPERABLE control rods in drop-out of the reed switch ati

|

| the reactor power operation the rod position required byl condition shall be no greater Specification '3.3.C. The

nuclear system pressure shall |than: be above 950 psig (with |Average Scran saturation temperature) and the 1

Rod Insertion requirements of Specification {

Position Times (Sec) 3.3.B.3.a met. This testing !shall be completed prior to

l'46 O.35 exceeding 40% power. Below 30%'

38 0.937 power, only rods in those26 1.86 sequences (A12 and A34 or 812

and 8 4) which are fully06 3.41 3withdrawn in the region from -

2. The average scran insertion 100% rod density to 50% rod ,

times for the three fastest density shall be scram timecontrol rods of all groups of tested. During all scran timefour control rods in a 2 x 2 testing below 30% power, thearray shall be no greater Rod Worth Minimizer shall be

OPERABLE or a second licensed l'than: ''operator shall verify that the

Average Scram operator at the reactor consoleRod Insertion is following the control rod

Position Times (Sec) program.

46 0.3738 1.0126 1.9706 3.62

3. Maximun scran insertion timeto rod position 04 of any0PERABLE control rod shouldnot exceed 7.00 seconds.

.

|

|

|1

||

-

Anendment 141 3.3-6 03/87 ||

(

.

-

_.

,

d

D:__ISE0El_DE_UUCLEGB_E9EES_CLGUI_0EES6II90:_ELUID01_QU9 PAGE 2010560221U00103

ANSWERS - DUANE ARNOLD -07/07/15-HARE, E. A,

t

| .

)

'ANSHER '5.01 (1 00)|

d.

REFEREf4CEDAEC RXTH-SH-16, pg. 2-2292003M110 ...(KA*S)

,

ANSWER 5.02 (2 00)'

True.

= Po e (t/T)Usins the equstion Psolving for time results in the equation:

t-=T,< In(P/Po)Fron this it can be seen that cince S/1 yields the same value at 50/10,and since all other factors i r. th( egostion are equc]e the tinie is

o c3m l . (2.0)

REFEREllCEDAEC Foset.or lheory, Period E.quation, Pg. 2-292003K100 ...(MA'S)

ANSWER 5.03 (1.00)

b.

REFEREllCEDAEC Heat. 1 r aresi er 14, Miti 3cting Reactor Core D a n.a s e 344203009K107 ...(MA'S)

ANSWER S.0a (1.00)

a.

REFEREfICTDAEC RXTH-SH2;-t.???006K107 4 292006M103 ...(KA'S)

|

. _ _ - - _ _ - _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ -. . _ , - _ _ - _ _ - ._

i

!:

.

---------------~~-- PERATION,O -------- FLUID'in AND PACE 21Pl. ANT------------ - ilCl.FAR POWERTHFORY OF N81 .,

1 -----------

l' 1 H F R.t.1 0 D Y N A M'l C S----.-----.---

ANSWER? -- OtIANE ARNULD -87/07/15-HARE, E. A.,

|

|.

1

||

ANSWER U.05 (1.00) .j

| c.

REFERENCED AEC R):1 H-SH-19e r . pg . 2?92000K107 ...(KA'S)

.

ANSWER 5.06 (1.50).

a. Padiolytic decomposition of water. (0.5)

'b. hotfl (fuel claddin3) to uster r e T,e l i o n or Zr - Water reaction.(0.5)

c. 0 fgon - ';

Sydrogen - 47. (0.5)

REFERENCEOuane Arnold Mitigating Reactor Core Damage, pg. 6-5, 6-10, 6-46

220001A204 223001A205 227001M404 ...(KA'S)

ANSWEP 5.07 (2.50)

s. Doppler LO.333 is the f'i r s t to add nogstive reactivity. The increase1 in pouet 1.w e l causes a rise in fue! t e nip e r a t u r e and a corresponding

=dditico of riog t ti ve pn etivity due to doppler e f' f e c t E 0 . 5 "I ,

t. . Mcdelstor T e n.p e r a t u r e Coefficient [0.33] is ne;4t cs there is - tarm@] ey (fuel '; 1 rw constant) for the heat generated in the fuol pelletto recch the coolant in the channel and cause the t e n> p e r a t u r e itinr:r m e [0. Z .

.

c. Void Cneffi :ent EG.337 is last e 4; the c.ader c t or tempeistore hc > t. -

increase to the po3nt of natur mt ion befor e voids are f o c n.e d i r,;, pr ec intale e,u a n i i t y . (A1 o aerept if there are no v o .i d s e, c li

,

ii nt;riop' C0.53. |r

RFFEPrN[I"7, pyg, 4 and 5DA[[ ov', .. g y .*

:

29200W'.14 ...(KA'S)

.__ _ ._ _____________ - _ a

!!

l .

5 THrnRY OF N!! CLEAR P O L' E R PtANT nPERATTON. FLI)TDn, AND PAGE 22.------------------------------------------------------

1SEEdODit!0blCS

UlSWERS -- DUANE ARNOLD -07/07/15-HARE,'E. A. 4

;

1

ANSWER 5.08 (2.00)i

a. DECREASE j

b. DECREASE ;

c. INCREASE I

d. INCPEASE(4 0 0.5 pts each)

i,

REFERENCE i

DACC RXTH-SH-29, pg. 4, SH-27, pas. 4 and 5 ,

292005K104 ...(KA'S) |

!

ANSWER S.09 (1 50)

Peripheral rod worth will increase. (0.5) High Xe concentration in th_center of the core (highu:t power tm f o r e r.cr w.) will depress the t h e r ra a l

neutron rive to t h e, t region c :; u s .i n s t h e relative neutron flui: "t n the

3 er. thus incterce the reletive rod worth inperipher01 bundlet to be hi hperipheral rud . (1.0)

PE r E r& N CE -

DAEC. RXTH-SH-29, pg, 2292006K107 ...(KA'S)

Al'S W E R 5 10 (1.50)

62 seconds (0.33)e. BOL: t = F: - P - (.0072 - .001) a

-

I__--- ---_---------

o P (0.1) (0.001) l'

EOL; t (0.0055 - .001),

= X <;econd- .'O.331_ _ _ _ _ _ _ _ _ _ _ , , , , _ _

(0.11 (0.001i Ll5 I

CHANGE 62 37< '><C, s e c o n d c (0.30) ,

% t') ji

b. Evildup of f'u-TOO coupitc Lith the burnout of U-235 ccuses >-

detteGsr in t;m ef * ec i i cr ch 11 'j e d neutr on friction (Deff).(?.5)

| EFFPEt:r p

DAIC b'e m e t o r l heer y. SH-TO. p ; -. B292003U306 ...fMA'B'

..

_ - _ _ _ - _ _ _ - _ _ _ _ _

,

-______-_-

1

.

L __lSE0BX_9E_UUGLESB_E9BEB_ELQUI_0EEB611901_ELUIDS:_600 FAGE 2310560901060100

A N C U E P'8 -- DUANE ARNOLD -87/07/15-MARE E. A.

ANSWER 5,11 (1.50)

a. This design utilinen a layer of circoniun mettl bonded to the inner5. u ;. , s

,turface of the c3odding. -T-;il e m. iii.. 1L. ui . ,

' ' i ewh-4+e t w e r n the - ; 11u - : aJm . ; . [() . 7 5tM --

.% .. , _

b. W ) t h e- full core load of barrier fuel, it is expected ths.t ope r s.t i o-La tsrgeted espor.vres without pellel-clad interaction failures oroperrtionol con: tr eint s on losd swings (preconditioning) can bed C h 3 F. / 0 0, . f h /.r j

,

3

FFFERENCFDAEC Systeit. Description A-4, pg, 0-9TV300?M101 293009K137 ...(MA'C)

A N 'fV 5.1? (: .50)

si , lotnsition boiling n: a y occ ur CO.5J. Th.s could lead toIt 'e 1 d a ll : 3 H EO.5'.

h. 10 c, s t. e the MCPR l i n i t ro a r e conservative to account for the

potm;bility of a sudden flou i n e t- e n c e e n c' the resultant pouerincierse. (1.0)

c. Increase:. (0,5\

ram r tE N C DDAF.C - T her m odyn s n<i es . Heat Transfer. and Fluid Flow, pg. 13-1??300?K120 ??300VK127 ...(MA'S)

/, N C U C T, , .13 (1.00)*

G4CM ,tEis 4 .1 4 . "' ps)g -- o??.7 psig

94$O.7 pa i I, [ 167 (j p g r A t? f

67 degtec- ' ( . 5 (> itd!7 degt ne r 400 degreet = r

,u,ean1 wnc m F, .

- R E F E R E t.'CI:

DAEC 't h c r m o d y n t sico 10-12 ? '1 0 0 3 K ', ? ' ...(KA'F)

._ - _ - . . _ _ - _ - _ - _ _ _ _ - _ _ _ - -

r___-_-_-__--__--_- _ - _ _ - _ . _ . . _ -. -

i

:

1,

E. _. _ _ _T H E D _R _Y _ O_ F . .PM J _C *L _ A R _ P O W E_ R_ _ P_ L A N _T _ O_ P E_ R A _T.1. 0 N_ _, F L_ U_ T O S. _, _ A N_ D 'PACE 2'

E__ __ ___ _ __ _ __ _ _ _. ___ _

T_ H_ F P_ M_ O_ D_ Y N_ A_ h l_ r_. G__ _

ANSWERS'- oDUANE ARMOLD -07/07/15-HARE, E. A. !

. . .

ANSWER 5 14 11.50)

a.. Condensatt depression or subcooling i

lb. . Helps pr ovide NPCM .to e ondero. ate . pumps to prevent cavitation

:e . Reduces plant-efficienc'/ --(this.is sdditionzl ha'at energy that 'fn, u s t be ptovided by the r e a c t o r )'. |

:(3 0 0. 5 e a c h . = 1.51'.!

'

REFERENCE-LDAEC Heat .1ransferr-pg. 16-15293003K116 2730061:110 ...(MA'S)

I

l

!

ANSWER 5 . '. S . (3.00)

n. Pump shul-off head it 'the pimp he d ct uhich the m',intainable flow;

rate is' reduced to nero L.1. 0 3 . It is undesi r able because the pun.poverhsats and nicy eesn'1L 1n rnochanical d;; mage to the pump [1.0:.

'b , 'Provided with e ninimun, flow recirculation valve and return line.~I(1 0) - L.,.41 w q J. rc

.1. . ' . ., , . , _ , , ,

. . . . , ,

< - ' ' ' '' |Cr ' b' 3 - # } ! ' '' -' ''

. REFERENCE ',i.

,

-

,- ' 's ' ' i

''

''

DAEC.1hermot$4iamicsr Hert Transfer, and Fluid Flow, p3 4-5 LU%A i\' isDAEC. System Description C-1, pg. 47293006H1?5 293006|(117 ...(KA'S')

,

|

l1

|

|

4'f-.

. .

,

-_ _ _ _ _ _ _ _ _ _ _ _ _ - __

.

s __ELOUI_01EICb2_0ESIGU _00UIE06:_000_IUSIBudEUI0IIOU PAGE 23.

ANSVEPS -- O ll t.N E ARNOLD -87/07/15-HARE, E. A.

f.NDUER 6.01 (2.00)

1. Roroeling platforn, pos:.tioned ne ar or over the core.

'2 . R e f ue ' s rig p i s t f o r n, boists are fuel-loeded (fuel grapple, f r a ca emounted h o i s ', , monorail courtad hoist).

!

'3 . Il P O I SPeppIO fiO ! fil 3 up

6- 9er"L e platforn$ hoist fuel-loaded.

5.- 0 4e rod withdrawr..

(4 of 5 t u,uired 0 0.5 pts each = 2.0)IREFER TO PAGE 25A .

REFERENCEDAEC Technical Specifications 3.9.1, pg. 3.9-6?34000A302 234000K502 ...(KA'S)

ANSWER 6.07 (4.00)

. Ceuces reactor level ta increcse E0.33] due to the level controlsyston having a level error, level set indicated leve] [0.53'

resulting in the feedwater control valves to open to ni a t c h new higherlevel Co.53. q

l

b. Pe+ctor level should remain constant E0.33] because the 'D" M/Atransfer e,tetion will lock up E0.5]. The 'A' feedweter control vcivewill control leve' E0.5].

c. Cruso reactor level to decr ease E0.33J due to the level control ;i

. . y r, t c. . nssing a stear:, flow / feed flow error, stean flow feed fins 1

[ 0 . 5 'J resulting in the feedwater control velves to close to netch I.

ne : louer level E0.51. .

!

!

REFEf'ENCE )

O f 'I t' By-tem Demeription p;. 6, 20-?2, Figure 5, 6 |

250001K108 259001K109 259001K301 259001K302 ...(Mo'"' !

!

_ - - _ _ _ _ _ _ _ - - _ _ _ - _ - -

i*

,

PAGE 25A !*

.

.

MODE switch in REFUEL and:

1. Trolley mounted hoist loaded with platform over or near core.

2. Frame mounted hois't loaded with platform over or near core.

3. Fuel grapple loaded with platfortn over or near core.

4. Fuel grapple not full up with platform over or near core.

S. Not all rods in and selection of a second.

6. Service platform hoist loaded

MODE switch in STARTUP and:

7. Refueling platform over or near core.

8. Service platform hoist loaded.

I

j

i

|.

|

..

uI 6:__EL6dI_SXSIEd3_2ESI901_C9BIE9L _600_IUDIBUUEUI61 ION PACE 26

ANGUER" -- DUAME ARNULD -87/07/15-HARE.- E. A.

ANSWER 6.03 (2.00)

e, Operating on unloaded diesel increases the air blower temperaturesto the manimum operating value due to decreased air flow. and ruyresult in blower damr,ge. ( 1.' 0 )

or

| Corbon-rich cortbustion products could collect in the E D/G exhaustpor ts and present a comburtion hazard.

. . f o e , s i.7Jr 4 a r.Tb U t t:cM-d-ewar. . (l.0) .b. M, -

,

- @,.. . . , > . c c, ' a c~ ,>e Ly& 7,

REFERENCE01 324, p g s, . 6 and 7DAEC System Des c r iption G--2 pg. 33264000A203 264000M401 ...(KA'S)

ANSPER 6 04 (2.50)

s. D e c nu - t.he regenerat.ve HY h o c. no flow through the secondary side,bit.edcun flow muct be 3 i rr. i t e d to t h c- capacity of the NRHX in or de- toprevent overheut!n3 of the ite:.ine r v l j r er bed. (1.0)

b. E:l o u d o u n is used der i r g stc t teap- heatup. or hot standby ope r a t i ore;f0.252 to rednee reactor water inventory E0.253.

c. In order to p r ev erit draining of the systen. CV 2729 c l o c. o s on loup r e r.. s u r e sensed up;trean. (5 psig). This pr events drainir.3 theRWCll s y _ t e r. to nmin condent.er in the event CV 2729 is not fullyc.losed. (0.5)

A3 a rlosec c 146 p:13 u'nsed downstrese, to protect the low pressurepiping, prevents pcscable over p r e s s u r i :' e t i o n . (0.5)

!REFERENCEDAE System Description E: - 4 . ,r g. 37 13 19204 000t 10'? 204000M402 204000U407 ...(MA'S)

I

_ _ _ _ _ _ _ ._ __ ____ _ ____ _ _____ _ -

.

- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - I N. S T R t J M F U T A T i. n N PAGE 2-A. PtANT SYSTEMS DFSIGN, CONTROL, AND------------.--

-ANSWERS -- DUANE ARNOLD -07/07/15-HARE, T. A.

I

11

ANSV?P 6.05 (2.00)

The s y n i e r- diccherge baron injection i. s limited such that the reLe o0increene in the concentr a tior. of naturel boron in the princry coolantoster is 'ast enough to o v e i r !. d e the rete of reactivit.y insertion caused ,

by cooldown of the reactor following the xenon poison penP. [1.03, e rrr'

m.,+~gi i; . . r. ' ' e4 h t-- t het9. -i n - ttMimnt crm i > J w baron dcot nct ;

r c c1 r.cul ate - tiu ough ta,e cor e in . .en. vs n conc +n t.r et i one. thrt could portib1y.c a v :> n nuclesi power 4. o rite end fn11 cyclice}1y C,1, 0 ] . . -

):L mb v(.cno. y ;Vi.;.. ; V. t . '>

.-e ,

REcCRENCT '

. -

DAEC Systeni Description C-4, ps. 9 ~h !; c. v41 -"k i 7, - r-

211000A107 211000K405 ...(KA'S>

ANSWER 6.06 (2.00)

a. (2) (1.0)b. (2) (1.0)

REFERENC''DAEC System Description A-2 pg. 64202002A106 20200?A107 202002K603 ...(MA'S)

ANSWER 6.07 (1.50)

2. If the field brealer is not shot within 15 seconds efter the p u m ,ncequence is started. (1.0)

(0.5)'

b. The recare MC dr ive n c + or bred er rk - it -krip'

wn \ \PEr F r7 pr'E

DAEC Rytten D , :. e r i p t i e r: A 2 pg. 3?. TsM o 1, Figure. 167 0 "| 0 0 : K112 202001E'r' 202001V6N ...(MA'S)

_ . - _ _ - _ _ - _ _

f-

4

l|

P 'd" 20 l| .A._ _. _ _ P_..A_ N _' _ _c,Y S _T U _M T;__nrE_I__CH_,_ r_ n N T R O L _,_ A_ N I)_ _ _ T H _':. _' r ' ' I t_F_ N _T A _T .10_ _f! i; _ _ __ _ __ _ ______ __ __ _ _ _

A N S tF " -- DUANE ARNOLD ~B7/07/15-HARE, E. A.

A N E;U E P 6 . O ff (^ .50)

a. r.u p r es s iir e e t ei. t.e r than J p .: i g .

coverese $ nCA cign:1 pree e nt ) - reactor venel leve. i r.'. ' 3 cor e

c o v e X '? 9 ncher .

Com' : t i n, e ;t Sprey Valve -uitch in ne a riu o l . ,

i. -1

,'

A , 'R'w.--, . . . -- \ '," T "' '' ya r d , L U.As b a'-,' : -i ,

i'

. , .. 1.0)( n.. , ~ ' t e_ p a_ r_ h : t

b. ' t. 7110ws o;: (ning of cont a i mi en t spray ,> e l v e <.. by bypassing the.

r eq.: iron ent for 2/3 ent e coveregex (0.5> ,

( t c; ) p,c (( s@ C ' . 'v i) e-'

'~ N- ' *

^FFERENCE'~

D AF C Sys tter. Deser ip tion C -- 1 2 pg. 37 > --

226001K10P 224n01M113 ...(KA'S)

t4 M c. W E ^ /3. 0 9 r1.00)

c.

F: F. F E T E M C E

DAFC % tern Descriptier D-11215000A103 ...(HA'S)

A l ' ?. is' E R 6.In (2.501,

h c l f - s t r 2 n-

b4 O ^ ions

l' . h iJ 1 I * O c i ^ n

d4 r c; c' hloch

t' i C r B li

(0.5 g 1. 9 i i in )

pgp , per

,. -

y 07 ' , n i i r 5-- 5'l ' r r '', s t r n. D r t - i .o t i o!, I -- ; . o 1. .:-

D A E r. -t %t:ription 1-3, 4 p;. O '$s.

^ ? O .l K 1 c ' '''2000K305 /1500SK101 2 3 cT 011' ' ~ 2 2 'i O '': e n :

(KA'S).

. _ _ _ _ - _ _ - _

_ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ - . _-__- _ _ -_ __

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'

4. PtANT SYSTEMS DESIGN,' CONTROL. AND It!G TRUM ENT ATION PAGE 29 )i'ANSWERS -- DUANE ARNOLD -87/07/15-HAPE, E. A.

. ANSWER 6.11 (3.C0)

a. The Turbine Stear. Supply Valve (MO-2404) closed. (0.5);

4

.b. When level decreases to the initiation level (119.5'), the 2404 )velve will r .3 0 p e n . (1.0)

c. The turbine test circuitry would be autonistically bypassed and 1

-the-RCIC system,would revert to f' 10 w control mode. (1.0)

d. No [0.25]. The mechanical overspeed must be reset locally [0.252.

' REFERENCEDAEC Systen. Descript,ico E-2, pas. 17, 24, 25, 36 38217000A101 217000A103 217000A301 217000A402 ...(KA'S)

| AN9WER 6.12 (1.00)

The charger will trip E 0 . ". ] (on h.tgh energency load starting currentti andto all associated loads CO.GJ (both n andpower would t, hen be lost

G [ & <A c. L., a ct f f Qit./.s 1 j f._; 9 f .g,7,?}) &pr m riemaraency). G f. 3L/s K j , . _ e.. ,,

. rr. _C..:

.ae ,. n e ,- _.e.,.. c, . ,.

-. v , ,+- _

' 3 .X o'REFERENCE s - " '- .' 1

DAFC OI 388, pg. U263000H102 263000K201 263000K302 ...(KA'8)

; i -.

!

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.

- - - - R n C F D .t.lP F 9i' . P. --- NOPMM . ADNORM..-----------------..AL. FMERCFNCY AND PAGE 30 2

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

R A D I O L.O G I C M--------CONTROL---- ---

AtiSWERS -- DUANE ARNOLD -07/07/15-HARE, E. A.

'

ANSUER 7.01 (1.00)

1. Relnu this range. toru ; heat cap; city is less of a concern since ther,hutdown cooling syster,i ru e y b e used for hert r e n> o v a l . ( 0 . D '>

7, S t e r n, iloo e ; t.e s duricia 3FV discharge will be suffic1ently lowte preclude u n t.t a : o condensation. (0.5)

'

PEFERENCEDAEC EO '- 7NFD0 30796, Danes for En.ergency Operating Procedures; ct DAEC, pa3e '-2295013!'104 295026A203 2950264102 295030M103 ...(KA'Ci

ANGWIR 7.02 (3.50)

;. To avoid rapid i n ,j e c t . cold unboratec' water d u r i rig"

dept os ufir inatiois 2. n d tt the restdting react!-ity encursion. (0.5)D o r o r, injection and CRD 11cv ere continued to achieve rNetorshULdown4 (0.5)

6. Un; i. above MARrP to provide rufficient s t e mi flow thrcuch the o,% n

S R th to ensure v4 9uv i e S TE A tt CDOLING tc an uncovered core < (0.04low sc c:c'te:1 to W control flooding rate and tho.Rept -

p.wsible power ( ,:cu r s ions . (0.5)

c. Wo .Id indicate that water i ruddenly entering the RPV e+ retem

that is l e r t. then Uc rete of steam produttion and ther e f er , 7PVw ") t e r ; e' < 15 d e c r e 6 % i II',,; . (0,5)

i

'1 6' L i' t- nEceSLOTy b e C' a v i - the RPV will brc, I U ! OT -f){ iVP t

it'',r s u r i r e d p .- i c.. e to flood, . ;. (0.5) C z' a t : m ' injett'ne otit'ide

the shToud ero P.'er' o to minitire colt wzter reactivity add: . ton.( 0. ';)

PIIt R E l.'!' EW "; CDP-;. p+i.- 51 t hi u Ytt P 3079(, D c4 9 Ni Crergency Operaljng Proceduret et DAEC.

5 1 /*. i. Ii r u C -$ C40908I . w

C. EpPf :( i 't.' fl C, P r J I. i [. ; C' r o ( p r.j i i y p p y [, d ' ;L e r, i f. l. 3 C6-i thrU C 'i - 3,L ]i ;= .,

{ C E / '31 C / 1 ^ ^ 9 5 0 "t 1 M 3 0 t. To!.0?'9012 . . . ( L' - '[ ] , A .", Q |-( ' 7 ^ i

<

.

.

I7. P e n r'F D tlP F S - NORMAL. ADNORM A' . . FMERGENCY AND PAGE 31~~~~EhbiU bb5EEI~Ebi}TRULI~~~~~~~~~~~~~~~~~~~~~~~~-- -- ---------- --

_

i

ANSWERS -- DUANE ARNOLD -87/07/10-HARE. E. A.'

1;

|

||

ANSWER 7.03 (2.50)

a. Drywell inspections shall only be performed under the followingcor da tions! |

Shift, Supervisors and Operators are noti f'ied o f entry cod e n i t. |'..

tin es and appropriate los enteies cre mcde.

2. The reactor' i s soberitical and ' 5% reactor power.

t

3. RPV pressure is below 400 ps)s,

1. No evolutions cre performed by operators that wouldsignificantly i n c r,e a s,e system pressure. . . .

C . J. - wu , / . . .,. , z s ' c-i

(4 E 0.5 pts each = 2.0)3. . A .. .~,v u . / .- -'

w. c ,..6,m' 'io' '. b v . 'r..' . .-

1 , ' '_ s , d * "

- ...

b. E mer gency eritt les beyond these restrictions must be paroved by the,'

P) ant Superintendent. (0.5) . ,g , , , , ;,,,,,,,.

"/~~' U'

~ " ''

REFERENCEDAEC IP01-2 pg. 25 h~ i t I''

223000C001 223001A106 2230011f116 .. (HA*S)! 'q, Q 4 ~

.

,..%

-ANF.WER 7.04 (1.50)'

|0 1L- (- |t - ; 'i' ,, , .

1. To conserve water inventory o . . I I. .. , .

'L., ,- i. i, -

1. To protect c o n t a i nnie n t inventory i'1

-

l '. . ' - i

\ l

3. 10 ::ni+ 1adacactive release to bc envi r onme n t. !(1

'

.t. k k$ , *%.

R i i E '~' E N C E |m c m -c, n r ee c eut . co = . p3 9, ceou on 1s

~ 2 9 0 0 0 2.c ? n , 2c'OOO2G001 ..(MA'E'

1i

|l

_ _ - . - - . - _ _ . _ _ _ _ _ .J

.

- - - - - - - - - - - - - - -.. . N n P M A L , A R N 0 0'M A L , EMERCFNCY AND PACE 3;.<ROCFOURFS:.--------- ---------------------

Ei2IOLOGIO6L_COUIC0L

AW4HERS--- DUANE ARNGLD -87/07/15-HARE, E! . A. |

:

I

e |ANSLER 7.05- ( 1.f 0 ) |

s

False j7

.

b. rue ;

1

1-If e 0.5 pts ench)

,

REFERENCEDAEC EPIP 1.?294001d116 ...(MA'5) |3

,

'

| ANSWER. 7.06 (1.50).

14 The e v e r; t

2. The t i r<. e declered

3. Artion(s) t a k ez n

REFEREtCEDAEC Ef''t 1, 3 -

294001M106 ...(MA'R)

|ANnWEP 7.07 (1.50)

Yes. CO 53 1he 250 volt DC battery ie coneidered inoperabla [0.5' i f'nere than one c o l ', i e out of e o r v .i c e ) .

Tho F!' Cl B y t t. e rr 'ihall also be coricidered inoperable. [ 0 . r. '

PEFEPENCFD6Er n1 100, pg. /s , ', 4

1echiict1 9pocifi cet i on ? b.E.?,c2 /;'16 0 t) fi 0 0 ' 2 4 3 O O O f; O A 5 7 / ') O O O l'I' C 1 '?'S),,,

i

|,

--- -___-_ _- _ _ _ _ _ _ . . _ .

.

----- FNCY AND PACC 73FMERC-------- D t i p F 9 - n rl R M A L . . A R N O R M A L.. .7. PROCE--- ---------- ------- ------ -

R A D '| O L O D T P. A L CONTROL-------- ----------

ANGUER3 -- Dl!ANE ARHOLD -07/07/15-HARE, E. A.

ANEVEr 7 . 0 f' (2.50)

v. 20%. I o . ' ,1

gj1] not ave- i.) r: e the (, h r i,.i :; ' # c ( e p. 31h 1br , i.t n p t. a e 1.1 f , {. Cit r e r'

C. r /My 94 u. q Actsi i rA ~ f..,.'L 7; - i. nit e! ed -- c i ca (1,0.v, , h ? - r -. u : t.....s ho 't,4 '

s.., o, -

. -..-

c. The unp'will : i off u 'w n the Mode Swlt,ch is shifte<. b e t u vw n(1.d)p _,

0o :: tions..

PEFET,ENCEOT 261 R V C l) , ons. 41 arid 06

-

t

204000A401 2040094401 ...(RA'S)

ANEWF R .09 (1.50)

t i a l d e *., s. 1: - Pejectc . would e'ceed the 10 CFP '' O e,i i a r ' e r 1 y 1. i : . i t"-

Cr roli d t , 1T Rejectrde w o e. : : r! e ceed the r ein i ni t t o et i ve c'u c t t e r- 2 y- ,

iieat

C J UI .; ' !- EI - Accepted 9 PVen th0 Ugh 5 (U-1@) PhCeeded the 1 i m ;t !.'

onlv. L.ooliec 11 ci o a n a to 3000 mrem /ott C a n d :i h t o. ic .

i e k0 ( I IP. # r > ( '

3 j D. ' t. r

R '~ I l~ R [ N C F

1 ('. || t R 20, D M" C He : li, E ! , f e, i e n Precedur- 3102.1r p ;; . 2"940011'10? .(KA'C'.

AN?,Ur .10 i;,n'.)~'

lo la i n i ti. i r e w( si or, the CFD p j <.t ori se '14 0)'

,

Y.*P', ';, f I e f p 9 O' t 1, I''is L I l- i

r_ U( !% C, I (''rn 4( A V6 P,.,_ s s

+ , + I,h'y; ' b ')'

,

e,6

. . - - - - . _. _. - _ _ _ _ . _ _ _ _ - _ - _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ - _ _ - _..

..

Z.:.__CEOCE00EES_:_UDEt!66 _60UDEd6L:._EUE-SOEUC'f _6UD PAGE 34E601GLOGIG66_GOUIBOL

+

ANSWERS -- DUAi!F ARNOLD -87/07/15-HARE, E. A.

i

ANSWER ~ 7.11 (2.00)

a, lo minimize therms) shot to the HX.

'' ' q ctorb. The i' l u u b y ;- .. . . . im m i .2 , ,. . ...,-

~~c oo l errt- ninh i ., u ; j c->i. ; .2 , u s ._ ..-

vu , . . . << ; , i . .- ,

' n' ' !c, o r .j. p, ,3m , ..,s

REFERENCI , ; pgen c. ,i c, . . , , .,

DrFC OI No. i4? ' * ' ' ''

'

.205060A110 2050001'102 205000l(502 217000G001 217000M105...(KA'C)

;

ANSWER 7.12 (1.50)

leert tWo independent indications [0.5] misoycret, ion _in automaticDy at 'c o n f'i r n e d E 0 . 5 3 .' D R E d e c;u a t e c o r e cooling is crsured C O , '~ ~ .mode is

RF.FERF.NCEDAEC DI Ne 149, 150. 151 end 3 f;"

' 03000H401 206000M407 209003K40F, ...(KA'S) iJ

ANSWER 7.13 (2,50)

|

To ptevent damage to the pumps hydrostatic thrust bear:.ne. (1.01 |.

hi l PCl 1 C40p E C 3 e c t i o rt logi(* Will m15tuhen3y E t f.u m e n O r th D 1 2 pump .

Ih p e r 7,1,i o ri e h i y i. s even thotigh 1 o f' the purnp di s char ge vs1ves i :;'I

e] c c e ri s;nce it osce p u rn e d e ] t e p to s,e n r e thit a p u r;.p iir runnin3- t

(1.5)

fEFEREU2FDAEC D) 26/12020012.224 202001M11/ ..(MA'G1

i

.

- - - - - - - - - - - - ' - - - - - - - - .i. A.D tJ O R t1 A l.. EMERGENCY AffD PAGE 3DP Tt 0 C E D tlR E S . -- N O R M Al...7.E8010L091G66 00'11806 - ---------------------

ANSWERS -- DU91E ARNDLD -87/07/15-HARE, E. A.

. ANCWER - 7 ,1 '4 (2.00)

e. Turn off circuit breakers (BUS A CUT 02 and BUS D CMT 02) to PowerRcnge' Neutron Monitor ing Systen. -( 0. 5 ) i ri the 1A3 switchgect roon(0.5)

.b. Claw ai r s uppl y 't o Scr a ri Valve Piloi Air Header located in Rr, Olds..757 level (Col. C6) (0.5) and Vent scram air header ct.PI-iC41/PS-1842'.(0.5)

PCFERENCE /,. c j.y- -~ / '

."DAEC EOP-/. pg. 17 )

295016A301 295016G006 ..(KA'S) i.

[ ,1.- 3 L'. l%[ 0Cr#I k D >. J MTodc$t.v / ,e " -5''- .['/

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Sz__60bIUILIB6IIME_EB90EDUEED:_G9E91110BS:_6U2_LIblIGIIQUS PACE 36

!

AN9WERS ---.DUANE ARNOLD -87/07/15-HARE, E. A.

ANSWER B.01 (?.00)

1. - c.2. h,

3. d.

4. a.

(4 (* 0.5 ptc each = 2.0)

REFERENCE - I'

DAEC Fuel and Reactor C o nip o n e n t Handling Procedure fi 5 , pgs. 9 and 10 1

DAEC Enabling O b .i e c t i v e . FRCHP tS-3204000A102 234000A401 234000G014 ...(KA'S) .

ANSWER 8.02 (1.50) ji

a. Felne. ;

li . Falco,

c. :True. .

i

(3 0 0.5 pte each = 1.5) i

i

REFERENCE' j-

D AFC Adniin i.s t r a L 3 ve Procedur e 1410.6, Fgs. 3, 6, 7

294001l'107 ...(K/'S)

i

ANSWER G.00 (2.00)

Fnc tlentons, if - deluse and Sprinkler system is no rPer letbnde i l 9 J

OpetBDlO. c r. hour 3 y fire witch patro: vith por tab]e fire extinguishinge qu i pum n t iii sl c rfected area' is r e gi e .i r e d to be est.ablished with.in one

i c hose s t r ti vri i rioper t ble, a fire watch p a t t' o l withhout i ', 4 0? e, rid w i t tpor table fire e :11 ngo:i ching equip a r nt shall be established within onehout until en edditiores: hose can be touted from an operable hose striion'ljo the ef f i p p o t e c ( ,: d EPe6 E_1. O T .

*

REFEPrhCEr, A P E 1 .. c h n i c ,1 9;, cification ^1.13 C End E a ri d LER 86-015-00.?i4000A105 296000G005 286000KcC1 ..(PA*Ci

- - - - - - - - - - 9

,

c

& _ _60 dI U I SI B 61 I 2 E _ C E 00 E D U B E 21_ C O U 91II 9 U S 1_689_ L ItJ I I 611000 PAGE 37

AtlSWERS ---DUAHE ARil0LD -87/07/15-HARE, E. A.

ANSWER 8.04 .(2.00)

!-- a .- 1 .' Chut~down the resctor!

| !

| 2. Close the tiSIV's ||-

..,-

,

'

|. ' ( 2 '3 0 . 5 o c c h )|

| b. Doiling occur.s at higher steaming rates causing dearation of.thb i

!~ recetor'. water, fhus maintaining oxygen concentration at low levelsand assuring that the chorlide-okysen content is not such as wouldtend to induce stress corrosion crocking. (1,0)

_.REFEREttCEOAEC Technical Specifications 3.6 D.1, 3.6.D.2,' 3.6.B Dases

'29400 A114 ...(KA'S)

!

ANSWER 8.05 (1.50)

The na ni nivn diesel fuel sur. ply of 35,000 gallone w]Il iupp_1y nnediessel generator C0.53_for s ni i n 3 ni u r.: of seven ti t.y s of operation [0,53,

REFERENCE~

DAEC 'iechnica) Specification 3,8. A . 2 ane: Technica1' Specification BAGES3.C.1.

264000G005 264000G006 264000M105 . . . ( l( A ' S ) .

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. _ . _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ . _ __ __ _ _ _ . . _ _ _ _ _ . _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ . _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ . _ ~ _ . _ .

_ _ _ _ _ - - _ - _ _ _ _ _ _ _ _ _ - . _ _ .

!

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-- - - -- .T N I S T R fi. T T u re------------- CEDilRES. CONDITTONS. AND I3MITATTONS par.E 38l' 'p. /, n M PRO- ---------------- --------------- -|

| ANSWERS - DUANE ARNGLD -87/07/15-HARE, F. A.

(: < , wi. - , ' .-. . . : .. ( ,,

< t v .- 2 .n 6, h a p . .u q . ..WL. e.r s.. e- ~.e me ( . , , s t .

AUSWER 8.06 (2.50) 6 ') , i''

1. Technacal Specification 3.3.A.2.e. states that control rods uithinoperable o c c u n,u i a t o r i. shs11 be considered i no p e r a b l e 3.-- = ,

;

!u ' " ertr*--?*'t?-tv et7*r cet elmt otr+cetion. (0.75) .

.a J ,. )-

-' .

s. < sed.,.c a .. . ' . r> . < < . . i . 13 Q. 1 .<cq<- oc . .

2. Teci'nicel Specification 3.3.C.2 r.tetes average s c r a n, i ns er ti or, times

2 array shall be no"or t, h u three fastest control rom in a 2 ',

gierter then 0.370 secs. f r o ni rod position 46. The three fastestrods have an avsrage time of 0.369 secs and t. h e r e f o r e , do not affect

;

plant operation. -(0.75)

3. Technical Specification 3.3.A.2.a. staten a rod which cannot bemoved by control rod drive pressur e is inopereb]e and since 26-O' lewithin the 5 5 array of 10-07, lechnical Specification 3.3.A.2.f.1steter the reactor ihs]1 be brought to cold S/D w i t., h i n 2 4 hours.

(1.0)

PnFRENCEDMC 'lechnic Specific.tiun 3.3'?0'0010005 ...(MA'S) '. ;

AN9WER H.07 (1.50)

e. No. (0.5) The bat..le ni e d i c a l qi..ialifications of 10 CFR 55 are nc

longer mei . (0.5) (Will accept alternate wot ding such as " Unfitfor puty".

jb, Yes. (0.5)

|

R E F E RE.N r F.10 CFr 55.3 , 55.41

i

''0'1(441A103 . . . '.lf A ' 9 i ]

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--------------------D LIMITAT10N4 PAGE 39 i

.

.. .

CONDITIONS. AN------------- EDURES.PROC- .' A D M .I. N I S T R A T I 'M?

.-- -------------

ANSWERS -- DUANE ARNOLD -07/07/15-HARE, E. A.

-

ANSPCR 8.06 (2.00) -

,

t ''

1, No more than 16 hours.in a 24 hour period (Tuesday 17 hours). ,

, T, n n - ' ' . , . .,!o <

2. No n, ore than 24 hours in a 48 hour period (Mondcy - Tuetday/. -|

3. At } east 0 hoorn rest between. work periods (Tuesday - Ncdnesday).

c. . No mote than 72 hours in'any 7 day period (86 hrs. Sunday-Saturday). !

i'

5. No more than 16 hours stoaight (Tuesday).

(5 P.O 4 pts each)

REFERENCFD AEC Arin,i n st r ati ve Procedure 1410.1

204001A103 ...(KA'S)

AN5WER 8.0" i' !' . 5 0 )

a. A men tier of the Plant Management Stsff and an Operations Shift !

Supervisor. (1.0)<

.Ib. 1. lo provide guidance in unusual situations not within the = cope

of procedures.l.

2. To ensure orderly and uniform operations for short periods when ,

to the plant. e system, or a component of a system is p e r P cir rn i n g |r m s o r' e i not covered by evist.ing aetailed procedures. nr hasi ri

b C .a t t modified or PUtef tded in stich 2 m atifie r that por ti Olk7 of|

62ther C s do n o l, J: p ;i l y .0 , , ; $_ ti rig p1 O(

P. Ir dl eet Opet E t i oris durjng tfsling and it e i n t e n s:n c e +a

l)4 To correct procedui: ] er rot d i scove r ed dur ing per f or rc = nc e

rf the procedurt

bS1 ~s' $ c ~,,. ' k2D' .,.|<,

*n

-'* I .A ,a in ., , .

(A y 3 i i i' 'v h s - a e c 0,ii l t e d ,s t 0.5 pts each) i. . , , . , . ,_ ,.

,,,j,%

r. +~ r,

g g; 7 ; ,[jg, f , ;c ,. ,PErEntgcr q 7.-

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DO"I A d ra i n i h t t e, t i V I P ' o cc e d u r e 1406.3 pg4 2. S; snd 6 T Mis CE /' % '#

29"SO1A10, ...(p'S) (b, I , .-,,,.: I. --.

e- j p 4,( ,s.' /'', ~ i l'). I O $ 1' V: d , . . > -s. . '*%,

.

4<

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_ - _ - _ - _ _ _ - - _ - - _ . _ _ _ _ __ _ _ _ _ _ __ __ _ _ _ _ _ _ --_ _

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,

132. _ _69 b lU l B I E 6 Il 2 E _ E B O G E Q U E [ h _ C O U D III O U h _6 U O _ L I[il l 6110 S S PAGE 40

LAt1SWEPS -- DUANE ARNOLD -97/07/15-HARE, E. A.

1

ANSWER 8.10 (4,00)

c. Mechanical and electrical systems which have direct design featureeinvolving cecident prevention and/or mitigation. (1.0)

tc . - Stop sffected work it ^ Fersonnel or safety hazard esists [0 53.McLe a duplicate lloid Ctrd snd msth it as c duplieste EO.5:.Note aduplicale" i n ued nent to t.he pertinent entry on theMaintenance Tagging Form E0.5J. (Work n cy be r esumed when j

proper isolation bcs been verified.) (1.5) !

c. The OSS E0.53, if deemed necessary for safe operation or shutocunof the plant'CO 53 but only a f t, e r investigating and assuring |

iii n /her t.el f that there is no danger to personnel and that othei i

:sersonne] involved have been informed'[0.5]. (1.5)

REFERENCEDAEC Administrative Contr ol Procedure 1410.5294 0 01 M 10'; ..,(l(A'S)

ANSWER 8.11 (1.50)

Operaba2aty: i

a. Either recirculation loop flow differs (by i 15%) from given I

epeed/ flow cheracteristle. !i;

b. Indicated total core flow differs (by 10%) from the vtive me t siir edf t cn loop flow nie a s u r e r.i e n t s .

c. O P f '.i :. u . - t o - 1 c L e r p l e m.n. de] ts P of cny individu 3 jct pump differtf' m norn. (by > 10%). |

(N,y 2 of the above P 0 . f. pts each)

% +.us's

Eli t.' s fE C r o s' T, 0 C u onF OW !! T p i Or I''t0WdOWn d t.> r- i n g L O C (~i . (0.5)$ '' f f | h Q k [f L O I' % $ ', <*'ll. .' >

,! ' $ t. '''1 t, s.r;t" -

_

. ,

PEFIRENCE, ., ,

' ; A'',' A /,. ( ' l- .('' -' ' 'o s ., , ,

OnEE TechnicT1 Soerifications,. Section?"' 3,6,E.', C 6 E.1, 9.6.'E.Av.

~ * y, . , s,.(d// IA !* '[' ',-^ ' ~

3nd kt( . h. L., y h V .f# ''

.

::0eo0 w e: 20:wm 1 c 3 ror em. c u r020n m ia 20 cm e.. 01M'94 .

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;t . ADMIN 1GTRATIVE PROCEDt!RFC, CnfJDITIONS, AND LIMITATInNC PAGE 41----------------------------------------------------------

A NS M E R S, -- DUANE ARNOLD -87/07/15-HARE, E. A.

ANGUEi 0.12 (2.00)

a July 27, 19C7 (1.0).

i. Utilur e to meet the t i r, e intervc1 for a surveillance c o n s t i i u t e t,

a failure to o,e e t t r, e onprobility r equi r r n,en t of the LCO. (1.0)e

TeEFEPENPEDAEC Technical SPecif3 cation 1.0, Definition 26206000C005 ...(Kd'S) F

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e

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.. . ..

iii,

-.e *TEST ER005 REFERENCE PACE 1-

OUCCTIOf! VALUE REFERENCE._.____. _ . . . _ _ _ _ . _ . . . _ _ _ _

05.01 1.00 EAH0001221 i

05.02 2.00 EAH0001222 !

0 5 . 0 "> 1.00 EAH000122305.0c 1.00 EAH000122405.05 1.00 EAH000122505,06 1.50 EAH0001224-05.07 ?.50 EAH0001227 :

r

05.03 2.00 EAH0001220 |05.00 1.50 EAH0001229 i

05,10 1.50 EAH000120005.11 1.50 EAH000123105.12 2.50 EAH0001232-05.13 1.00 EAH0dO123305.1c 1.50 EAH000123405 15 3 00 EAH0001235

. __ _ ,

24.50t

I

06.01 2.00 EAH0001236 -

06 02 4.00 EAH000123706.03 2.00 EAH000123006.04 2.50 EAH000123o06.05 2.00 E A H 0 0 012 '' n06.06 2. ?( EAH00012410 6. V 1.50 EAH000124206 08 1.50 EAH000124306.0Y 1.00 EAHOOO1244|

1

06.10 ?.50 EAH0001245'

I 06 11 3.00 EAH0001246I 06.12 1.00 FAH0001247'

- . . . , _ |

25.00

07.01 00 EAH0001243*4

07.02 3.50 EAH00012403

0 ? . O '- ' 50 E A H 0 0 01''.0l 07.O" 1 . 5 '- EAH0001251

07.o: 1 .. ' 0 EAH000125?| 07.0d 15' EAH0001253 || 07.07 1.50 EriH0001254 I

07.OR ?.50 EAH0001?5507 09 1 50 EAH0001256j

L 07.10 1 00 EAH0001257 |l

'

07.I1 '.00 EAH00017".R k'

0~.12 1 50 EAH000125907.13 ' 50 E. ," 2 0 012 6 0 i

07.< '.On EAH0001261 ,

..!

26.On

Or,c- ? oc r( n ; t 0 t ',12 A ;

<_

,_ -_ , ._ _ . _ _ _ - - . . _ _ _ . . _ _ _,

,

e'TEST CROSS REFERENCE,

PAGL 2OUESTION '' A L U E REFERENCE.

- - - . - - - - . . ..- . . - -.--.-- .

00 02 1.50 EAH000126308.00 2.00 EAH000126400.04 I'.00 EAH000126500 05 1 50 EAH000126600.06 2.50 EAH000126708.07 1.50 EAH000126800.08 2,00 EAH000126908.09 '?.50 EAH000127000.10 4.00 EAH000127100.11 1.50 EAH000127200.12 2.00 EAH0001273

-.- ---

25.00'

- - . - . -

-Wer gauamee

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