IR 05000443/1990009

Exam Rept 50-443/90-09OL on 900410-12.Exam Results:All Candidates Passed All Portions of Exams & Issued Licenses

ML20043B338
Person / Time
Site:	Seabrook
Issue date:	05/18/1990
From:	Eselgroth P, Norris B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20043B336	List: IR 05000443/1990009 ML20043B335
References
50-443-90-09OL, 50-443-90-9OL, NUDOCS 9005290138
Download: ML20043B338 (87)

Text

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S. NUCLEAR REGULATORY COMMISSION

REGION I

OPERhTOR_LICBNSING.BIAMINATION. REPORT REPONT Not 50-443/90-09(OL) FACILITY DOCKET Not 50-443 ! FACILITY LICENSE Not NPF-67 , LICENSEE: 'Public Service Company of New Hampshire

L FACILITYt- -Seabrook Nuclear Station EKAMINATION DATES: April 10-12, 1990 EXAMINERS: Barry S. Norris, NRC, Chief Examiner l Nancy E. Maguire-Moffitt, PNL l James E. Nickolaus, PNL Mark A.-Satorius, NRC .

SUBMITTED BY: I

'Barr7 f. Norris Date' ' Seni k Operations Engineer i APPROVED-BY ' / I Peter W.

Eselg h, Chief Date

PWR Section, rations Branch SUMMARY: Written and operating examinations were administered to three reactor operator (RO) candidates; in addition, three senior reactor operator (SRO) candidates were re-examined on-the simulator portion of the operating examination.

All candidates passed all portions 'of the examinations and were issued licenses.

i 9005290138 900518 {DR ADOCKOSOOggg3

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. e ? ,' REQUALIFICATION PROGRAM EVALUATION REPORT ~No'.~ 50-289/90-02(OL)

DETAILS TYPE OF EKAMINATIONS Initial ~ ' EKAMINATION RESULTS: RO BRO Total _ Pass / Fail Pass / Fail Pass / Fail ! Written 3/0 N/A 3/0 - simulator 3/0 3/0 6/0-Walk-through 3/0 N/A 3/0 Overall 3/0 3/0 6/0 l CHIEF EKAMINER AT SITE Barry S. Norris, NRC i OTHER EKAMINERBt Nancy E. Maguire-Moffitt,-PNL - ' James R. Nickolaus, PNL-Mark A.

Satorius, NRC 1.

WRITTEN EKAMINATION GENERIC DEFICIENCIES: The following is a; summary of generic deficiencies-noted during the grading of the written examinations.- This information is being provided.to aid the. licensee in upgrading

license'and requalification" training programs.

All' questions I ' were multiple choice.

a.

The operators were not able.to recognise the correct immediate actions for a high bearing temperature on a ~ reactor: coolant pump.

b.

The operators were not able to recognize the correct , temperature of an RCP lower bearing that would require closure of the number one' seal leakoff valve.

c.

The operators were not able to determine the correct available capacity of the-domineralized water storage tank given a tank level.

d.

The operators were not able to recognize the correct color that would be displayed on the plant computer if a parameter were in an alarm status.

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SIMULATION FACILITY REPORT: .-During4 the4 conduct;of,the simulator-portion of-the; operating an

, e examinations, no performance or human' factors discrepancies . were noted.

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FACILITY REVIEW OF THE WRITTEN EXAMINATION: The-facility provided two personnel'to review the written' examination in the-regional offices prior to the examination week.

Modifications-requested by the facility were considered by the NRC,,and incorporated as appropriate.

After-the examination was administered, the facility provided comments on two questions;'those comments and the NRC resolution follow

. Question No. 69-Facility' Comments.

. The reference cited does not support the stem of the question

for the correct time for transfer-to hot leg' recirculation to y take place.

Therefore there does not appear to.be a correct . answer for the question.

NRC Resolutions . ? Comment accepted..The technical error in this question should . have been identified in the pre-examination review.

The L question:was deleted from the examination.

Question No. 70 1.

L Facility Comment ' -This appears.to be a " typo" in the answer key because the reference cited for the question supports response "c" as being correct.

NRC Responses ! Comment accepted.

The answer key was modified to reflect that choice "c" is the correct' answer.

. '4.

COMMENTS MADE AT THE EXIT MEETING: The Chief Examiner discussed the generic deficiencies noted during the grading of the written examinations (see paragraph 1 above) and stated that no generic deficiencies were identified during the operating examinations.

v.Theafacility presented further comments,on.two of the written p~, _ _ examination questions-(see paragraph 3 above).

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REOUALIFICATION' PROGRAM EVALUATION REPORT'No. 50-289/90-02 (OL)

5.. PERSONNEL PRESENT AT EXIT MEETING Facilityt' U-L4 Carlsen, Training Supervisor.

J..Grillo,-Operations Manager 1R. Hanley, Operations Training Manager ' D.' Moody, Station Manager P.

Richardson, Training Manager NRC N.

Dudley, Senior-Resident' Inspector, Seabrook B. Norris, Senior' Operations Engineer, Chief Examiner M.

satorius, Operations Engineer (i NRC Contractors: N. Maguire-Moffitt, PNL J.

Nickolaus, PNL ATTACEMENT: .1.

Reactor Operator, Written Examination w/ Answer Key

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~< , % si - . ,Ns ?., Attachment 1 ' ,,,.. - T1 S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION REGION 1-I FACILITY: Seabrook-1

( REACTOR ~ TYPE PWR-WEC4 , DATE ADMINISTEREDs.

90/04/10 ' , , A&yfay . , - g INSTRUCTIONS TO CANDIDATE Points for each question are indicated-in parentheses after the question.

' =To pass this examination, you must achieve an overall grade of at least 807 ' Examination papers will be picked up four and one-half (4 1/2) hours after .the examination-starts.

I l-

I I l NUMBER l TOTAL l -CANDIDATE'S l CANDIDATE'S 'l l,-QUESTIONS l POINTS l POINTS l OVERALL l .l-l l l GRADE (%) .l- . l_____________l__________ _______________l_______________; > 'l i I I I l- ,# I 3D M00 l I i . I cj p 'l y L rc, I I I ' I I I I I t All work done on this examination is my own.

I have neither given '

nor received aid.

Candidate's Signature p.

l ! l~ ! I; l , . f, t - . . ..

. _ _ _ _ .. _ _., it .. ' .. . NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS . During the administration of this examination the following rules apply: 1. Cheating on the examination means an automatic denial.of your application l cnd could result in more severe penalties.

L

2. After the. examination has been completed, you must sign the statement on the' cover sheet indicating that the work is your own and you have not

' received or given assistance in completing the examination.

This must be ' -done after you complete the examination.

3. Restroom trips are to be limited and only one candidate at a time may leave.

You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.

4.

Use black ink or dark pencil only to facilitate legible reproductions.

.5.

Print your name in the blank provided in the upper right-hand corner of the. examination cover sheet.

. 6.' Fill in the'date on the cover sheet of the examination (if necessary).

?.. You may write your answers on the examination question page or on a separate sheet of paper.

USE ONLY THE PAPER PROVIDED AND DO NOT WRITE ON THE BACK SIDE OF THE PAGE.

8.

If you write your answers on the examination question page and you need more space to answer a specific question, use a separate sheet of the paper provided and insert it directly after the specific question.

DO NOT WRITE ON.THE BACK SIDE OF THE EXAMINATION QUESTION PAGE.

, 9.-Print your name in the upper right-hand corner of the first page of. answer sheets whether you use the examination question pages or separate sheets of paper.

Initial each of the following answer pages.

10.oBefore you turn in your examination, consecutively number each answer sheet, including any additional pages inserted when writing your answers on the examination question page.

11. If you are using separate ~ sheets, number each answer and skip at least 3 lines between answers to allow space for grading.

12. Write "Last Page" on the last answer sheet.

13..Use abbreviations only if they are commonly used in facility literature.

Avoid using symbols such as < or > signs to avoid a simple transposition orror resulting in an incorrect answer.

Write it out.

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. -14..The point value for each question is indicated in parentheses after the question.

The amount of blank space on an examination question page is NOT an indication of the depth of answer required.

15. Show all calculations, methods, or assumptions used to obtain an answer.

16. Partial credit may be given.

Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLANK.

NOTE: partial credit will NOT be gi,ven on multiple choice questions.

17. Proportional grading will be appliod.

Any additional wrong information that is provided may count against you.

For example, if a question is worth one point and asks for four responses, each of which is worth 0.25 points, and you give five responses, each of your responses will be worth 0.20 points.

If one of your five responses is incorrect, 0.20 will be deducted and your total credit for that question will be 0.80 instead of ' 1.00 even though you got the four correct answers.

18. If the intent of a question is unclear, ask questions of the examiner only.

19. When turning in your examination, assemble the completed examination with examination questions, examination aids and answer sheets.

In addition, turn in all scrap paper.

20. To pass the examination, you must achieve an overall grade of 60% or greater.

21. There is a time limit of (4 1/2) hours for completion of the examination.

(or some other time if less than the full examination is taken.)

22. When you are done and have turned in your examination, leave the examin-ation area as defined by the examiner.

If you are found in this area while the examination is still in progress, your 1icense may be denied or revoked.. I ! l l l- - - - - - - - - - - - - - - - -

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i r . I 'O , JREACTOR OPERATOR Page-4- t, f)- (QUESTION:'001 (1.00) . . ? . WHICH ONE: (1) Eof the following is used by the Rod Insertion Limits ' Manitor toidetermine; reactor power level? (1.0) , f a.- Auctioneered high T-avg !b.

Auctioneered high T-ref . t-c.. Auctioneered:high nuclear power , 'd.

Auctioneered high delta-T ! l I , s QUESTION: 002-(1.00) WHICH'ONEL(1); of the-following component failures will prevent ALL controltrod motion? (1.0) -, a.: Failure of:the following logic cabinet power supplies: ! ONE (1)L+100 VDC power supply, ONE':(1) +16.5.VDC power

. ' supply,.and'ONE (1) -16.5 VDC power supply . b.

Failure of the following power cabinet power supplies:- ONEi(1) +241VDC power. supply and ONE (1) -24 VDC. power , . supply L ' L' .c.- A power cabinet phase failure due to loss of thyristor gating 'd.

ALlogic cabinet slave cycler failure due to the slave

L cycler continuing to count after the cycle is complete with no further GO pulses received ) , l- ' , l .- ' \\ , - l' o a n ... -

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QUESTIONt 003.(1.00) l 'WHICH'ONE (1) of the following is a correct statement concerning ] RCP seal' failure? (1. 0 ). R a.

Failure of No. 2 seal would be indicated by a high No. 2 seal leakoff flow condition with a corresponding increase in No. 1 seal leakoff flow .l b.

Failure of No. 1 seal would be indicated by a low No. 1 seal leakoff flow condition with a corresponding decrease in No. 2 seal leakoff flow c.

Failure of the No. 2 seal would be indicated by a significant decrease in !!o. 3 seal leakoff d.

Failure of the No. 3 seal would be indicated by an increase.

in the makeup requirement to the standpipe ' QUuPTION: 004 (1.00) WHICH ONE (1) of the following is the minimum allowable #1 seal differential pressure required before a reactor coolant pump can i b2 started per 08 1001.05 uReactor Coolant Pump Operations"? (1.0) a.

120 psig.

b.

-220 psig c.

320 psig d.

420 psig , , _ _ _. . . . . . . .

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_ , ' '$' f '_ _ i ... r 5-REACTOR OPERATOR Page 6- 'QUESTIONt'005 (1.00) WHICH ONE (1) of the following is the purpose of the RCP anti-rGverse rotation device? (1.0) , la.

To minimize reactor coolant pump starting voltage l b.

To minimize reactor coolant pump mechanical damage , c.

To minimize the amount of core bypass flow-through an idle RCP d.

To minimize re-start time of the reactor coolant pump at low power levels . . QUESTION: 006 (1.00) > WHICH ONE (1)'of the following statements correctly describes the valve-interlocks associated with the water supply to the charging pumps? (1.0) ' a.- LCV-112B & C (VCT outlet valves) will close automatically if either VCT level channel senses a level of 10% or less ' b.

LCV-112B & C (VCT outlet valves) close automatically.if both VCT level channels sense a level of 10% or less c.. LCV-112D & E (RWST supply valves) will open automatically if either VCT level' channel senses a level of 5% or less - ' d.

LCV-112D E'E (RWST supply valves) will open automatically-if both level channels sense a level of 5% or lesa

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REACTOR OPERATOR Page

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QUESTION: 007 (1.00) ' , . 'WHICH ONE,(1) offthe following Pressurizar water levels is the l .cctpoint at which the CVCs letdown isolation valves will

cutomatically close? (1.0)~

r a.

'27% L b.

21% t c.

17% d.

12%. ! i QUESTION: 008 (1.00) WHICH ONE - (1) of the following conditions will cause the charging pumps; minimum.flowfisolation valves-(CS-V-196 &.CS-V-197) to-cycle -} to the open.and close positions following a safety Injection .nctuation signal? (1.0) a.. Open1with CCP. flow less than 60 gpm, close with CCP flow , at 100 gpm l f b.

Open with CCP flow less than 60 gpm, close with CCP flow ' at 120 gpm

c.

Open with CCP flow less than 80 gpm, close with~CCP flow.

' at 100 gpm

Q d.

.Open with CCP flow less than 80 gpm, close with CCP flow L atL120 gpm

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Page 8: i , .>- QUESTION '009) (1.00) WHICHLONE (1) of'the1following conditions / interlocks blocks

-cutomatic re-initiation;of Safety Injection.("S" signal)? (1.0) j a.

"S" signal' cleared . b., PER pressure above.P-11-c.

Reactor trip breakers open I d.

60 seconds have elapsed since "S" signal-l QUESTION: 010 (1.00).

FHICH 'ONE f(1) of.the following GROUPS of plant parameters are inputs for'the Engineered Safety Features Actuation System? (1.0) ~ a.

.RCS Pressure Containment Pressure RCS: Temperature b.

RCS Pressure-i Pressurizer Level Steam Line Pressure . c.

Pressurizer. Pressure .' Pressurizer Level RCS~ Temperature - d.

Pressurizer Pressure Containment Pressure Steam Line Pressure , . m.

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b QUESTION: 011 (1.00) 1 :- .Given the following conditions: - 75% power - Channel N-41 is the highest reading Power Range Channel - Rod-control is in AUTOMATIC - Channel N-42 instantaneously fails LOW - No operator action is taken WHICH ONE (1) of the following correctly describes the resultant control rod system response? (1.0) a.

Control rods will drive in at maximum rate b.

Control rods will drive in at minimum rate c.

Control rods will drive out d.

Control rods will not move-QUESTION: 012 (1.00) ~WHICH ONE (1) of the'following correctly describes the effect of On UNDERCOMPENSATED Intermediate Range Channel following a reactor trip? (1.0) a.

Indicates HIGH preventing P-6 from automatically i energizing the source range due to the 2 of 2 coincidence b.

Indicates LOW prematurely energizing the source range due to the 1 of 2 coincidence c.

Indicates HIGH; the source range will be energized by P-6 from the other IR channel due to the 1 of 2 coincidence

Indicates LOW; the source range will not be energized until P-6 is supplied from the other IR channel due to the 2 of 2 coincidence

v:- + a e,, ( '*i bl"*' 0; e? e tREACTOR: OPERATOR Page 10 , L _QUESTIONI 013 f(1.00) ,

WHICH ONE (1) of:the following actions'will occur if the operator.

w;re to pushithe!" SCAN" pushbutton on the Incore Instrumentation.

, System panel? ' ASSUME the,Incore-Instrumentation System is set up for automatic operation.

-(1.0) -

1 a.

Inserts detector (s) at I4W speed to the top-of-core limit ~ b.

Inserts' detector (s) at HIGH speed to the top-of-core limit , c.

Inserts detector (s) at LOW speed to the bottom-of-core limit-d.

Inserts detector (s) at HIGH speed to the bottom-of-core limit . . QUESTION: 014 (1.00) l WHICH : ONE L; (1).of the following is the correct type of. detection l instrument.used by Source Range Nuclear Instruments (SRNI) N31 and ' N327 (1.0) , a.' Compensated ion; detector ! b._ BF3 proportional detector- , c.- -U-235 Fission detector-d.. . Uncompensated ion detector-

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REACTOR OPERATOR Page 11-QUESTION: 015 (1.00)

, WHICH ONE (1). of the following is the correct Containment R0 circulation Filter System-(CRF) response in the event of a large ! LOCA? (1.0) ' a.

The CRF system is transferred to the filter mode when & "P" signal is-generated - b.

The CRF system is transferred to the recirculation mode when a "P" signal is generated c.

The CRF system fans and dampers are isolated when a "P" signal is generated d.

The CRF system draws air from the containment dome when in'the filter mode s ' QUESTION: 016 (1.00) WHICH ONE (1) of the following will result in a Main Feedwater Isolation?. .(1.0) a.

High-High level in any steam generator b.

Lo-Lo level in 2/4 steam generators c.

Turbine LOW condenser vacuum d.

Both main feedwater pumps trip QUESTION: 017 (1.00) WHICH ONE (1) of the following is an automatic trip of a Steam Gtnerator' feed pump (SGFP) during normal operation? (1.0) a.

LOW vacuum at 15 inches mercury b.

SG level at 80% narrow range c.

LOW NPSH at 250 psig for 10 seconds d.

Turbine bearing oil pressure at 2 psig -. - -

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REACTOR OPERATOR-Page 12 i QUESTION: 018 (1.00) ) WHICH ONE (1) of the following statements is correct concerning the

E2ergency Feedwater System (EFW) water supplies? (1.0) I a.

Condensate pumps provide NPSH for the EFW pumps b.

Suction for EFW pumps shifts to the Service Water System automatically on LOW condensate storage tank level l c.

Suction valves to EFW pumps automatically open when a pump starts d.

The condensate storage tank reserves 212,000 gallons for EFW usage QUESTION: 019 (1.00) .i-WHICH~ONE (1) of the following signals is NOT an auto start signal for-the Turbine Driven. Emergency Feedwater Pump? (1.0) a.

Pressurizer pressure decreases to 1800 psig b.

S/G Lo-Lo level in 1/4 steam generators c; Loss-of offsite power d.

Total feedwater flow decreases to 400 gpm QUESTION: 020 (1.00) , WHICE ONE (1) of the following is the motive force for the EFW flow control valves? (1.0) a.

Electrohydraulic b.

Instrument Air c.

Vital DC power d.

Vital AC power

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. REACTOR' OPERATOR' Page 13 I s- .I ! -QUESTION 1021' (1.00) , 'LWHICH ONE (1) of the1following is an automatic action that occurs- ' in the control center HVAC (CBA)-system as a result of a control ' . rsca ventilation Train "A" isolation signal? ASSUME the system' io aligned-for automatic operation.

(1.0) t & a.

Ventilation supply fan (FN-27A) stops b.

Damper-(DP-27A) closes ! c.

. Exhaust fan (FN-15) starts

_d.- Emergency cleanup fan (FN-16A) stops

LQUESTION: 022 (1.00)- WHICH'ONE-(1) of the following operating limits is based on minimizing the probability of brittle fracture of'the reactor ' vossel? (1.0) a.

Steam Generator Temperature Limits l b.

RCS Cooldown-Rate Limit c.

RCS Minimum Temperature for Criticality , d.

-RCS LOW T-ave Limit L I' QUESTION: 023 (1.00)

WHICH ONE (1) of the following is the proper valve status for th9 Residual Heat Removal System (RH) in the normal standby ECCS y

mode?, (1.0)

L, a.

RH heat exchanger bypass valves (RH-FCV-618 E.

9) OPEN b.

CCP and SIP suction supply valves (RH-V-35 & V-36) OPEN c.

Cold. leg injection isolation ~ valves (RH-V-26 & V-14) OPEN l; l d.

RH train A & D cross-connect valves (RH-V-21 & V-22) CLOSED l' '.. . !

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'QUESTIONt.024 (1.00) , l ~At'WHICH ONE (1) of the following RCS pressures do-the ECCS '

occumulator tanks begin injecting into the RCS?

(1.0) j , a.

.750 psig b.

650 psig ' c.

550 psig m i d.

450 psig i i QUESTION: ~025 (1.00) WHICH ONE (1);of the:following.is NOT anLexpected plant response ! if the pressuriner pressure controlling channel fe,ils HIGH7 ASSUME - no operator act:f on taken.

(1.0)-

a.

Spray valves OPEN'and heaters. turn OFF-t b.

. LOW' pressure reactor trip and SI

.. c.- Pressurizer PORV (PCV-456A) remains closed due to PT-458 interlock.

d.

Letdown isolates and heaters turn off . .- . I ^ I.

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QUESTION: 026-( 1.00) Civen the<following plant conditions: - PPC Channel 458 is selected as backup pressure control channel - ALL controls are 'in automatic - Plant is at 100% power ? WHICH ONE (1) of theifollowing is the correct response if channel 458 fails.HIGH7 . (1. 0 ) : ) a.

PCV 456A is allowed to open at 2335 psig and V-122 opens at 2350 psig j

1 b.- V-122 is-allowed to open at 2335 psig and PCV 456A opens at 2350'psig

'PCV.456B;is-' allowed to open at 2335 psig and V-124 opens c.

at 2350 psig - O d.

V-124 is allowed to open at 2335 psig and PCV 456B opens at 2350 psig . iQUESTION: 027 ,(1. 0 0 ) l / [Given the'following conditions (assumes no operator action taken):

' 'l .- Pressurizer Level Control Selector Switch in position 1-2

Charging flow reduces to minimum Pressurizer level decreases - Letdown automatically isolates and heaters trip ] - Level increases until high level reactor trip WHICH ONE (1) of the following correctly describes the pressurizer l level channel that failed and the direction the channel failed? (1.0) a.

Level Channel I failed HIGH b.- Level Channel II failed LOW c.

Level Channel I failed LOW d.

Level channel II failed HIGH ' d '

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, ' ist . REACTOR' OPERATOR' 'Page 16 < o , .1 QUESTION: 028 (1.00) . ; WHICH[ONE (1)-of the following groups of pressuriser backup heaters-10 powered.from safety related busses? '(1.0)

a..'A and B . t b.

A and O' - l c.

B.and C . d.

B and D e

, ,- 'QUEDTIONtt029 (1.00)

- WHICH ONE (1) of the following is the reason for the MAXIMUM- ~ prassurizer program level? ( 1.~ 0 )1 u - a.

Ensures there is an. adequate steam bubble in the

pressurizer and enables pressurizer-sprays to' perform as-designed

' )' lb.

Ensures there is adequate. level to prevent uncovering the pressurizer heaters.on a reactor trip c.

Prevents water relief through pressurizer code safety valves , d.- Prevents lifting of the code safety valves on an inadvertent start of a charging pump l, , , '

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,,. ,.4: . s ! .. f " REACTOR OPERATOR Page 17 . , , . QUESTION: 030 (1.00)- ,Civen the following plant conditionst ' -:100%' power - - All. control-systems in automatic EXCEPT rods which are in manual IWHICH ONE?(1) of the-following-events will cause Channel II OT delta T setpoint to DECREASE? (1. 0 )! i ' a.

Auctioneered high-T-avg unit fails LOW

- b.

N42' power range-lower' detector fails LOW - c.

Controlling pressurizer pressure channel fails HIGH d.

Reducing powerfto 50% with normal pressure and temperature-QUESTION :031' (1.00) c L Th6 following plant conditions exist for testing cf the reactor protection system: -Train B reactor trip-breaker open-Train B bypass breaker closed-Train A reactor trip breaker closed-Reactor at 100% power-WHICH ONE-(1) oflthe following is NOT the-correct system response L fif a. spuriousL Train B reactor trip signal occurs - and Bypass ' Brcaker'B' fails to open? (1.0) l - a.- Feedwater isolation valves close when Tavg is less than 564 degrees F b.

. Steam dumps controller shifts to plant trip mode y

c.

Reactor trips d.

Arming signal to Condenser Dump valves is generated 1.

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• REACTOR OPERATOR Page 18 QUESTION: 032 (1.00)

The following plant conditions exist for reactor protection' system (RPS) testing during MODE 12-Reactor trip breaker A open-Bypass. breaker A closed R-Reactor trip breaker B closed , -Bypass breaker B open , WHICH ONE (1) of the following describes why a reactor trip results I if Bypass Breaker B is closed prior to closing Reactor Trip-Breaker A7 (1.0) ! a.

Closing of both bypass breakers generates an automatic reactor trip signal b.

Closing of both bypass breakers causes an overcurrent condition to all four breakers c.

Bypass. breaker A will open on interlock l d.

Bypass breaker B will open on interlock j i . QUESTION: 033 (1.00)

'WHICH ONE (1) of the following Containment Building Spray (CBS) parameters can be monitored.on control room instrumentation (MCB - BF)? (1.0) a.

CBS pump recirculation flow b.

CBS system flow c.

CBS pump suction pressure l d.

CBS heat exchanger primary component cooling water flow I . - - -

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, , QUESTION: 034 (1.00) WHICH-ONE (1) of the following is the reason for_ adding sodium s-hydroxide (NaOH) to the Containment Building Spray System? (1.0) a.

It facilitates the converting of soluble iodine into insoluble iodine b.

It controls sump pH to limit corrosion of piping inside the containment c.

It minimizes the amount of hydrogen generated during a LOCA . d.

It reacts to produce a chemical' solution that provides cleansing action inside containment ' QUESTION: 035 -(1.00) , WHICH ONE (1) of the following provides control power'to Dus 5 br akers? (1.0) a.. 120 Volt vital Instrumentation AC b.

125 Volt Vital DC System c.

120 Volt Auxiliary AC System d.

125 Volt Auxiliary DC System , -

, ,

_ . . ..w - ' , > . 't

be . ;. _ - ,,

> o . . REACTOR = OPERATOR-Page'20 !

$4

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'QUESTIONI.0361 (1.00) > l-WHICH.ONE'(1)Hof the following will result in-an automatic ~ trip'of LM th3 emergency diesel' generator, if it is started after a safety, L cinjection by-depressing the'" Diesel Engine Emergency Start" . 'puchbutton? (l'. 0 ) : L ,

' i p<, a.. ' Jacket cooling water temperature at.165' degrees F .b.

Lube' oil ~ pressure at 70 psig

-c.

Lube oil temperature at 150 degrees F d.

Jacket. water pressure at 25 psig !: L . l L -QUESTION: 037 (1.00) l .WHICH ONE (1) of.the following loads would be sequenced'on by.

Ltha, Emergency Power' Sequencer (EPS) during an SI/ LOP incident? (1.0)- i , a.

Service air compressors L b.

Control room emergency cleanup filter fan L Containment structure cooling units c.

l L-d.

'CRDM cooling fans 1+ , l

1 l l-l

a -- --vm - e e

- ... _ - - - - - - -. _. -. .- ! . ;; ' . , .- REACTOR OPERATOR Page 21 ' QUESTIONI 038 (1.00) WHICH ONE (1) of the following is the correct automatic action that occurs-in response to a HIGH alarm on radiation monitor R6506A (CCR East Intake)? ( l '. 0 ) a.

Control' room air "A" train intake fan (FN-27) stops and ' "B" train discharge damper closes , , Control room air conditioning equipment is stopped b.

c.

Control room amargency ventilation fan (FN-16A) is shifted to the emergency cleanup recirculation mode d.

Control room remote East air intake isolation valve closes QUESTION: 039 (1.00) , .WHICH'ONE (1)-of the following statements correctly states the reason why a nitrogen blanket is maintained on the Pressurizer Rolief Tank (PRT)? (1.0) , a.

To reduce the potential for overpressurizing the PRT and deformation of the rupture disks b.

To reduce the potential for an explosive mixture of hydrogen.and oxygen c.

To reduce the potential for air binding the PRT pump when cooling the PRT in the recirculation mode

, d.

To reduce the amount of water necessary in the PRT to quench pressurizer relief valve discharge < ,

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'- '- - ~ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ~, ,y ,, , i?V Y' ,' ~' , >& . v / REACTOR OPERATOR Page 22 > ' i

k QUEITION: 040 (1.00)- 'WHICH ONET(1)~'of'the,following components discharge to the - l

Prdssuriser Relief Tank (PRT)?.

(1.0) .

La.

Cold leg accumulator: relief valves

o

' 'b.

RH suction relief valves a ' c.

Containment spray. header relief valve d.

-RCP #2 seal leakoff '? L ,

Y - - . t $, QUESTION: 041 -(1.00)

nn WHICH ONE (1) of'the following statements correctly describes ONE ' '(1)?of~the; automatic actions that occurs in the primary component cooling water system: (PCCW) following a "T" signal? (1.0) >t . l-D a.

All'PCCW-pumps stop

' b.

JSpent fuel. heat exchanger isolation valves OPEN

cc.

-Isolation valves to steam generator' blowdown system OPEN .

d.- . Residual heat exchanger isolation valves OPEN

>'QUEDTION: 042 (1.00) _.

' WHICH ONE -(1) of the following is a correct system response if the.Lemperaturc controllers for the PCCW heat exchangers are adjusted to increase the PCCW temperature? (1.0) .. a.

Thermal barrier flow increases c 'b.

Letdown; temperature increases ' E c.

Condensate pump bearing temperature increases d.

Turbine EHC cooler flow increases . . _ _ _ .

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

.~ . '4, -- .- REACTOR OPERATOR Page 23 i QUESTION: 043 (1.00) WHICM ONE (1) of the following is the MINIMUM Tavg/ Tref error 'j that will fully open bank 1 & 2 steam dump valves? [1.0) a.

5.1 degrees F b.

8.1 degrees F o.- 11.2 degrees F .- d.

14.2 degrees F QUESTION: 044 (1.00) If the level in the refueling cavity was decreasing, the radiation exposure from an unshielded spent fuel assembly will result in a dose rate in excess of R/hr at the operating deck.

(1.0) a.

b.

100 c.

1,000 4.

10,000 QUESTION: 045 (1.00) WHICH ONE (1) of the following actions occurs in the service water oystem-upon the actuation of the "A" train "TA" signal? (1.0) a.

Train "B" standby service water pump starts _ b.

Train "A" standby service water pump starts c.

Train "A" service water pumps trip d.

Train "B" service water pumps trip

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, . -.. REACTOR OPERATOR Page 24 ! QUESTION: 046 (1.00) WHICE ONE (1) of the following service water pump discharge pressure l CO2ditions is the MAXIMUM pressure that would initiate a service water ' trOin "A" "TA* signal? (1.0) ! a.

33.9 psig ' b.

31.9 psig c.

29.9 psig , i d.

26.9 psig i I QUESTION: 047 (1.00)

WHICH ONE (1) of the following conditions would NOT result in an cutomatic trip of the service air centrifugal air compressor? (1.0) a.

Low PCC flow ' , b.

First stage vibration c.

Low SCC flow ' t d.' Low oil pressure

QUESTION: 048 (1.00) WHICH ONE (1) of the following statements correctly states the . condition for which 081210.06, " Misaligned Control Rod", may be cntered? (1.0) ' a.

Any-time an individual RPI is NOT in agreement with its [ associated group demand height by plus or minus 12 steps ' b.

Any time group demand step counters in the same bank _ indicate a difference of greater than 2 steps ' c.

'Only as directed by procedure 081210.05, " Dropped Rod" ' d.

Only as directed by procedure 081210.07, "RPI Malfunction" i , .. -, , , . -.. . -. - - - -, _.. . .- - -.... -, - -.

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REhCTOR OPERATOR Page 25 QUESTION: 049 (1.00) Civen the following plant conditions: - A single control rod in bank D will not move - Reactor power is stable at 80% - Tavg and Tref are NOT matched ' WHICH ONE (1) of the following is the correct action to take in accordance with 081210.02 " Failure of Control Rod or Rod Bank to Move"? (1.0) a.

Adjust turbine load as necessary to maintain Tavg on program b.

Trip the reactor as directed by the procedure c.

Insert OR withdraw other Bank D rods as necessary to maintain Tavg on program d.

Do NOT attempt a match until malfunction has been cleared r QUESTION: 050 (1.00) ' ! Given the following plant conditions: , - Reactor power at 55% - PCCW flow is normal - "A" RCP MOTOR BEARING TEMPERATURE alarm lit - "A" RCP MOTOR STATOR WINDING TEMPERATURE alarm lit "A" RCP No. 1 Seal leakoff flow is 3.0 gpm . WHICH ONE (1) of the following is the correct action to take regarding

tho RCP per 081201.01 "RCP Malfunction"? (1.0) ' , a.

Immediately trip the RCP, trip the reactor and enter E-0 b.

Immediately trip the reactor, trip the RCP and enter E-0 l c.

Reduce power to less than 50% and trip the RCP within 30 minutes I Reduce power to less than 50%, trip the RCP within 30 d.. minutes and be in MODE 3 within 6 hours

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I . . .. REACTOR OPERATOR Page 26 QUESTION: 051 (1.00) WHICH ONE (1) of the following conditions require an RCP to be cttpped according to os1201.01, " Reactor Coolant Pump Malfunction"? (1.0) a.

seal injection water increasing to 120 degrees F b.

Pump lower bearing temperature increasing to 200 degrees F i c.

Motor bearing increasing to 185 degrees F d.

A motor frame vibration increasing to 5 mils QUESTION: 052 (1.00) WHICH ONE (1) of the following is the correct action to take to j Cnours an adequate amount of rapid boration has been injected following a plant shutdown with TWO (2) or more rods are stuck out according to 081202.04, " Rapid Boration"? (1.0) a.

Borate at least 9 minutes at 60 gpm for each rod not l fully inserted ' b.

Borate at least 150 ppm for each control rod that I failed to insert c.

Borate for 30 seconds using the rapid boration flowpath for each rod not fully inserted d.

Borate at 60 gpm until RCS concentration increases approximately 150 ppm , - , -. -

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-QUESTION 053 (1.00) + ! WHICE ONE (1) of the following is the time lir:it for tripping the ! rCactor following a loss of PCCW to.the RCPs according to 081212.01 ' "PCCW System Nalfunction"?- (1.0) l

a.

2 minutes ' f b.

5 minutes

e.

10 minutes . d.

20 minutes

- , QUESTION: 054 (1.00) f WHICH ONE (1) of the following correctly discriminates between a ,ctCamline rupture inside containment and a small break LOCA? (1.0) f a.

RCS temperature { I b.

RCS pressure c.

Containment temperature d.

Containment pressure

QUESTION: 055 (1.00) WHICH ONE (1) of the following symptoms and/or conditions may cause

Gntry into ON1233.01 " Loss of Condenser Vacuum"? (1.0) i a.- Increase in generator electrical output > b.

Increasing turbine exhaust hood temperature , c.

Increasing steam pressure to Gland sealing system d.

Start of the standby circulating water pump

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, -0~ REhCTOR OPERATOR Page 28 l . i QUESTION: 056 (1.00) . WHICN ONE (1) of the following conditions would indicate natural . circulation flow is occurring according to ERP-ES-0.1, " Reactor l Trip Response"? (1.0) < a.

RCS subcooling based on core exit T/cs is greater than i 15 degrees F , b.

RCS cold leg temperature is at saturation' temperature for 8/G pressure c.

8/G pressures are stable or increasing f d.

Core exit thermocouples - stable or increasing QUESTION: 057 (1.00) ! WHICH ONE (1) of the following times is the designed battery 'rocerve capacity for ensuring adequate power supply to the emergency 125VDC loads? (1.0) a.

TWO (2) hours b.

FOUR (4) hours

c.

SIX (6) hours ' d.

EIGHT (8) hours !

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~_ _ _ . _ __ __ ' ' .. . REACTOR OPERATOR Page 29 , I QUESTION:'059 (1.00) 'N WHICH ONE (1) of the following statements is a KEY CAUTION in ' , th3 operator action summary page for 081200.00, " Response to Fire

cr Fire Alarm Actuation"? (1.0) ~ l a.

GO To E-0 if the reactor is tripped and SI is NOT , initiated J b.

IF BA pump (s) are in use DO NOT allow BAT level to decrease to LESS THAN 50% c.

IF thermal barrier cooling NOT verified, maintain seal injection to ALL RCPs q d.

IF CST inventory is LOW, throttle EFW flow to steam generators to minimum value.

QUESTION: 059 (1.00) WHICH ONE -(1) of the following is NOT a required action per 081200.02 " Safe Shutdown and Cooldown from the Remote Safe Shutdown FCcilities" when the control room is evacuated for reasons other then fire? (1.0) , a.

Manually trip the reactor and turbine b.

Isolate main steam lines c.

Trip and pull to lock all RCPs d.

Place A and B train SSPS selector switches in TEST , l

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.

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. REACTOR OPERATOR Page 30 QUESTION: 060 (1.00) WHICH ONE (1) of the.following FRPs should have first priority if th y are all in a red path condition? (1.0)

a.

FR - P.1, " Response to Imminent Pressurised Thermal Shock Conditions" b.

FR - C.1, " Response to Inadequate Core Cooling" c.

FR - H.1, " Response to Loss of Secondary Heat Sink" d.

FR - 2.1, " Response to High Containment Pressure" . QUESTION: 061 (1.00) WHICH ONE (1) of the following conditions represents a RED path for core cooling? Assume Core Exit Thermocouples equal 900 dOgrees F and subcooling is 25 degrees F.

(1.0) . At Least One RVLIS RCP Running Full Range a.

no greater than 40% b.

yes greater than 40% c.

no less than 40% . d.

yes less than 40% j j . . - -..

. - - - - _ - - . -- '- . . . REACTOR OPERATOR Page 31 QUESTION: 062 (1.00) WHICH ONE (1) of the following.is the reason that all reactor C olant pumps are tripped according to FR-H.1, " Response to Loss of Heat Sink? (1.0) a.

To get increased safety injection flow by decreasing RCS cold leg pressure b.

To conserve reactor coolant inventory by reducing seal leak off c.

To conserve steam generator secondary inventory by reducing heat input to the RCS d.

To minimize the possibility of a tube rupture as EFW is restored to the S/G QUESTION: 063 (1.00) WHICH ONE (1) of the following is the correct action to recover from high RCS activity according to OS1202.05 nRCS High Activity"? - (1.0) ' a.

Increase VCT hydrogen concentration b.

Purge the VCT to remove non-condensible gases c.

Place the deborating domineralizer in service d.

Increase charging and letdown flow to maximum QUESTION: 064 (1.00) WHICH ONE (1) of the following is a symptom or entry condition for 081210.04, " Continuous Control Rod Withdrawal"? (1.0) a.

Detector current comparator alarm b.

VAS alarm control rod deviation c.

Delta I alarm d.

Rapid drop in RCS T-avg - - , . .. -. - -

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l REACTOR OPERATOR Page 32 , QUESTION: 065 (1.00) l-WHICH ONE (1) of the following situations requires a shutdown margin calculation be performed when a single control rod drops p;r 081210.05 " Dropped Rod"? (1.0) l a.

Prior to initiating a controlled shutdown ! b.

When the steam dump arming signal (C-7) has been reset , l c.

Prior to the dropped rod recovery 6.

When the dropped rod is realigned with the ' affected bank rods > QUESTION: 066 (1.00) WHICH ONE (1) of the following is the reason for verifying a turbine trip has occurred in Step 2 of ERP-E-0, " Reactor Trip or Safety , L Injection"? (1.0)

a.

Turbine trip signal is required to transfer AC bus power supplies b.

Reduces feedwater flow requirements I c.

Minimizes steam generator tube to shell delta-T d.

Prevents an uncontrolled cooldown l' QUESTION: 067 (1.00) WHICH ONE (1) of the following would NOT be an indication of a leaking pressurizer PORV per 081201.02 "RCS Leak"? ASSUME the bicek valve remains open.

(1.0) a.

Tailpipe temperature increasing b.

Acoustical monitor increasing c.

Containment. sump level increasing r d.

PRT temperature increasing lc - --

. .. ... - -. . _. - _.. . . e' REACTOR OPERATOR Page 33 l QUESTIONt-068 (1.00) WHICH ONE (1) of the following correctly states a reason for the rO2ctor coolant pump tripping criteria listed on the operator cation summary page of ERP-E-07 (1.0) , m.

Minimises two phase flow in a large break LOCA l b.

Conserves coolant inventory in a small break LOCA c.

Reduces overall plant electrical loads d.

Prevents accident consequence from exceeding 10CFR100 criteria , . ' QUESTION: 069 (1.00) - / / . WHICH ONE (1) of the,following is the cof,r act7, time / condition for l ' cntering ERP-ES-1.4 R'ecirculation"? (1.0) " Transfer to-Hots Leg? .')' N a.

16 hours after the OCA has/ occurred b.

Only if cold' leg recirculation flow is lost , Y 16,ho. 0urs a ser the Emergency Core Cooling Systems have c.

j been pgaced into cold leg recirculation , d.

Once t'he "RWST LEVEL LOW" annunciator alarms - /' ,/ - QUESTION: 070 (1.00) WHICH ONE (1) of the following RWST levels is the maximum level that requires that ERP-ES-1.3, " Transfer to Cold Leg Recirculation" b3 implemented if a large LOCA within containment is in progress? (1.0) a.

165,000 gallons b.

145,000 gallons , c.

125,000 gallons i d.

105,000 gallons ,. . --- -.

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. . ! . REACTOR OPERATOR Page 34 j i QU"sTION: 071' (1.00) WHICH ONE (1) of the following RCP lower bearing temperatures would i rcquire_ closure of the No. 1 seal leakoff valve if injection flow w;o.not available? (1.0)

i a.

150 degrees'F

1 - b.

195 degrees F c.

220 degrees F d.

295 degrees F- ! QUESTION: 072 (1.00) i WHICH ONE (1) of the following statements correctly completes tho sentence? During an ATWS-(Anticipated Transient Without Scram) with a loss of feedwater, the operator should..... (1.0) a.

"... leave the main turbine on line to provide a heat sink for the RCS."

b.

"... trip the main turbine to initiate a reactor trip."

, c.

"... leave the main turbine on line to reduce RCS pressure."

, d.

"... trip the main turbine to maintain steam generator inventory."

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-, REACTOR OPERATOR Page 35 t QUESTION: 073 (1.00) f WHICH ONE (1) of the following is ti.a purpose for procedure ERP FR-S.1, " Response to Nuclear Power Generation /ATWS"? (1.0) , a.

To restore the core to an adequately shutdown condition i-b.

To provide an alternate means of tripping the reactor c.

To provide guidance for initiating rapid boration d.

To add negative reactivity to a core which is critical when expected to be shutdown QUESTION: 074 (1.00) WHICH ONE (1) of the following is a possible automatic action if ,,, BOTH channels of Intermediate Range Nuclear Instrumentation (IRNI) fcil HIGH during a MODE 2 startup? (1.0) a.

Level trip switch on failed channels in DYPASS position b.

Source Range High Voltage de-energized c.

IR High Flux rod stop d.

Permissive P-10 energized QUESTION: 075 (1.00) WHICH ONE (1) of the following charging pump configurations is tho MINIMUM beyond which manual initiation of SI is required if prossuriser level is decreasing and a steam generator tube leak Cxists? ASSUME the plant is at 100% power.

(1.0) a.

ONE (1) CCP b.

TWO (2) CCPs c.

ONE (1) CCP and ONE (1) PDP d.

TWO (2) CCPs and ONE (1) PDP

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. .._ . ~ .-- _ _ _ - -- . . t j REACTOR OPERATOR Page 36 QUESTION: 076 (1.00) WHICH ONE (1) of the following is a reason for isolating all , f00dwater to a faulted steam generator? (1.0) a.

To reduce the probability of occurrence of a steam generator tube rupture in the faulted steam generator ! b.

To maximize the cooldown capability of the nonfaulted ' loops following a feedline break c.

To prevent all feedwater flow from entering the faulted steam generator and filling the generator, causing the PORVs to lift d.

To ensure the release to the environment . mains below the 10CFR100 limits on a design basis event ' > QUESTION: 077 (1.00) , While performing ERP-E-3, " Steam Generator Tube Rupture," prior to initiating the RCS cooldown, the SRO in charge directs you to datermine if the ruptured steam generator pressure is greater than 225 psig.

(If pressure is LESS than 225 psig,) ERP-E-3 directs you to transition to ECA-3.1, "SGTR With Loss of Reactor Coolant-Subcooled Recovery Desired."

WHICH ONE (1) of the following is the reason for ensuring the ruptured steam generator pressure is greater than 225 psig in this cose? (1.0) a.

To ensure the ruptured steam generator is not also faulted b.

To ensure the ruptured steam generator pressure is greater than the intact steam generator pressures c.

To ensure that a LOW steam line pressure safety injection does not occur d.

To ensure steam generator pressure is great enough to allow termination of break flow

, '

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' p . ~ REACTOR OPERATOR Page 37 i i ! QUESTION: 078- (1.00) WHICH ONE (1) of the following would cause a trip of BOTH Main

fCOdwater pumps? (1.0) ] l a.

Loss of non vital 125VDC b.

Loss of a 120VAC non vital panel PP-5 ) c.

Loss of a 120VAC vital instrument panel i d.

Loss of a vital 125VDC bus j .i QUESTION: 079 (1.00) WHICH ONE (1) of the following will result from a loss of DC bus

11A OR 11B7 (1.0) , a.

Loss of associated train diesel generator starting capability =b.

Loss of ON1233 RIS/HELB plasma display .i c.

Loss of control of CVCS makeup valves

d.

Loss of remote control capability of non vital 480V bus breakers QUESTION: 080 (1.00) WHICH ONE (1) of the following radiation monitors has automatic Cetions associated'with it per OS1252.03 " Area High Radiation"? (1.0) a.

RM6549, Spent fuel pool area monitor b.

RM6526-2, Containment Recirc Noble gas c.

RM6535B, Manipulator Crane Train B d.

RM6562, Fuel Storage Building Exhaust .. .

p-g'... . . REACTOR ~ OPERATOR Page 38-QUESTION: 081 (1.00)

WHICH ONE (1) of the following is NOT the correct indication to use, in conjunction with other plant indicators, to verify that the c

ntrolling pressuriser level channel has failed MIGH7 (1.0)

a.

Pressuriser heaters turn off b.

VAs high level alarm c.

UL-6 trip status lamp lit d.

Actual pressuriser level decreasing QUESTION: 082 (1.00) WHICH ONE (1) of the following fuel assembly locations will remain otvered on a loss of refueling cavity water? (1.0) a.

In transfer canal with refueling machine mast fully extended i b.

In upender and vertical c.

In transfer canal, unlatched, and horizontal on floor d.. In RCCA change fixture l l QUESTION: 083 (1.00) In-WHICH ONE (1) of the following time periods is the NRC required to be notified per 10CFR50.72 when a fuel handling accident occurs-with a release of radioactivity and an ALERT is declared? (1.0) a.

1 hour b.

4' hours -. l c.

8 hours d.

24 hours

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l . . , ' . I REACTOR OPERATOR Page 39 r

i ! QUESTION: 084 (1.00) . WHICH ONE (1) of the following CVC8 valves fails OPEN on a loss of

In3trument Air? (1.0) a.

PCV-8157 (VCT Pressure control valve) l b.

FCV-111A (Reactor make-up supply to blender)

c.

C8-V150 (Regenerative HX to Letdown HX) l ' d.

CS-PCV-131 (Letdown backpressure regulator) QUESTION: 085 (1.00) . A point source in the auxiliary building is reading 500 mrem /hr at O distance of TWO (2) feet.

TWO (2) options exist to complete a , tendatory assignment near this radiation source.

, OPTION lt Operator X can perform the assignment in thirty minutes i working at a distance of FOUR (4) feet from the point ' source.

OPTION 28 Operators Y and Z, using a special extension tool can l perform the same task in 75 minutes at a distance of ' EIGHT (8) feet from the point source.

WHICH ONE (1) of the following choices is the preferred option to . ocuplete the assignment, per the facility ALARA plan? (1.0) ' i-a.

Option 1 as X's exposure is 62.5 mrem ' - Option 1 as X's exposure is 125 mrem b.

c.

Option 2 as the exposure per person is 39 mrem

d.

Option 2 as the exposure per person is 156 mrem i I . , . . - __ _.

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.:. , i r REACTOR OPERATOR Page 40

QUESTION: 046- (2.00) ' MATCH the appropriate description in Column B with the RP 5.1

• Exposure Limit and Extension Request" allowable dose in Column A.

(2.0) COLUMN A COLUMN B l C.

100 mRom 1.

Quarterly NRC limit for exposure to

the extremities b.

200 mrem 2.

Quarterly Seabrook limit for personnel with unescorted RCA access o.

1000 mrem 3.

Quarterly NRC limit to whole body with complete exposure history d.' 3000 mrem 4.

Quarterly Seabrook administrative limit . 5.

Quarterly Seabrook limit for person without previous exposure estimate j 6.

Quarterly Seabrook limit for exposure to the skin d QUESTION: 087 (1.00) WHICH ONE (1) of the following is a qualified Level II tagger occording tx> MA 4.1 " Switching and Tagging List"? (1.0) l a.

Load dispatcher j l b.

Electrical supervisor l c.

Maintenance supervisor ] d.

Unit shift supervisor l l { l i L

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i L REACTOR OPERATOR Page 41 f QUESTION: 088 (1.00) WHICH ONE (1) of the following EOP procedures is entered ONLY by 'cp;rator judgement? (1.0) t I a.

E8 0.0 "Rediagnosis With SI in Service or Required"

b.

E8 0.1 " Reactor Trip Response" c.

E8 1.2 " Post LOCA Cooldown and Depressurization" , d.

ES 3.2 " Post 80TR Cooldown using Blowdown" ' QUESTION: 089 (1.00) l WHICH ONE (1) of the following in NOT a correct response for a rcdiation worker inside the RCA when he encounters an activated-rediation alarm per RP2.1 " General Radiation Worker Guidelines and ROCponsibilities? (1.0) a.

Report an activated monitoring device alarm and its location to the control room b.

Post the area immediately with radiation rope c.

Silence the alarm if authorized to do so by Health Physics or Operations personnel d.

Notify fellow workers in the monitored area of the alarm QUESTION: 090 (1.00) WHICH ONE (1) of the following represent the MINIMUM values of temperature or pressure, respectively, that require Two (2) valve iColation when working on a fluid or gas system? (1.0) , a.

150 degrees F, 500 psig b.

150 degrees F, 550 psig c.

200 degrees F, 500 psig d.

200 degrees F, 550 psig . _. - _ .

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REACTOR OPERATOR Page 42 s

QUESTION: 091 (1.00) WHICH ONE (1) of the following statements correctly applies

" Independent Verification" policy for initial verification of Components according to 081090.05; " Component Configuration C:ntrol"? (1.0) , a.

Independent Verification of a lineup can be performed by a trainee under the guidance of a qualified operator providing the qualified operator verifies the lineup a > second time b.

When Independent Verification is required on a system in a radiation area, the US/USS may allow both checks to be performed simultaneously to minimize exposure

c.

Independent verification of a system lineup may be performed utilizing control room indications d.

Independent Verification of a system lineup requires that components be locked in their required position after the position is verified for security reasons QUESTION: 092-(1.00) r WHICH ONE (1) of the following represents the MINIMUM number of m:mbers necessary to man the site fire brigade at all times, cocording to OPMM 2-1, " Shift composition"? ASSUME the plant is in MODE 1 operation and there are no unexpected absences.

(1.0) a.

THREE (3) b.

FOUR (4) c.

FIVE (5) d.

SIX (6) .- ---

__ _.

__ . ' . , . REACTOR OPERATOR Page 43 l QUESTION: 093 (1.00) ' WHICH ONE (1) of the following combinations correctly complete tho following statement? (1.0) C ndensate water chemistry is controlled by the chemical addition Cnd analysis system.

When the analysis indicates the need for Ch:mical addition, (1) is injected as an oxygen scavenger Cnd (2) is injected to control condensate pH level.

a.

(1) hydrazine (2) ammonia b.

(1) hydrogen (2) ammonia c.

(1) hydrazine (2) sodium hydroxide d.

(1) hydrogen (2) sodium hydroxide QUESTION: 094 (1.00) ASSUME that no' level indication is available in the control room to monitor Demin Water Tank storage level.

As the Control Room Oporator, you send an operator to check the tank locally.

The cporator reports back that he can hear water flowing through the ovorflow pipe beside the tank.

WHICH ONE (1) of the following is the correct AVAILABLE capacity in the tank based on the given information and the attached ttnk curve? (1.0) 198,500 gallons a.

~ b.

- 201,500 gallons c.

- 204,500 gallons d.

~ 207,500 gallons _

A.p 4 3 c., m

j i eopei.

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. . i ] .. REACTOR OPERATOR Page 44 , J-QUESTION: 095 (1.00) i WHICH ONE (1). of the following colors would you expect to see .grcphically displayed on the four center CRT's (VL-1, VL-2, VR-1, j VR-2) of the plant computer system if a monitored parameter were iG an ALARM status? (1.0) a.

Red b.

White c.

Cyan (high density) j d.

Magenta ' QUESTION: 096 (2.00) MATCH the type of tag in COLUMN A to the correct definition in COLUMN B.

(2.0) COLUMN A COLUMN B ........ ........ c.

Danger Tag 1.

Tags used on remote operators to I indicate that associated equipment is tagged < b.

Caution Tag 2.

Tags used to isolate systems and equipment to prevent personnel injury or equipment damage c.

Ground Tag 3.

Orange 2,5 by 6 inch three part tags , 4.

Tags used to provide additional instruction for equipment operation d.

Extension Control to prevent possible personnel injury , Tag or equipment damage l 5.

Tags used to identify a deficient indicating device, recorder or display on the Main Control Board 6.

Tags used to release material from a radiological control area J .. .. ._ _ _

, E. ' ' . REACTOR OPERATOR Page 45 - lp.. ' QUESTION: 097 (E.00) NATCH the loop descriptions in COLUMN B with the penetrations listed 10 COLUMN A.

(2.0) COLUMN A COLUMN B ........ ........ O.

Excess letdown 1.

Loop i hot leg b.

Normal charging 2.

Loop 1 crossover leg 0. - Pressuriser surge line 3.

Loop 1 cold leg d.

Normal letdown 4.

Loop 2 hot leg 5.

Loop 2 crossover leg 6.

Loop 2 cold leg 7.

Loop 3 hot leg 8.

Loop 3 crossover leg , 9.

Loop 3 cold leg i , 10. Loop 4 hot leg 11. Loop 4 cold leg 12. Loop 4 crossover leg (********** END OF EXAMINATION **********) i

i- } r = .. . t EQUATION SHEET -

,,,, f = ma y = s/t Cycle efficiency = (Net work cut)/(Energy in)

w = mg s = V,t + 1/2 at g. =2 i -

KE = 1/2 mv ,,gyy,y )fg.

A = LN A=Ae**

g n PE = ogn , Vf = V, + a t w = e/t A = in2/t-1/2 = 0.693/t1/2 - . ' w,, g.

, 'o2 t "' ifzeff a C(t m )( 4)) - A= ,, ((t1/2)*II)3 j b AE = 931 am .

A "*Y av * g. y "E" ,- .. Q = mCoat ' 6 = UAa T I = I t'"* . n I = I,10**/ M Pwr = 'd ah f ' TVL = 1.3/u sur(t) P = P,10 HYL = -0.693/u P = P e /T ' t o SUR = 26.06/T SCR=S/(1-K,ff) . . CR = S/(1 - K,ffx) . x . SUR = 26s/ t* + (s - s)T CR (1 - K,ffj) = CR (I ~ Ieff2) j

T = ( t*/c) + '[(s - o V Yo] M = 1/(1 - K,ff) = G /G, j , T = V(s - 8) M = (1 - K,ffe)/(1 - K,ffj) T = (s - e)/(Io) SDM = ( -K,ff)/K,ff

• " (E_afdbeff * #effM t' = 10 seconds eff

. , I. 0.1 seconds" . . = ((t=/(T K,ff)] + (a,ff (1 + IT)] / p !)d) = I d 2,2 2 P = (rev)/(3 x 1010) I)dj

gd

I = cN R/hr = (0.5 CE)/d (meters) R/hr =.6 CE/d2 (feet) Water Parameters Miscellaneous Conversions ' ' I gal. = 8.345 lem.

1 curie = 3.7 x 1010eps I ga]. = 3.78 liters i kg = 2.21 lbm 1 fe = 7.48 gal.

I hp = 2.54 x 103 Stu/hr Density = 62.4 lbm/ft3 1 m = 3.41 x loo Stu/hr Density = 1 cm/c..3 lin = 2.54 cm Heat of vaoorization = 970 Stu/lom

• F = 9/5'C + 32 dett of fus ten = laa Stu/ ttm

'C = 5/9 (*F-32) l 1 Atm = 14.7 osi = 29.9 in, dg.

I 870 = 778 ft-lbf I ft. H O = 0.4335 itf/in.

.. _ _ _,, .,- ~

' .* ' . , l > . , REACTOR OPERATOR ' Page 46 L ANSWERt 001 (1.00) , i 'd.

[+1.0)

! > REFCRtJNCE: ! s brooks Lesson' Plan Number L11131, " Rod control system", i section 3.2.6, " Design of the Rod Insertion Limit Monitor *, student objective 13. p. 20.

001000A302 (3.7/3.6) 001000K504 (4.3/4.7) i , 001000K504 001000A302 ..(KA's) . ANSWER 002 (1.00) d.

[+1.0) i

REFERENCE: ' S00 brook: Lesson Plan No. L11131, " Rod Control", Objective 19, p. 30-31.

001050F401 (3.4/3.8) 001000G007 (3.2/3.3) ' , i 001050K401~ 001000G007 ..(KA's) i i f ANSWER: 003 (1.00) d.- [+1.0) REFERENCE: . 80cbrookt Reactor Coolant Pumps, p. 33.

003000A201 (3.5/3.9) 003000A303 (3.2/3.2) 003000K602 (2.7/3.1) , 003000A201 003000A303 003000K602 ..(KA's) , t , l- ,

- - - - - -<,-. . - - - -. , - - - - - - - -, --,

_ _ , ! !

. . . ! REACTOR OPERATOR Page 47 i , AN;WER: 004 (1.00) b.

[+1.0) ' REFERENCE > Scabrook Lesson Plan Number-L11011, " Reactor Coolant Pump", Section 5.4.

800brookt " Precautions and Limitations", Student Objective 32, p.40.

003000K103 (3.3/3.6) 003000K103 ..(KA's) - ANSWER 005 (1.00) c.

[+1.0) REFERENCE COObrookt Lesson Plan Number L11011, " Reactor Coolant Pump", l Section 3.2.4, " Flywheel and Anti-Reverse-Rotation Device", Student Objective 29, p. 16.

003000G007 (3.2/3.3) 003000G007 ..(KA's) i j ANSWER: 006 (1.00) d.

-(+1.0) j REFERENCE , SOrbrookt Lesson Plan No. L11051, Objective 4.

800 brooks Chemical and Volume Control System, CS-51

004000K407 (3.0/3.3) 004010A305 (3.3/3.2) j 004000K407 004010A305 ..(KA's) i , - . __.

.

-- . .- - . - r

' . . , I . i REACTOR OPERATOR Page 48 ) ) , AN8WER: 007 (1.00) ' ! O.

[+1.0)

i REFERENCE j - CO: brook Lesson Plan Number L11081, "Pressuriser Pressure and i Level Control System", Fig. PPLC-4.11, 8tudent Objective 4 and 6, p. 34.

004000A302 (3.6/3.6) '

l i 004000A302 ..(KA's)

ANSWER 008 (1.00) r ' d.

[+1.0) ' REFERENCE ' SOCbrookt Lesson Plan No. L11051, "CVCS", Objectives 3 & 10, p. 23.

004010K606 (2.7/3.0)

004010K606 ..(KA's) ANSWERt 009 (1.00) o.

(+1.0) . REFERENCE 80cbrooks Integrated safeguards system, pp.23-24.

013000K401 (3.9/4.3) 013000K401 ..(KA's)

i ANSWER 010 (1.00) d.

[+1.0) , ... .. _ . _-. . - .. . .

.*... ' * " , - .. REACTORLOPERATOR Page'49 REFERENCE: . Sombrook s : Integrated Safeguards, p. 18-33.

013000A301 (3.7/3.9) 013000K101 (4.2/4.4)

013000A301 013000X101 ..(KA#s) . 'ANSWERt 011 (1.00) d.. [+1.0) REFERENCE:

e . . Seabrookt Lesson Plan Number L11131, " Rod Control", Student' Objective 5, p. 9-12.

l 015000A202 (3.1/3.5) 015000K103 (3.1/3.1) 015000K408 (3.4/3.7)

.015000A202 015000K103 015000K408.

..(KA's) ANSWER: 012 ,(1.00) a.

[+1.0) !

REFERENCE Seabrooks Lesson Plan-No. L11121, "Excore Nuclear Instrumentation",

Objective 6 & 11, p. 12 & 18.

015000K502 (2.7/2.9) 015000K407 (3.7/3.8) 015000K407 015000K502 ..(KA's) l ANSWER: 013 (1.00) a.-[+1.0) l l , , . .

_ . - - - -. ~ .

,,..s'

' < ,' 't: y& ! REACTOR OPERATOR" Page 50 - .

REFERENCE:-

8:abrook:; Incore' Instrumentation, p. 24.

i L Ctabrook:' Lesson Plan No. L1111I, objective 6.

b ' 015000A303 ;(3.9/3.9)? ~ t

015000A303

..(KA's).

. ANSWER:. 014, -(1.00) -b.

'[+1.0) l ' REFERENCE: } J ..

Cctbrook:

Excore' Nuclear Instruments, p. 13.

GOCbrook:' Lesson Plan;No. -L1112I, Objective 5.

015000K601 (2.9/3.2) 015000G007 (3.3/3.4) 015000G007 015000K601 ..(KA's) ' ANSWER: 015 (1.00)' b.

.[+1.0) i REFERENCE: i S32 brooks 'Contain~.stt.11710, r. 12.

' SCEbrook:- Lessol cita th, L1502I, Objective 4.. 022000A301 (4.1/4.R) l , 022000A301 ..(KA's) - ! - ANSWER:- 016 (1.00)' ' c.

[+1.0)- REFERENCE: Sacbrook: Lesson Plan No. L11281, "SGWLC", Objective 9, p. 23.

.Socbrook: Lesson Plan No. L13531, "Feedwater#, Objective 15, p.

49.

, ' 059000K419 (3.2/3.4) 059000K419 ..(KA's) l w,9

. ... . .. . .. ... 16,- 7,: ,' + 'y y , , u.

.; - REACTOR' OPERATOR.

Page 51 !

. i . ANSWER: .017 ( 1~. 0 0 ) - i d.- [+1.0].

. REFERENCER.

'Ccabrook:' Lesson Plan No. L13531, "Feedwater#, Objective 8 p.57.

059000K416 (3.1/3.2) 059000K416 ..(KA's) i ANSWER: 018 (1.00) [ ! 4.

[+1.0) ! REFERENCE: 83cbrooks Emergency Feedwater System, p. 26.

Soc. brooks Technical Specification 3.7.1.3, p. 3/4 7-6.

i 061000K401 (3.9/4.2) ' 061000K401 -..(KA's) ,

ANSWER:.

019 (1.00)

d.

[+1.0] REFERENCE: Ssabrook: Lesson Plan Number L11271, Student Objective 7.

Sacbrook:. Emergency Feedwater System, Section 4.1.2, "EFW Pump . Turbine Steam Valves (MS-V-393 and 394), p. 11.

' 0 610 0 0K4 02.,( 4. 5/ 4. 6) '061000K402 ..(KA's) , ANSWER: 020 (1.00).

a.

[+1.0) .. . -. . .

- t.

7,, = c - e - - t .. < l- -REACTOR OPERATOR Page152- ' REFERENCE: -f scabrooks Emergency Feedwater, p. EFW-11.

061000K201 (3.2/3.3) 061000K201' ..(KA's)

ANSWER:

021 (1.00)- E c.

[+1.0) -REFERENCE: ! 'Scabrook: Lesson Plan No. L11411, " Radiation Monitoring system", Objective 6, p. 45-Saabrook: Lesson Plan No. L11211, " Control Center HVAC", ! Objective 5,.p. 27)30 and 47.

! 072000K204 (3.3/3.5) 072000K403 (3.2/3.6) j l 072000K204 072000K403 ..(KA's)

i . ANSWER: 022 (1.00) I b.

.[+1.0) REFERENCES.

i scabrook: Lesson Plan Number L11011, student Objective 18.

fj Saabrook: Technical specifications Bases, Section 3/4.4.9, I ! " Pressure / Temperature Limits, p. B 3/4-7.

0 02 0 0 0G0 0 6 ' (2. 6/.3. 0) - 002000G006 ..(KA's) i ANSWER: 023 (1.00) } l 'c.

[+1.0) < i

-:_.-__________-__-_____-_ . _ _ _ _. _ _ _ _ _ - - _ _

. . - .. , t . . .-v '

. ;

.1 - q

4 RRACTOR OPERATOit - Page 53 ' ' REFERENCE !

COmbrook:LEmergency Core Cooling System, ECC-25.

- 006020A302 (3.9/4.2) .i 006020A302 ..(KA's) l . ' . ANSWER: 024 (1.00) .b.. [+1.0)- .> I . REFERENCE: ' Socbrooks Lesson Plan Number L11161, " Emergency Core Cooling a System", Section 3.4, " Accumulator Tanks", Student Objective 7, p. 18.

, ' 006020K603 (3.0/3.2) 006000K602-(3.4/3.9) 006000A301-(4.0/3.9) i ' 006000K602 006000A301 006020K603 ..(KA's) ,

ANSWER:-

025 -(1.00) d.= [+1.0) . ' REFERENCE: Soabrook: Lesson Plan No. L1108I, Objective 6 & 14.

r Scabrook: Pressurizer Pressure Control System, p. 16.

, 010000A302 (3.6/3.5) i .010000A302 ..(KA's) ' ANSWER: .026 (1.00) $ la.. [+1.0) <

i !

m

)

e '*~

. 4, l*

-i .' , , , d4

' REACTOR OPERATOR- ~ Page 54 / t i 1 REFERENCE: [ " .Stabrooks Lesson Plan No. L11081, . v r . "Pressuriser Pressure and Level t Control", Objective 11.& 12, p. 19.

010000K4031(3.8/4.1) 010000A403 (4.0/3.8) , ! 010000A403-010000K403 ..(KA's) Ji

, t ANSWER: '027 (1.00).

! cc.

[+1.0) ' REFERENCE: Socbrooks-Lesson Plan Number L11081, " Pressurizer Pressure and-Level control System", Section 5.3, " Plant Response to a Pressurizer Level Channel Failure", Student Objective .. 14, p. 43.

'011000A210.(3.4/3.6) i 011000A210 ..'(KA's) ANSWER: 028 (1.00) l c...[+1.0] ' REFERENCE: Socbrook: Pressurizer Pressure Control, p.

9.

- 80cbrook: ' Lesson Plan No. L1108I, Objective 8.

' - 010000K201 (3.0/3.4) 010000K201 ..(KA's) . ANSWER: '029 (1.00) -a.

.[+1.0] l l . . - - - . .

. _ _ _.__ ___ - ' . ,

, v.

M'

. ,., T e ;s ! .RRACTOR OPERATOR-Page-55-s m ,_ REFERENCES-t ' COdbrook: ~ Lesson Plan'No.

L1108I, objective 5.

I

' _80abrook Technical Specification-Bases, p. B 2-6.

1 0110 00K512 - (2.7/3. 3) 011000G006 (2. 6/3. 7 ) - , t

011000G006' 011000K512 ..~ ( KA ' s ) , . ANSWER:' 030 ( 1~. 0 0 ) i b.- [+1.0) REFERENCE: ' '800 brook: Reactor Protection System, p. RP-34.

012000A101~(2.9/3.4); 012000K611 (2. 9/2. 9 ) ; 012000A205 (3.1/3.2)

012000A205 012000K611' 012000A101 ..(KA's) t-ANSWER: 0 3 1-(1.00) '1 idA [+1.0]" " -REFERENCE ' Scabrook: Lesson Plan No. L11381, " Reactor Protection System", - Objective 2, p.- 12 & 43.

) ' 012000A406 (4.3/4.3) 012000A406 ..(KA's) ' 1 ANSWER: 032 (1.00) a.

[+1.0) .

. .- _.

_ ___ . _ , $,.i c

..,e.

J'. ? - _ REACTOR OPERATOR- 'Page 56 's , ,

REFERENCE

< , . !stabrooks Lesson Plan No. L11381, " Reactor Protection System", ' Objectives 10,.11, &'22, pp._12-14.. 012000K401 (3.7/4.0).012000K408 (2.8/3.3) '" ! '012000K408 012000K401 ..(KA's) l ,

i ANDWER: _ 033 ( l'. 0 0 )

c. - [+1.0) y REFERENCE: i Sochrook Containment Building Spray, p. CBS-29.

026000A401-(4.5/4.3)

026000A401 ..(KA's) ' ANSWER: - 034 (1.00)

b.. _(+1.0] I REFERENCE: 'Ssebrook:. Lesson Plan No. L11171,-Objective 5 & 6.

'Stabrook: Containment Building Spray, p. CBS-7.

02 6000K4 02 ~ (3.1/3. 6) 026000G007 (3.5/3.7)' , - f'

026000K402 026000G007 ..~(KA's) ANSWER: 035 (1.00)

l b.

_t+1.0) i L l ' - - - - - - - - -

a.

[-.. ; ' i , je ?' 1 REACTOR OPERATOR: -Page157 . REFERENCE:L <s x l 'COcbrooksiLesson' Plan' Number.L10971, #125 VDC Distribution System", D.

Table:EDC-4.5, Student Objective 2 and 4, p. 20.

063000K201. (2.9/3.1) ~ ' . ! i '063000K201 ..(KA's) ANSWER:. 036 (1.00) b.

.[+1.0) l

REFERENCE: ,

Sscbrook: Lesson. Plan Number L11001, Student. Objective 22.

l Emergency Diesel Mechanical, Section 4.1.1,

1. Remote

.! Controls", p.

24~.. I '064000K402 (3.9/4.2) . 064000K402 ..(KA's) u ~l-ANSWER: 037 (1.00) ..j - b.

'[+1.0) -j ' REFERENCE:' Sachrook:. Lesson Plan No. L11001, " Emergency Diesel Electrical", l Objective 21, p. 20.

064000A307~-(3.6/3.7) -l } 064000A307 ..(KA's) l q . . ANSWER: 038 - (1. 0 0 ) n.

[+1.0)

. f-i t j ! . . . . -- -- - --a

, .- . -.. .- .-. .. .. .,' .,:i

,.

.s.

REACTOR OPERATOR Page 58 < l REFERENCE: ' ' .. Sotbrooks Control. center HVAC, pp. 5-15.

Ocabrooks Radiation. Monitoring System p. 45.

l .00tbrook Lesson Plan No. L-1141I, Objective 6.

.l 073000K101 (3.6/3.9) 073000K101 ..(KA's)

ANSWER:

039 (1.00) -b.. -[+1.0).

!

REFERENCES.

ssabrook:

Lesson Plan L11021,? Objective 10.

, -Saabrook: -Pressurizer and PRT, pp. 8 & 30.

, 194001K115 (3.4/3.8) 194001K115- ..(KA's) ' ANSWER: 040 _(1.00) b.

[+1.0)-

i REFERENCE:. Soabrook: Lesson Plan No.;L11021, Objective 1.

l-Sacbrook: Pressurizer and PRT, p.

8.

~ 007000K103 '(3. 0/3. 2) - , i.

007000K103 ..(KA's)

1 ' ANSWER: 041 (1.00) s., as. - [+1. 0 )' l .l ' i -.

,, .,, .- - _~ _. -. - - - - -. ~ . -. ~- - . ' l. b ~ ' h- )(',7 Le ( , , th

. REACTOR OPERATOR ~Page 59 ) .i ' REFERENCE C0abrooks' Primary-Component cooling, pp. CC-33 & 34.

-8:abrook Lesson Plan No. L11181, Objective 12.

F 008030A304-(3.6/3.7)- 008030A304.

..(KA's) <. ' ANSWER: -042 (1.00) ' b. _ - [+1. 0 ) ' .. -l cREFERENCE: . ' Se.sebrook: Lesson Plan No. L11181, "POCW", Objective 3, pp. 30-32.

008000K102 (3.3/3.4)- .l 008000K102 ..(KA's) P ANSWER:. 043 .(1.00)

b.

[+1. 0 ) - -REFERENCE: ' SOS. brook. Lesson Plan Number L11291, Objective 11.

Scabrook:.. Steam = Dump System, p. 26.

041020K411. (2.8/3.1) ' 0 4102 0K414 ' {2. 5/2.8) t 041020K411 041020K414 ..(KA's)

< , iANSWER: 044 (1.00) c.. ~ [+1. 0 ] - ! .I g . . .. . - .

_.

'- - - _, k 0-7 J... ifi & . ' , > REACTOR' OPERATOR-Page 60- .; ' REFERENCE: Seabrook: 081215.05, p.

4.

c C0abrooks Lesson-Plan'No. L1142, Objective 3.

L 034000A102 ' (2.9/3.7) 034000A102 ..(KA's)

' m ' ANSWER: 045 (1.00) ? C.' [+1.0)' , REFERENCE: , L80abrook: Lesson Plan.No. L11191, " Service Water", Objective 11, p.- 11-12.

< 076000K402 (2.9/3.2) 076000K406 (2.8/3.2) < . ( 076000K406-076000K402 ..(KA's) , ANSWER: 046.(1.00) c.

.[+1.0)'

' REFERENCE: . s Ssabrook:' Lesson Plan No. L11191, " Service' Water", Objective 10

& 11, p.'12.

, '076000G008' (2.8/2.9) ,{ .076000G008 ..(KA's)

! ' ANSWER: 047-(1.00) =a.

[+1.0) i i

- _ .. -, _ _. . _._ _ _ _ _ _.. .. k < g j } L oe.

. REACTOR OPERATOR.

Page 61~ '! EREFERENCE ' Secbrooks Lesson: Plan No. L11041, " Service Air and Instrument Air", Objective 12,~p'.32-34.

. 078000K403 (3.1/3.3) 078000G010 (2.8/2.9) ' i 078000K403 078000G010 ..(KA's) i ANSWER 048 (1.00)l . ! 10.

[+1.0] " REFERENCE: Sanbrooks; Lesson plan No. L11851, Objective 3.

Sotbrooks'- 081210.06 " Misaligned Control Rod".

000005G011 ( 3'. 5/ 3. 6 ) 000005K303 (3.6/4.1) ' '000005G011 000005K303 ..(KA's) < L . ANSWER: 049 (1.00) > a. - [+1.0] REFERENCE: Stabrook: Lesson' Plan No.'L11841,' Objective 6..

S$2 brook:

0S1210.02 000005K306 (3.9/4.2) ' '000005K306' ..(KA's) s ANSWER:- 050: (1.00) -

.b.

.[+1.0)

' REFERENCE :-

- 'Ssabrook: 081201.01 p.

4.

' ' l 000015K303 (3.7/4.0) 000015K303 ..(KA's) ! c j - . - - . - - .. .

. - .. . .. - -. - - n.., Ja , , - n ..o , . .. R .ici REACTOR OPERATOR Page 62 . LANSWER ; 051 .(1.00) , ~ d.

[+1.0) REFERENCE: Stabrooks' Lesson Plan Number L11011, Student Objective 37.

scabrooks -081201.01, "RCP Malfunction", 10/14/88.

.-000015A208 ' (3. 4/3. 5)1000015G011 (3. 5/3. 6) ,' ' '000015A208 000015G011 ..(KA's) ANSWER:: '052 (1.00)- ' b.' [+1.0]' s REFERENCE:

Sacbrook:

LessonLPlan No. L11831, Objective 10, Sc& brook: 081202.04 p.

4.

'000024K302 ~(4.2/4.4) 000024A205 (3.3/3.9) 000024A205-000024K302 ..(KA's) ANSWER: -053.

(1.00) c.

[+1.0) L REFERENCE:

'ssnbrook :- 081212.01 p.

1.

~000026A206 (2. 8/3.1) 000026K303 (4.0/4.2) '000026K303 000026A206 ..(KA's)

' ANSWER

054 (1.00) a. -[+1.0]' > l ' l -. ' i , ?f

, .- - - -. - . - . -.. A' " ' _ i ,

<-

i

REACTOR OPERATOR'

Page'63-L i REFERENCE:-

>+ " l80abrooks E-0, " Reactor. Trip or Safety' Injection" p.13 1000040A203 (4.6/4.7) < t D i . - 000040A203.

..(KA's) e - [ ANSWER: 055 (1.00) -b.

. [+1. 0 ).

REFERENCE: - l Ocabrook: Lesson Plan No. L11801, Objective 3.

A Scabrooks ON1233.01 .! 00 0051G011: (2.7/2.9) , i 000051G011 '..(KA's) ! ' ANSWER:~ O'56 (1.00) b.c[+1.0) ' REFERENCE: Scabrook: Lesson Plan No. L1200I, Objective 8.

ssebrook: ERP ES-0.1, Attachment A.

000055A202.(4.4/4.6) i 000055A202 ..(KA's) ' ANSWER:' 057 (1.00) , n.

[+1.0)

J . l - -.a, - - -, --__.-------- - -- --_. - - - - - - - - - - - _ - - - -

. -.. -. .. - , . , o n 4-a , f L*i , . REACTOR OPERATOR .Page 64 .- r; / REFERENCE: ' 80abrook: 125VDC Distribution System,Lp. EDC-31.

000055K101 (2.7/3.4)

000055K301- ..(KA's)

c

. ANSWER:- 058 (1.00) o.

[+1.0) . ' REFERENCE: Ocabrook: Lesson Plan No. L1191I, Objective 4.

• Dochrook:

081200.00 t 000067K304 (3.3/4.1) , 000067K304 ..(KA's) l < > ' ANSWER:. 059 (1.00) '

d.-

[+1. 0 ]- REFERENCE: , l . . 'Seabrook:. 081200.02 I 000068K318 (4.2/4.' 5) , , l '000068K318 ..(KA's) i ! i.

a l ANSWER: 060 (1.00) , l .i l ' l l- 'b.- [+1.0]

1' l, , .- l i: ' , de

.7 - - . - ,.

' ', > p., e 16 %. a4 <

' .. -c , ' . . . t. I' t L HREACTOR OPERATOR-Page.65 j f 'REFERENCEt.

.dOmbroo': Lesson Plan No. L11961, Objectives ifE 3.

k 50abrooks-OP.9.2 , 000074G012 (4.3/4.4).

' i . 000074G012 ..(Kh's) . , ! , + ANSWER:- !_ . 061 (1.00) l " 0.. [+1.0) ~ .i REFERENCE: '

Scabrook:. EOP FR-C.1'# Response to Inadequate Core Cooling".

, 80abrooks: Critical Safety Function, F-0.2 " Core Cooling".

~300074G012 (4.3/4.4)-000074G011 (4.5/4.6) ' 000074G011 000074G012 '..(KA's) .i s LANSWER: ' ~ 062' (1.00) L c.

[+1.0) L L* ~ REFERENCE: 280cbrook Lesson-Plan No.'L1211I,. Objective 7.

i 0cabrook s : Basis Document EOP FR-H.1, Step 3.

1: '000074K304 (3.9/4.6) l: 000074K304 .. ( KAs ) ! l ' . ANSWER: '063l (1.00) .d.' -[+1.0] -.';_ , _ - I

. g . 5.

.. m l: e r

- REACTOR' OPERATOR, Page 66 - REFERENCE: i; i-Scabrook 081202.05, "RCS High Activity".

.s brooks Lesson Plan No. L11841, objective 8.

.000076K306 (3.2/3.8)'

000076K306 ..(KA's) ANSWER: 064 (1.00)

c.-

[+1.0] ' REFERENCE: Sctbrook: Lesson Plan No..L11841, Objective 3.

S chrooks- 081210.04

000001K122 ' (3.2/3. 6) 000001A2 051 ( 4. 4/ 4. 6 ) l 'l-000001K122 000001A205 ..(KA's) , ANSWER:- 065 (1.00) i

! c.- [+1.0] 'i ' REFERENCE, 8sabrook:. OS1210.05 pp.

1-2.

, ' ' 000003K304 (3.8/4.1) 000003K304 ..(KA's) j '

ANSWER

066: (1.00) d.- [+1 ~. 0 ]

.

hh.c !*'- K ' '* M,>,.4 .. .. ' , ., : h _ , ,REAOTOR OPERATOR Page'67 , , . REFERENCE: I , -i ' Scabrooks-Lesson Plan No. L1200I, Objective-2.

- Seabrook: Basis Document for ERP-E-0.

KA=000007K301 (4. 0/4. 6) ; 000007A202 (4.3/4.6) , , L 000007K301 000007A202 ..(KA#s) .

ANSWERi 067 (1.00)

0.. (+1.0) ~ . i REFERENCE: ' SOtbrook 081201.02 "RCS Leak", p.

1.

.000008A203 (3.9/3.9) 00000B A22 0 (3. 4/3. 6) 000008A220 000008A203 ..(KA's) _e ANSWER:. 068 (1.00) -b.

[+1.0) REFERENCE: Seebrookt' Basis-Document'for " Reactor Trip or Safety' Injection" ERP E-0.

-Sctbrooks Lesson Plan No. L1200I, Objective 3.

.000009K323 '(4.2/4.1) l 000009K323 ..(KA's) ANSWER: 069' 1.00) /6a?; ,,, - /

-.. . - - - - - - - - - - l

.,. ___ ._ _ __ _____ l (.;;.;.i ..: . \\~ l .. L.

. REACTOR. OPERATOR Page 68 ' / REFERENCE: , f CO;brookt[L on Plan No.'L1203I, Objectives 3 & 4.

' scabroci t jp(4.2/4.2), j - E-1 p. 15.

0000

p 11A111 ..(KA's) cANSWER: 070 (1.00) l .. &. , E- [+1.0] , ' REFERENCE Scabrookt . Lesson Plan No. L1203I, Objective 4.

LSOObrookt- .ERP-E-1, Foldout page step 4.

000011K315. (4. 3/4. 3) , 000011K315.

... ( KA r s ) - c ANSWER-071 (1.00)

c.

[+1.0]- - - ' -REFERENCE: SOEbrooks .OS1202.02 p.

2.

. 0 0 0 022K3 02 -- (3. 5/3. 8) 000022A109 (3.2/3.3) 000022A109 000022K302 ..(KA's) - ANSWER: 072 (1.00) 4- .d.: ' [+1.0] .. $

---

u------- .s - -- - - ,

.. - _. -. - .. ' ? - 3;;. Q ;.': ' ' - T REACTOR OPERATOR.

Page 69 ! ~MEFERENCE: COmbrook: ' Lesson Plan No. L11951, Objective 14.

CCabrooks FR-8.1 Bases.

000029K312 (4.4/4.7).

000029K312 ..(KA's) j ANSWER : 073 (1.00) d.

[+1.0] REFERENCE: Sotbrook: Lesson Plan No.

L1200I, Objective 4.

80cbrooks ERP-FR-S.1, " Response to Nuclear Power Generation /ATWS".

p.

1.

000029G011 (4.4/4.6).

000029G011 ..(KA's)

ANSWER: 074 (1.00)- o.

[+1.0]. - e-REFERENCE: - SOcbrooks Excore Nuclear Instrumentation Systems (NI), 3.2.2.

' 000033A202 -(3.3/3.6)

-000033A202 ..(KA's) i ANSWER: 075 (1.00) 8.- [+1.0) , _ _

_ _ _ _ _ _ _ _ _, _ _ _ - - _ _ _ _ _ _ _ _ _ - - _ - - _ _ _ _ - - _ _ - - _ - _ _ _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ _, > . v- .;, , t I !. 41: c-i, -,: c+ - ,p.

lc . ;- p , REACTOR' OPERATOR Page 70 , . t ' REFERENCE .Scabrook 081227.02 p.

1.

- -000037K305,(3 7/4.0) 000037K305 ..(KA's) , ' ANSWER:- 076 (1.00) 'b.. [+1.0): y - i REFERENCE Scabrook: Basis Document for ERP-E-2.

~ f Scabrook Lesson-Plan No. L1207I, Objectives 1 & 4.

-l 000038K306 (4.2/4.5) { i-

000038K306 -..(KA's) . l i .!

-ANShER 077 (1.00) ' i a.

-[+1.0) i } ! REFERENCE ' . . i Saabrooks ERP-E-3 p.12.

! 000038K301.(4.1/4.3).

-i 000038K301 ..(KA's) v ., ANSWER: 078 (1.00) b.- [+1.0)-

I l

.. .- --- - K '.

k; i.....: , ' '

g '* , REACTOR OPERATOR' -Page 71 , t REFERENCES.

' 80abrooks' ON12 4 7 '. 0 3 ~ p. 5.

000054G011 (3.4/3.3) 000054A202 (4.1/4.4) f' 000054G011 000054A202 ..(KA's) . ^1NSWER t.

079 (1.00)

, o ,

a.

.[+1.0) -REFERENCE:

SOabrook: Lesson Plan.No. L10971,. Objective 4.

SOabrook: 0S1248.01 p.1.

000058A203 (3.5/3.9) . e 000058A203 ..(KA's) t - ' ANSWER:; 080 (1.00)- .c.

[+1.0) . REFERENCE: Scabrook: Radiation' Monitoring System, pp. 44-45.. , . .Ssabrook:- Lesson Plan No..L1141I, Objective 6.

S$abrooks-OS1252.04 p.

3.

_ . 081252.03 p.4.- , '000061G010 (3.3/3.3) I 000061G010 ..(KA's) ' ANSWER: 081 (1.00) a.- [+1.0) - - . . -. - - -

. _ __ _ ._ , l'. +

, .. + a .,.,. ! , - .- , 'RRACTOR' OPERATOR' Page-72

i ' (REFERENCE: ' CCabrook:. Lesson Plan No. 1108I,' Objective 14.

! , 'Ocabrooks PressuriserfPressure and Level' Control p. 44.

000028A201 (3.4/3.6) 000028A210 (3.3/3.4) 000028G010 (3.5/3.7)

000 02 8'A210. 000028A201 .000028G010 ..(KA's) . AN;WER:- 082 (1.00) O.

[+1. 0 ] ; REFERENCE: i Gotbrook:' ,Ssabrook: ~ Lesson Plan No. L1142I, Objectives 2 & 3.

Lesson Plan No. L1192I,' Objective 6.

. Ocabrook:. 081215.05 p.

2.

00003 6K101 - (3.~5/4.1)

000036K201 (2.9/3.5) 000036K201.

000036K101 ..(KA's) ! ANSWER:. 083' (1.00) L c.

.' ' [+1' 0).

. ' REFERENCE: Socbrook:. Lesson Plan No. L15071, Objectives 2.& 5.

'83Obrook:' OS1215.06;p.:1.

- 000036G002- (2.7/3.7) 000036G002 ..(KA's) r L ANSWER: 084 (1.00) 1.

, l a.> [+1.0) REFERENCE: Ostbrook: ON1242.01 p. 4 & 5.

1000065A208 (2.9/3.1) 000065A208- ..(KA's) L .. -. - - . - - - - - - - .

_ _ i-

.

, i. e -; ~ T' . lEEACTOR OPERATOR .Page 73~ ' i ANSWER: 085-(1.00) , G.: [+1.0) t REFERENCE: socbrooks Lesson Plan No.

L1506I, Objective 2.

- COchrook: RP'2.1 " General. Radiation Worker Guidelines" p 4.

, 19 4 001K10 4. (3. 3/3. 5 ), 194001K104 ..(KA's)

ANSWER: 086-(2.00) ! . a.- '2- [+0.5] b.

[+0. 5] - ' c.

[+0.5] d.

[+0.5] . REFERENCE:' .

-Scabrook :.RP 5.'1 p. 4-10.

[ 194001K103 (2.8/3.4) - ' . 194001K103- ..(KA's) t ' ANSWER: 087-(1.00) d.- [+1.0] t , .i ,x ' * f

,

~ .j ,s.

< , c.[:.1 ' ' 'e . ' 4; } , < REACTOR OPERATOR Page 74: ] k IREFERENCE : ! E i ) 'ICcabrook: MA 4.1 " switching and Tagging List", p.

3.

' ' ~ Ocabrook: Lesson Plan No.~ L1501I, Objective 14.

i 194001K102 (3.7/4.1) 194001K102 ...(KA's) g , . . ., iANSWER - 088 (1.00)' 10.

[+1.0] i REFERENCE: Cocbrook Lesson Plan L11951, Objective 14 scabrook:: EOP Users Guide,.0P 9.2 p. 14.

1194001A116.(3.1/4.4)

194001A116

..(KA's) " ANSWER:, 089~ (1.00)

.b.

[+1.0] ' REFERENCE: schbrook: RP~2.1,-p.

6.

, 194001K103 (2. 8/3. 4 ) ' ,. 194001K103 ..(KA's) L i ANSWER: 090 (1.00) , c.

[+1.0)

i REFERENCE: ~ -sochrook MA 4.2, p.

9.

. ssebrooks:. Lesson Plan No. L1510I, Objective 17.

194001K108'(3;5/3.4) 194001K109 (3.4/3.4) r 194001K108 194001K109 ..(KA's)

s - , - - - -.. . - - - - - . -. - - - - - -

??

f.

C e ! ' 4 ',

o s if ;.L ' , P . REACTOR OP3RATORI Page 75 , i {: '! LANSWER: 091- (1.00) , b.

[+1.0)~ ,, k-REFERENCE: I I 8cabrooks- 081090.05 p.

4.

194001K101 (3.6/3.7) ~194001K101 ..(Kh's) l AN3WER:" .092 (1.00) i ' e c.

[+1.0) ! ! -' REFERENCE: ' Seebrook: OPMM 2-1 p.

1.. 194001K116 (3.5/4.2) . 194001K116 .. - ( KA ' s ) - I l .- ANSWER: 093! ;(1.00) l^ .0.

[+1.0) t l ' REFERENCE: 'S03 brooks-Condensate System, p. 13.

l Ostbrook: = Lesson Plan No. L10511, Objective 5.

j 194001A114 ' (2.5/2.9) ! ' i i , p 194001A114 ..(KA's) ! i

i - ANSWER: 094, (1.00) .a.. [+1.0) ! ! l , ) l

i I

..,- - . _.

--- ._

-> /*

..

• -

-r L

• '

' x.- o , f 4.. ' REACTOR-OPERATOR Page 76' l-REFERENCE: ' scabrook:~ Domin Water Tank Curve, DM-TK-109.

194001R108 (2. 6/3.1).

194001A108 ..(KA's).

, ANSWER: 095 (1.00) Ji > d.: -[+1.0) . REFERENCE: scabrook: Lesson Plan L10881, Objective 5.

Occbrook Station' Computer, SC 24 & 39.

] '194001A115 ( 3 ~.1/ 4. 4 ) 194001A115 ...(KA's)

ANSWERt' 096- (2.00) ~

a.-.2.- [+0.5] !b.- 4.

[+0.5] i c.

3.

[+0.5]

d.

1.

~[+0;5] REFERENCE :- S3Obrook MAL 4.2 p.

4-5.

. . 1' Seabrook: Specific Task Training Matrix - Control Room-Operator.p. 716.

194001K102 (3.7/4.1) c194001K102- ..(KA's) ,/ ANSWER: 097 (2.00) h c.- 9.

[+0.5] y b.. 3.

[+0.5] - c.- ~7.

[+0.5] d.

8.

[+0.5] l ., . ' , .

. - _ _.. , .- ,, i s

REACTOR OPERATOR Page 77

_, REFERENCE sembrook: Lesson Plan No. L11011, " Reactor Coolant System", Objective 2, p. 12 and figure RCS 3.8.

002000K106 (3.7/4.0) 002000K109 (4.1/4.1) _

002000K109 002000K106 ..(KA's) E ] r % .

- =

=5

Id , , , (********** END OF EXAMINATION **********)

r.

-- . i-g. ., RancTOR CPERAT03 P g3

. AN8WER SNEET Multiple Choice (circle or X your choice) Xf you change your answer, write your selection in the blank.

, 001 a b c d i f 002 a b c d ! 003 a b c d I 004 a b c d , 005 a b c d i-006 a b c d '! 007.

a b c d 003 m b o o

1. 009 a

b c d - ' 010 a o c a l _ ~01! a b c d . 012 a b c d i ' __ 013 a b c d ' 014 a b c d . 015 a b c d ' 016 a b c d i 017 a b c d j 018 a-b o d 019 a b c d 020 a b c d

021 a-b c d - ~022.

a b o d 023 .a b o d i 024 a b c d 025 a b c d

> . . . .. . .. _..._

.. _.. .. _ _ _ __.

, L .-

.. REACTom CPERATo3 PCg3

. t AN5NER SXEET Multiple choice (circle or X your choice) i If you change your answer, write your selection in the blank.

026 a b c d 027 a b c d ! 028 m b c d i , 029 a b c d

030 a b c d 031 a b c d i 032 a b c d ' . 033 a b c d 034 a b c d ' 035 a b c d ( ___ ,

036 a

b c d , F '037 m b c d - - , 038' a b c d ___ ' ' 039 a b c d c 040 a b c d ' lI y ' 04.1, a.

b c d i 042 a b c d

043 a b-c d ' l l 044 a b c d 045 a b c d ! 046 a b c d 047 a b c d ' 048 a b c d

049 a b o d 050 a b c d l t. .- ._ ..

i . l j, :, : C . RBhCTOR CPERATOR P;g3

, AN8WER SMEET , i j ' Multiple choice . circle or X your choice) ( ~ If you change your answer, write your, selection in the blank.

! 051 a b c d 052 a b c d I, .. 053 a b c d 054 a b o d-1 055 a b c d 056 a b c d , 057 a b c d oss a b

a !

7

. 059 a b c d 060' a b o d _ , OH-a b o

i , CG2 % b c

.> 063 a b c, d - _ 064 a b c d 065 a b c d

' 066' a b c d 067 a b c d ' -068 a b c d t t .069 a b o d , > 070 a b c d 071' a b c d E 072 a b c d 073 a b c d i i 074 a b-c d 075 a b c d

, - - - .- -..

.e:o i RRhCTOR CPERATOR P!.g3

,s l , ' AMSWER SMEET ! l Multiple. Choice (circle ci X your choice) i If you change your answer, write your selection in the blank.

l 076-a b c d ! 077 a b c d i 078 a b o d 079 a b c d , 080 a b c d i ! 081 a b c d 082 a b c d 083 a b c d _,_ 084 a b o o

.,.

-085 A b a d , OSd' natch with se) coted nur.ber in the blank , a _ _ _ b , _. _ _ C -.. d P 087 a b c d . 088 a b c d 089 a b c d P 090 a b c d _, t 091 a b c d i 092' a b c d 093-a b c d 094 a b c d 095 a b c d >

- - - , ,

. ! . .... , , REACTOR CPERhTOR p;g3

o

AN5WER SMEET ! ! 095-match with selected number in the blank i !

' a i b e

C i ! d i 097 match with selected number in the blank , & l b ! c _ d i

I i k i t ( , , h , i i i p , t ! , (********** END OF EXAMINATION **********) . \\ , l.

' - - _ .

.-- - , , i e s' REACT 03 CPERATOR P;g3

l AN8WER KEY i ) l

001

002

003~ d I a 004 b i 00s c

006' d l 007 o 008

009' c 010

- 011

012 c.

- 4 013 c.

,. - 014 b-r ' 015 b 016 a 017 d 018 d 019 d , 020 d 021 a ' 022 b 023 c 024 b 025 d t . .. ... _.,,. _ _- ._ _ _ _ _., .. _, ,.

, l l e .# RR&CTOR CPERATOR P293 2 ! i O &N8WER KEY I i ! i I 026 a I i.- 027 a j -

028 a '029 a 030 b i 031 d j 032 a ! 033 c

034-b

035 b 036 b , 0?? h 036 a 039 b , 040 b '

,

! 041 d i - f 042 b 043 b 044 c 045 o l .046 c , . . 047 a

= t= ' 048 a ~" 049 a 050 b ! l h . . - - -.-, . -

- . - .... - - -- . . ! l o ' a e XEACTOR CPERATOR PCg3

j o ANSWER KEY

i

] r 051 d ] f 052 b 053 c 054 a 055 b , 056 b , 057 a ! 058 c , 059 d - , 060 b 061 c . 062 o 063-d 064 o 065 o 066 d ) 067 c > . 068 b

/) /,f

-,.4 4 L, /

- ' w-

070 g6 C// '

.071 c 072 d < 073 d ? 074 c ! ' 075 a , y - - - -, ,-. - .

j + i'L- .i, o- ! REkoTOR CPERhTOR P;g3, 4 o' !. AN8WER KEY

i i 074 b l 077 a 078.

b 079 a 080 c 081 a I 082 e

083 a- ~ i 084 .d 085 a 086 match with selected number in the blank i a

1 ,

b

1 c

d

087 d i 088 a 089 b r l < 090 c 091 b 092 c ' J093 a-L '094 a .'095 d l-

< <

\\ . ,, -- - -. - - -, - - -,, .- . - -. -

. _ _.. . - .- _ -.- _ .. - . - _ e __ i , f A,, - c. . . RB&CT03 CPZRATOR p;go

{

- m AN8WER KEY t l , J , t 096 match with selected number in the blank a

b

) c

, d

' 097 match with selected number in the blank ! a

l b

, s c

d

t i .i . I ,

i l' 1^

) (********** END OF EXAMINATION **********) ' l n% y~~' ; N - < - - - .c . . . . . }}