ML20044B072

Exam Rept 50-461/OL-90-03 on 900604-08.Exam Results:Seven of Nine Senior Reactor Operator,Four of Six Reactor Operators & Two of Three Crews Passed Exam

ML20044B072
Person / Time
Site:	Clinton
Issue date:	07/06/1990
From:	Jordan M, Rau E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20044B070	List: ML20044B069 ML20044B072
References
50-461-OL-90-03, 50-461-OL-90-3, NUDOCS 9007170274
Download: ML20044B072 (80)

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,pe, U.S. NUCLEAR REGULATORY COMMISSION t REGION 111 s [' Report No. '50-461/0L-90, Dociet No. : 50-461-v Licensee: lilinois Power Company Facility Name:- Clinton Power Station i Examination Administered at: Clinton Power Station ~ Examination' Conducted:~ June 4d,1990- -Chief Examiner: [a -7 /fo Eddief4tij F Date h 0b ~ 7 /b Approved By:- M. 'J. Jpd/ni Date Examination Summary 4 Examination administered during week of-June 4. 1990 (Report No. 50-461/0L-90-03)).' ~ R Written-and operating requalification examinaticos were administered to nine ' Senior ~keactorOperators.(SR0s)andsixReactorOperators(R00).-TwoOperating Crews and one Staff Crew were evaluated during.the simulator portion of the: operating' examination. Results: Seven of nine SR0s; four.of six.R0s; and two of'the three Crews hassedtheexamination.;All;failureswerearesultofperformanceonthe simulator; JThe~ facility results matched those of the NRC.. l Independent grading by. facility and individual / crew performance results satisfied the criteria of NUREG 1021.-Rev 5. Based on this, the Clinton ,w Station Operator Requalification Program is assigned an overall rating of' Ll satisfactory. - i 65 l is W.s y 9007170274 900710 PDR ADOCK 05000461 V -- PDC ,j 3

y,, [ ,. W s: (h, -. !.gf,6 - f 'l fi y r t th 4, REPORT DETAILS p q [ 1. 'Examinerj j 7 E. Rau,. Chief Examiner, NRC Region 111 T. Morgaa, INEL C. Ty9er, INEL O 2. 'Pers9ns Contacted e L ~ J. S. Perry, Vice President - R. W. Morgenstern, Manager-SOM

• J. D. Palmer, Manager-NTD F. A. Spangenberg, Manager-Licensing & Safety h

tP. D.L.Yocum, Director-0perations

• H. W. Lyon Supervisor Requalification I
• D.Antonelli, Director 4 Ops Training.

+ h R.'T. Kerestes Nuclear Station Engineer e [L J.- Greenwood, Maneger Power Supply-Soyland S. Paige Hall, Director-NPAG' .t 9,. K. A. Baker.. Supervisor-l&E Interf ace y J. Kouski, Senior Instructor-0Ps i

• P. G. Brochman, Ser.ior Resident inspector-NRC E

n All individuals listed aboVe were.present at the management exit meeting a . conducted onl.)une 8,'1990. In addition, tbo a individuals marked by an asterisk were present for a training department pre exit briefirg. y:. y

3.

Operator Performance a p . The following strengths and weaknesses were identified for the~ crewsL a.. and individuals that passed the.NRC Requelification Examination.. i + Factors contributing to Crew and Individual failures are presented in Section'4 of: this report. (1) Strengths g s' Comunications . Knowledge of Interlocks. Ability to use. alternate / multiple indications j, SR0 board manipulations 'l e Taking conservative actions 0 f Pressure and level control during ATWS l o

(2) Weaknesses ~

(a) Failure to prepare for a manual scram (b) Lack of E0P placekeeping 4 h li ' r i 2 ,j. ,"o h

J ' t ,g e .f I, ? -O f i W[ 4.- FactorsContrjbutingtoFailures b a. The following items were identified as factors contributing to both the individual and crew failures. >(1) Lack of identified control room command (2 R0s and STA's not assertive in communications RO's and STA's not involved in decision making o SRO's not aware of safety-related parameter trends f, No one person was directing E0P implementation g

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Training Department a. Generally, the quality of the facility examination material was good. The following deficiencies were noted during the examination F process. 1, (1) Several JPM's which should have been identified as time. h critical were not identified as such. (2) JPM questions were not task related and had to be extensively revised during the examination development g w. b. The training department was very receptive to correcting all material.related deficiencies identified by the NRC as a result of m the examination ~ process. c. One item of concern was nr,ted during the examination process. This it was a' failure of three individuals to abide by the requirements of the examination security agreement.. Once.in effect, the security. agreement requires that ao instruction of the operators to be examined be conducted Py those individuals under the agreement. Eventhough indiviouais had signed the agreement they provided some instruction, not directly relatcd to the Requalification Program, to the operators, Although no compromise of the examination was Q identified, you should be sensitive to-this issue. 'l 6.. Simulator Fidelity al Simulator Fidelity will be discussed in Attachment 1 to this report. [> 7.- Procedural Deficiencies a ~ a. Instructions for reset of reactor scram with fuel damage present are not p.roceduralized. b. No procedural guidance exists for fast reactor shutdown 1 (preparationsformanualscram). b i 3 p. b' 5

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[m c. -Remote shutdown procedure steps should emphasize coordinating 4 conjuctions(or,.and,if). Refer to E0P-Writer's Guide for details. 8. Human Factors Deficiencies a. When a diesel generator is paralleled and the synchroscope switch is turned off the diesel will trip. Since turning off tie Sync switch is a step normally associated with the completion of parelleling operations, the potential for inadvertent M trips is presented. It is recommended that,.as a minimum, an operator aid y be instituted. c .9. Exit Meeting A pre-exit briefing, with the utility training staff, and a formal management exit meeting was conducted on June 8, 1990.' The individuals who attended the meetings are listed in Section 2 of this report. During the exit'all items contained in this report, with the exception of item 5.c, were discussed in detail. Item 5.c was discovered after the formal exit and was subsequently. discussed with the training staff. The facility was also informed that examination results were preliminary, pending regional management review, ' J In addition to the report details, the facility was informed of the-a requirement to remove all examination failures from shift and-remediate all defiencies prior to resumption of licensed duties. T \\. a I i i 4

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pg c T % y s:' n'- lQil 'iV+ [ f a i. h' .c p f' e P + .g_ 2 +,p t 3< Enclosure'3 ,;4 'REQUALFICATION PROGRAM EVALUATION Facility:. 'Clinton Power Station Chief Examiner: E. D.' Rau t s Dates of EUAluationi June 4-8, 1990

y Areas Evaluated

; Written, Oral, and Simulator d

LExamination Results:- R0 SRO Total Evaluation t Pass / Fail Pass / Fail Pass / Fail' (S. M, or U) m Written Examination. 6/0-9/0 15/0 - Operating Examkation"

Oral, 6/0 9/0 15/0.

S i Simulator' 4/2-7/2 11/4 S I Evaluation of[ Facility Written Examination Gradirig: 'S 4-Crew Examination Results Crew 1 Crew 2' Crew 3-- Evaluation Pass / Fail Pass / Fail-Pass / Fail' (S,'M;'or U)2 m Fail . Pass; Pass-S: Overall Program Evaluation . S'atisf actory - ,1, ,u r A 'Ic 3 - Submitted: Forwarded pprov ' tau ( Jordan @h gh . Examiner Section Unief . Branch Chief 7/6/90 7//M/90 4 7//0 /90' / ,.n '}.

{3f f.[oy*'. dh;ph %d ;, g v. - Enclosure 4 ao ' ti s S SIMULATION FIDEllTY REPORT p u-- l l' Facility Licensee: Illinois Power Company, Clinton [xD Facility Licensee Docket No.:50-461 en 0perating Test-Administered At: Clinton Simulation Facility ,m 'During the examination the Response of the' simulator to the ATWS Event-and the Q RPV Flood Evolution were excellent. -However, the following non-fidelities Ll,, pg _f were' observed:.. Eg < + ~ ITEM 4 .r k,._ (1) RCIC trips on overspeed when shutdown from remote shutdown panel. 1c y ~~ (2) Indications observed for. leak ~from RCIC Steam P.iping NOT consistent with ~ expected system response. v. L(3) During.a recirculation flow decrease Feedwater Control System response was sluggish resulting:in a level 8 trip g,f '(4)'.During'maingeneratorsynch. Both running & Incoming voltage meters ?4 ' indicate pegged.- .-(5)..-Interlocks preventing paralleling of the ERAT, RAT.and DG were not ' functional. L,y ~ m 6: t 1c(is m b 'O h 4% i t' .j ~ s; e 1 00 !. R ,j v

n y C; 4 f. **, Q@bTb CLINTON POWER STATION LICENSED OPERATOR REQUALIFICATION EXAMINATION COVER SIIEET PLANT PROFICIENCY (STATIC) SRO X RO X_ EXAM NO: SS-\\B ) F# ASTER CO3 fC DATE: /e/F0 APPROVED: [- I .1 i t .\\ \\

r l, N s REQUALIFICATION WRITTEN EXAMINATION RULES q, a 1. Print your name on the cover sheet of the examination. 2. Print your name, social security number and date in the blanks provided on the answer shcot. 3. Answer each question on the answer sheet provided. If additional paper is required, use the examination. 4. Use black ink or dark pencil ONLY to facilitate legible reproductions. If your change an answer, erase completely or cross out, initial and date. S. The point va'lue for eac'h question is indicated on each question. 6. Unless solicited, the location of references need not be stated. 7. If parts of the examination are not clear with respect to their intent, ask questions of the examiner only. j 8. In the' simulator, due to the existence of questions that will require all examinees to refer to the same indications or controls, particular caro must be taken to maintain individual examination security and avoid any possibility of compromise or appearance of cheating. Close procedures and change computer displays on PMS when you.are through with a

question, 9.

Each section of the examination is designed to take approximately 90 minutes to complete. You will be given two hours to completo each section for a total of four hours. 10. Passing criteria is 80% of the total score of the Limits & Controls and Static examinations. 11. You must sign the statement on the answer sheet that indicates the work on the examination is your own and that you have not received or been given any assistance in completing the examination. This must be signed AFTER the examination has been completed. 12. Rest room trips are tc be lir.ited and only one examinee at a timo may leave. You mu0t avoid all contact with anyone outside the examination room to avoid even the appearance or possibility of examination compromise. 13. Cheating on the examination would result in a revocation of your license and could result in more sovero penalties. 14. When you are finished and have turned in your completed examination, leave the examination area.

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SUMMARY

SIIEET U, y =,. + 4 M . SCENARIO NO: SS-18.

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, INITIAL CONDITIONS - i h t c-y y y,: he plant was at '1006 power when a major. plant, event occurred.. The ) OlQ- ^ Combustible cas Control System Compressor IB is tagged out for. l l compressor replacement. l ~ C ' )p- { l h, 1]; ,p;4 1 + w .m . OPERATOR ACTIONS TAKEN, 1 D4 i V6, ;., '}. Silenced, acknowledged and reset annunciators g - i n. v+ q Reactor mode: switch in Shutdown '+ J' i a } y jf ' i ? l-.. V'M-6, i TROCEDURES USED: -1.AST STEP TAKEN j 4 1 -4 e r $s. i., CPS <Ho.-4100.01, Rev. 8-P 3,1-1~ o s~ y: y i s - i h , 9.. 7;- SIMULATOR DEFICIENCIES CORRECTIVE ACTION TAKEN 1 }x ;, N/A. N/A 'a , _ = f ' t ,:df y-OUESTIONS NOT RElATED TO EVENT f 4-j b SS-18 04 'i w f v 1 9 6 1-i Page.- 5 5 P ly 4 -~ ~~"

o a n 70' "1 s y, -1 n "l y ~ k.'..- 4 g ,, a 5. +y 11 CLINTON POVFR STATION B s ^'- PIANT. OPERATIONS (STATIC) SRO X' RO,_X j y l c, i ~ QUESTION-NUMBERi-SS 18 01-POINTS: 01 What is the 'cause of the RAD CSF box on the SPDS Display? ,,I. i i. . Secondary Containment Area Temperature High aj Secondary ) .a. Containment Floor Drain Sump High High' Level. b. Stack HVAC release rate at the Alert level a,ILd Secondary 'l F Containment Floor Drain Sump High High Level. 1 6 . Secondary Containment Differential Temperature High and Secondary c.- ,; ~ Containment Low Differential Pressur., d. Reactor Pressure Vessel Pressure aj Containment Pressure. j e d ) p te i 3 ti;, ) et a 3 'l .j av t-s ..i-t ..'t /' t 4 s l', ~s 2 ..t [ i !.1 ~[ I f. t ~lIEVIS10H NO:- 1 5

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QUESTION: NUMBER:

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,)' .1 . 'i' 3' L - CLINTON POWER STATION. 1 1 - PIANT OPERATIONS. (STATIC)- SRO X RO ,2,,, ..e y, i QUESTION: NUMBER:. SS 18 03 POINTS: 0. $ 0,,,,,, 1

Select the reason.for the initiating event based on current plant conditions.

The:"D" Main Steam'Line is. ruptured.inside the'Drywell. -a. b.~ The Reactor Water Cleanup (RWCU)' piping has-ruptured.in a RWCU! pump: room. .o. . Plant Chill Water (VO) to Containment Steam Tunnel is isolated..

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'reedwater piping, has ruptured outside the Containment. th, -; 1[

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I ' el f j IA g I' ( g{; W ( 'C1.INTON. POWER STATION. .,a - o . PLANT OPERATIONS (STATIC) U L SRO X R0 1 7 g a-li e* QUESTION NUMBER: 'SS 18-04 POINTS: 0.50 c.- A 1 Based on present conditions of the Diesel Generators, select the required L ': ' action. a. Within two hours, perform CPS No. 9082.01 and at least once per 8 hours thereafter. b. Within one hour, perform CPS No.. 9082.01 and at least once per 8 m +"a hours thereafter; ~ Perform CPS No. 9080.01.and 9080.02 on-the. L" O remaining operable diesel generators separately within 24 hours, i es Perform CPS No; 9080.01 on diesel generator 1A 31 days from now. d.- Be'in at least Hot Shutdown within 12 hours and cold shutdown .within the following 24 hours. s t

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u. PLANT OPEPATIONS (STATIC) m SRO

' I _-- RO - X 4 - QUESTION NUMBER: SS.18 13 POINTS: 0.50 Determine thei cause'of the Reactor Recirculatim puupsLtrip. s" .High Reactor Pressure Vessel-(RPV) pressure.- a. b '.. Loss of. power.

c.

Low RPV LeveI.'.~ Level 2. y . d-Pumps are transferring to slow epeed. . r: }.

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( - 6 i 'i ; 'c.g'. 3 b 1 1 l{ \\ ' 5' r' i ${. k f x I e j. I .I l*g w i :l REVISION No: '0-ig.

w }_:J;6.'.L CLINTGN PSWER STATION ) LICENSED OPERATOR REQUALIFICATION ANSWER SHEET C ',t iiI,_. NAME: DATE. ciasi3 oni) (mi) (mm) au) (w) ', SOCIAL SECURITY NUMBER: EXAM NO. SS 18 GRADED BY: SCORE: o INSTRUCTIONS: COMPLETELY DARKEN THE APPROPRIATE LETTER FOR YOUR i RESPONSE. ERASE ERRORS COMPLETEC( TO PRECLUDE MISSING THE QUESTION. SS 18-01 tu Ibl(c)id) SS 18-02 lal N [cl[d] SS-18-03 lal[b](c) M SS-18-04 lal M IclIdl SS-18-06 lalIbl M Idl SS-18-07,5lb)Icl(dl SS-18-09 talIbl(c) M SS 11 lal (b) (c) M SS-18. I 2 lal M (c) (dl SS-18-13 m Ibl(c)(d) ,,l M Signature below cortifics that the work on this examination is (ny own and that I have not received Y .or boon given any assistance in completing this examination. (sign af ter exam completion) / o wm om ,i

CLINTON POWER STATION i LICENSED OPERATOR REQUALIFICATION EXAMINATION COVER SHEET i PLANT PROFICIENCY (STATIC) SRO X RO X EXAM NO.:55; N i l 4 M S ER COP NAME: .5 !Nd APPROVED: -M /// DATE: / t t

d REQUALIFICATION WRITTiti EXAMINATION RULES 1 1. Print your name on the cover sheet of the examination. 2. Print your name, social security number and date in the blanks provided on the answer sheet. 3. Answer each question on the answer sheet provided. If additional paper is required, use the examination. n 4. Use black ink or dark pencil ONLY to facilitats legible reproductions. If your change an answer, erase completely or cross out, initial and date. 5. The point va'lue for each question is indicated on each question. p 6. Unless solicited, the location of references need not be-stated.

• /.

If parts of the examination are not clear with respect to their intent, ask questions of the examiner only. 8. In the simulator, due to the existence of questions that will require all examinees to refer to the same' indications or y controls, particular' care must be taken to maintain individual examination security and avoid any possibility of compromise or appearance of cheating. Close procedures and change computcr-displays on PMS when you are through with a question. 9. Each section of the examination is designed to take r approximately 90 minutes to complete. You will be given two I hours to complete each section for a total of fcur hours. a 10. passing critoria is 80% of the total score of the Limits & Controls and Static examinations. e 11. You must sign the statement on the answer sheet that indicates the work on the examination is your own and that you have not received or been given any assistance in completing the examination. This must be signed AFTER the examination has been completed. 12. Rest room trips are to be limited and only one examinee at a l time may leave. You must avoid all contact with anyone j outside the examination room to avoid even the appearance or possibility of examination compromise. 13. Cheating on the examination would result in a revocation of your license and could result in more severe penalties. 14. When you are finished and have turned in your completed examination, leave the examination area. I

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.g o 1 2. 1 fi SIMULATOR OPERATIONS ~ F-

SUMMARY

SilEET' i 1 L -SCENARIO NO:- SS-19 j INITIAL CONDITIONS The plant was at 1006' power when the "B" Control Rod Drive (CRD) Pump'. tripped..The A" CRD Pump could not be started in time before the ', !

reactor was scrammed'by placing.the mode switch to " Shutdown" per'the-Tschnical-Specification:for Inoper.tble Accumulators.

i v: QffEA* LOR ACTIQNS TAV,JH a'. Mode-Switch to Shutdown. b. Silenced, acknowledged and roset annunciators PROCEDURES USED. IAST STEP TAKEN CPS No.14100.01, Rev, 8' Step 3.1~ 1 i SIMULATOR DEFICIENCIES CORRECTIVE ACTION TAKEN Nono. N/A ! OUESTIONS NOT REIATED TO SVENT -None: Page 5 . ?. Na -

cs .( 9'., .c CI.INTON PO'JER STATION ' PLANT OPERATIONS (STATIC) N SRO ' ' X RO X -j QUESTION NUMBER: SS 19 0 L POINTS: 0.50 Based on present plant conditions, the status of the Alternate Rod insertion / Recirculation Pump Trip System 1 and 2 is: Both system 1 and 2 have initiated and can be reset, a. b. Both system 1 and 2 have initiated and the 2 minute timer has not timed out. 1 I Both system 1 and 2. have initiated but valves F403A and B should c. t i be shut, d. Both system 1 and 2 have initiated but valves F402A and B, and' F403A and B should be' shut. .l ) ~ I, I i t , = w -)> REVISION'NO: 0

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s, j. s _.g dy &), w, y, ! - The _ Reactor: Feed Pumps tripped-on: t.- .u. s m. w a.f law.$uction Header Pressure. g p %<-w L, '.m.., m.'

b, High

reactor water level.

w ,5 t '1 ) + hkj[y 1 ~ ' Reactor Coro Isolation Cooling (RCIC).Valvef(E51A T013)cnot; fully L c.1 L & M f. 4" ' closed and'RCIC flow greater..than 120 gpm. m -.c 7-g:z / ,U. I -d - Main Condenser Low Vacuum yn d. L, e. w.< f:. -L +.t h ., - n', I .-.),- , p. h)f m + m.m [& i: m. o ~. >' l) 6 ,i'm k fi " -?{ om _ '/

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. PIANT OPERATIONS L (STATIC) - i r +L

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4 (: .q, 8 'b rw ? f r ,--) li = + ,jL Jg l QUESTION NUMBER: SS-19 03 POINTS: 0.50 -{ Ai. ,'1 M, . t ' M ~ J ~

The. Reactor Recirculation Pumps : tripped off on:

..,[ N t . Lo'ss ~ of. power to: low speed circuit 'on: downshif t. ' Y m' a. } cry,.' b. ' Reactor water level lov :1AVel 2. s +y m l fc. .ltigh Reactor Pressure of 1127 psig. 'd.' ' i. Low delta T Steam' Dome / Recirculation' Loop Suetiont t S 4 -i .. -p 4 3 .y 1 5 g., s j w -h.cp 1 a?: 'u s .7' 1 3 3] 4 6: Q si

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t 6L QUESTION NUMBER: SS 19 Of>- - POINTS: 0.50-4 ,. Based on Jthe current ' conditions, what is the. cause. of the. Average Power Range-EMonitor (APRM) Upscale LTrip. annunciators?. y ,1 j a. A reduction.in reactor recirculation flow due-to:the' pumps .m* tripped. p . b., Lessi than?l6 Local Power Range Monitor (LPRM)1 inputs per ' channel.. 7 4 t A c. Reactor Mode Switch in SHUTDOWN.- React' r Core Isolation Cooling (RCIC) injecting cold water. d., o / .r i::. ' ;u f., " g j

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.1 15 l ., 8 r l g; l i i g.: W, i lM .. REVISION NO: 0

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• l CLINTON POWER STATION PLANT OPERATIONS (STATIC)

SRO X RO __X__ -QUESTION NUMBER: SS-19 07 POINTS: 0.50 Which one of the methods listed below is available for control rod insertion for the plant conditions as they exist now? Activate the backup Alternate Rod Insertion (ARI) System, a. b. Reset reactor scram and manual scram, c. Reset reactor scram and doenergize the Reactor Protection System (RPS) scram solenoids. d. Vent-the Control Rod Drive (CRD) withdrawal' lines. j. i REVISION N0i o

b .')' y y s'., m =

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SRO' X

'RO X '0l1-ij b m t s. ...,, :e p t ,jy I n l_N l d: .9 .e.,i ' REVISION NO: 1 o. II,. ,di.

7 - i 0+. o p- ' + ; - i.- ,'4 dd T, 1 s ,, J.? o CLINTON POWER STATION = j o Ef-[ PLANT OPERATIONS-(STATIC) SRO X-RO X t on ', y. a f. \\ li : QUESTION NUMBER: SS-19 ll-L - POINTS: 0.50 i

Procedurely you are directs.d to restore 6HD maintain Reactor Pressure Vessel level between-level 3 and Level 8.

Assuming the 'A' Control Rod Drive pump . can be successfully started, what other systems are available and could be. used to maintain level based on plant conditions that oresentiv exist.. ~ a {l( a.. Reactor Core Isolation Cooling (RCIC) and either A or B Turbine - Driven Reactor feed pump. i> b. RCIC and Low Pressure Core Spray (LPCS). 4-RCIC and the Motor Driven Reactor Feed pump, c. d. .RCIC and High= Pressure Core Spray (HPCSl .7 n[: lY + 4 ? .-t t s l 1 o

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, PLANT OPERATIONS'(STATIC)- q._, ; .p . SRO'. 'X RO.,_K._ %;a.. % s t; 4 ,y >n. :, c >1 r pl.1 j i,. ?rm 1 t i , QUESTION NUMBER: SS-19 12 _ 1 1 sc POINT.S : 0.50 -4 : ) + ). I ' Based on. present_ plant conditions. and with no further operator action!. which 1 e . of the-following will' occur? a,. y y Main Steam-Isolation Valves will isolate on low = main condenser- 'a. Vacuum, - .I ]E ~ Main' Steam-Isolation Valves will isolate 1on loss.'of instrument b.-

air,i "l

- 7, -.1 ~ ' Hain Steam. Isolation Valves will isolate on level I; c, I a .j Main' Steam Isolation Valves will-isolate on high drywellipressure, d,- u s t I t i t !

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PLANT; OPERATIONS (-(STATIC) -

l/,, i Slio '1 { R. O- X + n Y' 4} T u i 2 j2 . $\\f \\b I?: -d,a - - t ~~ r l90EST10NLNUMBERn SS-19 13 POINTS: 0.50'- -,.'~ 1i 1 +.' N"

Why is'the Division III' Diesel'Cenerator running?-

j 1 c -r ;, ; ~ a; Reactor Pressure Vessel low level at, level 2.' vna 'l i 1d p ' c .b.. i 4160 Volt bus :101 undervoltage, ye i .c. - High Drywell) Pressure.-- 4 A;6 . Manual" initiation'of Division'III'. d,- .H e i

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• g CLINTON POWER STATION PLANT OPERATIONS-(STATIC)

't SRO X RO X i t o, .1 t . QUESTION NUMBER: SS-19 14 POINTS: 0.50 t Which of th,e following is the cause.of the current status of train A Standby'Cas Treatment. pg,}4e -- t a. Exhaust fan 0/;02CA tripped. b' Did not receive an initiat on signal. i 6 c. Train inlet damper OVC0 failed closed. d.. Deluge. valve 1SX071A is open. L-e e Y .i r l.

l l-1 3

J lI REVISION NO: 0. i

s - CLINTON POWER STATION r- 'fn LICENSED OPERATOR REQUALIFICATION ANSWER SHEET' E,..,,uq NAME: .DATE: (last) (test) (mi)' (mm) (of) (w) -SOCIAL SECURITY NUMBER: l EXAM NO.SS-19 ' GRADED BY: SCORE: INSTRUCTIONS: COMPLETELY DARKEN THE APPROPRIATE LETTER FOR YOUR-RESPONSE. ERASE ERRORS COMPLETELY TO PRECLUDE MISSit4G THE QUESTION. i SS-19-01 I tal RilIcl[dl ' S S-19-02 lal M (c) id) SS-19-03 lal titll IclIdl 3 LSS-19-06 lal (b) 11R Idl j! SS-19-07 i SS-19-09 115l lbl [c] (d) S S-19-'11 ~ lalIblRilIdl. SS-19-12 lalIbl15 (d) SS-19-13 pel(bl(c)id) S S 1 -1 21lbl (c) (di .) My sigr.ature below certifies that the work on this examination is my own and that I have not received ) or been given any assistance in completing this examination. (sign af ter exam completion) / \\ SQ0alure Date I

,../,k,. 'd? @S CLINTON POWER STATION ~ ' LICENSED OPERATOR REQUALIFICATION EXAMINATION COVER SHEET LIMITS-AND CONTROL EXAMINATION SRO RO N i ' EXAM NO: lo M l l I O STER CO3Y l i NAME: b -APPROVED: ( G DATE: f 1

j* ld? l i j t REQUALIFICATION WRITTEN EXAMINATION RULES' Print your name' on: the cover sheet of the examination. 1. g 2. Print your name, social s6curity number and date in the blanks provided on the answer sheet. Answer each question on the answer sheet provided. If j, 3. additional paper is required, use the examination. i Use b?.ack-ink or dark pencil ONLY to facilitate legible I 4. reproductions.. If your change an answer, erase completely or ~ 4 1nitial and dat'e. cross out, 5. - The point value ' for each' question is indicated xxi.each i question.: t 6. Unless solicited, the location of references need not be stated. 7. If; parts of the examination are not clear with respect to their intent, ask questions of the examiner only. 'c 8. In.the' simulator, due t.o the existence of questions that will; 'I . require all e,xaminees to refer to the same indications,or_ controls, particular care must be taken to maintain q 'individualsexamination' security and avoi'd any possibility;of ~ y compromise !or appearance of cheating. Close procedures and-change computer displays on'PMS when you are,through with a ~ s question. 9' Each section of the examination is designed to take i: approximately,90; minutes to complete. You will.be given two hours to complete cach ~section for a total of fourihours. y o 10. Passing critoria is 80% of the total score of the' Limits & Controls and Static examinations. 11. You must sign the statement on the answer sheet that indicates the work on the examination is your own and that you have not received or been given any assistance in completing the examination. This must be signed AFTGR the examination has been completed. 12. Rest room trips are to be limited and only one examinee at a time may leave. You must avoid all contact with anyone outside~ the examination room to avoid even the appearance or possibility of examination compromise. i-13. - Cheating on the examination would result in a revocation of / yourxlicense and could result in more severe penalties. 14. When you are finished and have turned in your completed examination, leave the examination area.

l ti ' CLINTON POWER-STATION-LIMITS AND CONTROLS. SRO-X RO _){_. QUESTION NUMBER: LC-011 POINTS:. 0.50 t The.following plant conditions exist:- The reactor has been manually scrammed. The reactor pressure vessel temperature is 450*F. Lake level has reached 675' MSL. From.the following listed methods of plant cooldown, w).lch would .be utilized for the existing plant conditions listed above? Use of the. Main Condenser Bypass Jack. a. j b. ' Adjusting the pressure setpoint of the Steam Bypaestand '-t Pressure Control System. Adjusting Reactor Core Isolation Cooling System-(RCIC) c.

flow, d.

) Residual' Heat Removal (RHR). system operating in the - Shutdown Cooling Mode. i 1 1 i-REVISION HO: 2 9

.o l .r <+ .i CLINTON POWER STATION LIMITS AND CONTROLS lq .i SRO X RO X y i j QUESTION: __ LC-013 POINTS: 0.50 i, i The Plant is in a normal shutdown condition. Severe weather i has been predicted by the local weather services and all~on-site personnel have been alerted-of this-possibility. l Sometime later meteorical data indicates straight line winds- ] sustained at 77 miles per hour with_ HQ tornado sightings. 1 What is the proper E-Plan classification for this event? .i 3 a. Notification of Unusual Event b. Alert Site. Area Emergency c. d. General Emergency 1 4 + i f I i + f . REVISION MO: 1 A

Ig r ,,1; CLINTON POWER STATIO" LIMITS AND CONTROLS .SRO _X = RO _,X._- QUESTION NUMBER:. LC-016' POINTS:- u0.50 ..1 i Following a: Loss of Coolant Accident (LOCA) and subsequent Reactor SCRAM the following conditions exist: Suppression Pool Temperature 120'F. Suppression Pool Level 17'4". Drywell Presstire 2.5 psig. Drywell Temperature 310*F. Reactor Water Level - 110" (wide range). t For the aboveilisted plant-conditions, what operator action is required? Emergency Reactor Pressure Vessel (RPV) a- -Depressurization-i b. Emergency RPV Depressurization and'RPV' Flooding i Start one Combustible Gas Control System (CGCS) c. i Compressor p d. Initiate the Suppression Pool Makeup System I i 'I i i i a REVISION NO: 1

7.

d i

I CLINTON POWER STATION LIMITS AND CONTROLS l SRO X RO X i V QUESTION'HUMBER:' LC-026 POINTS: 0.50 Given the plant conditions provided below, determine what i operator action is required in accordance with Containment { Control: -t Standby Gas Treatment System (SGTS') is in operation. Containment Temperature is 130*F. 1 i Containment Hydrogen / Oxygen Monitoring'is in service. Containment Pressure is 2.5 psig. ,e Reactor-Pressure Vessel (RPV) Level is -155" and steady.. Low. Pressure-Emergency Core Cooling systems are requiredito maintain level. a. Place the Residual Heat Removal (RHR) System in the Containment Spray Mode. b. Prevent RHR from shifting to the Containment-Spray Mode..

• Emergency Depressurize the. Reactor Pressure Vessel.

c. d. Commence Steam. Cooling 'l i t REVISION NO: 2 i

l > y SNd 7 CLINTON. POWER < STATION l sT. LIMITS AND CONTROLS - j SRO 1 RO ' 1 e w:

• j f.'; s r

QUESTION NUMBER: LC-032 POINTS:- 0.50 The reactor is at 65% power when-one control rod withdraws-without operator action due to a Rod Control and Information-System (RCIS) malfunction.' Which of the following is the required operator action? i Immediately. cease rod movement, reduce power'by 50 MWe,t a. and stagger adjacent rods, b.- Depress IN TIMER SKIP, reduce power by 50 MWe, and stagger adjacent rods, c. Depress IN TIMER ~ SKIP, reduce power by 50 MWe, a'nd reset RCIS. t l d.- Depress ROD SELECT CLEAR, reduce power by 50 1003, and I stagger adjacent rods. l l -1 i i i ( '1 i 4 i ) REVISIOtl NO: 3

-'~-~~ ~ ~3

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"[, CLINTON POWER STATION -LIMITS AND. CONTROLS SRO X RO -X -) = i -QUESTION: LC-035 POINTS:- 0.50' I 'The reactor is in' cold shutdown and the operators are moving-irradiated fuet in the secondary containment. One Main control. Room Air Intake. Radiation Monitor is being repaired. If a second Air Intake Monitor in the same intake fails, which of' the following actions must operators take? Restore the second Air Intake Monitor to OPERABLE a. status within-7 days. b. Perform a control room area survey to ensure MCR m,, radiation levels are less than 10-mr/hr. Within one hour, initiate and maintain operation of the 4 c. Control Room emergency filtration ~cystem in the HI RAD mode of operation. d.- Place the unit in STARTUP within the next 6 hours, HOT SHUTDOWN within the following 6 hours, and COLD SHUTDOWN within the subsequent 24 hours. j l IF d 4 O l& \\ \\ ) i

... REVISION NO

2-l

i j

-CLINTON POWER STATION LIMITS AND CONTROLS GRO._X_ RO _X_ -l QUESTION NUMBER: ,_bC-076 POINTS:_ 0.50 i t The operators are running the 1B Diesel Generator (DG) in parallel with off-site power for surveillance testing.- A spurious-Loss of Coolant Accident (LOCA) initiation signal is received by the 1LB' DG logic, - tripping the output breaker. From the following, choose the operator action that allows the 1B DG. '.to automatically pickup emergency loads: Place control switch for the DG output breaker'to Pull-a. to-Lock, then reset the breaker 86 device, b. Turn off the auto-reclosers for breakers 4502, 4522 and 1372, then reset the 86 device locally. Re-close the* output breaker and raise load to at least c. 3875 KW with the governor control switch. d. Place the output breaker control. switch in the TRIP position'and then release to normal. 3 k I 1 REVISION NO: 4

y i s'. CLINTON POWER STATION 2 LIMITS AND CONTROLS SRO X RO. X .)- QUESTION NUMBER: LC-090 POINTS: 0.50 .) With the plant. operating at 83% power, the' Component Cooling-1 Water (CC)-System pump suction develops a leak which exceeds'the' capacity of'the CCW expansion tank makeup. The operators 4 determine CCW system and plant shutdown is required due to loss l of cooling to vital reactor auxiliary equipment. Choose from the following the action the operators should take when CCW is lost. l Verify, cooling water automatically transfers to the a. Shutdown Cooling (SX) Sytten. b. Stop the' plant Service Air Compressors within five (5) minutes. Stop the Fuel Pool Cooling and Cleanup'(FC) System c. pumps within five (5) minutes. d. Stop the Reactor Recirculation (RR) pumps within one (1) minute. q i i .{ k i k i I t ,/ REVISION NO: 2

I, 'nc' i .le ( i CLINTON POWER STATION a, LIMITS AND CONTROLS SRO __X RO ~X I QUESTION NUMBER:_ LC-093 POINTS: 0.50 I The plant is operating at 100% reactor-power whenLthe "A" Reactor ) Recirculation (RR) Pump trips.. After taking the proper actions, l the problem is determined to be a faulty overcurrent relay on 'j breaker SA. The relay is replaced and the operators prepare to start the "A" RR pump. The following conditions exist: Operating loop flow is 14,950 gpm. Differential temperature between bottom head and steam' dome is 96'F.- Differential temperature between RR loop "A" and "B" is 59 ' F. - RR Flow-Control Valve "A"-is at its minimum position. Both RR Flow Control Valves are in MANUAL. "A" RR' loop'is unisolated. l Evaluate the above information and chose from the following list, the action needed to be taken before returning the idle loop to i service. I a. 1 ;rease Reactor Water Cleanup flow from the bottom l head region. b. Adjust the "B" RR loop flow to greater than 15,670 gpm. Slowly open the "B" RR loop Flow control Valve to 50% c. position. d. Slowly throttle open the idle "A" loop Flow Control r t . REVISION NO: 2

1 ,, t ~ f q (, y

CLINTON POWER-STATION.

< LIMITS AND CONTROLS SRO X ,RO X y . QUESTION NUMBER: LC-098 POINTS:. 0.'50 Following a major plant transient the following conditions exist: Reactor is-shutdown. l vessel' level is -165 inches and steady. Vessel pressure is 700 psig and steady. Feodwater system is HQI available. HQ ECCS is available. Alternate inje' ction systems are HQI-lined up. Which of the following contingencies should be entered for'the ~ > present plant conditions? a. Reactor Pressure Vessel (RPV) Flooding 4 b. Emergency RPV Depressurization 1 F c. Core Cooling without Level Restoration E d '. Steam Cooling q 4 ~$ a i i s o l l-l l-h ) l l -REVISION NO: 1 _. 7

_ _ _ _ _ _ _ _ _ - - _ _ - - - - - - - - - - - - - - - - - - -- --- -'-~- - ---~ ~-~- ~ --~ ~ is.

r '

w CLINTON POWER STATION' l LIMITS =AND CONTROLS -SRO -X -RO __X 3: 1 QUESTION-NUMBER:- LC-107 POINTS: 0.50-A plant: transient has resulted in the following plant conditions: Main Steam Isolation Valves closed due to a Steam Leak. Reactor Core Isolation Cooling System out of service. Boron Injection completed, Control Rods'are at the 100% Rod pattern. ~ Suppression Pool Water Level 19'. Residual Heat Removal Shutdown cooling mode is out of service on both divisions. Further cooldown is required. Evaluate the plant conditions provided above,= and from the-following list determine which method of cooldown is required to be used. 'a. Main Turbine Bypass Valves b. -Safety Relief Valves c. ' Reactor Water Cleanup System d. . Alternate Shutdown Cooling ' REVISION NO: 3

'q, m: CLINTON POWER STATION 'g LIMITS-AND CONTROLS + SRO-X- RO X -_ -QUESTION NUMBER:- LC-124 POINTS: 0.50 I 1 The following conditions exist following a reactor scram in which I i several control rods failed to insert: !-) Reactor Protection System (RPS) Manual scram-inserted [ Reactor modo switch position' Shutdown Main Steam Isolation Valves (MSIV's) Closed Suppression pool temperature 80*F i 'l i Reactor-water level -5 inches j (increasing.) j Recirer.lation flow l 50% I ) Alternate Rod Insertion (ARI) Activated Reactor power-t 4.0%- 1, ~ ~ Select the' statement which.best describes the next action the I operator'is required to take: i a. Commence Emergency Cooldown; i b. Manually trip both recirculation pumps. Initia'te boron injection to the reactor vessel' c. d. Deliberately lower level to reduce reactor power below i i I 6 ~) REVISIOll illO: 3 l

+ CLINTON POWER STATION LIMITS AND CONTROLS SRO X RO X -QUESTION NUMBER:- LC-130 POINTS:- 0.50-i The plant is operating at full power. Residual-Heat Removal System - (RHR) loop A has been out of service for four (4) hours due to a scheduled maintenance outage. A problem has just occurred with one of the "B" Containment spray containment pressure instrument analog trip modules which makes it inoperable. Which of the following actions is required to be taken by Technical Specifications (T/S)? i -Declare "B", Containment Spray loop inoperable a. immediately-. b. I Place the failed Analog Trip Module (ATM) in a trip condition within 1 hour. c. Restore 1 inoperable Containment Spray loop within 8 hours. i j d. Place the unit in STARTUP within the next 6 hours, HOT-SHUTDOWN within the following 6 hours, and COLD SHUTDOWN within the subsequent 24 hours. i l 14 L 4 l ' REVISION NO: 3 l'

7 \\- CLINTON' POWER STATION LIMITS AND CONTROLS c. SRO X RO _ X QUESTION NUMBER: LC-136 POINTS: 0.50-Which of the following describes the potential consequences.of operating at full power with the END-OF-CYCLE Pump Trip System in Bypass? (EOC) Recirculation = High decay heat load may damage fuel following a. scrams from high power at EOC. b. Void collapse could add positive reactivity faster than control rods can add negative reactivity at EOC during transients. 1 Sudden thermal transients can. damage core structure c. I following MSIV.isolations at high power near EOC. d. Core Thermal Hydraulic Instability may result in severo reactivity transient during a Reactor Recirculation t i pump trip from high power near'EOC. k ) i i ) REVISION NO: 4

4 CLINTON POWER STATION LIMITS AND CONTROLS I SRO -X RO X l QUESTION NUMDER:. LC-139-POINTS:. O.jp It is discovered.that both Drywell High Range Gross Gamma Monitors are inoperable. If the plant is at full power when this occurs, which:one of the following courses'of action.will satisfy. ALL the requirements for this situation? a. Restore the inoperable monitors to operable status within 7 days or be in at least Hot Shutdown within the .next 12 hours. L b. Initiate preplanned alternate method of monitoring and report event to the Commission within 14 days. t ): c. Initiate preplanned alternate method of. monitoring, p within the next 72 hours. d. Restore the inoperable monitors to operable status within.48 hours or be in at least Hot Shutdown within-the next 12 hours. Ii 'l '1 .1 ll l { H \\ L i -t .) / 1 l l REVISION NO: 0-1

c g" f g CLINTON POWER STATION L LIMITS AND CONTROLS SRO _X,_ RO )L, i. QUESTION NUMBER: LC-147 POINTSt. 0.50 Due to a stuck open Safety Relief Valve (SRV), SRV 1B21-F041A, the plant has been shut down and is in the process of a cooldown. Because of other plant conditions it has become necessary to open SRV's. Which of the following sets of SRV's should be opened? a. 1B21-F047D and 1B21-F051G - b. 1B21-F047A and 1B21-F047D c. 1B21-F051G and 1821-F041G d. 1B21-F051B and 1B21-F041D 4 Yy. 4 1 1 - REVISION 110: 3_,_ l

(O l..'.: - 4 L CLINTON POWER STATION LIMITS AND CONTROLS - SRO X RO 1 QUESTION NUMBER: LC-160 POINTSt_ 0.50 The chemistry group reports that Reactor Vessel water specific activity is very high suggesting fuel damage. Which of the methods listed below may be used to determine the approximate location of the fuel damage? Closely observe Average Power Range and Local Power a. Range Monitor flux levels while moving control. rods in -and out. 1 b. Determine the specific activity in the reactor coolant at the Post Accident sample Panel, Monitor general area radiation levels and compare these c. regions with reactor core orientation. d. Monitor off-Gas radiation levels while moving control rods in and out of the reactor core. 4 5 \\ REVISION NO: 3 5

~ CLINTON POWER STATION LIMITS AND CONTROLS SRO 1 RO 1 1 QUESTION NUMBER:- LC-176 POINTSt. 0.50 During a reactor power ascension with the plant operatin power but at. low ciow conditions (above 105% rod line). g at high Choose from the following, how the reactor power rate of change will i respond to a change in core flow rate compared to lower rod line operation. 1 Increases faster and decreases slower. a. b. Decreases faster and increases slower. No change on increase but decreases slower. c. d. Increases faster and decreases faster. 't-REVISION NO: 3

I i i CLINTON POWER STATION LIMITS AND CONTROLS SRO X RO X i i 1 i QUESTION No: LC-280 POINTS:- 0.50 i With the reactor;at full power, one control rod is i determined to be' drifting out. The operators stop the rod drift, reduce poWor by 50 MW(e) and obtain a P-1 from the Performance. Monitoring System computer. Attempts to contact the shift Nuclear Engineer have not yet been successful, so the operators evaluate 0D-11, option 3. If this evaluation indicates that the leading histogram node is 0.9 Kw/f t over the preconditioned envelope, the Shift Supervisor should direct which one of the following actions: Maintain present power level Nntil the Nuclear a. Engineer reviews the data. b. Reduco reactor power an additional 90 MW(e), Declare the control rod inoperable. c. d. Begin an orderly reactor shutdown within one (1) hour. i l t l- \\ i l l REVISION 1:0: 1

t L. CLINTON POWER STATION [ LIMITS ANJ CONTROLS [ SRO ,,,,X., RO _,X_ i. { f l \\ QUESTION NUMBER:- LC-360 POINTS:. O'.50 i i \\ The plant is presently in a condition where.the Reactor Protection System shortin Technical Specifications.g links are required to be removed per l While removed from their respective cabinets,.where are the links stored? t i In the Control Room Operator (CRO) key locker. a. b. In the Main Control Room fuse storage cabinet. In the Supervisor - Control and Instrumentation key c. locker. l, i d. In the Shift Supervisor (SS) key locker. 3 i i ) 'l k I i i i I i 4 l 4 l itEVI SIO:1 110 : _ 2 1 I

M($0 $ 3 '- !h khI ~ M jV CLINT@N P3WER GTAISH t LICENSED OPERATOR REQUALIFICATION ANSWER SHEET NAME:, DATE: (tast) (Pst) (m.L) (mm) (o:1) (w) SOCIAL SECURITY NUMBER: EXAM RO.06 90 GRADED BY: SCORE: INSTRUCTIONS: COMPLETELY DARKEN THE APPROPRIATE LETTER FOR YOUR RESPO.NSE.. ERASE ERRORS COMPLETELY TO PRECLUDE t MISSING THE QUESTION. i LC-011 0 lal(b) W id) lalW[c]Idl LC-136 LC-013 lal 5 (c)idl lalM(c)idl LC-016 la)l'l(c)M lal 3 (c) (d) b LC-147 LC-026 al 5 (c)idl la)(b)Icl$ l LC-160 LC-032 lal 5 (c)idl lalIb)Ic]5 o LC-176 lal(b)Icl 3 LC-035 lal(b)W(d) LC-076 LC-280 'lal W lol [d] lal(b)Icl M LC-090 la)(b)[c]g LC-360 lalIblIcl 3 ~ lalIbl(c)W LC-098 lallblic) M . -107 lal 3IclIdl I' ~I ) tal9IclIdl My signature below cortifies that the work on this examination is my own and that I havo not received or been given any assistance in completir>;1 this examination. (sign af ter exam completion) / Ognature Date yy,,,,,,, -,, . _., _.. +

] 3 h, grt g r CLINTON POWER STATION LICENSED OPERATOR REQUALIFICATION i EXAMINATION COVER SIIEET LIMITS AND CONTROL EXAMINATION l SRO k RO EXAM NO: d ~ To f f ASTER C 7?Y NAME: APPROVED: "//[ 7C_ DATE: / [d ~ /

E 4 i REQUALIFICATION WRITTEli EXAMI!1ATION RULES Print your name on the cover shoot of the examination. 1. Print your name, social security number and dato in the 2. blanks provided on the answer sheet. 3. Answer cach question on the answer sheet provided. If additional paper is required, use the examination. 4. Use black ink or dark pencil ONLY to facilitato legible reproductions. If your change an answer, erase completely or initial and date. cross out, The point va'lue for each question is indicated on each 5. question. 6. Unless solicited, the location of references need not be stated. 7. If parts of the examination are not cicar with respect to ~ their intent, ask questions of the examinor only. B. In the simulator, due t.o the existence of questions that will require all c,xaminces to refer to the same indicatior)s or controls, particular care must 'bc taken to maintain s individual' cxamination security and avoid any possibility of c'- compromise or appearance of cheating. 'C1'oso procedures and change computer displays on PMS when you are through with a question. i 9. Each section of the examination is designed to tak'c i approximately 90 minutes to complete. You will be given two hours to complete cach section for a total of four hours. 10. Passing critoria is.80% of the total score of the Limits & Controls and Static examinations. 11. You must sign the statement on the answer shoot that indicates the work on the examination is your own and that you have not roccived or been given any assistance in completing the examination. This must be signed AFTER the examination has been complot a?. i 12. Rest room t';ips are to be limited and only one examinco at a time may leave. " u must avoid all contact with anyone outside the examination room to avoid even the appearance or possibility of examination compromiso, 13. Cheating on the examination would result in a revocation of 7 your license and could result in more severe penaltics. 14. When you are finiched and have turned in your comp 3 cted cxamination, leave the examination area.

.4 CLINTON POWER STATION LIMITS AND CONTROLS SRO _X_ RO _X_ s QUESTION NUMBER:- LC-006 POINTS: 0.50 The plant has just experienced a complete loss of BOTH onsite AEQ offsite AC power. Under which of the below listed conditions is a SITE EVACUATION mandatory for this event? Immediately upon the loss of offsite and onsite AC a. power. b. Loss of offsite power for greater than 15 minutes, with onsite power restored, Loss of onsite power for greater than is minutes, with c. offsite power restored. i d. Loss of both onsite and offsite power for greater than 15 minutos. N I 1 i REVISION No: 2

CLINTON POWER STATION LIMITS AND CONTROLS SRO _2.,, RO 1 L QUESTION NUMBER:- LC-011 POINTS:- 0.50 l The following plant conditions exist: The reactor has been manually scrammed. The reactor pressure vessel temperature is 450*F. i Iake level has reached 675' MSL. From the following listed methods of plant cooldown, which would be utilized for the existing plant conditions listed above? i U6q of the Main Condenser Bypass Jack. I a. b. Adjtsting the pressure setpoint of the Steam Bypass and Pressure Control System, Adjus'.ing Reactor Core Isolation Cooling System (RCIC) c. , flow. d. Residual Heat Removal (RHR) system operating in the Shutdown Cooling Mode, i t REVIS10!! No:_2

4 CLINTOli POWER STATION LIMITS-AND CONTROLS SRO __X RO X QUESTION __LC-013 POINTS:_ 0. 5 0__ The Plant is in a normal shutdown condition. Severe weather has been predicted by the local weather services and all on-site personnel have been alerted of this possibility. Sometime later meteorical data indicates straight line winds sustained at 77 miles per hour with HQ tornado sightings. What is the proper E-Plan classification for this event? a. Notification of Unusual Event b. Alert Site Area Emergency c. d. General Emergency REVISIO!1 NO: 1 1

CLINTON POWER STATION LIMITS AND CONTROLS SRO 2i_ RO _)L l i QUESTION NUMBER:- LC-020 POINTS: 0.50 1 A transion has occurred resulting in the following conditions: i Reactor scrammed Reactor Vessel Level - maintained Level 3 to Level 8 Drywell Pressure 1.5 psjg Only two (2) Safety Relief Valves (SRV) will open in the relief / ADS mode due to an air line problem. Drywell temperature 335'F. Suppression Pool level 19'5" Based on these conditions what operator action is required? Rapidly depressurize the Reactor Pressure Vessel (RPV) a. using the two (2) SRV's and the Main Turbine Bypass Valves. b. Rapidly depressurize the RPV using the two (2) SRV's. Rapidly depressurite the RPV using the Main Turbine c. Bypass Valves. I d. Depressurize the RPV using the Main Turbine Bypass Valves and two (2) SRV's to maintain less than 100*F/hr cooldown rate, s A REVISION NO: 0 t

{ CLINTON POWER STATION a LIMITS AND CONTROLS SRO 1 RO 1 I QUESTION NUMBER:_ LC-026 POINTS:- 0.50 Given the plant conditions provided below, determine what operator action is required in accordance with Containment control: Standby Gas Treatment System (SGTS) is in. operation. ( Containment Temperature is 130*F. Containment Hydrogen / Oxygen Monitoring is in service. Containment Pressure is 2.5 psig. Reactor Pressure Vessel (RPV) Level is -155" and steady. i Low Pressure Emergency Core Cooling systems are required to maintain level. I Place the Residual Heat Removal (RHR) System in the a. Containment Spray Mode, b. Prevent RHR from shifting to the Containment Spray.

Mode,

-Emergency Depressurize the Reactor Pressure vessel. c. d. Commence Steam Cooling 1 ) REVISION NO: 2

h CLINTON POWER STATION LIMITS AND CONTROLS SRO X RO X QUESTION: LC-035 POINTS:__ 0.50 i The reactor is in cold shutdown and th' irradiated fuel in the secondary containment.o operators are moving One Main Control Room Air Intake Radiation Monitor is being repaired. If a second Air Intake Monitor in the same intake fails, which of the following actions must operators take? a. Restore the second Air Intake' Monitor to OPERABLE status within 7 days. s b. Perform a control room area survey to ensure MCR radiation levels are less than 10 mr/hr. Within one hour, initiate and maintain operation of the c. Control Room emergency filtration system in the HI RAD mode of operation. i d. Place the unit in STARTUP within the next 6 hours, !!OT SHUTDOWN within the following 6 hours, and COLD SHUTDOWN within the subsequent 24 hours. REVISION HO: 2

g a ) CLINTON POWER STATION LIMITS AND CONTROLS SRO _X_ RO _X_ ? QUESTION NUMBER:- LC-042 POINTS:. 0.50 I i A transient has occurred in which a primary system is discharging outside the secondary containment. The following plant conditions existt / Offsite release rate is 7.4 ci/sec and increasing. Suppression pool water level is 19'2". i Only 2 Safety Relief Valves (SRV's) can be opened and both are presently open.. Group 1 isolation has occurred. Standby Gas Treatment System (VG) is on the crimarv npntainment. Which of the following actions is the operator required to perform next? Shift Containment Building Ventilation to Filtered a.

Mode, b.

Emergency Depressurizo using the 2 Safety Rellof Valvos only. Emergency Depressurizo using Reactor Core Isolation c. Cooling (RCIC) only. d. Emergency Depressurizo using RCIC to augment the two open SRv's. j RL'V IS. ION tlO: 3_

l CLINTON POWER STATION LIMITS AND CONTROLS SRO _K_ RO _X_ QUESTION NUMBER: LC-076 POINTS:_ 0 12 The operators are running the 1B Diesel Generator (DG) in parallel with off-site power for surveillance testing. A spurious Loss of coolant Accident (LoCA) initiation signal is received by the 1B DG logic, tripping the output breaker. From the following, choose the operator action that allows the 1B DG to automatically pickup emergency loads: Place control switch for the DG output breaker to Pull-a. to-Lock, then reset the breaker 86 device, b. Turn off the auto-reclosers for breakers 4502, 4522 and 1372, then reset the 86 device locally, Re-close the' output breaker and raise load to at least c. 3875 KW with the governor control switch. 3 d. Place the output breaker control switch in the TRIP { position and then release to normal. \\ I l i REVISION HO: 4 i

O CLINTON POWER STATION LU;.ITS AND CONTROLS I Sit 0 X RO X i QUESTION NUMBER: LC-090 POINTS: 0.50 With the plant operating at 83% power, the Component Cooling i Water (CC) System pump suction develops a leak which exceeds the capacity of the CCW expansion tank makeup. The operators determine CCW system and plant shutdewn is required due to loss of cooling to vital reactor auxiliary equipment. Choose from the following the action the operators should take when CCW is lost.

• Verify cooling wator automatically transfers to the a.

1

Shutdown Cooling (SX) System.

b. Stop the plant Service Air Compressors within five (5) minutes. Stop the Puol Pool Cooling and Cleanup (FC) System c. pumps within fivo (S) minutes. d. Stop the Roactor Rocirculation (RR) pumps within one (1) minuto, t t REVISION NO: 2, _

m ~ ~, 4 4 CLINTON POWER STATION LIMITS'AND CONTROLS SRO. -X RO X QUESTION NUMBER:_ LC-098 POINTS - 0.50 Following a major plant transient tho following conditions exist:. i Reactor is shutdown. . Vessel level is -165 inches and steady.- Vessel pressure is 700 psig and steady. i .Feedwater system is EQT available, HQ ECCS is available. a L Alternate injection systems are HQI lined up. Which of the following contingencies should be entered for the - present plant conditions? Reactor Pressure Vessel _ (RPV) Flooding a. .b. ' Emergency RPV Depressurization Coro Cooling without Level Rostoration c. d. Steam Cooling Oa 4 i I e h v E . REVIS10!I !!O: 1 .g ~

, 41 l CLINTON POWER STATION L LIMITS AND CONTROLS [ f SRO _ X _ RO X + ! QUESTION NUMBER:. LC-107 POINTS:_ fl. 50 [ A; plant transient has resulted in the following plant conditions: Main Steam Isolation Valves closed due to a Steam Leak. - Reactor Core Isolation Cooling System out of service. Boron Injection completed, control Rods are at the 100% Rod f -pattern. j Suppression Pool Water Level 19'. L Residual Heat Removal Shutdown cooling mode is out of l service on both divisions. Further cooldown is required. Evaluate the plant conditions. provided above,.and from the following list determine which method of cooldown is required to be used.- a. Main Turbino Bypass Valves

b..

Safety Relief Valves t t c. Reactor Water Cleanup System 4 t d. A1tornato Shutdown Cooling i r i i L i

l

>REVISIOtt NO: 3 j:,

(li,._.

Cl.INTON POWER STATION LIMITS AND CONTROLS SRo X Ro __g__ QUESTION NUMBER:- 1r-124 POINTS:. o.so The following conditions exist following a reactor scram in which several control rods failed to insert: Reactor Protection System (RPS) Manual scram inserted Reactor mode switch position Shutdown Main Steam Isolation Valves (MSIV's) closed Suppression pool temperature 80*F Reactor water level ~5 inches (increasing) Recirculation flow 50% A1tornato Rod Insortion (ARI) Activated Reactor power 4,og Select the statomont which best describes the next action the operator is required to take a. Commence Emergency cooldown. b. Manually trip both recirculation pumps. Initiato boron injection to the reactor vessel. c. d. Deliberately lower lovel to reduco reactor power below 3%. 1 1 REVISION NO: 3

CLINTON POWER STATION o LIMITS AND CONTROLS SRO X ;._ R O _ X QUESTION HUMBER: LC-130 POINTSt_ O.50 The plant is operating at full power. Residual Heat Removal System (RHR) loop A has been out of service for four (4) hours due to a scheduled maintenance outage. A problem has just occurred with one of the "B" Containment Spray containment pressure instrument analog trip modules which makes it inoperable. Which of the following actions is required to be taken by Technical Specifications (T/S)? Declare "B" containment Spray loop inoperable a. immediately, b. Place the failed Analog Trip Module (ATM) in a trip condition within I hour. Rostore 1 inoperable Containment Spray loop within 8 c.

hours, d.

Place the unit in STARTUP within the next 6 hours, HOT SHUTDOWN within the following 6 hours, and COLD SHUTDOWN within the subsequent 24 hours. O -l / I REVISION NO: 3 t f

i:

i

I t -. CLINTON POWER STATION i ' LIMITS AND CONTROLS SRO X Ro _X__ QUESTION NUMBER:- LC-136 POINTSt. 0.50 Which of the following describes the potential consequences of operating at full power with the END-OF-CYCLE (EOC) Recirculation Pump Trip System in Bypass? liigh decay heat load may damage fuel following a. scrams from high power at EOC. b. Void collapse could add positive reactivity faster than control rods can add negative reactivity at EOC during transients. Sudden thermal transients can damage core structure c. following MSIV isolations at high power near EOC. r d. Core Thermal llydraulic Instability may result in sevoro reactivity transient during a Reactor Recirculation pump trip from high power near EOC. 5 4 ) REVISION HO: 4 .l l

I CLINTON POWER STATION LIMITS AND CONTROLS SRO _ X RO X l P QUESTION NUMBER: LC-139 POINTS: 0.50 It 10 discovered that both Drywell High Range Gross Gamma Monitors are inoperable. If the plant is at full power when this occurs, which one of the following courses of action will satisfy hLL the requirements for this situation? Restore the inoperable monitors to operable status a. within 7 days or be in at least Hot Shutdown within the next 12 hours. b. Initiate preplanned alternate method of monitoring and report event to the Commission within 14 days, Initiate preplanned alternate method of monitoring c. within the next 72 hours. d. Restore the inoperable monitors to operable status 1 within 48 hours or be in at least Hot Shutdown within the next 12 hours. i ? ) l REVISION NO: 0

f- ] { CLINTON FOWER STATION + LIMITS AND CONTROLS i SRO 1 RO 1 QUESTION NUMBER:- LC-147 FOINTSt. 0.50 1 Due to a stuck open Safety Relief Valve (SRV), SRV 1B21-F041A, i the plant has been shut down and is in the process of a cooldown. Because of other plant conditions it has become necessary to open SRV's. Which of the following sets of SRV's should be opened? j a. 1B21-F047D and 1B21-F051G b. 1821-F047A and 1B21-F047D c. 1821-F051G and 1B21-F041G ) d. 1821-F051B and 1821-F041D l 4 1 REVISIO!1 NO: 3 .v +

1* CLINTON POWER STATION LIMITS AND CONTROLS SRO X RO X QUESTION NUMBERt_ LC-160 POINTS:. 0.50 The Chemistry group reports that Reactor Vessel water specific activity is very high suggesting fuel damage. Which of the methods listed below may be used to determine the approximate location of the fuel damage? Closely observe Average Power Range and Local Power a. Range Monitor flux levels while moving control rods in and out. b. Determine the specific activity in the reactor coolant at the Post Accident sample Panel. Monitor general area radiation levels and compare these c. regions with reactor core orientation. d. Monitor Off-Gas radiation levels while moving control rods in and out of the reactor core. 1 ) REVISIOli 110: 3

p, f CLINTON POWER STATION ! n LIMITS AND CONTROLS SRO X RO. X. t. QUESTION No: LC-276 POINTSt 0.50 During full power operation, temperature indications show that ono (1) Safety Relief Valvo is leaking. Attempts to close the SRV have HQT been success (SRV), ful. However HQ MW(e) decrease has occurred and EQ Acoustic Monitor noise can,be detected for this SRV. Which one of the following actions should the operators NOW perform? Declare an Unusual Event per EC-02. a. b. Initiato CPS No. 9000.05 Suppression Pool Temperature Log. Declare the leaking SRV Inoperable por Toch Spocs, c. d. Commence an orderly plant shutdown. 1 I I l t l 4 ) l l 1 L REVISION NO: 2 i 1 1 I

i l- + CLINTON POWER STATION LIMITS AND CONTROLS o-SRO,_)L RO,__Yu QUESTION Ho:- LC-280 POINTS: 0.50 . With the reactor at full power, one control. rod is determined to be drifting out. The operators stop the rod drift, reduce power by 50 MW(e) and obtain a P-1 from the Performance. Monitoring System computer. Attempts to contact the shift Nuclear Engineer have not yet been successful, so the operators evaluate OD-11, option 3. If this evaluation indicates that the leading histogram node is 0.9 Kw/ft over the preconditioned envelope, the Shift Supervisor should direct which one of the following actions: Maintain present power level until the Nuclear a. Engineer reviews the data. b. Reduce reactor power an additional 90 MW(c). Declare the control rod inoperable, c. d. Begin an orderly reactor shutdown within one (1) hour. i i REVISION 00: 1

c' ' .CLINTON POWER STATION LIMITS AND CONTROLS O S R O._ X, RO,,X_ QUESTION NUMBER:- LC-360 POINTS - 0.50_ The plant is presently in a condition where the Reactor Protection System chortin Technical Specifications.g links are required tp be removed per cabinets, wherc are-the links stored?While removed from their respective In the control Room operator (cRo) key locker. a. b. In the Main Control Room fuse storage cabinet. In the Supervisor - control and Instrumentation key c. locker. d. In the Shift Supervisor (SS) key locker. I-1 I i )' l REVISIOli 110: 2

,s kf f, ih[1 gj _o CLINTON POWER STATION Dilenif)[l.,$Fjf LICENSED OPERATOR REQUALIFICATION ANSWER SHEET NAME: DATE. (last) (tast) (m.i.) (mm) (ck1) (yy) ~ l SOCIAL SECURITY NUMBER: EXAM SRO-06 90 GRADED BY: SCORE: INSTRUCTIONS: COMPLETELY DARKEN THE APPROPRIATE U.iTTER FOR YOUR i RESPOySE. ERASE ERRORS COMPLETELY TO PRECLUDE MISSIAG THE QUESTION, LC-G0c LC-130 lal3 (c)idl lalIblIcl84l LC-011 LC-136 lalIb] M [d] lal 9 [c](d) LC-013 -139 lalWIcl(d) lalhtelIdl LC-020 W lb)Icl[d] LC-147 lalIblIcl5 j LC-026 LC-160 _lal B IclIdl lalIblIc]$ LC-035 LC-276 lal(b)5[dl lal$IclIdl LC-042 LC-280 lalIblIcl B lalSlolId] LC-076 lallb][cl g LC-360 lallblicl $ LC-090 lal(b)Icl R LC-098 -talIblIcl$ LC-107 lal ki tclidl LC-124 lal M [c]Idl My signature below certifies that the work on this examination is my own and that I have not received or been given any assistance in completing this examination. (sign af ter exam comple' ion) / Sagnature Dato l .}}