ML20245L222

Exam Rept 50-368/OL-89-01 on 890801-03.Exam Results:Three Applicants Passed All Portions of Exam & Have Been Issued Appropriate Licenses.Fourth Applicant Failed Written Exam

ML20245L222
Person / Time
Site:	Arkansas Nuclear
Issue date:	08/11/1989
From:	Mccrory S, Pellet J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20245L217	List: ML20245L211 ML20245L222 ML20246C903
References
50-368-OL-89-01, 50-368-OL-89-1, NUDOCS 8908220040
Download: ML20245L222 (58)

Text

{{#Wiki_filter:7% ' p' 4 gx ', 3;"c:W"% l ,c 3 M yn y' Q;', *, g d s s [b -p j i 4 E .'v, , gg APPENDIX ~ y, -U.S. NUCLEAR REGULATORY COMMISSION x REGION-IV. s u r a. [, e ' Operator Licensing Exam Report: 50-368/0L89-01 Operating License: NPF-6 . Docket'No: 50-368-4 ~ LLicensee: Arkansas. Power & Light. =P.O. Box 551

Little Rock, Arkansasi 72203 Fscility Name

Arkansas Nuclear One, Unit 2 (ANO 2)

. Examination'at:. Arkansas: Nuclear One, Unit 2 r

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,$1 Chief?Examir r: W M NL A gn .L( Mq0rory, L6ad Examiner Date v eratoP Licensing Section Division.of Reactor Safety 1 x ) rQ j.. Tiet, Ecction Chief, , Date' ' ~ parat r Licensing Section Division of Reactor Safety'. I f g ' Summary NRC-Administered Examinations: Conducted Durina the Week of July.31,'1989 .(Report 50-368/0L89-01)- J n NRC.administeredexaminationstofourseniorreactoroperator(SRO) upgrade. applicants.= Three of the applicants _ passed'all portions of the examination and ' .have been issued the. appropriate licenses. The fourth applicant failed the swritten examination. 1 Performance on the written examinations was marginal.: The average score on' the written examinations was:81 percent with the highest being 85 percent. If' lthe pilot Generic fundamentals Examination (GFE) results had not been averaged j Linto the overall written examination grade, one more applicant would have scored less than 80 percent. In Examination Report 50-368/0L88-02, SR0 performance i 'in Category 6, " Plant Systems Design, Control, and Instruments," was reported.to .be' about 10 percent lower than in the previous set of SRO examinations. This 8908220040 890814 PDR ADOCK 05000368 V PDC ____-_________-___-_-_-_________-_D . ' +: -

y .w reduced level of performance continued to be evident in the systems area of . Category 6. " Plant Systems and Plant-Wide Generic Responsibilities," of this examination. There was a further slight decline in the systems area. The written examination consisted entirely of multiple choice, matching, and fill-in-the-blank type questions. This is the first time that ANO applicants have been given a written examination of this type. Frequently, a new examina-tion format is blamed for a decline in performance scores. -However, en applicant who knows and understands system design, operation, and procedural scope, intent and use should not be impacted significantly by the question format or examination organization. What is indicated is that previous applicants have relied on partial knowledge about systems and procedures. The format of this / examination requires the applicant tc correlate knowledge about systems and procedures and reach an end point decision or conclusion. It is appropriate to test in this mode since the plant is operated as~ a result of the end point decisions that operators are continually making during the shif t. In Examination Report 50-368/0L88-02, deficiencies in simulator documents and simulator capabilities were noted as significantly affecting the development and administration of the simulator portion of the operating examination. During this visit the simulator performed satisfactorily. Since only two scenarios-were required to evaluate this group of applicants, a meaningful evaluation of the revised documentation or simulator upgrades cannot be made at this time. The results of this examination did not indicate weaknesses which challenge safe operation of the plant. However, NRC is concerned about the evidence of declining performance of SR0 applicants on the written examination. NRC encourages the facility licensee to evaluate this trend. No formal response to this report is required. However, NRC representatives will review facility licensee actions or planned actions as a result of NRC concerns on this matter in future site visits.

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u, 3 9.9) ,yr \\ v DETAILS' .c 'f 1 '- I J 1. - Persons Examined SRO J Total. I f License. Examinations: Pass:. 3 0 3. . Fail"-- 1 0' 1 n< 2. Exeminers [y S. L. McCrory.. Chief Examiner 3.- Examination Report o - Performance results'for individual candidates _ar'e'not included in this report because examination reports are placed in the NRC~Public Document. '?. Room as a matter of course. l Individual performance 1results are.not-subject to public disclosure. + o a. Examination Review Comment / Resolution ~In general, editorial comments.or changes made as a result of g facility: reviews prior'to. the ' examination, during. the examination, or subsequent grading. reviews are not addressed;by this' resolution section. This,section reflects resolution of substantive comments" submitted:to the'NRC by the. facility licensee after the examination. The facility. licensee post-examination comments, less the supporting, documentation, are included in the report immediately following the master examination key.. Unless otherwise indicated in this section. - the facility licensee comments were incorporated into the answer key. - 5.11 The question goes beyond the scope'of SR0 required recall. The question asks for memory knowledge of discrete sections of.a 67 page procedure which has no immediate actions. Delete from question bank for future examinations. Response: Reject.' The focus of.the question is not-procedural knowledge, but system knowledge. The terminology provided in the answer choices represents the type of information an operator would receive in the control room. To answer the ques _ tion, the applicant must know something about the' alarm logic of.the fire protection panels and automatic fire suppression actuation logic and capability for the ~.. subsystem monitoring the identified space. Further, the-questions did not focus on trivial or obscure areas of the plant. 9 ---.--.--_-----_-.---._--.--_._~_x _a

,q w -4 l 6.30 Accept choice "b" as an additional correct answer. Response: Reject. The distractor is a common misconceptier. on the part of operators concerning the objective of ALARA programs. b. Site Visit Summary The facility licensee was proviced a copy of the examination and answer key for the purpose of courenting on the examination content validity. The facility licensee was informed that examination results could be expected the week of August 7,1989, if comments on the written examination could be provided by the end of the examination visit.' The Chief Examiner informally communicated to the Unit 2 training supervisor and the NRC senior resident inspector at ANO that no -l generic matters or significant concerns had arisen during the operating examinations. The facility licensee training staff determined that a formal exit meeting was unnecessary. c. General Comments Performance on the written examinations was marginal. The average score on the written examinations was 81 percent with the highest i being 85_ percent. Two of the four would have scored less than eighty percent overall if the pilot Generic Fundamentals Examination (GFE) results had not been averaged into the overall written examination grade. In Examination Report 50-368/0L88-02, SRO performance in Category 6. " Plant Systems Design, Control, and Instruments," was reported to be about 10 percent lower (84.7 percent vs. 94.0 percent) than in the previous set of SRO examinations. For this exan.ination, the average performance in the systems area of Category 6 " Plant Systems and Plant-Wide Generic Responsibilities," was 82 percent -(question numbers 6.01 - 6.25). The following question numbers represent those on which 50 percent or more of the applicants scored less than 70 percent of the question value and are provided to assist facility evaluation of training weaknesses: 5.05 5.29 6.19 5.09 6.05 6.26 5.11 6.08 6.27 5.25 6.10 6.30~ 5.27 6.11 6.33 5.28 6.16 6.34 The written examination consisted entirely of multiple choice, matching, and fill-in-the-blank type questions. This is the first time that ANO applicants have been given a written examination of this type. The common tendency is to blame a new examination format for a decline in performance scores. However, this has minimal

^ g J . legitimacy, especially since supervisors of the training staff were told. of this examination format change in May 1989. An applicant who knows and understands system design, operation, and procedural scope, intent and use should not be impacted significantly by the question format or examination organization. What is indicated is that previous applicants have relied on partial knowledge about systems and procedures. The format.of this examination requires the applicant to correlate knowledge about systems and procedures and reach an.end point decision or conclusion. It is appropriate to test in this mode since the plant is operated as a result of the end point decisions that operators are required to make often. In Examination Report 50-368/0L88-02, deficiencies in simulator documents and simulator capabilities were noted as significantly affecting the development and administration of the simulator ,ortion of the operdting examination. During this visit, the simulator performed satisfactorily. Specific comments to the simulator performance are in>the Simulator Fidelity Report contained elsewhere in tHs report. No significant revisions to the prepared scenarios were required as a result of the simulation preview. The facility licensee provided a partial preliminary "Cause and Effect" manual for scenario development,for these examinations. Since only two scenarios were required to evaluate this group of applicants and since several of the individual events were taken from previous scenarios, a meaningful evaluation of the new documentation or simul _ator upgrades cannot be made at this time. The results of this examination do not indicate weaknesses which challenge safe operation of the plant at this time. However, NRC is concerned about the evidence of declining performance of SR0 applicants on the written examination. NRC' encourages the facility licensee to evaluate these trend evidences in the SRO license training program. NRC representatives will review facility licensee actions or planned actions as a result of NRC concerns on this matter in future site visits. d. Master Examination' and Answer Key A master copy of the AN0 2 license examination and answer key is attached. The facility licensee comments which have been accepted are incorporated into the answer key, i e. Facility Examination Review Comments The facility licensee comments regarding the written examination are attached. Those comments not acceptable for incorporation into the examination answer key have been addressed in the resolution section of this report. L

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l U. S. NUCLEAR ' REGULATORY COMMISSION - SENIOR REACTOR OPERATOR LICENSE EXAMINATION REGION 4 FACILITY: acKansac hiu r b.a r nna-? REACTOR TYPE: EWE-rF DATE ADMINISTERED: BSZD21.21 CANDIDATE: lblSIEUCIl0NS_ID_CeunlDaIEl-Read and follow the NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS attached to your examination. The passing grade reouires at least 70% in each cetegorr and a final grade of at least 80%. The results of the Pilot G2neric Fundamentals Examination you recently took will be factored into your.overall. grade. Examination papers will be picked up four and one half (4 1/2) hours after the. examination starts. % OF CATEC2RY' % OF CANDIDATE'S CATEGORY __UAl t!F _IDIAL RrnRF _UAf HF __ _ faIEEDRY _5D D_ _ _21.DD _ 4. REACTOR PRINCIPLES / THERMODYNAMICS / COMPONENTS _31.QB_ _32JD 5. EMERGENCY AND ABNORMAL PLANT EVOLUTIONS (33%) - _a3.Da__ _a3.Da __ 6. PLANT SYSTEMS (30%) AND PLANT-W1DE GENERIC RESPONSIBILITIES (13%) 12dJa _ TOTALS FINAL GRADE All work done on this examination is.my own. I have neither given nor received aid. Candidate's Signature

r + l SLEtaEESEblCLablD_aBUDRMAi pt attr_EUDUE1DNS Page. 2 L43%11 L s c. .t V n p- ' 0UESTIQ4 5.01 (1,00) Fo'r abnormally high containment pressure-and temperature conditions following a ' steam line rupture-inside containment, which one of the "following statements is-correct. a. ' Steam Generator. pressure is indicated less than actual and Pressurizer p. pressure is indicated greater than actual. b. Steam Generator pressure 'is indicated greater than actual and Steam Generator level is indicated less than actual, c. Pressurizer pressure is indicated greater than actual and Pressurizer level is indicated less than actual.. 'd. Pressurizer pressure is indicated less than actual and Steam Generator level is indicated. greater than actual. ANSWER 5.01 (1.00) d. - REFERENCE AND 2' Heat Transfer, Thermodynamics, and Fluids Handbook, p. 96, 97 045000K412 000040A107 000040K306 000040K106 000040A112 ..(KA's) (***** CATEGORY 5 CONTINUED mJ NEXT PAGE *****)

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'3 133%1~ ' p 0UESTION 5.02 (1.00)=' l -- Which one' of the following sets of. symptoms. best. indicates a leak in a CCW/RCP Seal heat exchanger with the. plant - at full power? a'. VCT level decreases, CCW surge tank level. increases,- SWS gross activity increases b ~. CCW surge tank. level decreases, RCS Tave increases, RCS gross activity increases c. 'RCS Tave decreases, VCT level increases, CCW loop 11 return temperature decreases d. CCW loop 11 return temperature increases, LTDN flow decreases, CCW gross activity increases ANSWER 5.02 (1.00) 'd.' . REFERENCE' AN02 STM 2-03, pgs 6, 11,.STM 2-43 pgs 3, 6 000026A201 ..(KA's) (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)

5 ' worsEtanY MD_afitdDEdal. Et mT EVDLLillD!)S l ,L Page 4 i L33%r ' d i I QUESTION 5.03 (1.00) 1 Which' of 'the f ollowing opera >or. actions represents the MINIMUM REQUIRED by EDP 2202.01 in response to a failure of the-RPS to initiate a reactor trip when a valid trip condition exists? Assume that each individual action -produces the' expected response;. a. Push manual reactor trip buttons. .b. Push' manual reactor trip buttons and open CEDMCS M/G supply breakers. c.- Push manual reactor trip buttons, open CEDMCS M/G supply breakers, and align boric acid to the charging pump suction. d. Push manual reactor trip buttons. open CEmiCS M/G supply breakers, align boric acid to the charging pump suction, and open charging pump suction to the RWT. ANSWER 5.03 (1.00) a. REFERENCE AN02 E0P 2202.01 REV 7. pgs 16, 17 000029G010- ..(KA's) 00ESTION 5.04 (1.00) ' Following' a steam line rupture resulting in MSIS. E0P 2202.01 places significant emphasis on stabilizing RCS temperature at post cooldown leuel and even returning Tave to hot shutdown value if possible. Which one of the following represents the principle reason for this action? a. Reactor vessel stress -b. Steam Generator stress h c. Pressurizer stress d. Restart accident (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) l.

l i 52__EBERGEldCL4&lD ARNORMAI Pi ANI_EUDLUIlDtiS 'Page U p 13 -.- l ! ANSWER

5.04 (1.00) a.-

L

REFERENCE

'AN02'E0P 2202.01 REV 7, pgs 61-63, T.S. BASES pgs, B 3/4 4-10, B 3/4 7-4 000040K204 ..(KA's) l QUESTION .5.05-(1.50) Select the choice closest to the available shutdown margin for the plant conditions-given below. (Extract from RCS OP 2103.15 provided.') Reactor tripped, all rods inserted RCS Tave = 450 deg.F EFPD = 200 Current boron concentration = 1000 ppa a.. -3.0 X'/\\K/K b. -4.0 % /\\K/K c. -5.4 % /\\K/K- -d. -8.4 % /\\K/K . ANSWER 5.05 (1.50) C. REFERENCE -AN02 RCSOP 2103.15 REV 22, E0P 2202.01 REV 7, pg 13 000024A205 ..(b4's) (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)

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EESEtJCY_eUD_eBUDEt%L_PI N4T A>DI FIT 10 tis Page 6 ,ug.,. p. p IGUESTION 5.06 -(1.00) Select the choice which most correctly completes the following statement'. With two (2) or more CEAs stuck out of the core f ollowing a reactor. trip. cmergency boration will continue until

a.-

boron concentration is 2500 ppm b.- avail able. shutdown margin ~ is >/= -6.0 % /\\K/K c. actual shutdown margin is >/= -5.5 % /\\K/K r 'd.- ' boron concentration is increased 250 ppm for each stuck rod ANSWER 5.06 (1.00) F B. REFERENCE AN02 E0P 2202.01 REV 7. pg 17, RCS OP 2103.15, pg 2 000005A203 ..(KA's) QUESTION 5.07 (1.00) Following a LOCA with RCS pressure at 500 psia, one RCP in each loop may be started if RCS temperature is </= deg,F as read on ___. 437,[CETs a. b. '467, CETs c. 467, hot leg RTDs d. 497, hot leg RTDs [ i i } '(*****. CATEGORY 5 CQiTINUED DN NEXT PAGE *****) 1. b

=. W L(llE SHEEGENCLGND_aWORL%f Pt NT EVDLLfIlDNS-Page 7. .. gm. ' ANSWER - 5. 0 7. (1.00)- A. " 4- - REFERB4CE. AN02 E0P.2201.02 REV 7, pg 75, 142, CE STEAM TABLES 000011A210 000074K208 ..(KA's) ~ QUESTION 5.08-(1.00) Which ~ one of the' f ollowing RCP f ailures/ malfunctions is LEAST likely to . produce. symptoms which would cause the operator to refer to AOP 2203.25. Reac tor Coolant. Pump Emergencies, for corrective action? a. Motor bearing seizure b. Pump / motor shait shear c. . Seal fallure d. 'Dil reservoir leak ANSWER 5.08 (1.00) B. REFERENCE AN02 AOP 2203.25 REV 1, pgs 1-3 000015G011 ..(KA's) (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)

.;i MERGEtJCYED3BUDHtML5 AhfT EUDLUIIDtG Page 8 + Lg321 3)v QUEST 10H '5.09 (1.00) RWhich one of the following systems DOES NOT require some amount of realignment when starting an EDG manually following a loss of 125 VDC power?'

a.

125 VDC control power i b.f EDG starting' air c.. Service water system 'd. lEDG' fuel oil system -ANSWER 5.09 (1.00) D.- ,/ . REFERENCE AN02 EOP 2202.01 REV 7, pg 36, ASOP 2204.36, pgs 30-32

000055A102

..(KA's) 'QUESTIG4 5.10 (1.00) Select the~ choice below which best completes the following statement concerning.the bases for Technical Specification requirements for liquid waste. The' radioactive material content of an unprotected outside temporary radioactiveLliquid' storage' tank is limited to curie (s). This ensures that an uncontrolled release would result in concentrations less than the I limits of ___ in the nearest surface water supply in a(n) area. a. '30, Technical Specification 11.1.4. monitored l ' b. 1;, 10 CFR-20, controlled 1 .c. 10, 10 CFR 20. unrestricted d. '1, Technical Specification 11.1.4, free release 1 1 1 l l (***** CATEGORY' 5 CONTINUED ON NEXT PAGE *****) l L[ l \\.

so x-I e. -C Et:lERGEury mn_ABblDHtsi pi mT EUDLIJIlDblS. ~Page :9 g-g ' ANSWER 5.10 (1.00) C. ' REFERENCE

AN02.T.S. 11.1.4, BASES pg B 3/4 11-2 000059G004

..(KA's) 'QUESTI ON 5.11 (1.00) Which one of the. following redilight alarms on panels 2C343-1 thru 4 is positive' indication that fire suppression media is being admitted to the affected space or equipment assuming proper system response or actuation? a. 1-1-4(B), Cable-spreading room b. 11-2-4(T),.EDG room #2 c. 3-3-4(T), TG bearing and lube. oil piping d. 3-3-4(B), Generator exciter ANSWER 5.11 (1.00) D. l l l REFERENCE AN02 AOP 2203.09 REV 8,:STM 2-60 000067A106 ..(KA's) 1 1 1: l l l-l l i (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) l ~. l-i 1

b p a 51 NRCENCY_auD_aBUDEt:1eL PI NT.EUDL1111DNS Page 10 (133%1 t' g LOUESTION 5.12 -(1.00) ' Which:one of the following sets of actions most. correctly represents the' expected immediate. operator response upon receluing the " LETDOWN RADIATION H1GH/ LOW" alarn in the. control room? Assume actual activity.is high. a. Read rad monitor,; increase purification flow, sample gross activity b.- Read rad monitor, secure seal return, sample for iodine activity c.- Secure seal rTturn, bypass' ion exchangers, diuert to BMS d.- ~ Secure charging, letdown, and seal return ANSWER 5.12 (1.00) A. REFERENCE

1. 402 AOP 2203.20 REV 4, pg 1,' AOP 2203.12L REV 19, pg 11 000076G009

..(KA's) QUESTION 5.13 (1.00) Choose the answer which best completes the f ollowing statement. ~ If' Alternate shutdown of unit 1 must be performed due to.a fire in the unit -1 control room, then unit 2 must 3 a. Maintain stable plant conditions. 'b. Conduct a normal shutdown. n c.- Shutdown at maximum safe rate. d. Trip and go to hot shutdown. l (***** CATEGORY 5 CONTINUED 0 4 NEXT PAGE *****) r

a ' 5-_E!:!ERGEUCY AND,,ABUQB!MI PLANT FUDLijIl0NS. .Page 11 l' . f.: cL33%1 ANSWER 5.13 (1.00) -C. REFERENCE AN02 AOP 2203'.14, Rev.8, pg 7 00006BG010 ..(KA's) ~00EST10N 5.14 '(1.00) Which of the parameters below REQUIRES that maximum HPSI flow be reestablished or maintained per E0P 2202.01 section 9. " Rect,very Actions for SIAS?" a. Pressurizer level < 29%. 'b.- RCS pressure < 1400 psia. c.. SG 1evels ( 23% wide range. d. RCS' saturation margin < 30 degrees. ANSWER 5.14 (1.00) d. REFERENCE AN02 E0P 2202.01, 9.7.1.A.3., p. 78 000009K324 ..(KA's) (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) i f

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y QUESTION 5.15 (1 '. 0 0 ).

1f, during a steam generatorL tube rupture event with RCS Thot.( 545 deg.F,

'theJ af f ected. S/G 1evel is increasing and cannot be controlled with maximum S/G blowdown fima,. which of the f ollowing actions is reau tred by-E0P'2202.017 a._ Open the MSIV bypass valve on'the affected S/G. b. 1Depressurize.the RCS with: pressurizer spray. c. Isolate S/G blowdown for the af fected S/G. d.- Open the SDBCS valves further manually. ANSWER 5.15 (1.00) a.. / REFERENCE .AN02 EDP 2202.01, 11.11'.3, p. 106 DD0037A214 ..(KA's) ' QUESTION-5.16 (1.00) Which one of the following recovery actions sections of E0P 2202.01 may be entered without a manual or automatic reactor trip? L a.- Degraded Power. 1 L b. Blackout. 1-} - I" c. SGTR - Wi th in -Charoino.Capac i ty. I L d. Inadeouate Core Coolino. l l l I l 1 l: l l l L i i i j (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) l-1- f. ) i L_ _ _ _ _ _. __ _ _______________ _ _ J

4, l L__EtdEEGEurY mb ABUDEtML.Ei mT runt irr10tLS Page 13- "~ 133%1. 7 ANSWER-5.16' ' (1.00). .'C. m REFERENCE EDP 2202.01 section 1.0, " Entry Conditions,".p. 1 000038G012 ..(KA's) -QUEST 10N' 5.17 ( l '. 0 0 ) Which one of the following is an -immediate action required by AOP 2203.21. ' Loss of Instrument Air?" a.- Cross' connect Unit 1 instrument air header, b. Open dryer bypass and place alternate filter in service, c. Initiate search for air line break. d. Cross connect breathing air compressors. 1 ANSWER 5.17 (1.00) a. l REFERENCE AOP 2203.21, p. 1 0000656010 ..(KA's) l I 1, I (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) 1, l 1 lL___._

m-f., d - 5.__EldERSENCLatfD_aBblD2th_ Pl MJT EDLi!T10NS - Page'14 ctg 3g11 -QUESTION 5.18 (1.00) Whic'h one of the following E0P tabs is the correct EDP tab to use'during a loss of all feedwater' transient with S/G 1evels less than 70 inches wide > range when.the E0P has been followed through opening the ECCS vent isolation valves (i.e., to which of the tabs below does the E0P direct the opsrator after opening the ECCS vent' isolation valves)? a. Reactor Trip, b. Blackout. c. SIAS. -d. ICC. ANSWER 5.18 (1.00) c. REFERENCE' E0P 2202.01, p. 120 000054A104 ..(KA's) I QUESTION

.19 (1.00)

Which one of the f ollowing 'is'a symptom of a loss of shutdown cooling but NOT loss of RCS inventory per AOP 2203.29. " Loss of Shutdown Cooling?" a. Increasing RWT level. b. - LPSI pump breaker trip alarm. c. Increasing CET temperature. d. Erratic SDC flow. 1 L l (***** CATEGORY 5 CONTINUED ON NEXT PAGE ***<*) i F L.

h.': ' () K.. 5 _EtdERGEtJCY ANB ABtJDat%L_ELatdI_EUDLullDtiS Page 15 [ .L33x1 ANSWER '5.19 (1.00) B. L-REFERENCE ll AOP 2203.T:9,'" Loss of Shutdown Cooling," p. 1, 3. 5 I 0000250011 ..(KA's) QUESTION 5.20 (1.00) i i .The initial symptoms of a pressurizer steam space leak are best indicated by pressurizer level ___ and pressurizer pressure

a...

decreasing,; decreasing .b.. increasing,' decreasing c.- decreasing,-increasing .de increasing, inereasing ANSWER 5.20 (1.00) b.- . REFERENCE i AN02 AOP 2203.16 REV 3. pg 1 000008A212 ..(KA's) l (***** CATEGDRY 5 CONTINUED ON NEXT PAGE *****) i I i

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J DUESTION-5.21 ,(1;00) ( ) ' 6elett'.the choice below which best completes the following' statement concerning accidental gaseous waste release. If, after receiv.ing'an alarm on the' waste' gas. discharge monitor, the reading'on-the 'is >'1.0 MPC and: pro.iected off-site activity from the ___1is > 1.0 MPC but.( ___ NPC, declare a(n) a l' !? ~ SPING,. GERMS,; 10, NOUE a.- b. GERMS, SPING, 10, NOUE c. SPING, GERMS, 100, ALERT d.- ' GERMS, SPING, 100, ALERT ANSWER 5.21 (1.00) A. REFERENCE' AN02-EPIP 1903.10'REV 25, pgs 37, 38, AOP 2203.06 REV 6, pg 1 000060K301 000060K303 000060G002 000060G008 ..(KA's) ' QUESTION 5.22 (1.00) AOP 2203.28,- PRESSURIZER SYSTEM FAILURES, provides specific guidance to the operator for all pressurizer system failures EXCEPT which one of the f oll owi ng? - c. Level channels .b.. Pressure channels .c. Heater controls d. Spray' valves t [ (**'** CATEGORY 5 CG4TINUED ON NEXT PAGE *****) l

.:,= q L ' rMrnGENCY AND ARNDRtML_EleNI_EVOL111102S Page 17-t3xD t . ANSWER 5.22 (1.00) C.. REFERENCE ..ANO 2 AOP'2203.28 REV 2 000027G010

..(KA's) 00ESTION 5.23 (1.00)

Which one of the radiation monitors below is NOT required by Technical Specifications to be operable during fuel movement in the spent fuel pool?- a. Containment Purge & Exhaust Isolation Monitor, b. Spent Fuel Pool Area Monitor. ~ _c. Control Room Ventilation Intake Duct Monitor, d. RCS Gaseous Activity Leakage Detection. ANSWER 5.23 (1.00) d DELETED AS RESULT OF EXAM REVIEW. NEEDS MODE IDENTIFICATION TO ELICITE EXPECTED ANSWER. REFERENCE AN02 TS Table 3.3-6 000036K202 ..(KA's) l (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) c___.._______________

5 _Et1EESNY mn 4NDEtdaL_ELehtI_EUOLilIl0NS Panz 18 133%i1* ~ ^*~ iQUESTION 5'.24 .(1.00) Which one of the?following choices best represents the minimum entry . conditions to go from the." Reactor Trip" tab of E0P 2202.01 to the " Degraded Power" tab and NOT the " Blackout" tab? a.- Momen tary loss of normal control room lighting, both EDGs supplying-their buses, either non-vital 4160 bus dead. -b. Nomentary loss of normal control room lighting, either EDG supplying its: bus, both'non-vital 4160 buses dead. c. Control room lighting shifts to emergency DC, either EDG supplying-its-4160. bus,-either non-vital 4160 bus dead.

d..

Control room. lighting shifts to emergency DC, both EDGs supplying their~ buses, both;non-vital 4160 buses dead. ~ ANSWER 5.24 (1.00) B. REFERENCE AN02 E0P 2202.01 REV 7, pg 5 000056G011 ..(KA's) i i I i i ( E i l i (***** CATEGORY 5 CDNTINUED ON NEXT PAGE *****) i l-l 1 \\

---

_-__----_-_____1

7.-,-,-----

.-51IEtdERSEtiCY etJD_aBUQBtiaL_ELatil_EUDLilI1DtiS Page 19 I

cL33%1/ * { .. i.j QUESTION < 5.25 -(2.00): a Match-the~ operatcrs in. column 2 to the operator actions'after 1eaving the. l ~ ~ control room in column 1 based on the designations in AOP 2203.14, ' ALTERNATE SHUTDOWN. 'Itemsiin column 2 may be used more than once or not at. all.- 1 Operator Action Operator. a.- Trip main ~ turbine at front standard 1. RO #1 ___b. Verify EDGs running 2. RO N2 ___c.. Operate 2P7A locally. 3. WC0 ___d. Verify BAMT gravity outlet v1vs open 4. A0

e..

Ensure: operators get proper gear' 5. SAA-from Alternate Shutdown Locker 6. CRS/SSRO' f. Trip MFW pumps at the standard 7. SS ___g. Remove DC control power from designated breakers .___h.' Control 2P360 at breaker ANSWER 5.25 (2.00) a. 7. SS b. 6.- CRS c. 1. R0 1 d.. 2. RO 2 e.. 5. S44' f. 7. SS. .g. 6. CRS 'h. 2. R0 2 (0.25 EA) REFERENCE q .AN02 AOP 2203.14, REV 8, pgs 11-23 00006BG010 000068A100 ..(KA's) i i 1 (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)

7 ' ;( 5 ' EtdEEBENCLablD_aBUDEtM1_ELaul_EUDLLIIlDNS - Page 20 i r99z) i i i i . GUEST 10N-5.26 -(1.50) j Fill;in the blanks in th'e fellowing statements concerning increasing l condenser.pressuro. Blanks may represent single.words'or short phrases. Per:AOP 2203.19,- Loss of Condenser Vacuum, l'f turbine load is reduced to : '( _(a)_% and condenser vacuum is not </= _(b)_ " HGA. trip the turbine. An automatic turbine. trip occurs at a condenser vacuum >/= _(c)_" HGA. ANSWER 5.26 (1.50) 'a. 30

b.

5.0 c. .7.5 (0.5 ea) REFERENCE AN02 AOP 2203.19 REV 1, pg 1. STM 2-24. pg 26 000051A202 ..(KA's) . QUESTION 5.27 (2.00) Fill in the blanks'in the following. statements concerning the bases for the Technical Specification requirements for moveable control assemblies (CEAs). Blanks may represent single words or short phrases. For misalignments ( _(a)_ inches, a time interval of _(b)_ hour (s) is sufficient to allow time for troubleshooting and corrective actions while having-a small or minimal effect on power distribution, available SDM, e.lected CEA worth, or _(c)_ redistribution. Continued operation at normal full power conditions is permitted with less than the minimum number of CEA position indicator channels operable because additional independent CEA _(d)_ indication can be used to verify CEA ~ position. l^ l l l l (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) l E____________--____.

d ,5' -:52.... FMFESEtEY AhlD_eStjDEl%L Pt MIT FUOLUIIDtjSi Page 21

f 3xn.

ANSWER 5.27 (2.00) a, .19 b..- 1 c.- > xenon 'd. full.out (1imit) (0.5 ea) REFERENCE-Y AN02 T.S. BASES, pgs B 3/4 1-3, 1-4 000001K302 ..(KA's) QUESTION 5.28 (1.00) Fill.:in the blanks with single.words or short phrases in the following statements. relate to loss of 125 VDC. A reactor. trip following a loss of all ESF 125 VDC will appear. normal until .the operator realizes the _.(a)_ is (are) not tripped. 'After correcting.the above condition-the highest priority action is to establish feedwater to the SGs by manually operating _(b)_.. ANSWER 5.28 (1.00) I i a. Generator output breakers .b. 2P7A (TDEFWP) (0.5 EA) i REFERENCE AN02 AOP 2203.37, " Loss of 125 V D.C.,"

p. 1-2 000058K302 00005SA201

..(KA's) l (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) l 1 l l~ l

. i ,5CEtdERGEtn mn ABtdDRt%L_21 mT runtijI1DtsS q Paoe 22 g. 1 1 l 'l QUESTION .5.29 (1. 00) l . t ~ ~' Fil.1 in' the blanks with single words or short phrases in the following statement concerning Nuclear-Instrument, malfunctions. k If..(a)_ Stantuo Channel (s) fail (s) durino startuo and Dower is U= _(b)_L 1 trip the reactor. t l ANSWER 5.29 (1.00) 4 m.- 2 (both) b. 10 E-6 -(0.5 ea) REFERENCE AN02 AOP 2203.26 REV 0, pg.3 000032G010 ..(KA's) s l l l .l l l l' 1 l 1 l~ 1 i l t-1 4 (***** END OF CATEGORY 5 *****) l-i [ i i

.CELatC._SYSIEtiS_13fPD AND_ELaWI:W1DE_GENEE1C - Page 23 ^*'- !RE.SEQUS181L111ES_113Z1 UESTION' '6;01 (1.00)- Nhich one of?the following concerning the CEDMCS is correct? ~ A single con' trol rod may be placed.on the cabinet hold bus, a. b.. A " Maintenance Error" alarm is caused by improper voltage on the-hold bus. .c. .The hold bus places holding voltage on the upper gripper of the affected CEA's. d.- The CEDMCS Power Cabinet'aexiliary undervoltage relays output.to the Rod Motion' Inhibit circuitry, i ANSWER 6.01 (1.00) c. l REFERENCE ANO LP AA-52002-12, Pp. 6, 10, 16 l 001000K105 001000A407 001000K401 001000K202 001000G008 i ..(KA's) l l 1' L l L i I I i k i 4 l. (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) ) 1 I. L-a-- - __--e-

{ .y. h.f % ELaMI_SYSIEMS_L3a%1_AND Etaul:W1DE_ GENERIC Pege 24

- ^

1RE,SEDUS181LII1ES 113%1 R r I v J [00ESTION _6.02' (1.00): Select"the statement below which best represents action an operator is

directed to take by OP 2104.04, Shutdown Cooling System, in-the event of

. the following: ~ While placing.SDC -in.operatlon, per OP 2104.04, during normal shutdown,'RCS flow of- ) ~3000. ppm cannot 'be established within one hour of stopping _the 'RCPs. a. Pressurize above minimum pressure for RCP operation and start a RCP. b. Establish natural circulation cooling via either or both S/Gs. Allow temperature'to go above LTOP_ limits and begin HPSI feed & bleed. c. d.

Place HPSI pumps in. pull-to-lock.and manually.initlate SIAS.

[. , ANSWER 6.02 (1.00). a '. REFERENCE .AN02 OP 2104.04 PEV 12, pg 8 005000A203 ..(KA's)- )- ). ). i (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) i .mm_._________

6 EtatdI_SYSIEtdS_L3aZ1_atalD_EL6tdI:W1DE_GENEE1C Page 23-EESPDtdS1BILillES' f 1 Zo - QUESTION 6.03 (1.00) LWhich one of the following. statements is correct concerning the LPSI/cDC -system?' a. The.LPSI/SDC pumps in both trains can both be operated from the Remote Shutdown Panel (2C80) as well as the Main Control ~ Board. -b.' As RCS temperature decreases the flow rate through the SDC Heat Exchangers will increase if a constant cooldown rate is maintained, c.- During hot. leg recirculation after an accident, Both LPSI/SDC pumps discharge directly through the heat exchangers into the hot legs, d. 'The total flow of an LPSI/SDC train is automatically maintained constant by a butterfly valve in the Heat Exchanger outlet. 1 ANSWER 6.03 (1.00) b. REFERENCE AN02 STM 2-5, pgs 11-13, ASOP 2104.04, REV 12. E0P 2202.01 REV 7 pgs 83-86 LP AA-52002-004 L.D. 4.9C, 4.11 006000K406 ..(KA's) QUESTION 6.04 (1.00) Which one of the following CVCS conditions / malfunctions will have the largest absolute impact on Shutdown Margin if each persists for the same length of time? Assume the plant is at full power EOL conditions and all system parameters are at their normal values. a. 2CV 4823 (NRHX inlet) shuts b. SIAS c. VCT level (5% d. 2CV 4926 (BAM flow control) fails shut during blended makeup to VCT (***** CATEGORY 6 CONTINUED ON NEXT PAGE *** **) i

% Pt mJT sysImR -(M MJD PI MT-WlDF r,WFRIE.' -%H" RFRPrWJR1 A111TT FR '(17M 'Page.26 ANSWER.

6.04 (1.00) b REFERENCE _

1. 402 STM 2-4, ASOP 21004.03 REV 18, pgs 21, 22. 59 004000K519

..(KA's) ~00EST10N. 6.05 (1.00) Select the answer below which best completes the following statement ~. During. operation.at power, the excore nuclear safety channels use to produce a wide range signal' proportional to reactor power which is displayed on the 0-200%. safety channel meters, a.-- linear amplifiers b. campbell circuits

c.-

pulse counting circuits' d. ' pulse height discriminatory ANSWER-6.05 (1.00) a REFERENCE AN02 STM 2-67, pgs 2-0 015000K602 015000K601 ..(KA's) (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)

_ ~.. /r pt arr nynTmS_I3a'n mn PLAttT-UlDr nmFRic - Page 27. prepnosts1L111rm (t m QUESTION

6. 0 6'-

-(1.00)- Select the answer below which best completes'the following statement. The alarm annunciator. " Nuclear Instrumentation Inoperative" will actuate. if:--. a. a safety. channel low' voltage is lost b. 'a circuit card is removed from a control channel c. a.startup. channel calibrate switch is in Test Low d. any excore N1 channel's trip test switch is NOT in off ANSWER 6.06 (1.00) a. 1 REFERENCE AN02 STM-2-67, pgs 6-8 .015000A202 ..(KA's) 1i' QUESTION 6.07 (1.00) 1' Which one of the following Containment Spray System (CSS) indications or parameters can be monitored on control room instrumentation? DO NOT p consider annunciators / alarms. a. CS pumo running current 1 b. NaOH. pump discharge pressure c. CSS' header level d. SW D/P across a CS pump cooler l l I ) L (***** CATEGORY 6 CGJTINUED ON NEXT PAGE *+***) I fE

I l + E x:. pr un RYSIFMR QQ*a MJh.pl NM-MDF (FNFpif. Page 28 3.. - * ' prepnrJAinti1TlES 112 1-4 ANSWER 6.07 (1.00) C. REFERENCE 'AN02 STM 2-08, pgs 13-15, STM 2-42, pg 16 026000A401 ..(KA's) QUESTION 6.08 (1.00) Select the following choice which clearly permits continued full power operation to continue for at least 24 hours without further operator action to comply with Technical Specification 3.8 (provided). Assume that unstated parameters are at satisf actory levels. a. While being powered from bus 2864, battery charger 2D34 is connected to bus 2D01 af ter battery charger 2D31 is declared inoperable, b. Battery charger 2D32 is inoperable and all cell' voltages on battery 2D12'are 2.14 vDC except for one pilot cell which is 2.11 UDC. c. During weekly surveillance, a pilot cell of battery 2011 has a cell vol tage of 2.06 vDC. d. Bus 2002 voltage is 130 vDC with one cell of battery 2012.iumpered out . and the lowest cell vol.tage on the remaining cells is 2.10 vDC. ANSWER 6.08 (1.00) d. I REFERENCE AN02 T.S. 3.8.1.1, 3.8.2.3, STM 2-32 pgs 37-40,122, LP AA-52002-007, LO 7.5 l ' 063000G005 ..(KA's) l-l l l. (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) l I o b e

A.; PIAin EYSTFMS-(30%) AND PlAtH-WIDF RFNFR1l' Page 29 RESE0 tis 1811.111ES_113n -

-QUESTION 6.09 (1.00) An increase in which one of radiation types listed below is most likely to cause an increase in the crmtainment area radiation monitor indications? a. alpha b. neutron c. ganna d. beta ANSWER 6.09 (1.00) C. REFERENCE ANO 2 STM 2-62 072000K601 072000A101 ..(KA's) QUESTION 6.10 (1.00) Which one of the following indicates the lowest radiation level at which the High Range containment radiation monitors are capable of reliable indication? a. 10 E-1 R/hr b. 10 E+0 R/hr c. 10 E+1 R/hr d. 10 E+2 R/hr 1 (44SWER 6.10 (1.00) b. (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)

f-r.., / ~ Pags 30 L y; r pt awT svRIEtdS_130%1_et4D PI AhfT-Lt1DE_GEtiERIC ' RESEDtdSIBIL111ES_113%1 - h REFERENCE-j- ANO'2;STM:2-62, TABLE 62'.2 ~ -0720000008-072000A101 ..(KA's)._ i+ OUESTION' 6.11 (1.00)- f Which one'of the following electrical. system conditions or malfunctions -will definitely render emergency feedwate ,, ump 2P-78 inoperable?. 1

a.

Loss of bus 2A1 b. Loss of 125 VDC MCC 2026-c' Loss of EDG 2K4A ' d.' Loss of 12il VDC DP 2D-23 ~ ANSWER 6.11 (1.00)- d. REFERENCE AN02 STM 2-32, pgs 65, 118, STM 2-31 061000K202 063000K302 ..(KA's) i (***** CATEGORY-6 CONTINUED ON NEXT PAGE *****) r

m,,,,,

.t !.,.

JA. PlAfJT RYSIFMR ( #40Y) gjD Pt 4dJT-WIDE _.GFNFRt C- .Page 31 RESprwnintttTtFR (1 ay) k u. !QUESTI'ON 6.12 (1.00) k 4 ' Select the one choice.below which best completes the following statement.

Following automatic actuation of an ESF component, it may be overridden by

' cycling the pump control handswitch to the actua'ted. condition then to a. the desired position. b. placing the: pump control handswitc'h in pull-to-lock. c.- cycling the _ valve control handswitch to the override position then to the desired position. d.' placing; the valve control handswitch in the desired position. ANSWER 6.12 (1.00) 'b.- ~ REFERENCE ANO:2 OP2104.39 LP AA-52002-004-15A 006000K603 006000K409 .(KA's) (***** CATEGORY 4 C0tfTINUED ON NEXT PAGE *****)

cmr: -- s c.. h- , L Elat1I_SYSIEMS_130%1_auD_ELatII:WIDF fiFNERIC' Pege'32 (! W ~ RESEQUS1Rf1TTTFR'(13%1' h '0UESTION 6.13 (1.00) L

A pressurizer codessafety value is leaking to atmosphere. The pressurizer-

'Is at 2250.osta. Which one'of the following statements.best describes the condition of tha exhaust. team from the leaking pressurizer safety valve? a.. Temperature is approximately.655 degrees F. b. Moisture content is approximately 3% ~'c, . Temperature is approximately 145 degrees F. -d. Moisture content is approximately 36%

1. ANSWER b.

REFERENCE-ANO HTT&F pg 91, CE STEAM TABLES' 010000K501. ..(KA's) (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) L_

'i 1__Pt MJT SYSIEtdSi130%1 eND_ELGNI. MIDE_GENEH1C Page 33 ) EESE0NSIBIL111ES_113Z1 .j i f 1 J l 1 '0UESTION ~ 6.14 (1.00) j i (The pressurizer _ level transmitter selected for level control is j

inadvertently isolated.at the transmitter and the variable leg of the j

~ transmitter is.depr.essurized. Assume the plant is at 100% power and actual -pressurizer level was~at program level initially. . Select the one statement below which BEST represents the response to the Robove condition? a. Pze control channel level hi hi alarm, backup heaters energize, spray valves full open. b.- Pzr control channel level lo lo alarm, spray valves shut, a' backup-charging pump starts, c. Pzr ~ control channe11 level hi alarm, letdown at maximum, proportichal heaters go off. d.. Pzr control channel level lo alarm, letdown to minimum, both backup charging pumps start. .. ANSWER 6.14' (1.00) d. I REFERENCE AN02 OP 2103.05, AOP 2203.12J REV 14, pgs 27-30. THERMAL SCIENCES FND-21, LESSON D-7 011000A208 011000A211 ..(KA's) (***** CATEGORY 6 CONTINUED G4 NEXT PAGE *****) [

( - --= r-b a l.' jd hl ANT RYRTFMR ' (jfl%I AND Pl ANT-Lfij)F GFNFR1C. .Page 34

9FRpnnsts1LIIIEs_11321 l

l i QUESTION 6.15 (1.00) -An EDG is manually started and paralleled with-the grid. The " governor" Thandswitch and the " voltage" control-handswitch are taken to RAISE or 4 -!NCREASE. d Which one of the following:is correct concerning the actions taken? 'a.. Kw increases and EDG speed increases.. 'b.- . Reactive 1 cad increases and Kw increases. .c.. Output voltage increases and reactive load increases.. d. EDG speed increases and output voltage increases. 'l ANSWER 6.15 .(1.00) a b.. ~ REFERENCE 'AN02 OP'2104.36 4 l64000A402 064000A103 064000A401 ..(KA's) QUESTION '6.16 (1 00) Select the choice which best completes the following statement. If' all fuel oil storage facilit.ies on site are filled to capacity, there is 'enough fuel'o11 capacity to allow a single EDG to run fully loaded for ___ i days without bringirg additional fuel oil on site. Assume that fuel oil facilities designated for Unit 1 are not available but system realignments may;be. performed as necessary. "-a.. less than 3 -b. 3-5

c. 8 d.

more than 9 I 1 (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)

y,. e. - - - ;I r ll

y. ;l,.

lE #*A P PIANT SYRTFM9 f'40D 'AND PLANT-W1DE..fiENERIC' 'Page 35 RESE0blSIBILII1ES ' (1 m ([:.ANSWERL 6.'16 (1.00) d., g. y REFERENCE-lAN02 STM 2-31, pcs 16, 17, 22, 42, LP AA-52002-016 L.O. 16.3C 064000K103 '- ..(KA's) . QUESTION .6.17 '(1.00)' .Which one of the.fol'1owing combinations of open reactor trip circuit breakers (TCB) will result in power interruption to ALL CEDMs? a. 1, 3, 4, 6 n.- 2,3,5,6 c. 3, 5, ~ 6, 8. .d. 2,4,5,7 ANSWER 6.17 (1.00) .d. REFERENCE AN02 STM 2-2, FIG. 2.25, LP AA-52002-012, L.D. 12.4 012000A406 01200DK201 ..(KA's) (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) f \\

p m !f pi mT synTmm (3 tin AND PI MT= Wine GEUEElt-Page 36 .'% ' EESEDUS18111T1FS_113%1 - GUESTION' 6.18 (1.00) With the plant in.a normal full power line up, which one of the following.- malfunctions or conditions'r:111 definitely result in the automatic start and loading'of'elther EDG? a. The feeder to the 4160/400' transformer to bus 285, 2A-301, trips.- b.- The feeder to bus 2H2 from the unit aux transformer, 2H-24. trips, c. The feeder to bus 2A1.from the unit aux transformer, 14-112, trips, d. The feeders'from buses,2B64 and 2B61 to inverter 2Y22 both trip. ANSWER 6.18 (1.00). a. REFERENCE AN02 STM 31, pg 1, STM 2-32, pgs 21-30, 44, 45,116.117,122 062000K302 ..(KA's) OUESTION 6.19 (1.00) Using figure 6.1, it can be determined that the range of explosive gas mixtures'is best defined as a. 10-75% H2, 30-90% air, and 5-70% steam b. 20-60% H2, 40-80% air, and 0-30% steam c. 30-90% H2, 30-90% air. and 10-70% steam d. 50-80% H2, 40-80% air, and 20-50% steam (***** CATEGORY 6 C&4TINUED ON NEXT PAGE *****)

l..

..L__El MJT' RYSIErdS_L3DZ) MJD Pt #3I:W1DE_ GENERIC Page 37-4*: EES20blSfBIL1T T FR (13Z1 . ANSWER-6.19 .(1.00). b. ' REFERENCE ? AN02 STM 2-06, pgs 1, 2.1D' 028000K501 ..(KA's) QUESTION 6.20 . (1.50)' ' Pressurizer pressure is 2280 psia. decreasing and pressurizer level is -4.0% from program level;and decreasing. Assume that the reactor is operating at 100% and charging pumps B and C are the standby and backup pu'.nps respectively. Natch' each of the components in the first column with.one of the choices in -the second column which.BEST represents the condition of the component. (NOTEi Terms such as OFF and MINIMUM are NOT synonymous.) The conditions in the second column may be used more than once or not at :- 1 1. COMPONENT CONDITION a. Spray valves 1. ON '.__b. Proportional heaters 2. OFF c. Backup htaters 3. OPEN _ d. Letdown flow control valves 4. SHUT ____e. CCP B 5. MAXIMUM __ f. CCP C 6. MINIMUM 7. 1/2 OPEN 8. 1/2 MAXIMUM l i l l l l :. p p. 1 l' j l (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) l.- 1 __---__-_________-_----________-___a

yl? -p [i! ' pf 'APJT ' RYgFM4 - ( 90Y) AND PIANT-Uff)F GFNFRIE. Page-38 p."*- -nF4preJ91R111TIF4'(1 wi IJ f V' t . ANSWER '6.20 ~ (1.50 )' .a , l3...Open b.' 2. Off- c.- 2. Off-d. 3. Min-e. ' t.. On -f.. 2. Of f.- (0.25 each) REFERENCE AN02 STM-2-03, RCS, pg 11,: Fig. 3.'22 010000K603 011000A102 011000K101 ..(KA's) (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)

. L__'El ANT RYET FM A (JD*D AND PLANT 4flDF GFNFRIE Page 39 RF4p m R181LillVR L13%1 QUESTION 6'.21 (3.00) For each of the following conditions (a - c) LIST ALL actuation signals and trips (1 - 8) that should have automatically occurred. CONSIDER each condition separately. Each condition may have more than one answer _from the list of actuation signals or trips. 1. .SIAS 2. CSAS 3. RAS 4. MSIS 5. CIAS '6. EFAS 7. CCAS 8. none a. A steam line break has occurred in containment and containment oressure = 7 psig containment radiation = normal background NR S/G 1evels = At 60% B: 50% Pze pressure = 1800 psig S/G pressures = A: 700 psig B: 650 psig RWST level = 93% .b. A LOCA has occurred and containment pressure = 25 psig containment radiation = 6 R/hr NR S/G 1evels = A 38% B: 38% Pzr' pressure = 1300 psig S/G pressures = A: 380 psig B: 450 psig RWST level = 5% .c. A feedWater problem has occurred l containment pressure = 1 psig L containment radiation = normal background NR S/G levels = At 63% B: 39% Pzr pressure = 2180 psia S/G pressures = A: 900 psig B: 910 psig RWST l e v e l = 85% l l l (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)

. 2.. PI MJT RYRTEtiS f WA AND'.Pt mir-t. Jing nEtEE1C - Page 40 . RESP _0tiSIBILII1FR (1 Tn ANSWER 6.21 (3.00) a. SIAS (1)

MSIS '(4)

.CIAS (5) >CCAS (7) (0.25 each) i b. SIAS (1) CSAS (2) RAS (3). MSIS (4) C!AS (5) CCAS (7) -(0.166 each).. c. 'none'(8) (1.0) REFERENCE AA-52002-013 ESFAS STM-2-70 PPS/ESF 013000K101 ..(KA's) i 1 l 1 i l-i 1' 1 l'- 1 i i l ) -(***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) f. r 4 L i

t.. -

Q Q r i__EleNI_SYSIEMS 130%1_auD pi mi.-J41DE_ GENERIC - Page.41 I . RFEPflh!S$111.1T.IFR (1 To t

1. QUESTION 6'.22

'(2.00) 'The.Lfollowing ouestions pertain to a' loss of instrument air' assuming ' normal,'at power,, initial conditiens.-

• How wou'Id a sustained loss of' instrument air header pressure immediately affect the following components / systems? Match one of the conditions or positions in column-2 to the components in' column 1.

Items in column.2- ,may be used more than once or not at all. . COMPONENT. CONDITION / POSITION l __ a.. Main Feedwater Regulating Valves 1. fall open or flow maximum ]J b. Pressurizer spray valves 2. fail closed or flow stopped c. Letdown flow control valves 3. fall as is or flow cannot d. Up-stream Atmospheric SDBCS Valves. change. _e. EFW regulating valves _4. no immediate effect or _f.' EDG service water supply valves system-functions normally _ g. Auxiliary Spray valve h. IAS cross-tie valve (2CV-3004) 1 ANSWER 6.22' '(2.00) a. '3. e. 4. 'b.- 4. f. 4. c. 2. g. 4. d. '1.. h. 4. (0.25 ea) REFERENCE

p

.AN02 STM 2-69, pg 6, STM 2 03, pg 10, STM 2-04, pg 8, STM 2-15, pg 15, STM 2-19, pg 10, STM 2-42, pg 6. STM 2-04, pg 15. STM 2-48, pg 3 078000K302 ..(KA's) i (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) ) i -}

U d ELANI_SYSIEMS_L30*n_auD_ELGUI_-W1DE_SEtiERIC Page 42 EESEDNSlB1L1I1ES_(1To s l - QUESTION 6.23 (1.50) .For each of the plant locations listed below, match the type of automatic fire suppression. system installed at the location. The items in the second column may be used more than'once or not at all. LOCATION-SUPPRESSION SYS a. Electrical' Penetration Rooms 1. Dry pipe l. b. 'New CPC Room 2. Wet pipe ___c. . Diesel Fuel Oil Vaults -3. Deluge H d. Lube Oil Storage Tank Room (354' elev.) 4. Pre-action e. Cable spre ding room 5. Cardox ___f. TG exclter housing 6. Halon ANSWER 6.23 (1.50) a. '4. Pre-Action Sprinkler b. 6. Halon c. 3. Deluge d. 2. Wet Pipe Sprinkler e. 3.. Deluge 4. 5. Cardox (0.25 EA) . REFERENCE AN02 LP AA-U2002-51-21.3, STM-2-60 pgs 4-7. ADP 2203.09 REV 8, pg 66 086000K407 086000A302 086000K406 ..(KA's) (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) t

l: p-L 1 ' pi Ahrr WSIEtdS_L3GO._a2D_EletfI:W1DE_GEblEElC Page 43-H

• EESE0tfSIBIL111ES_11TD l

l -0 VEST 10N 6.24 (2.00) -Fill in the blanks in the following statements relating to Reactor Coolant Pump (RCP). operation. - The.rnaximum RCP operating time wi thout CCW flow is _(a)_ minutes. This

limit is based on _(b)_.

CCW flow to RCPs is restored by bumping open the isolation valves at _(c)_ intervals to establish'a 100 deg.F/hr cooldown rate. "This limit is based

on.

(d)_. 14 the RCP rnotor.has been running at least _(e)_ minutes, the operator may Lattempt up to _(f)_ start (s). .The fourth R P shall not be started until.RCS temperature is equal to or greater-than _(g)_. The basis of this limitation is to _(h)_. ANSWER 6.24 (2.00) a. 5 b. overheating RCP motor components c. 1 second d. RCP seal thermal shock considerations e. ^60 1. 1 g.' ~500 deg.F h. prevent core lift (0.25 each blank) ' REFERENCE. AN02 E0P 2202.01 REV 6, pg 142, AOP 2203.25 REV 2, pg 2, RCSOP 2103.06 REV 6. pg.3 1 003000G010 003000K404 OC3000K112 ..(KA's) (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) =

9 pi dJT ws.IFMR. (3DELatjD_Rf ANT-LiIBF' nFNFRic Page 44 .l RFRprem1BILIIIFA (m j 1

QUEST 10N

'6.25i '(1 90) l l 8 Fill In:the blanks In-the'following statements concerning'the Containment Combustible Gas Control. System. [A' containment. dome sample may be taken by placing the hydrogen purge 1 '2C33.. manifold selector' switch to position 6 and _(a')_ with handswitches.on Panel-The. hydrogen l analyzers are placed in service af.ter a(n) _(b)_ event'to monitor.'any change-in hydrogen gas concentration inside the Containment Building.. .{ 'Eoch hydrogen recombination unit is capable of maintaining containment s hydrogen concentration below._(c)_ volume percent following any-postulated 4(d)_. ANSWER 6.25 (1.00) .o..' opening dome sample' valves (2CV-8351 & 2SV-8341) b. LOCA c.. 3.5 or 3.8' 'd. LOCA .(0.25 each) l ' REFERENCE AN02 STM'2-06, ogs 3-6 028000K601 028000G015 028000A403 ..(KA's) l 1. l l-1 i l (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) 1

f l p -{ N .[ [- f. Pl #H RYSIEtiS_13D%1_giD PI Mn-W1DE_GEtJEElC. Page 45 J'C EESE0tJSIBILillES ll3%1 E O l: y . QUESTION 6.26 (1.50)- .. j A condition arises which requires entry into.a high radiation area. The operator entering the area will receive a whole body dose of 40 mrem. The- . personnel listed below, with.their related personal information,-are -available to do the work. Each' candidate is technically competent and physically capab)e of performing the task..~EmergencyJ11mits do not apply and time constraints do not permit obtaining authorization for an exposure limit ~ increase. -Circle each candidate who has acceptable exposure margins .to perform the task? NOTE: Each exposure below (qtr, yr, life, etc.)Lincludes the exposure i above it. Assume the current quarter is the fourth calendar quarter. All exposures are in mrem. Candidate' A B C D Sex male nale' female male Age. 27 3e 24 20 Today's exposure'- 50 10 10 20 Wkly exposure 90 150 90 250 Qtr exposure 1220 600 90 1230 Yr' exposure 2200 2995 .210 2810 Life exposure 54730 5200 9770 -Remarks. history 4 months unavailable pregnant ANSWER 6.26 (1.50) B,D (0.75 EA) REFERENCE AND OPA 1000.31, Rev 7, pg 37, 38 194001K103 ..(KA's) (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)

.x----. >u l L_Eletfl SYSIEtdS_L30%1_eND_Ei mT-LilDE_GENEE1C Page 46; -E . RI'EPflNSTRILITIES _ f12"d 'k l j j 1 ) 0UESTION 6.27' (1.00) t-Wh'ich'one of'the following is correct concerning performing an independent

verification.to a valve / breaker-line up?

a. Remove the. locking device from locked valves and then check position 'in the same' manner as the initial positioner / verifier. { b. Independent verification of valves in high radiation areas may be 1 waived.by the Shift Supervisor, i .c. For throttled valves, shut the valve counting the number of turns, then reopen to the original throttled position. 7 d.. Independent verification of breakers may be performed by observing }; control room board indications when available. q l f ANSWER 6.27 (1.00) d- ~ REFERENCE. ANO 0AP 1015.01, SEC 15. pgs 41-43. REV 37 194001K101 ..(KA's) i OUEST10N 6.28 (1.00) Which one of the following represents the correct method for INITIAL verification.of valves / breakers per DAP 1015.01, Conduct of Operations? { ) a. Normally open valves are fully backseated then shut i 1/2 turns and ' finally reopened i 1/4 turns. j I b. Normally closed valves are verified by available position indicators ) or system parameters, they should not be operated in either direction. j 'I 'c. - Locked open valves must be verified by available position indicators i or system parameters if the locking device will not allow movement, j d. Throttled valves are fully shut while counting turns then reopened to the. number of turns specified on the valve alignment sheet, i I 1 (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) i l

{ + h. f. 'pt mr'RvRTFMR ( M1ED_EletdI: WIDE _GEtJEE1C - Page 47 'S ' RESEntJSfB11 iT T FR ( 1 W1 - 's

f. "

L iANSWER.. 6.28-(1.00)- 'd,; t-

REFERENCE

'ANO OAP. 1015.01, pgs 39, 40, REV 37 194001K101 ..(KA's) -QUESTION 6.29 (1.00) ' Select the choice which represents the MAXIMUM exposure an operator could . receive in an area posted " CAUTION-RADIATION AREA" inside the controlled

access.if.he/she remained there for 30 minutes, a.

2.5 mrem-b. 5.0 mrem c. 50 mrem d. 100 mrem ANSWER 6.29 -(1.00) c. 50 mrem REFERENCE. -ANO OPA 1000.31, REV 7, pg 64 194001K103 ..(KA's) f..' V l (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) L:

y- ,l J di__Etatf1_SYSIEtdS_LSD%1_GND_ELatfI: WIDE _SENERIC L Paga 48 i .EESEOUSTR11iTIES (13%1 M. QUESTION. ~6.30 (1.00) Choose the statement below which best represents the definitic conditions. or. requirements found.in the AND ALARA Manual, OF,: .000.33. a.1 Judgement as to what is ALARA is based upon the benefits from the improvements and regulatory requirements. b.- The goal of the ALARA program is mainly to maintain the individual exposure of ANO and. contractor ' personnel "as low as reasonably achievable". c. Jobs.are classified into one of four' categories for ALARA consideration on the. basis of radiation levels at the work site. d. Individual ALARA reviews are not required for, lobs of a repetitive nature and sirellar radiological conditions if a Standing ALARA Review exits. ANSWER 6.30 (1.00) d. REFERENCE ANO OPAP 1000.33, REV 5, pgs 3. 8, 10, 13 194001K104 ..(KA's) (***** CATEGORY 6 CONTINUED G4 NEXT PAGE *** * *)

3 ] x r,. 5 ' PI M_SYSIEtfS_L30%1_atiD PI M-U1DE_ set 1EElC Page 49 ( 'EESEDtJSlBIL1IlES O3%1 QUESTION 6.31 (1.00) Whichione of the.following correctly represents requirements for access control per SAP. 1000.19, Station Security Requirements? a. Individuals responding to an emergency but not normally authorized-i . access to a particular vital area may piggyback with an. individual with proper access and then report to security after the emergency is-controlled. b. When escorting a large group, only the escort needs to enter his/her PID and card to pass through doors as long as the group is not divided up wi th additional escorts.

c..

An individual-checking out a key for a security door will specify the

reason for entry and all personnel entering the space, during key check.out. Further reports to. security are not necessary until the-Key is returned.

'd. An escorted visitor is permitted to enter a space alone as long as there is only one way in or out and the space is not a vital or sensitive area, such as a restroom or conference room, and the exit is monitored by the escort. ANSWER 6.31 (1.00) d REFERENCE. AND SAP 1000.19, REV 16, pgs 5, 9, 10, 194001K105 ..(KA's) 1' l 1 l 1. l l l (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) L_--_-.

g I o- ,n. ..g_m arr RLSIEtdS <9nYi udD_EtatfI:b!1DE_ GENERIC Page 50 f=- l EE.SEONSIBILIIlER (Ni E l l-1 1 i ' QUESTION 6.32 (3.00) l l Using the extract from EPIP. 1903.10 provided, classify from column 2, as-applicable, each of the conditions or events in column 1. If you feel i more than one classification is possible for any condition / event, select I a' single classification and.iustify ycur answer. i EVFNT/ CONDITION CLASS .___a. Both shutdown cooling trains become 1. NOUE d inoperable but at'least one can be 2. ALERT restored within 45 minutes. 3. SAE 4.- GE b. - Control -rcom evacuated and plant 5. none shutdown in progress locally. ___c. Area radiation monitors in Containment reading 2500 mR/hr 90 minutes atter plant i trip following full power op3 rations for 90 days. ___d. Siis experiencing sustained winds of 80 mph. ___e. Steam'line break outside containment (nonisolable) with a 12 gpm primary to secondary tube leak. i ___f. Dose equivalent 1-131 in the RCS is 350 uCi/gm, and there have been no power or thermal transients in'the plant. ___g. All annunciator power is lost concurrent with a generator trip. ___h. RCS leakage of 75 gpm. l (***** CATEGORY 6 CR4TINUED 04 NEXT PAGE *****)

'.. N._iPlANLEYSIEtdS_13D%1_auD_ELatII:W1DE_GEtdEE1C Page 51 RESE0tdSlBILII1ES_113%1 c (. ANSWER' -6.32. (3.00) la'.

5. none b.

2. ALERT

(6.8)

- c.,

5. none

-d.

3. SAE (8.3) i e.-

.2.' ALERT (3.3) .f.

1. NOUE (1.2) g.

5. none h.

2.. ALERT'(2.2). L(0.375 EA) REFERENCE ANO EPIP 1903.10, REV 25, pgs 15-125 -194001A116 ..(KA's) . QUESTION: 6.33 (1.50) Match'the-badge background colors in the right column to the type of individual' desiring controlled access entry in the left column. Base your answer on the type of access generally granted or required by the individual. The numbered items in the right column may be used more than i once or not at all. ___a. General visitor 1. White b. AP&L corporate personnel 2. Blue ___c. NRC Commissioner 3. Yellow d. INPO personnel 4. Green j .__. e. Plant administrative personnel 5. Red j ___f. Contract personnel supporting an outage t

1. 4SWER 6.33 (1.50) a.

5 d. 3 b. 3 e. 1 ) c. 5 f. 3 (0.25 ea) (***** CATEGORY 6 CONTINUED DN NEXT PAGE *****) )

,m_.. 'n ,.D j M EtatfE_SYSIEldS_13H%1_AtiD_EtatfI:W1DE_BEtJEB1C Page 52-

• 1 RESEDtdS1Bil iT1M ( 1 W1

' REFERENCE -AN0' SAP 1000.19, REV 16, pg 7 194001K105- ..(KA's) I -QUESTION 6.34 ~(2.00) J e . Fill in'the blanks in the following statements related to fire brigade organization and responsibilities. In the event of a fire emergency,-command and control. responsibility will be. .essumed by.the _(a)_ Shift Supervisor. -Excessive water level is of. concern in affected areas since the integrity of _(b)_ equipment is only verified (guaranteed) for an actuation time of. _(c)_. Under normal circumstances the two Fire Brigade (Security Force) Support . Personnel should not perform _(d)_ activities unless directly instructed by ,the Fire P!gade Leader. ANSWER 6.34. (2.00) 1 a. affect unit's-b. (safe shutdown) electrical c. 20 minutes .d. extinguishing i (0.5 EA) 1 REFERENCE ANO DA 1015.07, REV 8, pgs 2, 3 f-19400!K116 ..(KA's) F. (***** END OF CATEGORY 6 *****) (********** END OF EXAMINATION **********) -}}