ML20006A086

Exam Rept 50-313/OL-90-01 on 891113.Exam Results:Two Out of Four Reactor Operator Applicants Passed All Portions of Exam.Remaining Applicants Failed Written Exam Only

ML20006A086
Person / Time
Site:	Arkansas Nuclear
Issue date:	01/16/1990
From:	Mccrory S, Pellet J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20006A083	List: ML20006A082 ML20006A086
References
50-313-OL-90-01, 50-313-OL-90-1, NUDOCS 9001250201
Download: ML20006A086 (93)

Text

{{#Wiki_filter:-. q,.(i y .( <to y, t'v APPENDIX X U.S. NUCLEAR REGULATORY COMMISSION REGION IV n. 5 Operator Licensing Exam Report: 50-313/0L 90-01 Operating License: DpR-51 Docket: 50-513 [" < Licensee: Arkansas power & Light Company P.O. Box 551 Little Rock, Arkansas 72203 ~ Tacility Name: Arkansas Nuclear One, Unit 1 (ANO 1) Examint' ion et: Arkansas Nuclear One, Unit 1 E Chief Examine *: +[ / /e/Y6 '5. L~. McCr6ry, Examiner // Darte / Operator Licensing secti6n i. Division of Reactor Safety Approved by: l!!(, 90 J.. L. Pellet,Tection Chief Date Operator Licensing Section Division of Reactor Safety i Summary NRC Administered Examinations Conducted Durino the Week nf November 13. 1989 (NRC Report 50-313/0L 90-01) NRC administered examinations to four reactor operator (RO) applicants. Two of P the applicants passed all portions of the examination and have been issued the appropriate licenses. The remaining applicants failed the written examination only. Performance on both the four written and operating examinations was merginal. The average score on the written examinations was 79 percent with the highest score being 84 percent. On the simulator portion of the operating 'e examination, the applicants displeyed hesitance, confusion, and inattentiveness to the point that their performance wes marginal. NRC examination results for the past year have highlighted declining senior operator performance. In recent weeks, operating errors committed by licensed operators, including e senior operator, resulted in two unnecessary plant trips. The performance of the applican h on this examination coupled with the above facts further emphasired the NRC conclusion that a downward trend in overall operator and applicant performance is in progress. ow1;r.o;o1 coolie PUR ADOC3 05000313 V F DC

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p The written examination consisted entirely of multiple choice and matching test items. Remarks from facility individuals conveyed the impression that unfamiliarity with this test item femat adversely affected examination scores. This'is the second time that ANO applicants have been given a written = s examination of this type. The first was given to Unit 2 senior operator n, upgrades in 1.ugust 1989. -While changing examination formats will affect examination scores to some extent, the time between this and the August r =U examination should have been sufficient to familiarize applicants with these ' types of test items to reduce the impact on examination scores because of l format changes. ~ Comments provided by the facility licensee at the exit meeting and,later in AND Letter ICAN118909 of November 27, 1989, indicated serious concerns over validity of the written examination. The extent of these comments and the 'i . perceptions conveyed by them prompted the Region IV staff to request a meeting s' . with members of youf staff to address the comments. The meeting was held on

December 21, 1989, in the Region IV offices.

It was apparent from the comments and discussions in the meeting that facility licensee training staff had a very different interpretation of the KRC license examination process found in,the 1 'various NUREGs, which govern examination development and administration. Three Emajor characterizations are evident from the post-examination review comments. E' i 1. Test items designed to require syr, thesis of system knowledge to determine system behavior or proper system operation were perceived as requiring ' memorization of procedures relating to the system operation. Frequently this appears to stem from the fact that the questions could be answered by recalling specific procedural knowledge or the use of a system related ? procedure as a reference to test' item development. 2. The perspective from which a test item solicits knowledge was mistakenly, ,seen as the focus of an expected knowledge area'. For example, asking about safety'and safety-related system knowledge from the perspective of system related alarms or annunciators should not be construed as expecting operators to know the cause of all alerms or annunciators. 3. Individual test items that were otherwise sound were challenged for minor, deviations from development guidelines. The Examiners' Handbook (NUREG/BR-0122) and other development guides must be read carefully and in context to be properly applied. Because of the small number of applicants examined and crew responses to recent plant trips from operator error, the NRC concludes that safe plant operation is not jeopardized at this time. However, NRC is concerned that indications of declining performance that are no longer limited to senior operator applicants as noted in prior examination results, a

P o + 3 3 3- \\ DETAILS 1. PERSONS EXAMINED s i R0 SRO Total L Licensee Examinations: Pass - 0 2 2 [ Fail - 0 2 2 p L 2. EXAMINERS p, 1 p S. L. McCrory, Chief Examincr D. N. Graves 3. EXAMINATION REPORTS Performance results for individual candidates are not included in this report because examination reports are placed in the NRC public Document Room as a + matter of course. Individual performance results are not subject to public disclosure. 3.1: Examination Review Comment / Resolution l r In general, editorial comments or changes made as a result of 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 coments 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 t master examination key, Unless otherwise indicated in this section, the = f acility licensee coments were incorporated into the answer key. s At the end of the examination visit, the chief examiner was given the facility licensee post-examination review coments. The cover letter to those coments expressed the facility licensee opinion that the written examination was u ' invalid in scope and content. In subsequent discussions, the ANO Training Manager stated that the cover letter inaccurately expressed the facility licensee perception of and concerns about the written examination. The ANO Training Manager was asked to clarify formally the facility licensee's position on,the validity of the written examination and to make further comments to l' express fully concerns about the test items. This was completed in ANO Letter ICAN118909, which concluded the examination was valid, but made extensive comments. The extent of the additional comments and the perceptions ,l conveyed by.them prompted the Region IV staff to request a meeting with l facility staff to address the coments. The meeting was held on December 21, 1989, in the Region IV offices. The detailed resolutions of the post-review comments were covered during this meeting and are not contained in this report. However, three major characterizations are evident from the post-examination review comments, w3 m-- -m - ~ - - - - - _ - _ _ - - - - - _ - - _ _ - _ _ _ - -., - -, - - -

!t} ' j if-E 4 jz - Sil.1 Synthesis Versus Memorization Test items designed to require synthesis of system knowledge to determine system behavior or proper system operation can be perceived as requiring memorization of procedures relating to the system operation. Frequently this appears.to stem from the fact that the questions could be answered by recalling I> specific procedural knowledge or the use of a' system related procedure as a reference to test item development, h5 The NRC neither expects nor advocates extensive memorization of procedures i-~ related to system operation. The Np,C does expect operators to have sufficient h system design and behavior' knowledge along with a general familiarity with L facility procedures to respond to test items focusing on system response or 3~ proper operation. The fact that system related operating procedures are often referenced is largely the result of the lack of detail in the system '4 description material provided. Such detail is necessary in order to provide ,the assurance that a test item is accurate. 3.1.2 Question Perspective The perspective from which a test item solicits. knowledge is often mistakenly ,L* seen as the focus of an expected knowledge area. For example, esking about safety and safety-related system knowledge from the perspective of system-related alarms or annunciators should not be construed as expecting 4 operators to know the cause of all alarms or annunciators, bI The operator knowledge required to assure safe plant operation is a subset of the' knowledge base an operator needs to operate a plant safely and efficiently. Tested knowledge-is lin ked to plant safety, but individual test items may be' n ' phrased or placed in an operational context using the larger knowledge base. d However, operators have neither been expected nor required to demonstrate knowledge of all systems as they relate to these perspectives. 1 3.1.3 Development Guidelines Individual test items.that sere otherwise sound were challenged for minor . deviations from develo) ment guidelines. The Examiners' Handbook (NUREG/BR-012P) and otler development guides must be read carefully and in context to be properly applied. Absolute adherence to the development guidelines by each individual test item is of much less importance than the collective impact of deviations on the examination as a whole. Any imbalance is undesirable, whether it relates to importance factors, negative focus, or any other types of deviations. Comments i in this area should focus on overall examination impact rather than individual test items. l

( } j q w p ) -S-1 3.2 Site Visit Summary 1 The facility licensee was provided a copy of the examination and answer key for i the purpose of commenting on the examination content validity. The facility licensee was informed that examination results could be expected the week of November 20, 1989, if connents on the written examination could be provided by

• C the end of the examination visit.

ALworking level exit meeting was held with the following persons in attendance: -1 NRC FACILITY S. L. McCrory E. Force D. N. Graves K. Canitz J. L. pellet D. Slusher 1 D. Smith i J. Vandergrift j . Facility personnel asked about simulator performance during that portion of the operating examination..The chief examiner reported that no simulator deficiencies arose during the examinations nor did simulator modeling or design limitations prohibit the use of the prepared scenarios. The Chief Examiner provided feedback to the facility personnel in three areas. f 3.2.1 Distracting Examination Activities There were some activities peripheral to actual examination administration which may have adversely affected conduct of the examinations. The start of the written examination had to be delayed because pens, paper, steam tables, i and calculators were.not prepositioned in the examination room. Unescorted access levels of badged examiners had not been upgraded to allow freedom of movement during the walkthrough portion of the operating examinations. Health physics personnel were resistive to inquiries as to how to enter the radiologically controlled areas while the computer logging system was down. The main impact of these events was that applicants were forced to deal with matters which are not a part of their examinations and were required to wait while these matters were corrected. While not'directly tied to tested knowledge, such problems may have had a negative impact on applicant performance during the license examinations. 3.2.2 Recognition of Passive Failures During the simulator examinations, there were several instances in which applicants failed to notice passive system failures. Specific instances included an emergency diesel generator (EDG) service water valve failing to open on an EDG start signal and an emergency feedwater pump remaining shutdown following an emergency feedwater start signal. In the case of the EDG service water valve, the affected EDG was the only source of electrical power available, and an EDG critical condition alarm in the control room was not

= e 7, t l}{ i, c la .. sufficient' to cause the control room operators to verify all control room ' : indications of systems affecting EDG operation. Proper implementation of 4 the' emergency operating procedures could have revealed the problem before the' t i critical elarm was received. . 3.2.3 L Radiologically Controlled Area Entry During the walkthrough examinations, applicants repeatedly demonstrated lack of familiarity with the current procedure for entry in radiologically controlled areas.; They further admitted to not having been in the plant recently. - 3.3 General Comment _s_ Pbformanceonboththewrittenandoperatingexaminationswasmarginal. The average score on the written examinations was 79 percent with the highest being 84 percent. On the simulator portion of the operating examination, the 1 applicents displayed hesitance, confusion, and inattentiveness to the point that their performance was marginal. NRC examination results for the past year have highlighted declining senior operator performance. In recent wee ks. operating errors committed by licensed operators, including a senior operator, resulted in two unnecessary plant trips. These facts coupled with the results of this examination visit further support the NRC's concern that performance of x ANO. operators and applicants is declining. ' The written examination consisted entirely of multiple choice and matching test -items. Remarks from facility individuals conveyed the impression that lack of familiarity with this test item format adversely affected examination scores. This is the second time that ANO applicants have been given a written examination of this type. The first was given to Unit 2 senior upgrades in i August 1989. While examination formats will affect examination scores to some extent, the time between this examination and the one in August should have been sufficient to familiarize applicants with these types of test items to be expected and to reduce the impact on examination scores resulting from format changes. From the nature of the post-examination comments on the written examination test items and discussions in the December meeting, it appears that facility licensee training staff had an incomplete understanding of the content and . application of the NRC license examination process. This examining process is set forth in NUREG-1021 (Operatnr Licensing Examiner Standards), HUREG/BR-0122 -(Examiners' Handbook for Developing Operator Licensing Examinations), and NUREGk1122 (Knowledges and Abilities (KA)) Catalog for Nuclear Power Plant Operators: Pressurize Water Reactors; these documents govern exenination . development and administration. During the last three years, the objectives and methods for development and administration of license examinations have been well publicized. There have been no significant changes in the objectives or methods during this time. The increased use of multiple choice and matching . test items in the written examination has been most noticeable, but does not represent a charge in programmatic focus. The KA catalog defines the bulk of information on which an applicant nay be tested with subjects outside the KA 1 'd i y

3 f, o y e. 7 catalog or with low KA importance factors being approved on a case basis. The = sampling outline developed in accordance with the Examiners' Handbook helps assure that a random, but balanced sample of KA subjects, is used for each examination. This process has and will continue to result in some test items -which were not emphasized in facility licensee training. 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. i e 30 44 65 15 32 45 68 16 33 48 74 1 20 37 49 25-42 59 Because of the small number of applicants examined and crew responses to recent , plant trips from operator error, we conclude that operator performance is acceptable to assure safe plant operation. However, there is concern that the indications of declining performance are no longer limited to senior operator applicants as noted in previous examination reports. The facility licensee is encouraged to continue investigating training effectiveness and operator performance, i 3.4' Master Examination and Answer Key A master copy of the ANO 1 license examination and answer key is attached. The facility licensee coments which have been accepted are incorporated into the answer key, 3.5 Facility Examination Review Coments The facility licensee coments regarding the written examination are attached. Those coments not acceptable for incorporation into the examination answer key were addressed in a separate meeting with facility licensee representatives as stated in.the resolution section of this report. 3.6 Simulation Facility Fidelity Report All items on the attached Fidelity Report have been brought to the attention of the facility for corrective action as eppropriate.

11 gm yte A @ 3 h,,MIh, k.kP # ^ n. c wg m 7, s u V%,, m }ie ey + Di SENIOR REACTOR OPERATOR' LICENSE EXAMINATION -U.<S.' NUCLEAR REGULATORY COMMISSION su' REGION 4 4 e m Y ~ FACILITY: ARKANSAS. NUCLEAR ONE UNIT _1~ REACTOR. TYPE: EWR-B&W177

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w: lDATE ADMINISTEREDiJ1989/11/13?

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7 II > CANDIDATE:- M CTIONS TO' CANDIDATE-Readiand:followLthe.: NRC RULES:AND GUIDELINES FOR LICENSE EXAMINATIONS attached' tolyoursexamination k lAn;overall grade of at least 80%;is required to pass the: examinationc Examination papers.wil1-be_ picked:up four and'La-: half-(44) hours after theoexamination; starts.- p' .: SITE: SPECIFIC: WRITTEN EXAMINATION EXAMIHATIONWPOINTS i.._BL.00 CANDIDATE!S' SCORE. 4 FINAL GRADEl Allworkdoofonthielexamination.lemy'own. I have neither given nor rpreived. aid'.. Candidate #e Signature i s L . :, R. i O -' -}.. u 5 5 F ! I I; 1

m~ m A. ( NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the-administration of thie examination the following rules apply: 1 Cheating on the examination means an automatic denial of your epplication .and could result in more severe penalties. 4$2.Restroomtripsaretobelimitedandonlyonecandidateatatimemay y li veo You must avoid all contacts with anyone outside~the examination

room to avoid even the appearance or possibility of cheating.

f $3 T_ pass the examination, you must achieve an overall grade of 80%, 4 [4 There is a time limit of 44 hours for completion of the examination.- 5.The point value.for each question is indicated in parentheses after the question. The. amount of blank space on an examination question page is ~NOT an indication of the depth of answer required. Show all calculations, methods, or assumptions used to obtain'an answer x ept for multiple choice and matching questions. L7JP:rtial credit may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLANK. NOTE: partial credit will NOT be given on multiple choice questions. Be Pr~portional grading will be applied. Any additional wrong information th2t is provided may count against you. For example, if-a question is _rth one point and. asks for four responees, each of which is worth 0.25 points, and you give five responses, each of your responses will be worth 0e20 points. If one of your five responses is incorrect, 0.20 will be d: ducted and your total credit for that question will be 0.80 instead of 11,00 even though you got the four correct answers. NOTE: Proportional gr: ding will NOT be applied to multiple choice, matching, or fill-in-the-blank questions. '9, Multiple choice questions may contain one or more choices which are correct IF certain assumptions are made. However, the correct answer bill not need assumptions or qualifiers. Therefore, when more than on: choice seems to be correct, select the choice which BEST answers or~ completes the question or statement. 100 If the intent of a question is unclear, ask questions of the examiner

inly, hliU;Dblackinkordarkpencilonlytofacilitatelegiblereproductions.

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

13, Vill in the date on the cover sheet of the examination (if neceesary),

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w..w y .4 b -i ' 1, u, 03 145l Write your answers on the examination' question'page or on a' separate' sheet' Ef paper as specified by the: examiner. USE ONLY THE PAPER PROVIDED AND DO ,1NOT< WRITE ON THE'BACK SIDE OF THE PAGE.

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1 LWhen exami~ nation specifio answer sheets'aro provided, ONLY the answers

• 1 fmarked on the: answer sheet'will be considered-for examination grading.

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• ? LInformation or answers marked:on scratch paper or on.the examination 4

}? Lwill NOT be credited during examination grading.-

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15. Printt your name [in the. upper right-hand corner of the firstLpage of your answerisheets whether you.use'the examination question pages.or separate:

sh;ets of paper. cInitial each succeeding page. F' Q1'6f If you write'yourianswers'en'the examination question page and_you need core space to answerca speoL(ic question, use a separate sheet of.the. , 'p2per provided and'insertEit directly after the. specific question.- DO NOT WRITE ON THELBACK. SIDE?OF'THE EXAMINATION QUESTION ~PAGE. 317J Before you-turnfin'your examination consecutively number.each answer cheet, including any additional pages inserted when writing your answere 1 on:the examination question page, bl8AlfLyou ate using separate sheets, number.each answer the same as the question to1which it refers and ship at least 3 lines between answere to Lcllow spaceLfor grading. 319. Writel '.'Last Page" on' the last answer eheet.- 320. Une abbreviations;only if they are commonly used in facility literature.- Avoid using? symbols such as < or > signs to avoid a simple transposition Orror resulting in an> incorrect answer. Write it out. 21k After you complete your examination, you must. sign the statement on'the J cover sheet;. indicating that the work is your own and you have not received LnorLsiven assistance'in completing the examination. l @2. Wh0n turning in your examination, assemble the completed examination in the ~~ (following:ordor: .1.- Signed cover: sheet 2.. ' Answer-sheets: 3.- LAll other examination material 4 '. - Scrap paper. 63J W) n y'ou are'done and have turned in your examination, leave the examin- ~

intion area as-defined by.the examiner. -If you are found in this area

whileithe examination is still in progress, your license may be denied or

-ravoked. c;Thasaiins'tructions do not apply if an examination epecific answer sheet is providedJ l

Pag 2 ~ QUESTION: 001 (1.00.) JWhich ONE (1) of.the following etatemente describing the design of the fuel transfer tube is correct? .a. A blind flange le used to close the transfer tube on BOTH the containment side and the spent fuel side. b A valve is used to close the transfer tube on BOTH the containment side and the spent fuel cide. A valve is.used to c3oce the transfer tube on the containment side and a blind flange.is used on the spent fuel side, d.- A blind flange de used to close the transfer tube on the containment side and-a-valve le used on the spent fuel side. ANSWER: 001 (1.00) d (1.0)

REFERENCE:

'AN01 STM-1-51 pg 7 034000K101 034000K402 ..(KA's) QUESTION:~002 (1.00) Group. rod motion is stopped at the full in or out positione by: 3 a cam operated mechanical switch .bi a magnetically operated' mechanical switch a magnetically operated solid state electronic ewitch d, an optically operated eolid state electronic switch

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REFERENCE:

_ f., 1= s. .vm M, m.AN01"STM-1-02:psc14.-LP AA-51002-0101pg~16 4 mE.._ m._;M.4OO1000A202 -..(KA'e): 3 6' [_ b 'a ,' g ,3 a ;; i/o d.i T( y p -f ? r r R g yi; 'l J ', + e ,b 2g 4 A m. ( + l'..- .f' 4-' 7 1 ' E i C3 4 e-7' g, ., -m '. 8,,r n 2. ;.v.-4.~ a + Ys.'$ J r 3 y

p pg ry.c,y g q $pj[. ym< * [ .p j Pagy 4: a;; 3.v.:. y ynl.lgh. v- ,- g S' FGUES. TION:?0042 L(1;OO): t "-Theiloss of-a_RCPJwhile at. full power will result-in which-one'of the .Rifo11owing automatic. responses? y - tr. c 4 'Ai_runbackito'75L ULD andithe~'affected' loop OTSG being on low level 4 7.'ilimite w hb iTave inputito!..ICS from-the affeeted loop, selected and. A Tc near zero. 1 1 j; : ? Reactor.: power reduced :to lessthan 79.9%: and upper' load limit reset 'to LV '~750jMW. LLf

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1AL2:liapportionment of~0TSG feed flowfand ICS in track, n h:.{c{ t. :l% > Q Q p., YANSWER:- "Ob4;J(1.00); [di f(1.0j m %) ?

REFERENCE:

1 glAN01LSTM-l-64.pss'57, 58,-AOP.1203.22 REV 2 pg"1,~OI 1105;04'REV 8 pg 3 h phosooo'K305t ^..(KA's) .w 1 t. ', Q. .1. i, f.. J t ' TQUESTION:t005 (1.00)- 5-4 s ,3Wh.ich oneiof-theffollowing choices represents a correct cause'.for and. S prtf;rrediresponse?toca~RCP'1P32 SEAL' COOLING FLOW LO alarm whileiat full T power 7-mm M% . LICW: flow to any.RCP <30gpme start standby ICW pump. m ,e t i ..a lW ISealuflowsto any;RCP <3gpm, adjust valve MU-28 (A-D). q;j.} DOAqn ICW flow to any.RCP <30gpm, trip affected'RCP. ,P ;' -Seal flow to-any RCP <3gpm, trip affected RCP. d. ? -,5 4 IF ~ g x wm ) l + 5 s N 0 ., y e' h

ag_, wwenwy Page 5 p g 4 's A > I ANSWER:_ 005 -(1.00) ca- - (1.0)

REFERENCE:

' AN01'.AOP 1203.12G'pgs 6, 7..AOP 1203.31 pg 6. ?003000G008 ..(KA's) -QUESTION: 006 (1.00) 'nie pressurizer level control and indicating eystem providee control signale to whichlone of=the following? 1 Primary makeup pumps and the pressurizer ERV. bi Letdown isolation: valve CV-1221 and high preneure aux epray. Pressurizer heatore and makeup valve CV-1235. d-Preceuizer'epray valve and letdown orifice bypass valve CV-1223. ' ANSWER: 006 (1.00)- (l'.0)

REFERENCE:

TAN 01 STM-1-4 pse.4-16, LP AA-51002-003 pga 38-40, STM-1-69 pg 8 004000K101 ..(KA's)

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b [I kly]N-l1 <( r %m s GUE,STION:1007.:A(1[00f s ,e Y % s - Sprimary;. makeup pump P-36A designated as. the running makeup pump : the LWith's = notatu.st of,d.the remaining, primary: makeup' pumps will be: 2, . = - .T JP-36B?in ES' standby;oniA3 and;P-360 in standby on A4.. cA. v,k SP-36B?in" standby on A31and;.P-360 in'ES. standby on A4. M m - - y>..., - u m 3 q p;-36B N ESistandbyjon:A4'and P-360 in standbyon'A3.. -,.n i . Edi;Q: P-36BEinfetandby'on;A4i'and;P-360 in:ES standby'on A3', p;c a

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s m.,, ' a. y w; ? ANSWER:: O'07 i (l'.00) ,J.b: ' .( 1. 0) ' h N.. '. { l4 [

REFERENCE:

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y5 J'404000K202: .3(KA's): s iQ ESTION':c008J.(1.00) m ms m .'s. 8 ';On' ithehtripisignal"has cleared following-ESAS actuation, which one.of.the J f;11owing recovery 1 sequences MUST-occur'in:the order specified to %:succ1ssfully);; reset ESAS7 - + x + ,i 12 4 ~~OverrideLactuated! devices.then reset.' digital subsystems.. 3x - m r-n _. L 'abx , Reset 1analogisubsystems,'then reset digital subsystems. .vm ,W g 4, Jdverride'actuatedidevices,.then reset analog, subsystems, ~

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~. yds 1Resetfdigitalieubsystems, then reset analog subsystems. + 1 <- mi v3y q;, g. %f n :; Vi LANSWER:. 008- (1.00) m c.iSh L( 1.' 0_ ) ' @g + mi a i .g. ? f k ',. i 7 g

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{?, y x i 1 190ESTION:s 009L'(1.00)i w,, 1 i..,... r j.' ; y_,i - e... ?The?TechnicalcSpecifications for ECCSiidentify a train:of. emergency; cooling fas: JHPI) pump,DaiLP1 pump and both: .+- sg nb.m.. spray; pumps. x v. lbl servibeLwater pumps. i k .t U i RB;; fan;and cooling unitse a; ~ L . L jd> 'icore: flood.: tanks? ? t:: '\\ -V;';, j (ANSWERp4 009l:,(1.00) y d,a -:( 1: 0)L g; a 1 f n-1

y 91%

i k 5REFERENCEi-I..ANdiTSL3.3;pg39: 4 , f o.l'30gogSo1L ....(KA's) y m QUESTION: 1010 :(1,00_)! ww,. 1MW$M i one'of!the following will most likely result in an: increase in source 'rans 'NI1(gamma ~ metrics)Jindication.following a reactor trip? ~ ,,x "M Release _oficorros' ion products from RCS internal surfaces. .w, @D Purifibation demineralizer resin retention element failure. 4 ' '- y 3.-

• bw; Rapid uncontrolled depressurization of the RCS.

Wdk 'High' reactor' building temperature and humidity. w 1 3 '):'5 - k -' r [. r. v._.s kj .;h ElJ t' UUk:1.s .,)-

W w ,7h og w",w s q h,ns .e-3.y' s l*ko.Aq;;, s ?

• P' i
• f w

Page; si

+t w s sw ,8 i + v 2. yp c ; %,- hiMN ; + [*)h [ ug - r .6u g ': ,3 , e. v, ~ + '. y;;gm ~ 4 'l ANSWER:- 1010i /(if00): c-w.u w,. :a -. 3c?,W(l'.'Oh' l r in;7 :T; 's .,.a.- w,.. m ( p..g. - e i m B

REFERENCE:

j: ANAHOULP[ AA-21008-000) pge : 1 4, E STM-1-67 pgs 2, '. 3,' TABLES 67. 2-4 : I o ,w llLjgM01500dA103LL..;(KAis)]

y; s

s y; a, ,, m Sh0NSTINb,011y(1.0b) gg<... _s.s. .i s s g_ 3 7

1. Which oneL of.the' following conditions 4will generate 1 a REACT PROT SYSTEM

.;4 TROUBLE Jalarm?. 8-i 6 J '2 4 M. Any: PowerD range NI Lohannel detector power:off. e >-l' %-y f+. .i<,. .y ' /td ; o 'Any:channelfof-RPS'in bypass.

3..

s n' ?;V jAnyEpowerJrange NI channel 41n test or calibrate. A o m,[ r e$nybehanneliof RPS in. test.. id w 'Q S "5 s e e.{.m ~ - ' .,:g s o i g ' ' ei 7'I.h 'i f } )g.;- j;I -,'. h ' idANSWER: (011 '(1.00)J 4 8 c. I g ,.( l',' 0 )' - < ~, ,g s-s. v e, ( g 6h;. J..

REFERENCE:

h; %. .x f: MAN 019AOP3120.3;12Ipg32-m.m -.r, A (01SOOOA302" .(KA*e)- n, N-4 -. a: H. e+ , r., i k o e-v 'k 3 $t . i ~ o, a,. p - o h3 + 8 Y.: 1 s

/'g@;e' i

n -]r; .a ? ~ 1,-{ [}' H ():3 e e M i,. 3')c 'N 'W ,f_

mr. + e .,ww a. m a bf*![% yh, njrh' # Y / fi pdge 'g s v w, n y l 7, < <y+,,.- o 4 w I L

k' w)-

,1 n m; "GUESTION:1012 (1.00)., ~~,..,,,'one'ofLthe following-ev'ents will mostulikely result in automatic ^- .m... W Which j,, i ijoperation:of theiReactor! Building' Ventilation system in the ES mode from a- ~ W; full-Power' condition?; ^ r >.4 ~ - a, OTSG tube. rupture. .,12 ? W b ' ", "PZR;ERV fail open.- ( ] ? i -:o: 4 ;Re' actor: trip"'Lwithout1a turbine trip. t 3. , c.o c J

OTSG manway' access' cover rupture.

a

t x

u. r /. 1 .;}

• Q, '

012 -(1'.00) 7 ANSWER:? hJ '( l' 0 ). .s. f l$ sREFERE,NC.EIS !^ 7vt, a 4, ANOl'STM-1.09 pas 2 1-4,5LPaAA-51002-030 pg 6-h022000A3b1L 3..(KA*s) ~ { r

QUESTION:f0131 (1.00)'

/ LAlrui>ture91n the common. discharge header. from the main chilled water pumps 4(VP1A,B)?will'have whichione'of the following-impacte on the Reactor n -l Building lVen.tilation system fan.and cooling l units?' w TheyLwil1Cbe inoperable in the ES mode but-available for normal J, Jcobling. WWk WheyLwill bel l inoperable in.the normal mode.but available for ES ~ cool'ing. -

They jre.not affected by the loss of: main chilled water.

, Jah .They;are!not capable of any cooling without main chilled water. ~ m. O - ' i 1 y i 1 4 h Y u jfbY i Liiadwi

Wil , lg : % ?**WVl lI lY d / g [ 6lja; E, b; W- ,#~ Page?10-U g ap., o #;- u x m. .,,t-h t.. [f b,0 s z;l x a' x!.., 3 v. /AgggWERP 013t L(iOOj. o 4.. 73* ..#bN f(ilio); m ,p , s- ._ r. - t, 4 1 .). .,j, j' e b x ~g s i

REFERENCE:

-o - i.. a s. i JANOISSTH-1-09s.pssi1-4,(STH-1-45 pas.4-6 hh .l. ].R a:.. E~ iO22000A2057 ...(KA's):< ay,g;% s y;; w.. y.4 A I E 190BSTION:i:014 + >(1.00)' R ~i s s.Which onelof'the:following:' condensate ~eystem parameters affects control ,- l:3,,, signals.i to t.he main feedwate.r: pumps?. ~ a i }[ Sofliwateripressure i. y. w + M.g7 Low (preneure heater? AT. o q '#s.', -lDischar,..ge pressure.: g b ,f, J... ,H

m.w >

l ia. (Heswelnlevel.' q K j.q, w 4 n~.. + ', '{ '. 4 4 h 11 m-. 4 0.141 :(1. 00 ) ~ R -LANSWER: 1 4 'I t(100)i. &u -- 3

REFERENCE:

-l q s M AN01.<STM-1-19:pg 4,-STH-1-20f -p1 [s 'j 056000K103" (KA's) 4 w a, ~ w j 4 cd E (i.. i + N 4 [N s J 1 i s j o i i ~ h 7,, 4 .. i p 7 j i + i I' I ? __.A

.. 1 g

.i i .f g ,l..- r yv ? I( l f ,S S id'd'. ;. ' h %.1$ 'n '. *e {

QF: 93, cp > ,g.y ypNwy m ej MWA.2 W' c- ~; 'Page.11: 1 Q::wbQW L s t rfpA r i a l.4 g li% r*r <t W>. lf.. .c (WB8T10N:l(015 E - (1.00.)4 3 - .7.......... s nHpyAt(full;poweriwithi condensatespumps P2B and.P2C running, breaker 152-111 is pg ohnthresultingiinia' CONDENSATE PUMP TRIP alarm. Which one of the following-hwil1@enthevresultfofthierevent?', , f;ab J P2Cf running: with runback Lin progress. y ' ~., 9 @ by n P2A startis -Lin Tetandby and : P2C remains running;

s. n'~.

3 ", W. .Srunning with runbackfin progress.- P2A a Edf OP2A?st' arts;sn standbyiand POB remains running. A

j. 'ii.$

..i y,, + ~ t jANSWER:(;015 i(1.00): 4 . ( 110 )' x {,.;jj Q i

REFERENCE:

1 $ AN01iSTH 1'-20 pgL8h OP 1107.01LREV.33 pg 12 2 0 56000A204L .(KA's), hQUESTIONF016 (1;00)1 ~ i i 4 g 7 -sE : J t gWhich?one of the following is correct'concerning the operation or behavior s;fathe-Reacto.rfVessel and-H.ot-Leg Level Indicating System? r ,, p dTheldN1'taLTlbetween the.. heated and the unheated thermocouple decreases y

• f *intalsteam-environment..

.. Jg., 2 ..f 17bb A J Loss of heating to' the junction of the heated thermocouple will cause W,..i..# s 7aflow; level-indication. 1;AUunheated thermocouple at 690 den.F will generate a low level alarm. i OJ. s s M.d.h Indicatedilevel will be. greater than actual level if reverse flow is Os

initiated;through.the reactor vessel and core, e u o

t 1 .,,3- { s i L 'i

• +,....

i e , xg \\ '

• a b.

4

pm n y &mwt. ,g-wa ,:J -1. mp-4e .o ... m r 7 r. gg QM vWu i < V i 4,

3...

. Pag 3 12 0 ' S. g}s'w'd % '_ ;f + 1 n

\\ \\

y. em o s;qqg m. .,s 1 ?c z I%MQ ; y AN9WERF 1018 -(1.00')' r 0 4-i, w i : Trd$ 31)00)? y;% w> p s

REFERENCE:

m

1. ' A' N016LP: AA-61002-009 pg 8-IS, 1017.000A202Di dOOO74A116 t..'(KA's)

.f" myger r m l-p :{ ^ _a;. W \\@@j}CV ( w V% _..K _ j, T., __. ^ y(GUESTIONi:017) (1>.00)1 Which' one Lof; the :following/ is ;a! correct response of. the Gaseous: Radioactive Wastef(GRW)[ system.to a,high gaseousfactivity level?- aq - w. 4 m

1. , 2 'Hisf activity 'atithhi stack' gas monitor. (RE 7400)' secures flow from' the

/[ ] hGas Collection: He'ader; and: diverts ABVH ito-the. waste gas surge ' tank.

2.,

t E

• l

.t' @J*'4GRWheader;downstreamof:F116-anddivertsiABVHtotankaT-17. .bn; * [Hi'sh' activity 3 atithe wante? gas monitor (RE 4830') secures flow:from the' R s s. m p, m 4 JW '. iHEshlactivity:ad the~;st'ack sas: monitor-(RE:7400)isecures flow from the, b,a 7 'J.ABVH4and'divertsiflow from.the;REVH to:the' waste' gas" decay l tanks. W 0o > N di # LHigh5activihy at theLwaste gas'. monitor.(RE-4830) secures-flow from;the, [Q+f-ABVHLand/ diverts'flowfromtheLRBVHtothe'wastegasdecaytanks, y ,3. j i. u ' a SNNSWER'il LO17N(1.00)$ a g M, Q(l'.0)? gy _. s .;n - W-

REFERENCE:

l 4 gep;3

a. ANO1ESTM-1-541pgs I'l -5,J STM-1-62, pgs.'10, 11 it

i M go71000K10_6:

.. (KA's)'

Y, f e, 3p? P. ~ g s s i. } ;.' Q* 4-o r $&l c-l4 a .1b _g h.([ . : 2.A ~ t eu 3

@p %m% mu .q q&ic

.m w.+%%,y#. Q,,,

1 SM h

Page:13f e

p gemy gg((;4 m r. va :,. u i i %.. < '.... '.1/ L [

p i Q,,!'Il% !

f_,_ F i i w f GUESTION: ; 018.f l(0100)"

{ > W.

2 .'3 E.. a. - dhC , i. .L,; v $m+ -[,.. DELETED ASzALRESULT'OF. POST-EXAMINATION REVIEW.' x ,h, - 6,. ,h. , ' f '.e 4 ! r y 8 i r o t .~ /m, iE_ ; 1 c 7 sANSWER: f018X-(0.00):, c, _ cm ? DELETED!- m g 4 >. 4 4 p. A m xREFERENCEt; ~ 4 J, W y .I f ' b,' :,}. B_ t v~ tDELETEDf w ~ [ 5LO7iOOOA20'2E [a ..'KA~e) ( .o. .'{ d I j-g I i ,e ut. r. c, '1 'k 1 r.

b. ;{

l a ! GUESTION :-J 010 ' (l'. 00 ) R , p p ":: N oon;:whi$hloneJof)theLfo11owing. areas'does thetventilation:eystem noe a s.JIn trolcsignalideveloped'from-an area radiation monitor?2 e.

m. : -

a ; -u

r 1.y T M;

Perietration" rooms ' ...~, ( Spents fuel': handling' areat s c -q i @s,:, DCont'r.ol?Roomi hdbs. AuxiliN5yMilding.' w. .. m

.py., "

,%o -- g GLESTION

. 0201~(l.00)'

w - .t,'f' 9' itWhichE:oneTof::the following.would result from the loss of power to the: 9de.t.ector'..of.most area radiation. monitors? g; & ja.,

• Indication'atifull'iscale.

,+ s T [z, Jb7f ' > Iridication:atL minimum scale.- e. t i P,, ^Indicati.on atL: warning setpoint. m 'q] h >w b,'jIndication-at-alarm-lsetpoint.. - -, :s .i ,'? & ; w s

~;

mp~ .3. p i a-SWEk:L 020'.J(1'00) -.o c 4c N,- ((110): gg e,.

REFERENCE:

[AN01{STH-1-62Lpgs11-3) fBEdIN' GROUP.11. . H J072000A201 (KA*s) jn g 3m dh0ESTION:002i';(l.100)., Se1C t3he Lanswer which correctly compic.tes the -following statement. ,lIffpres'surizer; pressure-is2100 psia,quenchtank'pressureis.5psigand hcinitialJguenchitank. temperature is 90 deg.F, a leak across the pressurizer "1ERVfwhilevatifull power will cause'a-downstream ~. temperature indication of

l bout:

..7w=< 162 des.F g Q f2281.deg.F1 L318sdeg.F- .. _. ~.. Gdg ' 6 4 0.. d e g. F og y .I -?

• a s

t--.'. } s-w Y. E a b

-,_ m,_,e Page 15 ' ANSWER:' 021 (1.00)' .bb 228 des.F (1,0) 1 1

REFERENCE:

.- Steam Tables THT&FF. THEORY 000008K302 000008K101 002000K105 ..(KA's) QUESTION: 022 (1.00) The loss of which one of the following DC panels would directly impact the =nutomatic operation of pump P34B7- 'a, Dil D21 D15 D25' . ANSWER: 022 (1.00) b. (1.0)

REFERENCE:

AN01 OP 1107.04 pge 28-31, STM-1-32 pg 28, STM-1-5 pg 4 '006000K201 ..(KA's)

llkfhYfl ^ 47 K L,*4* f?$f yMSN}P l "f'-lgf ^ 'Y 'f 4 81 7 Pagi 16' EMp 3 ' ' > + n e f~, mnp n + Id,i%:~ l@f!, ' M& ;,. 8~ a ma u

WM 1 A.,

,.

SABST10NE023) f(it00h, .: ;x w v.m s-

d. :

..N., p,ithich[onetofitheffollowing'pressurizeripressure--controlsystemmalfunctions 4

W would moottlikelycresult'..in'ESAS actuation?:

p 7 i,, " ~ %./!. iPre ssure '- instrument? f ail a rlow.. 4, ~, v. 1: .e "lb M HHeatersifaillon.- v c. - ?:, t=. Mc& i;. ?.;. Heaters;failioff;. $$n v (. Y.,' \\'~ sw + -; p,?. :.. ,,.4. .z, F1d1,' i Sprayivalve? sticks;open. a b '5 y y ..# G;; j.k / p y. _,,.#'b t \\ (ANSWERi' (023 :(1100).. , d., i s.. :c fdM' _-( 1. 0 ); ' y y,( jo c m. L

REFERENCE:

i p-x d ANO11STH51'-69)pge 2,3;13. STM-1-65.pg 2,.STM-1-3 pgs:6-8,-LP AA-51002-001 n x .nnH,s,,m m -. ~.. m 01000.0K303i '(KA's)9 x.. ya 1 ^S J-g' /,, yy- .g gt . a. (QUESTION:f024;((1.00); r. .... +. Y Whithione of the following.is the correct' initial response of the Makeup M andsPupification::sys_ tem to the. loss'of_ temperature compensation to the. C..'ntrolling pressurizer. level channel? W Q' I;.?y,1, Makeup flowcincreases whilo letdown flow remains constant. ~. ;+ ; x -*i,g,-99 ,g 6 b.,F.. SMakeup! flow increasesfwhile letdown flow decreases, u" i {li h. -ff gn% Makeup flow decreases?while letdown flow remains constant. m N d # ; ?'%';-iMakeupj-flow; decreases while letdown flow increases. 3,Q,*'-' } $ \\.f M. W m IANSWER: 0247 (1.00)- m we,, ~('1;0) y 5~T o -- i s ..,.fW m 4 e-l bl 2 i =j. - a3 i. ' Q: i s e p.?

W W o.7",_ :: k

1. w a,

7Wf ; b ' T ' d Fg.g.g r l;E > c-Page 17: w: No.. v. t. tA,*m o-p,...wn ~ r i i, pchN 1 MpB3tENCE: J 1,- 4, J}y B'4 s 4 p u;1 ? DAN 0150P11103.05p[5,-lOP110402pgf8-11',STH-1-69pg7,~CHARTERISTICSOF

,-_<.p n :.,.

BESATURATED: LIQUID' ' 6.4% - N (011000K402 ,L.. ( KA '.s f 1 w g: < -.f zr - 3 _It r '~ j IGhNSTIONI O25? '(iko0f ' ' '.+ ,u T, :::., sAccording to Techriical7 Specifications. :which one of the following, RPS trips- ~.. . =... y ,.-Jisl.NO.Tispecif. ically; intended for DNB protectio'n? ; n hM4 ~ 1, ,.ta bv &' -l-[C PowerMimbalanceb flow. y,. + .m ,: c + Wb., - Low 4 pressure. 3 W...c aMi(('{High[temiserature-- M i 'W L..., 6

d g.

o u.h # TVariable' low.preneure: i' 'f hy.'I, jr. 1 i e..

2. g., [ N'V x

I ((~

A ;f ANSWERi> LO25 ', l(1; 00)

. 3 ey,...,. '. / .(- '4 Q;;l: l ? '(,. 1. 0 )f ,m p/.

REFERENCE:

L t-5 g pSANO11TSJpgsi11-13,?LP[AA-51002-006pgsc18-23 L g{m.20ooK501 o1 -..(KAts) g i_ V ( l E g N: ' is v + f, f l-t ${i: - i !i:.>. y K

.fd I

( j 1

. k, I A

3 M , 4. Y. ,,Q,., hy 9..; g 'y-1

y-- P:g: 16 QUESTION:.026 (1.00)

The~ CONTROL ROD PATTERN ASYMMETRICAL alarm is generated by an indiviual rod position.more than:

ja. 7" out from.its RPI group average and will be accompanied by the anymetric rods lamp on the diamond panel being on. b.- 9" out from its API group average and will be accompanied by the individual fault 3 amp on the PI panel being on. 7" out from its API. group average and will be accompanied by the individual fault lamp on the PI panel being on. 9" out from its RPI group average and will be accompanied by the anymetric rode lamp on the diamond panel being on. -ANSWER: 026 (1.00) (1.0)

REFERENCE:

AN01 STM-1-02 pga 17-21, AOP 1203.121 pg 49, AOP 1203.03 pg 1 014000A102 ..(KA's) ' QUESTION: 027 (1.00) -Following a failure of an ICS Turbine Header Preseure Instrument LOW, at which one of the following ICS control stations can the transient be terminated by the operator? Diamond Panel b; Turbine Bypase Valve H/A station es Steam Generator-Reactor Master 'd TG control station

%g c , m pf q 3d[hl Wls c-) e,'fM. N Page[19 K 2': ' + + + g;yl a' g f q,' u j-. ~ i s. g m

o :

@: ;-%,g%s ", .Q ; ' L > :-

g. -

E. fANSWERi.n f026 :(.1100).- .ud +.... h;M, 1 ( 1. 0 ) ' tw= e' c (REFERENCEi4 w w [ANd1STM-if64jpgs?2030$ F 1

filGg, L<

SJ /01 a,p~ w, x.6000A201 -..(KA#s): ~f f 6 g-/ v, 1 - o._. GQUESTION:c028k(1.00)) w e, -.a ..,,3.., e ViWhich,one;.of;theifollowing'is correcticoncerning'automatio-operation 6f'the G.ReactorfBuilding! Spray ~ system?.. y '.?At 61.BWSTLlevel,'RBSLpumps stop untillthe, suction is shifted'to the c [,, w. "RBisump. ~ '1 a .Jbi -,LAt".RB pressure of 41 psig',-the outlet / discharge' valves-from the.-BWST' gNr and RBS;pumpsiopen.. 1 --k, -( whichlwill'have to be manually: restarted. lAfteriESASEactuation, a'losstof. bus A3 or'A4 will strip the RBS pumpj 'l Q;Sn; - S... ' i db At?RB. pressure ' of. 30: peig,: the NA0H tank-outlet; and spray; header cdischarge valves.open.- ..s ta [; ' bi\\c 1-t-s w fi ~ ANSWERi? 1028':(1.00)' u if 4 n E dv' f ( 1".0)l . um.: + r p TREFERENCEi? IAN010STM.18'lpgs2-7 5026000Ab01'. ..(KA's) c,s f..., R l.. . l; t9 e" (U-n. Oi . =' Y

r. -

ft,[ 4 g .? Q/. a

m

_=,

- - - _ _ _ -.. =

s..,,

,-d Page 20 ef _;, c ,7 s A. f.1 x00EST10N: 029 (1.00) When startin the RB Purge system with a negative pressure on the RB, open the purge inlet valves before openin the purge outlet valves to prevent: a. damaging RB penetratione during suc). den pressure change b. inadvertent relenee of radioactive contaminants. c. damaging purge discharge due to reverse air flow. d. reverse air flow through stack sample monitor (RE-7400) - ANSWER: 029 (1.00' c (1.0) hEFERENCE: ANO1 STM-1--09 pge 4-6, STM-1-47 pge 6-11, 19 029000A401 .(KA's) QUESTION: 030 (1.00) Enich one of the following spent fuel system parametere or conditions produce abnormal condition alarms directly observable in the control room? a. Spent fuel pool reetreulation flow. b. 1CW flow through the spent fue.1 coolere. c. Spent fuel cooler filter differential pressure. a d. Fuel transfer tube ge_ t.e valve not fully shut

1. NSWER:

030 (1.00) a (1.0) 3 s

f % ]ff}f T f as c ,b? Ny$@Q

P u t 2i

49 v-ew W s 4 c y:1.Yfa., e,_- -.g ly: ,i 37 c. 4 t ?15E14RENCE:$ w A1 x g ...vs X .,a,i.. s >>,._c p gl,p.%-- ly ~,~~m AN01hSTMti-07Epgs?2-8h0P21101.02;REVl8:pgs 16,.18 9%, ^ 4;c ^ '~ 1 -m : ~ ;, ' ' ', M, m..kO330 BOG 00BJw ('KA's): v - w .,e. 1 2, 3 .T_' t j p. scn. -. JQUESTI. ON: t 031f.; ( f. 00)- T WhichEoneLo 6theifo11owing isDoorrect,concerning design and/orloperation of: pi. the-l.MSIVs?;, 3 '_I. d' 4 J Going f,to '"open'G onithe.HS causes-an internal'Lequalizing: valve to openi (%, l, 'andEwhen'pressureLacrossithe: MSIV11s </= 50 pei..the' pilot-operated M? Epneumatic<ventsvalves open:the".MSIVa e.y. = s gpfG E. m Eb./ Theiaccumulatori keeps th'ef MSIVs: open ;to ' allow: ' ontinued. power c ($ 1 y fgenerationLwithilow IA:hea' der pressure. m jr E 4 ' .v. 4 5. i. .,.. i k Og. 40ne"close,",geprings'_ provide'the'< motive force for. valve closure while: 1,1 closurefspeedTis?regulatedLbyfaniorificelin(the-? vent.line!.of: pilot-s r f=%;operatedipneumatic vont valves. m., -~. z mu u-dE iTheyhydraull'odoperator:onithe-valve:is intended,to ensure valve! ~ C'E 9 closure'onLlossiof' instrument + air. ~M> a q 'w ,g

r. -

(d, '. (c.... "..., jy. ii; u gg y1.. RANSWER W;;0311;(;1300) g,... M. bf A M if 0f ~y w G. i'?-l l t ii M._

REFERENCE:

l

e.

Q,.u.$,wAN01? STMi-1-15i pgs iiO,411, 19 4 ,n, s e >E035000K601f i(KA's)- 1 .,p %s m H ,c J'hk ) os .w s y c; .] w + - t r.. p,.9 .:3 e 3 _ i ,s-- .l.' g 1 h ilmQ!, F k dp J f h. t Q T o s t i_d t T g , y(;,( i.y j / i 4 4

p. fU i[ ^

• E 4

6 &;$!$ 4Oil_- i l, m

g,. P: 22 ,1 JQUESTION: 032 '( 1.'00 ) .Whi h one of the following will be the response of the turbine bypass ,v_1va,T to a steam header pressure increase to 960 psig from the initial @ ndittons._below: Load demand ~12% Turbine latched and loaded to 12% in operator auto Turbine bypass valves' shut Steam header pressure at normal setpoint - 5 peig. / Valves remain shut since setpoint + normal bias not exceeded. b;

Valves open and reduce preseure to setpoint + 50 peig.

c,

-Valves open and reduce pressure to setpoint + 10 psig. d. Valves open and reduce pressure to setpoint.

ANSWER:

1032 (1.00) d (1.0)

REFERENCE:

AN01'STM-1-15 pgs 11, 18 STH-1-64 pgs 8, 9 039000K106 ..(KA'e)

, s pu sn e n f 1,Mi' -Pr.g ^23 j

.3

, Y v:,; l x 1 a-QUESTION:1033.(1000) 4rWhich one of;the^following condenser. vacuum system malfunctions will have ~ 3ttheiHOST"immediate adverse'effect on-condenser vacuum? Assume the plant. 911s1 -t:fullLpower.in iluly,:the~ condenser vacuum system is in normal iau6omatic1 operation, and all automatic functions occur as' designed except

leispecified bi the malfunction'.

' Operating seal. water-recirculation pump' trips. v b; ' Aux 111ery' cooling' water to the seal water coolers is lost. The: motive air val've to the air ejector fails shut. ,d; Air? ejector bypase valve fails (open) to' hogging mode, m IANSWER: 033 i (l'.00)- (1.0) REFbRENCE:. E AN01 STM-1-22 pae 2-6 055000K301' ..(KA's) (QUESTIONi 034,(1000) 'iWhich oneiof'the following is' correct concerning the continuous run time of 'ingleLEDG-running fully loaded with ALL fuel oil storage facilities on it; filled to capacity, fuel oil systems designated for Unit 2 not Ev111ablejand system realignments performed as necessary? 3. less than 3 days b.; l3-5 days- =c. l6-8 days d.; more than 9 days m Y

c Page 24'

.;11 +, q l:u 2 > e ;.

c.

JkNSWERi 034.(l','00): ,[ds (130): /NEFERENCE:' LAN01!STM-1-31, pga 6, 7, 15 + n 2 064000K103 ..(KA's)- s " QUESTION: 1035: ~(1.00)',

Aside from improving-plant operating efficiency, the Circ Water Waterbox VacuumLsystem is important to:

91 a.'

Prevent" lake? water from entering the feedwater system as a result of-

.Bmall.condenBer(tube-leaks. 'b; Reduce circ. water pump discharge back pressure to keep pump motor-temperatures within limite. 'c i. Prevent damage to;condenner tubes which results from steam impacting .on dry 1 tubing. 'd.- Remove 1disolved' gases.from lake water which interfere with antifouling ' chlorination treatment. ' ANSWER: 035' (1.00). Loi '(1.0) i

REFERENCE:

INO1 STM-1 40 pg 2 2

075000A203 ..(KA's)

i[h}

n Paga._25 e ; 6_ ',. ' '

s.; !, ;Y LlR ' s QUESTIbd: _036" (l'00)' N t K (Th: tervice. air' to-instrument air crossover valve (SV-5400) automatically topenb when: s rdN 'instrumentLairiheader pressure _ decreases to 50 peig. ibt ' service air: header pressure decreases to.50 psig. .. ic',s ainotrument' air header _ pressure' decreases to-75 peig. m /d.1 serviceLair'h'eader pressure decreases to 75 peig. ? ANSWER: 036-;!(1.00) M - ( 1. 0 -).- w 5

REFERENCE:

A ?ANO1LSTM-1-49 pg 1, AOP 1203.i2K_pg 29,-AOP 1203.24 079000A401- ..(KA'e) IQUESTION:-1037L ?(1.00) ~ With-respect._toLfire-protection instrumentation, the term " cross-zone datection, system"Lrefers to the fact that: ta. multiple 1=ones-are monitored by a common detection system. Jbb audomatic actuation requires a signal-from at least two detectors. ' ci-detectors;for one safety train are powered from the opposite train. id. a zone is monitored by more than one type of detector. 8 i i $ ANSWER: LO37 (1.00) (b: (1.0) 1 1

lii

]' s

. q, TTF W T - ;, 7.- TY- ---= ya g y c; ;' er,. [%.,@mm; MOM Q.77 e,.$ s y LP::gf261 ve. : M s m. g s w x , ; $y 3,,. .a Om, m 4 1 4 - .m TBEFERENCER ~'. %;p(AN011STMilb60: pas s17 f)181 f! qu,., vy ;.. <, ',.. ',, _.y;.. + c y e" g% edROUPMII/4R $*%!;0,86000A3021 w + 2: -.J(KA'5)? n 1 ~ u 9 MM J= ' R + y :r :WM g _.,. @;; pESTION:s:03Bi f(14.00)k g#,, m --,, ;. .o ^ 4:t ..'v ^~ 1J Oncetthel hydrogen':recombinersLhave been started following Ja :LOCA,c $significant hydrogen: recombination,will not begin foi about: (ATTcCL hm;l<[ tot 0Pj1194)31$ provided): ..a y M / % v1 M 2? hours;< ? a> e @ % Y,, L2 W 3: hour.s.. ,M.. n y- ,'y < ;gg, s Jf,. 63;t-}4hburs.-- H o h.f -, ;?a 53 @! d,f~1l(, m.- 1 4 S - R 5 h'o u r s. s s k$ff ' Js. S'y *m q ^ . ;G t. f yl' ? q. /. "r: 1 wW ". ..x o, _ 3% 4 ANSWER:, 't_..0381 ((1.'.00)4' ~ " - ~t.m -.. x... u q%. 3 }zi,0f (jQ ' l ['. l. n [v$FENENCE: R x ,,m o ~,:.. t '^l,;. ~~

~

..ru MANOliOPJl'104!311pgsS2k12 W

1. m.5 WM J:0280.00K601?'

028000A401~

-028000A202 028000A101. ..(KA's) n y j;; Q > w g",f ?._ 'lf ;p 4 QUESTION:h039)1(1100)' , :n > $0niESiactuationUthe'DHRcoolersareprotectedfromoverpressurizationby: d 3 ;r m; ;% w; >, <fttiriglthe 'inletJand ' outlet valves and opening the bypass valve. - t eh i C , 4 'Tbhecksvalves:in:the core flood injection /DH removal lines. 3a~ l i k.fch <(thd automati'ciclosure and interlock system.

a

, [dh. Jnothing since the coolers are designed for normal RCS pressure. p

• N,$, n. > 3 -

i y ',H! 'l* l#w ", 9 t 1 Qh o 3;y, r s:.gly,.. p, n y;,n -, A1,Q.) / y

,3 :. .Pago127 5 6g,, o ;. 4 f,;. 4 ~ PAN 5WER:; .039 -(1.00)J r[ bj

(1.0)-

c k

REFERENCE:

cAN01'STM-1-5-pga 2-10, P&lD'M-232-E' -005000K603 ..(KA*e)- QUESTION: 040 (1.00) L'3WhNchoneofthe-followingsetsof:containmentparameterswouldhave-the-mont' impact onithe reliability of NNI in the containment following a LOCA r;withJ1% fuel failure? i ?< [. (c. Temperature, pressure, humidity.

b1:.

Pressure, humidity, radiation. /c.. Humidity, radiation, temperature, ilfd. Radiation,-temperature, pressure. , 1.'00) "ANSWERt

040

( c., (1.0) 'REFERhnC3: ! AW ^ jf PLANT-WIDE-GENERICS 103000A101 ..(KA'e) 1

m Page-28 j; 3, o a - 1 ' e $. LQdESTIONi 041' (1:.00)- iWhich one~of.the:following is correct concerning performing an independent - varification tot an INITIAL valve / breaker line up?

.a.

Remove _the locking device'from locked valves and then check position -in'the-'eame manner ae'the initial positioner / verifier. ~ ~.: Independent verification of valves in high radiation areas may.be waived by,the Shift Supervisor, o? For throttled valvea,'chut the valve counting the number of_turne. then reopen to the~ original throttled position. 'd. : ' Independent verification of breakere may be performed by observing -control room board indications when available. (ANSWER: 041 -(1.00) Jd; - ( 1. 0 ).

REFERENCE:

'AN010AP 1015.01, SEC 15. pge 41-43, REV 37 '194001K101. ..(KA'e) 1 [ QUESTION: 042 (1.00)- LWhich one of'the following represente the correct method for INITIAL .alignmentcof valves /breakere per OP-1015.01, Conduct of Operatione? . a '; Normally open valves are fully backeented then shut 1 1/2 turne and -finally reopened 1 1/4 turne. 7 e b..

Throttled valves are fully shut while counting turns then reopened to the' number of turns specified on the valve alignment sheet.

' Locked open valves must be verified by available position indicatore ac '.. =or system parameters if the locking device will not allow movement, d. Normally closed valvee are verified by available position indicatore or system parameters, they chould not be operated in either direction. l l

Nkkhk hk h[IY,$1k N, [" M I h4wn. m.m:o. s i Pan. 29c m m n &e x. g %, R. . g ra y a-mw ' nw C J 4 ' ' p' ~ t4CMpcsAny dy4uMIp;niE m A, ' t,i P ~; *

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• ,3 ;I )' v - r' ' ' 7 L

vW:i x' r 3 u s + VL s ..I I,h f (pl 5/ ' -( te%n*M;. '[ TANSWER W O42 M,-(1.00)?m n ; ; :ca,' 'r'N'. i [_j,ey= w n'cs - (s - y, e* 1 g i t il 4 g w' s y o m. w/% 4 + b :. e ,.,p -- n., g A i n;- % k M W :f,b O)? l- -g;c #f' >( -n. - ^

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jg i e.m, r.y.+ s, r

'+, w n; . s.g .a i;r VANOE0APa 1015. 0,1 ? pas E. :39, J ~40,/ REV -l37c - - n u,~ - N ~ S.. N.9m!. -D~ d'9IOO1EION,' d.,N. lKAN~, )l ' il m, \\ 4 * , bK> ly ) s. ,e

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v'g iU:. ..;; %s I s s W,p s 'iI 4.w~ f i g:- f,.. ?. t z- .d 14' 4 ~%lg$1-?j j,p.;g, g' 4 q: s , 9:n ; wh ? 1QUESTIONn 0432f(li,OO) W s, a at: i 8s u 7 :q ;,, .z?:Q... g..?+v .epresents the? MAXIMUM exposure anioperator' lcould? MSe1Mtittihej choiceTwhihh@d 3" CAUTION-RADI ATION ( AREA" s ineide v the contr 2 receive"inianearea7poste $a - 3 1 Q ccets:'if7he/she hemainod?therebforj30Dminutes.- w. 4 z Min klg "-.' QL y* _(

n,,

.s ? 12 6fmrem= w g,_b_ m7 6 Or m. rem, m, . %s -,- @c m!. s-50 w:.d h., 4 1 0. 0. 7 m r e m..i W. + Awcl# t.m.r.e,m: m 1 m pg 7 pg., ) r 6 "g94 'h[ }.h., y/ ;' Oi-A %:- eg. j g' r 3 ..;7 74, ]W@3 -'.i Ng-4 h ~id '4 m,. , M,., ~ ', i i.i'3 ,ty'

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a 1 v a- '1 '\\ g N; y *ldk;' xy] .st, n 1

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c tyg:;K ;; Hmf + a._ s ^# +- 4-f+, QUESTION' @- <44311 00)i. n., r . kl 3,. i

e. ;

,.g , (., _g e U.. f WilfdalRWPiindicateesthatia';; task is(subject 1toEal Standing ALARA:-Reviewf(SAR)W this-

9) ': ' n wY Waean? E M dj 'that::

d Mn @ a MiPari[ALARAEbreifing is;notirequiredLpribr fto each' entry underLtheiRWP." c. c N.

• . Vs

-.. _'. ; L :-..- ,e_ . ^ a sj W y tantALARA breifin,g. mustibeiconductediprior toleach. entry underjthe RWP. 4 m.a m i' [ t hy e h1 ?' t 4 e .c .r., ._....r-r p @ ithe'i M alEestimated> man-rem for;the task'is?less:than i-~ man-rem. 4

e..,, _..

g d M f ther,t'otal estimated man-rem for5the taski.is; greater.than'10;manyrem. ~ pn pf j e t 'h .I. ,@@n i 4 h i ,$4

if.,1; A f.

m. '3. QD s - 1 .o i ?ANSWERp <~O.44 ((;1.00h ~ m s.- s l ;i , ed (~f. 0) - _

1. ,, :1'c.l,,

8 l 4 'm.> I l { '., g 6 nr w t E

REFERENCE:

ev pw a._ r. bANOfOPAPN000L33,)REV[5, pga110 -13 tan g s u i - :. gp? M194001K104J

. ( KA's) v m

%m*, QR ;g s .bb r g g g;' r M;'9). . < t s 1 n gt...s .O y t 9 . n.'. i k b (%'f 's5 '., T y y*-_}~_> i qs 4 s i t

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m. w k'h O I

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s M.,@

1 hh s a i i ~ b + - 6 1 g,y. 7[h h i + g i c ? ) ~ gls f-ll l'tJ; > - n.q m, y.. '. i ..i, Ngh 3 i y ~

f j.$ Page 31 ,s k y l LQUES ION:'045 (1.00)- KWhich one of the following correctly represente requiremente for accese l control'per OP 1000.19.. Station Security Requiremente? 'a.

Individuale:reeponding to an emergency but not normally authoriced accese 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 doore as long as the group is not divided up.with additional' escorts. cc. ' Arr 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 le~ permitted to enter a space alone as long as there is'only one way in or out and the epace is not a vital or sensitive area, such as a restroom or conference room, and the exit is monitored by'the escort. ANSWER: 045 (l'.00). d1 (1.0)' ~

REFERENCE:

ANO SAP > 1000.19, REV 17, pge 10 - 15 194001K105 ..(KA*e) l l

__= 'k Il Page 32-l' R& :, di Ty ;,f L.Q $$ TION':L046 L(1.00) L e: Excessive ~; water level is of concern in affected areas since the integrity- '?of: safe shutdown electrical equipment is only verified-for an-actuatior. r 'itime of:' La.- 10' minutes. s b;. 20 minutes Ec. 30' minutes:

d...

60-minutes. ANSWER:

046

{ 1. 00 )- '2 0

b:

. ( 1. ' )

REFERENCE:

!LANO OAP - 1015.07-REV.8.pg'2 194001K116 001000K100- ..(KA's) -QUESTION: '047-- (1.00)' EUnder' normal. circumstances the two Fire Brigade (Security Force) Support Personnel should not perform extinguishing activities unless directly instructed-by:

a.,_ the Shift Supervisor.

b'. s operatione. personnel-at the scene. ,c., .the" Fire Br$gade Leader. Jd. the SAS Supervisor. cANSWERi .047. (1.'00) c (1.0)

M MWs'TQM. ##.M. %. m% 14-., - m._ .. - -n M_ V@.+%p. p 4,h_ge;gn%g7}u[ m .6 + + x e q a = ,. e ' _ h_$ m 3;Q' r G .Q L~ w.-m'.?,fsjbG >Pa'g&V 3.~ naa n i , s pdegdAm a 4 "g -@f .,gy. \\ m 3 @ ps-e c. -ma a __ w _, y t, e-p; ~ w. + m. - m. 9n w ww.u.~,ndwre%, 'a p%ERBRENCEd '. - qm. ~ - - w- ~ + - mnw . + + s W Wr ~ s g s w' g. y

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.w ~ .._aq- .n., cm w A ~ ' MAN 010AT,1.015f.07QREVi8#pgs32 i new; o,,n .a n-. M M dO,1000K100s > $,194061K116h ~h(KA'e)) ~ ~m e ~,, 1 .f' g 3 ^ g 7[ f i c c T,. f I i L .m, o, 1 - " t'[ l " m w,[ -w,f s y ,.' ' ' n n'h.' Y %yF .e 4 I 4 I +h[. C,.M a,l7 [* g.v 'w 4 ?^ ~ a + m. s, m c..4. m. w,, -- .mo w m ,m - -., m., p. u .=.m_ r a r c. $.n 'UESTION no,48 5 l ( 0.'00); m.- w+ G w w + n - w h-q;Q;@.*p {m: w.g' " pNq y@p s > 4 w. xt a m < i4A1 Of _ aq, '4s k m,, hp 2 .c.,' 3c ug g ) 4 g@$a,,3 1 h r-p . pm v,. x.t 4 7 $DELETEDTAS? AERESULTEOF. POST-EXAMINATION 7 REVIEW 5 c ,+ nle af;wf;ff y om. ~ _3,..,_ W{'- f.. d " - r.l$ G j .,r b I. 't.-' Ma+ + g* i;4s, n . ~ i 1 ,. @mh'Et' .., w %w, .1 y?- _ j' h,^ i .[, .[~[ ' ! 8 t y

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sgq

$,4 s -. ANSWER:5,f1048? (0200 M M s.= vv v.w:, / ~ 4 w~ -n ' e% m,S_v..o ,a. t.n :: ; (DE,LETED: 4

5

+ a. mr s w_. me e,m a + 4 m e.m, s7 ;Q i r ~ s i.y. ysn .,m~ b -. t.,.% r.3 %' l., r,,, s ! ^ A s._' 1 ) f_. c J

REFERENCE:

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Pagt 34o a %g g O;.e.'*m 4 t ty' y Wh?hkY M M(0.! " TJh& ? ' G i:b Wl Mh:DOW@s NQ ',. ~ 3, YQUESTION:i(049 Q. 1.00)i u. c Y:. 4 _ g q A Mhl':Eity$s? operating"atl1.00Mpower1whenthefollowing1alarmsiarereceived: w> m; @[% 1RCPdP32?SEAMW 'IER FLOWiLOl(K08-F1). $ $ ' > LRCPf1P32 ?SEAIT COOLING 1 FLOW SLO :(K08-E1)? '~JW g?RCPJSfBLEEDOFFJWTR TEMP HI (K08-A4~). MlWB iRCPZSEAL1CAVITYcPRESS.HI/LOf(KO8-A5):- El.! L RCPJ HIGHiVI,BRATION1, -( KOB-BS)i ' w mv .m'._ 1 m ? -M.%'Mrtvis'wtofcpanel:instrumenthtion5dusing the > next five ' minutes indicates: a_ Q[a" [ Seal (cavith pressure? indications _-are erraticJf6r RCP P-32CLand.~32D J ~ hb'.4 1 ~ 6 Y 1AcontrolledfbleedoffitemperaturesJare indicating l175 degrees.F.for RCP-y[el$$f:Pn320andi32Di CV-1207f(RCLPump Seals' Total'INJ-Flow)Mindicates closed _. b LCV;2233E(NucleargICW)ForiLetdown1 Coolers and RCP Seal Coolers RB' h@e l, 'DInletQindicates: closed?. St . 4 _...& $Which one$of f thef follciwin's iisithe -c'orrect immediate.Lastions per.1203.31'.. is !1Retotor1 Coolantf Pump; and: Motor:- Emergencies?'* ~ ~ L um: + ic %

TrifthetreactorJandLreferd.oEOPil202.01.

h 5 ' ITripiRCP/PA32C;and 32D and verify ICS in_ track-and runback in" ~ - M.yb b., -p,s eprogress.- yg [i(b ' 7 Mob _,,.2 a sr ~

ReopenTCV--1207; addJverify sealE injection-flow; rates of. 8-10 gpm per

$!' i

gpump, c&

e .r Bdk,1 !Tripfthe[reactorLand.then:tripiRCP_P.-32C and 32D. + - + ( ',Q" i t t' m t /. 4- .1 .s g. @ANS,WERig ).O_49' ;(1.00)! .m

m g

f ? di-t - ,+ ' :::c: gW - i y th

REFERENCE:

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myi,

,:x,.~,.. i eQUESTION: 1050 M(1100.) . g s r ec .e w I. MVN[Jw. .I fF ^- g M,_ ,P " h.i Q)$torbs?redirid31fitwoic6ntroMrodsfailftoEineertfona'reactordtrip' g.d WhichYonejofTth M fd11owing; correctly 1 escribes;the3 amount 1ofJ.boroniexpected:

?

4 W tilife?! % '* ym_ ' e v; + pa:, ", l < 4 ~ 7 , w. M. ', * @;" 3 Q g. E_@ L p 200lp,. pm v 2., lg , f . y-s v @ _:Q.y;T4. 0 0 ? p p m M +&. l. "e m ? 7 w, if ?. f% % , l;. f. 2 r -L r [p Nc: l600x.-ppm. y - -3 4 w w;,x x a. g7gh 80b$p'm.4.f s 4 Thhdi ', ' L

• A

~" o mesm w, a W +:i~R..$ f aff < a -3 ,, r _. ,q Q ..] o s..,z g ;,ee. A. 4 \\ :M

3 Qp i

p 75'0: L(:1N00); MANSWER:3 0 twe 4 ? m,(.s / x. +f"2 l j fr. ' fn 9 P <> j g k',- __$ p .$ e 7.' t, y j t 'lp .] x

e n

c. ...-m." 'o 4 REFERENCE 6 ,a... 4 f ~, ii 'r . flg 5 u W 4 j $13iO2j0$R'evp17@id~314 1 1 n, s... . : I G' .T' J M.0.0,0'0 2.4 K 3 0. 2,!.. .d. KAFe )~.- .d-J q .g y bi! y. '., & 4 1' ^ ?$C i W i !% # ~ g, SQdESTIdNh051Lf(liOO)T -3;-- x u ~

- k +

• 1If $rhadtorSpressilrej haelolowly 3 decreased !to/ 21151 psig, 2 what hea'ter _. banks n

iaut'omaticallycenergizeDin addition,to;thosefnormally energized?- dwil'll q v;n,., 9 M_.ir;Ba,nksV1E.and 2;b s,. y ~ y n.,. ;_, p l., ......,,.?... y Mbg W Bankesi;,L::2 Jandc3: $.5 ' s I 5 1 t dcys 4 'Banke d,$2,7 3,;andN4! + w: i %u --dM i ?B,anks:l1,v:12,#3;14, and15 w:.,. m;, e

• ~i j l, b e i

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L yo c

IANSWER P /dS19 (1.00) %rU: ' .:~c,' 1 M,;am ., - v. i i cL, ; 4 f %u -., ,7, - f up 'm

1. t' 9

I f I ' y .t ym:n , d-u, < i-7 ) ci-u,,- ,( , 3 n /;%.pW, 4 s -f y Ajs' f j,.N d 1MnyWE i

-Page 36. 3 v-LEEFE;RENCE: 1203015,oRev. 5, p. 5 .m 000027A205 ...(KA's) MUESTI N:-~.052 :(1.00)

Which onefof the following-ie'the correct tab or taba in 1202.01,

'! Emergency Operating Procedure,"Lfor the following.' conditione. 1T+0 -Reactor trip.from:100% power due'to low RC pressure. All; control rode fully. insert. No' secondary activity' alarms. LT+30ceo Immediate actione of. Reactor Trip tab were completed successfully. Follow-up actions of Reactor Trip tab were ocmpleted until transfer criteela met. T+1 min- ^ Main steam']ine : pressures are 800 peig and decreasing, RCS:eubcooling.ie 40 degrees F and decreasing. Pressurizer level 10-40 inches and decreasing. RCS pressure.1650 peig and-decreasing. RCScT-cold.ie 540 degrees and decreasing. T-hot-is following T-cold 4

ai

-REACTOR TRIP 1 concurrent with OVERCOOLING.

b.

OVERC00 LING.= Jc. ,: LOSS OF SUBCOOLING MARGIN.

d.-

OVERCOOLING. concurrent with LOSS OF SUBCOOLING. ANSWER:- -052 -(1.00)

.b.

L

REFERENCE:

.1202.01i?Rev. 17, p. 20,'29 000040G012 ..(KA's) s

p[.A 4:ys WpMM*u 'wd q 7' ypigN,37f ?^ s+. s M qpcc$$f.m f,, s ' w e. r .m m x W,1 ,,[ l li;{i M Q, ^ s. 5 y A,d4 R W< 9 O: Je;. ;W.L, e ys :n ; ~ , GUEETION:iiO53 : ;(1100.); i

1. zm -

<<.\\ l #. f .'.... ~,, -.%w a. jh ' ; f '~ "$WhichEons?ofs,theifollowinglis a :correctEstatement:'regardingscondenser 4 e jyacuum[andkreactorfoperation?), l W.L N: 97 ~ ~ Quwu ~ ~

1. E cIfJreactorjpowereistat: 40% Land c'ondenser.vacuunicannot be. -maintained J,C& %Nabovei24.5" Hg,?thencthelreactor must beltripped'.--

a, b

y s

$p ',@, mjIf! reab't6r,ipow'erlisflese(thani30%. anil condenserfvacuum cannot c N maintainedLabove: 26.5",Hg, thenithe. plant must(be. shutdown pertOP-M w 11102 10.x ~ w c( ?l0 .a ? =!p ;4, /If[;c5ndenser lv,....acuumidecreases-tocless than-17" Hg,ethen reactor-power- ,, Lmustib'eireducedit'otlessLthan13%. g, g< r s - w c. i i ! <f.N

'D

~ fdh M Ifico6densernvacuumcdecreases.to less than 5'? Hg,;thenLthe' reactor d f M imust be1placed in5at suberitical condition' withini 6 hours. g%, Q. ' =q ?% ce p_ r J.:.

s. w

= Q' fM,SWEh.. }; 9 1 7 --053 ?(12.00) + jg .m ; 3 j L. w .. D k-a- u}p,. < m 7 m; . +.= pc 9

REFERENCE:

/ > w '.,., '1.-- w t'. I-3 D c_. I. .5.. 0{1203L16,-fRev;{4GpM254 m gu. - C.g,000051A202i 7.l( KA's ) I hS q w b 'q,. r, MW . E . ?. - c... io 1 t. EQUESTION:0054 E(1.00): d pvon m y)Whichtone sf/,theifollowing?iststopped per"1202.01 during a station blackouth ~n 9 f.c?to M duceidrain on station batteries?- l9 E ' n M.. l W @um.pl emergencyJLldbe. ' oil pumps. nm - h4;N>$FWl pump 4emergencyiube'oilpump, i po[ iHPitAUXD1ube oil pumps. n 4 s \\e,. w u O ?.,V,, ' m a ggTED0hsoakdbackloilEpumps.

i

~dA

m.;

p$$K. ' 4 c :me ;.> y J wy w; np N ~ 4l 17 l v 1 n m ll vr, n ll* qc. ;,' p.\\;, y ' ', y s + 4, j sB Sh & a1 ia m1.1 -4

Wlh ,3sd Page 38 [' 7e r v i- \\ ]AN,SWERii'-054- (1.00)' Ed. 4 - !R$FERENCE: /1202'.01', Rev. ! 17,. p. 216-- s 000055K101' =..(KA's) ,P. s QUESTION: 055 :(1.00)- Which oneEof the following statemente correctly describes the' relationship (between a lose of.X and Y NNI power supplies? . a; 4 oLoss of NNI X. DC is more ' eevere ' than' NNI Y DC and loss of NNI' X AC is more:eevereLthan loss of NNI Y AC.. iL' s's: of -NNILY1DC is more eevere than NNI X DC and lose of 'NNI Y' AC la b.; o more severe than loss of NNI' X AC. ' To. . Loss of NNI X DC ~1s more severe' than NNI Y DC and loss of NNI Y AC is < more eevere' than loes of' NNI X AC. 2d.. Loss:of NNIT!Y-DC is more severe than NNI X DC and loss of NNI X AC is imorefeevere-than11oss of NNI Y AC. $ ANSWER: 055' (1.00)-

a'. -

E

REFERENCE:

1202'.01, Rev. 17,

p. 243 000057K301

..(KA's) .+fL t-A

a EA Page 39-j*;}, (.'..N i l QUESTION:.056) (1.00) 1Which~one~of the_following actions is required to enable reflash of J (cubsequent alarms after the initiri FIRE-alarm'(K12-A1) on the fire ' protection panel-C463 control unit? , ca. Reset = panel-C463 using Reset / Lamp. Test switch on Control Unit, jfbt

Deprees the " Alarm Silence," button on CP-35 in panel C463.

Lc.

Toggle-the " Trouble Silence," switch on CP-35 in pane 3~C463.

d '.x iReset-the FIU by depreesing the Reset / Lamp Test switch on CP-35.

(

JANSWER: 056: (1.00) Tb. P

REFERENCE:

(1203.09, Rev. 10~, p. 31 00'067A106 ..(KA's) 0 ' QUESTION: 057 (1.00) Which one of the following is an INCORRECT statement of the requirements (forfReactor Building Integrity per 1203.05, " Loss'of Reactor Building Integrity?1" .a., Both-doors.of the personnel lock are closed and sealed. One door on-the personnel airlock is closed and sealed during . b. 4 personnel access. ,c. Tall non-automatic reactor building isolation valves are closed as required. $d,

All automatic reactor building isolation valves are operable.

$, ;V ', '* .Page 40 o J ~.+,e; b- ,t-g q-..;q % g /'.. JANSWER: 0571-(1.00)'- N ~ ' adi l

REFERENCE:

) 11203.05, Rev'.-5,;p.11 (000069A201) ' ..(KA's). QUESTION: 058 -(1.00) The entry-conditions for'.1202.01,- section 7;0, " Actions to Correct lIna'dequate' Core Cooling," are: 17.'1'.1 Superheated'oore exit temperatures, or' 7.1.2: . Primary to secondary heat transfer cannot be established AND

HPI; cooling.is inadequate.

{Which one ofEthe following INDICATED conditions satisfies these entry 4l conditions-(Assume'all.RC pumps are stopped in.all cases): iRCS Press. Core Exit Temp. Tc/Th difference EFW Demand-to (psia) (deg. F/ trend) (des. F/ trend) maintain SG_ level ' a'. .1000 -440 / decr. 25 / decr. Yes nbu 7500 420 / incr. 200 / incr. No 'c. 1200 300'/ decr. 100 / decr. No Id, (1800 500 / incr. 10 /-incr. Yes LANSWER: 058- (1.00). <bi u 9-

e

< c; Page141

<c

a. =,

JPEF8EENCE:- i g -(1202[Oi'.JRev. L17 ; ' p. 102,'106 00007dG011 ~ .f(KA's) UESTION : '1059, (1;00)- ,Which oneLof the following is a symptom of FAILED FUEL.per 1203.19, "High ' Activity in Reactor' Coolant?" 3 a. Increase in grosa/ iodine activity ratio on recorder RR-1237. Nb. DecreaseJin grose/ iodine activity ratio on monitor.RI-1237. E ncrease1 n grose/ iodine activity ratio on monitor RI-1237. I 1 ~ L o '. d. Decrease in gross / iodine activity ratio on recorder RR-1237. i; ANSWER: 059 (1.00) id;

R5FERENCE

1203'.19, Rev. 4, p.

3-000076A104 ..(KA#s) -QUESTION: 060 (1.00) 'Which one of the following is the first. corrective action for a blackout condition, per_1202.01, section 10, " Actions to Correct Blackout?" Ta'. Establieh natural circulation decay heat removal. 'b. , Verify HPI cooling established. Nn-Verify 480V MCC BSS & B56 energized. d.: Select REFLUX BOILING cetpoint for EFW.

tv

j. 1 Page.42' yy, I.':t j.

^:;,, hAN'SWER:L4-l060i (l'.00)_ s JREFENENCE: 1 h-{1202:01, Rev.- 17,.p. 205' !000055G012- ..(KA's) QUESTION:=061-(1.00) 1Which one of;the following tabs.is to be performed while attempting to lrcatore NNI'_powerDeupplies per 1202.01, section 11, " Actions for Loss of

NNILPower,"'. step 11.57

.at

Emergency Boration.

b. ESAS Actuation. 'c. Main Steam Isolation..

d t-

-Reactor Trip. os. i; ANSWER: -! O61. (1.00)

d';

[REFERENCEi-

12.02.01,-Rev

-17, p. 237 000057G012- ..(KA's) L: QUESTION: '062 (0.00) DELETED AS A RESULT OF POST-EXAMINATION REVIEW m

m m. k ? j A e. y 9 W' JE M_k/Ola - ) ' ,-+- E. ~j ', -- c~ y ,6 9 .iPagei435 %g4g w;;p- ' < v - t ,9 v p n x n ga;L A@ ,,p+c-q,,O ' n,- 4 i i + + r a. u ;g. g 0 p yvefe, g-

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!$ANSWERis 0062V (0 00)1 ' qb;m c - +v e h did b. DELETED)N;7 s %~ we - ' Wig ]Q,c a w$, t;.y,q 7, . 1 q@

REFERENCE:

V..y ', w 3 1 m s.- s w m hhbN"ODELETkD[ h' Q)%,0000003K205:',:4(KAfSF ^ @W;, n v -. '. .w x .~ -a~ ym, Q [} __ _ _[ m, s -8 v u m i' < !: MUESTIONGLO63 E(1;00% ' ~ 7., g .t! s.. f, " a > ~ W; 1.f. m. s Whi:ch-one of!thelfollowingToorrectlyncompletes the paragraph below?, 3 g:m.3.,. g,. + y -..s T.. - ) Following'l al reactor Etrip,J the: SPDS CRT ATOGsdisplays will1.,,..,show<a p ; g%:% norma 19transientJwindowswith"the" minimum <and maximum'expectedipost-J ..y u P* c E N. egi itripi 1, '.IiThet'emal10 box 4inside this windowLehows the; expected" .+ P =Twol boxes show expected! f %.i <for3normalthotn..ehutdownto'onditions. g -o 6duringlnatura10 circulation.: m qn, 7 g 4 1 @,. c;q (T-ho~t~eand?T.. cold ? average? temperature,; pressure and temperatur'.

• 4; e

(,.r;4aq,s v. r.,

b41)w' Pressure's/and temperatures, c P-T frelationship, T-hot andDT-cold.

u 3 nn,j dA% [Prsesures lan'd{ temperatures, ; average temperatures, -T-hot and' T-cold t'ir 5 % '4 '. 171.: + tC, (h s . @/idyf mT-hot andjT-c61dt P-Tlrelationeh'ip; 4 m_ s.. pressure and1 temperature. ,h j pklm%% +, ~ l gu 4

Upp, 1

1 g)ii/ F., f. t a j i .I. /m mANSWERi1 ' 4 0639 i-('liOO) e e. ~ e:, my4 L l p%. y, Yk k], i Y a pm ;W: L

REFERENCE:

o@ !s s. - - ~ [{% 1202LO1W Rev!.$17L p. 28 m .~.. m<, p ;X00000.7K203: ... ( KA's ) ' i g, w pua., m w m, s ' t 91. , p-yg 1 43 It R t 1 kb t a 3;p'i. . N. <p2 ; - 5[, ,,._ ;Ci s, p; t 5 T Y } .) { t -J j r,l) -.,3 ,iY. p

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REFERENCE:

-J ,A > ~,, yv..

m;. ip y:2g# DELETED.:-

--n. + 4 k: nu a w,J. mm. M;FmN0bD00$A10'6L YT. (KMA)b ' ..'<f 1

own,

.=7*, u. .. i" s i 0 1 -' h; f }lg-e w w . f* e ,,. 4., :. N,1. '; ';,,..,...,.. q _ (p065 b 1200)! g

1. 4,1ESTION n/-

- - i, _., a c. Mt,V ., MQ 9For%hichiefdhe [fonosingjregionsi ( refer to ' the? attached? Figure. S') L doesu JM2021011ressise 3thaty.themoperator? run all four. RC pumps.L defeating starting. 1 n 3 d int:rlockadif neaessary?/ w% ' 4m .m ,..m. 1 ;"- & ' : l ggDR q..L %; ; i f R e g i..o n 1 1), 4 1 ~ g 7 F n.: N/M. a W TR$'Idi6.n. Y) I m m . - m }tJW= M. 1 Region:3 g : 5 r 'e.' 1 x 5 A: i s, ,'q 3.w.t. e. M, 4 m: - x, : yo %dn

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REFERENCE:

a2. 4 w% w w,p 4 1 A M 1202:01k Re,v.(171 p.

110, r wgl,;D ?l :;.e,..,.

1 a iOOOOO9A201~ .(KA'.e)- 1 m a V r ;,, l t ll qh; ;,-Q , c. a . y T ~ s Am, e?. s a -- M ,d q 3 1;g _> r bh j ' N,!D ) ...J, ) J a.. g,; r = 5.'.

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g p !khi.5 j k.1, ? ,N, h,:(f,.1 i h 8

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{- 1[ l .#u'_. u i i q ](,d p g*, .__.,e a y c g ..r,. p ')' T

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.-t , r,f h /S ' '.

k. d '

n> Page 45 x ;:. ~ ..g?^ QUESTION:;066: (0.00) f" < ' DELETED AS A RESULT OFLPOST-EXAMINATION REVlEW L: ANSWER: . 066 -(0.00) y . DELETED

IREFERENCE:

> DELETED. -p f0000i1G012 .. ( KA ' s )' ' QUESTION: 067 (1.00) LWhich'oneLof theLfollowing alarms indicates.that the DH pump has lost esuction,1 causing a-loss of DH removal, per. 1203.287 ' a'. DHl pump trip. 3 b. .DH-flow--low. .;ci RCS ' low' level'. , Mi iAux.'bu'ilding sump level'. ' ANSWER: 067-(1.00) lb. J

REFERENCE:

-1203.28, Rev. 5, p. 4 (000025K202 ..(KA's) r 4

gp y;v@gh, wnypq , ';n w:; ,u pyum a .q-yn 4 = u .? q 3 d 'u 2 n,; VPd W 461, th;pd gb, ; ;A Mr W. y < l';! ' c -y- m e p (vic/,.c::m,4.A ^- M ;;i' y.fif y s,+ c, j 4 Mi d ZMSR ' i"jj ;MY f Qn, X P. epu o* ^U ~^y ll WW W T.. W, . g+ ?-QU.ESTIONn068;41100)fe. W 4 ~ ~ ^Y f

.,,g,___,;

~ 4 y, i Whichsone""of;theLtfo11owing obrrectly?complEtesEtheftwofrsactorit'ip' eiverifications(fromM1202.01,4REACTORrTRIP: tab?' r s I wy y + ow y: :..,, y _.(' 4 y e v s. - v e g p l 2$1),{ j SVer.ifyf ', ~

1. 56J-;.klT2[ q [, Verify powerfdecreasingcon J@ W % :" ~.

%u x[h2 trange'NI's.1 + $@%@m..NoimoresthAntoneDcontro10 rod. failed:to fullyLinsert,' wide. ';W T 4 D M ' -?Allsrode onj!bo't6m,iinterme'iate'. t d e <-e u- =. 6 n+@m.~INo:more5than:,one"controlsrod failedJto! fully; insert,;-intermediateW N = n,. y p;; t d y 5JA11$.rodspon; bottom f,wideL pM&p? ? 10l$ a s Q l ' *.A p,.' M s .o g,'SWER6 ?.068..(1.00F. , ~ VA. N _ _ 1 4 ,::e a w .h ',,. ;p 'it .,s y, _ _ %F pq r a Y EFERENCEO ~. N RSm ind62N155 17k p j37 w ; ; c; x y W l0dbb.2.9K301 "s.-(KAis): 4 y 2,gg .,g-yf yj wJ i,, ! 6:; e i, ,zY.i 5 +k aQ <, 'A N'. "N A i'.' ...r-s...,., 2 7 QUESTION':J069L-(1^.00)? 9,' ye. a 3 ' ?If Mth$sourceirange[ indication was;lostiduringia1 reactor'startup dueEtofloss of~ power! supply,Jwhich one'of the?following slarms is-likely when 4 W itosingnthe6 power?: k;d, ^ t qs " dCONTROL ROD cWITHDRAWALT INHIBITED - ( K10-DS). c m ( - se g i O b. b.., s ! POWER: DISTRIBUTION-ALARM;(K08-B7). 3 I m i I ,1

Melf, iRESCTOR PROT SYSTEM; TROUBLE.(K10-A4).

y[

W MA '

e % d'up !UNITLMASTERiIN~' TRACKING (K07-E4). x, ; x h* 9 1 I 7 g -- g ';s ,~ 1 bye z )...( -q u ?$.-' ,ts; q h _ -3 t t -t If 9 s s b .jj .v ,E

Wn.;

WJ ? (s s ij,du,> Y k .i

J,,, ', *, f, ~Page 47

7.

• g w.

y;;.g IANSWER:"

069 (1 00)f a.

F

REFERENCE:

1203;21,,Rev. 3,1-p. 5 a ,.000032A101.: ..(KAls)- 1

QUESTION:1070 (1 00).

• Which one of the'foll'owingLeondit' ions indicates.a lose of subcooling margin

'during a Steam Generator 1 Tube Rupture.per the TUBE RUPTURE tab-of-1202.017 RCS Pressure .T-hot T-cold . Max. Core Exit. ~ =(psi'g) . ( deg. ~ F). (deg. F) (des. F)- !a. 1050 530: 525 540-1 ,,b.,' 1150 510 505 520 <;c. 1250 520 515' 530 q: ? d.- 1350 530: 520 540' . :+ CAHSWER: 07_0.(l.'00) 1 ,ia.-

REFERENCE:

1202.01, Rev.-17,.p. 28 000038K101 ..(KA's) l = h

Page 48 m 'e QUEST 7.ON: 071 (1.00) , Which one of the following correctly d3 scribes why the OVERHEATING tab of 1202.01 directs the operator to feed 3 dry SG alowly? a-To allow the turbine bypnee valves to maintain SG preesure. b. To reduce the probability of emptying the PZR during the cooldown. c. To minimize'the probability of SG failure due to thermal strees, d. To minimize the potential for water carryover into the steam lines. IL ':'hNS'.fER: 071 (1.00) o. 4

REFERENCE:

1202.01, rev. 17, p. 76 -000064K305 ..(KA's) 'QUEGTION: 072 (1.00) If pressuriser level transmitter LT-1001 is selected by the Precourizer Level Transmitter hand switch on panel C04 when the reference leg for LT-1001 develope a elow leak, which one of the following correctly describes anticipated instrument or plant responee? LRS-1001 LIS-1002 LR-1248 (Per level) (P:r level) (M/U tank) irn Increasing Decreneing Increasing N-Decreasing Increasing lnereasing ni Increasing Decreasing Decreacing d. Decreneing Increasing Decreneing m

4,_ y .)., Page 49 s i -ANShER: 072 (1.00) a.

REFERENCE:

1203'15. Rev. 5, p. 8, 9 000028K101 ..(KA~e). m 1 {N

f k w.p W @ ( 1 4 N m 9' iPagi50L n p.p, 4' ' g '8 s.

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~ ,[& RtS ' @Mp;; >c

gs; m

~ c EfEST10M H07f '(3i00) ', ' ~* r -S c t h'5 ,g( .. -i. [ 1 For.[each of[the(events / conditions given below (a-s) select'the' correct EFIC' Meesporioef (1-5)., ' ;In ? all cases. assume ~ that: the plant-starts from a normal' M fulle! power / lineup,eallaautomaticiresponses are.as designed,1no: malfunctions l exist:otherithaniwhatris, stated,'and NO OPERATOR? ACTION ~is taken.- LResponses1(1-5) may.be used more1than once or not at all. m o! - ' i t' h ~'G s EFIC' RESPONSE gg s. +- c ,yT Lib. / EFIC actuat'ediand-feeding both OTSGs' 4'

2.:

i EFIC-actuatedLand feeding no OTSGs FMg ( 3;- JEFIC?actuatedLandifeeding-0TSG A-only J g, g,7 ,EFIC actuated 1and' feeding OTSG B.only e; mW 35E =EFIC does;not actuate? %,l \\

EVENT / CONDITION!

OTSG LEVEL OTSG-PRESS; 1 .' A' .B .A BE g g. 4 ~ ' n Plant tri1s dde'to.I loss;of. 100"' 120" 050: 860i S k#Qoffsite. power. p"' PFo11owing-;a' manual. reactor. 29" . 30"' 800

780 itrip RCS pressure l=.1885'paia?

3...

' $I M [Plhntstrih>e on low: pressure. 25"' 05" ~ 580; 270: ,J.3 -withTa steam 1sak-: upstream of: F ]s.?;1 pressured1750.psiar EtheiHSIV'on OTSG B,-current RCS- "" fl v y M[g tpoweri-I[d (T51pidueetoiliidh reactorL 50"' 65" 880 885 m..I -. s - y

TripLjdue ; toylossDof. HIN -

12" 13"

.590 650 y s w gf[ iTrip. Ton 4owl pressure duel,. 41" '43' 520' 540 h ; M torlarge: break.LOCA, current N".s, tpressure:::l1400spsia: p 7 Du-J:yJ,. t kI ', c- \\' j, l 4 fANSWERE 1073'.(3.00): f[ i ', lip [- b .. d '. - 5.

j

p. b P L5j:

fe. 14. -l } , ? 3.: .f.

2. :

b(;0?S:EA)L v

T 4

-lf,' s I 't 4 e o 'b h y_ i,.- r i g ? + f I c S, z 7 , =p q g - t i 5 - lt 4 3 )

Q@MigQMWTW K

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• ~

+ > WQ JX i% Pagy $1' ^ g.$./ > s yy,.. 1.'~, y mW w

7

, SEREltENCE:Dmc ^. whJ I ;' niMOS ST.M-1. 66; pas 1-3, 34; 35,e OP' 1102.04 ATTs E-H,-EOP 1202.01 - ;m l' 5 '061000K402 _.. 194'001K100' (KA's)- ,s o-1 jf , ' ? ' '.t ! QUESTION-4074 (3,50)1 ~ ~. , MatchEeach" load in: column 11-(a-h)cwith its closest (immediate). power supply 1 din 0 column 4 2 L (1-10).c If a-load has multiple' alternate: power; supplies. yMoolect theinormal1(perferred)-power supply. - No credit will"be giventfor .;&}selM ting 7a'powerQsupply which indirectly < supplies the load through its: 1:sest epower(supply..: 1 Items"in columnL24may.be).used more'than once or'not1 G ;ti :lli i .1 e A LLOADi POWER SUPPLY - y"= s., e s e : Ps .-BatteryLoharger DOS 1. 1A1 U i k ' ~ 2, 1A2' M@' : Core floSdltankLT-2Al outlet dCV-2415)-

3.

1A3:

d

1

.5. sBS 4. 1A4' 4 ,'"w {CRD 480V, supply-:~ .6. 'B6 y t., > ldg = Circ 1 water pump: P3D~

7.. -

MCC B51 ~ ~, J'l% 8 '. MCC B56-EW ; pump 'P.7B : 9. MCC B61 10. 'MCC B71? m f gl~ ? Fire.. pump"PGA: . y Lab /AFW pump (P-75')' %mu LIALcompressor;C2B.- l 3 m m. i hNSWER:l LO74- '('3. 00 )L s.i k).ih. 73. mfe .1 e. 3

sbnu 8)

Jk 6; ig.

2 O:diO 2 c h. -- - 0. Eg(0 37.5 each))

m.,

b's. Q '

'

'4 ~ g_ E 3 y w g ? E, 1 a; in Ja' N f {_l, _ y y + .n

• h w(h;ww

= x-y 0

y :.T.g y: gggW' m, a 'p:m.g. 7,p;7 %dpp;; 4 S g ;x. ;'p- - Page 52 2 ,-p : 4 s 1 m,. - 1 3 i r ..,e e m g., j' -

• k,I,

_ 7 f t,ggFERENCE: i e c w.c .f3 $..M . !l.. 1 NANO 1?STM-1-321 pas 0100-104,JOP:1107.02'ATT.A-C, OP-1107.01 pas-21-28. g ~

O62000K201

'194001K100-L..(KA's). Q _l, , v; + ww w r.

. r,.,

r ~\\'T y LGUESTION: L 075. : (-3.00)1 m .m. i NJA. j. MatchitheicomponentskyEtemsLincolumnif(a-h).tothe'coolingsystemsin ..yeolumnf23(1-4);by which,each is:most directly cooled.- m ,3,. 'CONPONENT/SYSTEMr COOLINGiSYSTEMs .',.1 'c,"

• 1

' + 1 I Cirefwater? pump m6 tors 1.

CIRC WATER-

<g;, 2.< ' SERVICE WATER a- .cn a dWsterbox'lvacuumipump^ seals ' '3. -CHILLED WATER %V

4..

~ACW-m.,"b~:DHR?pumproom, cooler--( 5. --

ICW-m u Nd

] )SA' compressor:aftero olers. p,

?!LOTSGysample" cooler.

a Y 5, g., y . f,m./?Controliroom: chiller-r . jkEFWi-pump; roomicobler..

r,

'O '; { p ....,4 .,t cm . hi TGflube oil' cooler L 4 s sy je t s m LANSWERE .075;, (.3. 00). a n,; I ap, , iin:21 . Te.t ~5; + 1bif 4 ' ' P f.:'n4 M(di,3 5 '1 Eg.i 3: I i ~2T , ah. : l14"

i

((0.375 eu)2 m

s h [?J... (.4,.. t l 9

REFERENCE:

+ w ( h 075000K101~

076000K119 008000K102 194001K100

..(KA*s) ,P ( +... A 4 i - 7 M kW " y s 4 4 l )

,? ;

Cf.. ' :). * ?; bl '} k '

.n' P gJ G3 ' QUESTION::076' (2.00) ' Match the:P&ID. symbols in column 1 (a-j) with the one name or function in . column 2 (1-16) which best identifies the symbol. Arrows indicate the . normal orfdesign' fluid flow direction. SYMBOL' NAME/ FUNCTION-1. Manual gate valve

2. '

q 2. Air actuated valve 3. Check valve b, ili 4. Venturi 'I 5.. Orifice <f 4" 6. Vacuum breaker c., 7. Temperature Regulator 8. Relief valve Esi i. 9. Backpressure regulator d. ___,4)y ' ' 10. Pressure reducer 11. Motor operated valve 12. Damper

c..

13. Hydraulic valve 14. Solenoid actuated valve 15. Stop-check valve f. / 16. D/P level detector '/ 8. h. 4h 1. x ~j. X . ANSWER: 076 (2.00) -b. 11-f. 15 g b.- 5 'g. 8 c. 2.- 'h. 12 n[; ~o. 'd. 13 1. 9 6' j. 7- '(0.2 ea). u-

. w m Page 54 ,y <. T- '.- EEFERENCE : ANO P&ID M-2200, 2201 194001A107 ..(KA's) QUESTION: 077 (2.00) ' Match each piece of equipment in column 1 (a-f) with the appropriate location in column 2 (1-7). Locations may be used more than once or not at 11. EQUIPMENT LOCATION RO #1 copy of 1203.02 (Alt S/D) 1. Lower ecuth penetration room b HPI~ Loop A Block Valves 2. Alt. ehutdown file cabinet (CV-1219 & CV-1220) 3. Upper north piping penetration RB Coolere VCC-2C & 2D PI-3813A ISOL (SW-3813A) 4. Alt. shutdown radio cabinet P-7A (CV-2802) & P-7B 5. Main steam line penthouse (CV-2800) SUCT from CST 6. EFW pump room P-7A to SG-B isolation (CV-2620) ISOL (SW-3812A) 7. Outside letdown filter rooms on elev. 335 f1 RCP Seal Bleedoff-(Normal) Return (CV-1274) ANSWER: '077 (2.00) >2 d. 6 .b'- 3 c. 1 7 f. 3 > L(Oc33 ea)

REFERENCE:

1203.02, Rev. 6, p. 16-19 ~194001K100 OOOO68K201 ..(KA'e) 1 p

19 74, - Page-55. r U~. . QUESTION:~ 078 (2.00) Match.the primary to secondary leak rates in column 1 (a-d) to the appropriate action in column 2 (1-6). Each action may be used more than -once or not at all. LEAK RATE = ACTION REQUIRED a.. > 0.1 gpm 1. Normal shutdown per 1102.04 & 1102.10. b > 0.35 gpm 2. Trip reactor. >.1.0 gpm 3. Notify NRC through plant liceneing. > 10.0 gpm 4. Shutdown at ~5%/ minute per 1102.04 & 1102.10. 5. Shutdown at 10~30%/minuto per 1102.04 & 1102.10. 6. Go to 1202.01 TUBE RUPTURE tab. ~. ANSWER: >078 (2.00) 1 b-. 3 4 d, ~6 (0 5 ea)

REFERENCE:

1203123, Bev. 5, p. 2 194001K100 000037G005 ..(KA's)

UM4 R 4. MMW' W.3"B", p:hin

r.

. Qffli i f, hyj Y p "n ^ ~ ~ ' .p n g; & g g i *;,w ; *c J^v ' Pane!56; daa s q:. 4 ,.R 4 g*~' ?llf, :a) G c: W, ;y ' .. ;ra n ;Qs b-i * '?;i ..,g s' u_se t o m. g 4 4 ,,j)fN %.. ' ' i t s,4WSSTIONM079Lf(2.00)l 4 e. +, g

3.,

m ? Natch!thercriticaliair-operated' components lin column-1 (a-e):to the. wappropriate11osa of air: pressure failure modo in column.2 (1-3).' Failure O modes'mayybeLusodimoreithan;once orEnotcat'all. +, o .t.' a .i s, ' FAILURE'HODE W ', -COMPONENTSs 1 .' l N v: .la;".< f14(tdown orifibeiblock valve (CV-1222) 1. Open. e + U. a., s c. x + 2. Closed'- x ' bE,. >.PressurizerElevel control L(CV-1235) ig3'M E7 ' R.i 1Mainisteami; isolation (valves (CV-2691/2692)- 3. -As is. i m :2 -.W',, L,;. w "jdb W LRCi.pumpfeen1(totalyAnjectioniflow '(CV-1207)- w r;; ~ %,o,L?,4.$.. N SG-A atmospherio: dump con' trol. valve,(CV-2618)- '~, : . 5. .n; a&..) )L :. ? . if ll ) l s Q' as.- [', ' - TANSWERP' 079M(2;00O w, !4'y._ .g, s .; ' O, '31m @lc.-b1 '; y 2; A, m, ", ,a.. 2 7, - 19 - ph :\\.1;, e r b-u d, M i 3 s : ;.21 e Ii2 D 'M( 0 2 4S ea')[; s%. p. a: ' I' ^_ \\_ 0

REFERENCE:

, t '

. 0, -. @1203*24, Revh 4L pt a pl 13-15L - F,.+; Y194001X100; .000065A208-(KA.*e) u / } g.,o i ~ y 7,l N 1) i q l,.t :,. ~ ' . ).

a s 'g

.

~ ir, t / 't p.- l g

v g$:2 M. - %'

.c - i. o ,m m t ; ' qp; ' 'C-y;w w (*.********* END OF EXAMINATION ***4***444) O i o 7. [.j 9 p_o p 7'l; .y.].,. g g N W:' .d;L # W h, / &

F h L FACILITY LICNESEE COMMENTS c. OVESTIONS RELATING TO ANNUNCIATOR OR COMPUTER ALARMS: Operators are trained to refer to 1203.12, Annunciator Corrective Actions, when an alarm is received. The symptom is " alarm", the action is " refer to 1203.12", Annunciator Corrective Actioas. The 1203.12 procedures list "Causes" and " Actions Required". These are not taught in the same regard as " Symptom" and "Immediate Actions" of the abnormal operation procedure. There are 650 different annunciator responses (causes and actions required) not including the causes of plant computer alarms of which there are hundreds more. Memorization of 650+ causes and actions is not required of the operators since these procedures are available to the operators in the control room. Any condition that would require an immediate action is covered by E0P 1202.01 and AOP 1203.XX Abnormal Operating Procedures. Questions 5, 11, 26 and 30 all refer to control room alarms. The R0 is expected to respond to all control room alarms. He acknowledges the alarm, confirms the alarm, and reports the alarm condition to the SRO. QUESTION #5 Which one of the following choices represents a correct cause for and preferred response to a RCP 1P32 SEAL COOLING FLOW LO alarm while at full power? a. ICW flow to any RCP < 30 gpm, start standby ICW pump b. Seal flow to any RCP < 3 gptr, adjust valve MU-28 (A-D) c. ICW flow to any RCP < 30 gpe, trip affected RCP d. Seal flow to any RCP < 3 gpn, trip affected RCP Answer: a.

Reference:

AN01 A0P 1203.12G Pgs 6, 7, A0P 1203.31 Pg 6 003000G008... (KA) QUESTION #11 Which one of the following conditions will generate a REACT PROT SYSTEM TROUBLE alarm? a. Any power range NI channel detector power off b. Any channel of RPS in bypass c. Any power range NI channel in test or calibrate d, Any channel of RPS in test Answer: a. I

L j t-1

Reference:

AN01 AOP 1203.121 Pg. 32 015000A302 ...(KA) 1 QUESTION #26 The CONTROL ROD PATTERN ASYMMETRICAL alarm is generated by an individual rod position more than: i a. 7" out from its RPI group average and will be accompanied by the asymmetric rods lamp on the diamond panel being on b. 9" out from its API group average and will be accompanied by the individual fault lamp on the PI panel being on c. 7" out from its API group average and will be accompanied by the individual fault lamp on the PI panel being on d. 9" out from its RPI group average and will be accompanied by the asymmetric rods lamp on the diamond panel being on Answer: C.

References:

AN01 STM-1-02 Pgs 17-21, A0P 1203.121 Pg 49, AOP 1203.03 Pg. 1 014000A102 ... (KA) QUESTION #30 Which one of the following spent fuel system parameters or conditions produce abnormal condition alarms directly observable in the control room 7 a. Spent fuel pool recirculation flow b. ICW flow through the spent fuel coolers c. Spent fuel cooler filter differential pressure ,1 d. Fuel transfer tube gate valve not fully shut Answer: a.

References:

' AN01 STM-1-07 Pgs 2-6, OP 1101.02 Rev. 8 Pgs 16, 18 033000G008 ... (KA) 2

p 7 .3 V *,; t L., QUESTIONS CONCERNING THE SCOPE OF R0 KNOWLEDGE The scope of R0 level knowledge is not clearly defined. In exam item construction, questions should come from information that is expected that the R0 has memorized. Obviously no one can memorize every paragraph of every procedure. The following questions relate to test items requiring memorization over understanding 4 and items not considered relevant to safe operation concerns. QUESTION #8 Once the trip _ signal has cleared following ESAS actuation, which one of the following recovery sequences MUST occur in the order specified to successfully reset ESAS? a. Override ectuated devices, then reset digital subsystems b. Reset analog subsystems, then reset digital subsystems c. Override actuated devices, then reset analog subsystems d. Reset digital subsystems, then reset analog subsystems _ Answer: b.

References:

AN01 OI 1105.03 Rev. 5 Pg 12, STM-1-65 Pgs 2-8 Comments This question-requires the RO to pick 2 of 3 procedure steps from a normal operating procedure and then place them in the correct order in which they are required to be performed. All 3 steps are required by the procedure when resetting the ES signal. This question does not examine the operators knowledge of ESAS but rather his ability to memorize procedure steps, and decide that procedural complaince is not required to accomplish the task, t QUESTION #16 Which one of the following is correct concerning the operation or behavior of the Reactor Vessel and Hot Leg Indicating System? a. The Delta T between the heated and the unheated thermocouple decreases in a steam environment. b. . Loss of heating to the junction of the heated thermocouple will cause a low level indication, c. An unheated thermocouple at 690 deg. F will generate a low level alarm. d. Indicated level will be greater than actual level if reverse flow is initiated through the reactor vessel and core. Answer: d. 3

l'_ e

References:

AN01 LP AA-51002-009 Pg. 8 017000A202 000074A116 ... (KA) Comments-There is no ANO specific reference for this question. The specific infor-mation could not be found that would allow this question to be answered. This quest' ion was described as " Generic Industry Knowledge" by NRC. Unless ANO has a reference to support this knowledge we cannot train our operators to respond to the conditions specified by the question. QUESTION #18 When initiating a gaseous release from the waste gas decay tanks per OP1104.22, CV-4820 is slowly opened to; a. </= flow rate determined in the preliminary release report by monitoring flow on FR-4831 b. </= flow rate determined in the preliminary release report by monitoring total flow on FR-8001 c. The lesser of 10 CFM or the preliminary report flow rate by monitoring flow on FR-4831 d. The lesser of 10 CFM or the preliminary report flow rate by monitoring total flow on FR-8001 Answer: a.

References:

) AN01 OP 1104.22 Att. C Pg 4 071000A202 ... (KA) i Comments Half of this question's answer requires the R0 to have memorized the numerical designation of flow recorders, differentiating between FR4831 and FR8001. QUESTION #38 Once the hydrogen recombiners have been started following a LOCA, l significant hydrogen recombination will not begin for about: (Att. C l-to OP 1104.31 provided) 1 a. 1 - 2 hours b. 2 - 3 hours 1-c. 3 - 4 hours L d. 4 - 5 hours L 4 l l

r ,. + _. I Answer: c.

References:

AN01 OP 1104.31 Pgs 2, 12 028000K601 028000A401 028000A202 028000A101 ... (KAs) Comments i This question keys on the R0 knowing that H2 recombination occurs at 1135' F. This number comes from the body of the E0P. The figure provided is of no value without the 1135" F knowledge. This information is not necessary for the.RO to safely operate the system as he is directed by the SRO when to start up the recombiner. The SRO level is more appropriate for the understanding of this recombination temperature. This is not a question of the importance of Hz. control following a LOCA, rather a question of the j importance that an R0 have the 1135' F number memorized, j QUESTION #44 Which one of the following is the correct tab or tabs in 1202.01, " Emergency Operating Procedure," for the following conditions? T+0 Reactor trip from 100% power due to low RC pressure. All control rods fully insert. No secondary activity alarms. T+30sec Immediate actions of Reactor Trip tab were completed successfully. Follow-up actions of Reactor Trip tab were completed until transfer criteria met. T+1 min Main steam line pressures are 800 psig and decreasing. RCS subcooling is 40 degrees F and decreasing. Pressurizer level is 40 inches and decreasing. RCS pressure 1650 psig and decreasing. RCS T-cold is 540 degrees and decreasing. T-hot is following T-cold, a. REACTOR TRIP concurrent with OVERC00 LING b. OVERC00 LING c. LOSS.OF SUBC00 LING MARGIN L d. OVERC00 LING concurrent with LOSS OF SUBC00 LING Answer: b.

References:

1202.01 Rev. 17, Pgs. 20, 29 l '- 000040G012 ... (KA) l l i i

c; pn g j m.: .i g1 QUESTION #53 Which one of the following tabs is to be performed while attempting to restore NNI power. supplies per 1202.01, section ll, " Actions for Loss of NNI Power," step 11.57 l a. Emergency Boration

b. -

ESAS Actuation c. Main Steam Isolation d._ Reactor Trip i Answer: i ,d.

References:

i -1202.01', Rev. 17, Pg. 237 000057G012 ... (KA) 4 QUESTION #58= If, following a small break-LOCA, the RCS stabilizes at 200 psig and '300 deg. F while performing the actions of the ESAS Actuation tab in 1202.01, which one of the following is the correct E0P use to continue recovery?. a.. Go to LOSS OF SUBC00 LING b. Go to'0VERC00 LING AND continue in ESAS ACTUATION c. Go.to OVERC00 LING d. Go to LOSS OF SUBC00 LING and continue in ESAS ACTUATION Answer: b. p

References:

1202.01, Rev. 17, Pg. 281 000011G012 ...-(KA) Comments i.: Questions 44, 53, and 58 all relate to plant conditions that require entry into a specific tab of 1202.01 by application of "GO-T0" statements from the E0P. R0s are not expected to have memorized as symptoms the 64+ "GO-T0" statements that would direct actions to another E0P tab. The R0 is expected to monitor his control boards and keep the SR0 informed of 4 changing plant conditions. The SR0 will use the plant conditions and apply them to the E0P "G0-T0" statements for direction to the appropriate tab. The SR0 would have the benefit of the complete transient, the R0's reports of plant conditions, and the E0P as references for identifying appropriate "GO-T0" statements. 6 e

g,' QUESTION #52 Which one of the following is the first corrective action for a blackout condition, per 1202.01, section 10. " Actions to Correct Blackout?" a. Establish natural circulation decay heat removal b. Verify HPI cooling established c. Verify 480V MCC 855 and B56 energized d. Select REFLUX BOILING setpoint for EFW Answer: a.

References:

1202.01, Rev. 17, Pg. 205 000055G012 ... (KA) gmments Requires memorization of the order that steps in the " follow-up" section of the E0P occur in. This is not relevant for the R0 as the SRO will direct the R0 action to establish natural circulation decay heat removal. QUESTION #54 If the unit is operating at 100% power, with all systems normal, when the PROGRAMMER t. AMP FAULT LIGHT on the Diamond panel illuminates and group 7 rods start driving in at jog speed, which one of the following is correct if the fault is in lamp group A? a. Pulling the fuse for lamp group A, fuse F-3, will cause the rods to drop b. Pulling the fuse for lamp group B, fuse F-1, will cause the rods to stop. c. Pulling the fuse for lamp group A, fuse F-3, will cause the rods to

stop, d.

Pulling the fuse for lamp group B, fuse F-1, will cause the rods to drop. i Answer: l C.

References:

1203.03, Rev. 12, Pg. 10 000003K205 ... (KA) 7 i

p: - i: jy ; l-Comments l-This question requires memorization of fuse numbers that are clearly listed in the abnormal operating procedure. R0s are not required to have specific paragraphs from the " follow up" actions of the AOPs memorized to the level of detail this question requires. Since the question does not ask for the correct action, there are two answers that are true if the appropriate fuse is-pulled. Answers "C" & "D" are both true. Although the correct action is to stop the rods, if the F-1 fuse is pulled, the rods would drop. i. QUESTION #57 For which of the following regions (refer to the attached Figure 5) does 1202.01 require that the operator run all four RC pumps, defeating starting interlocks, if necessary? a. Region 1 r b.- Region 2 c. Region 3 d. Region 4 Answer: d.

References:

1202.01, Rev. 17, Pg. 110 000009A201 ... (KA) Comments This question requires the memorization of actions detailed in the " follow-up" section of an E0P tab. This is an SR0 level question. l OVESTION #68 If a RWP indicates that a task is subject to a Standing ALARA Review [ (SAR), this means that: a. . An ALARA briefing is not required prior to each entry under the RWP l b. An ALARA briefing must be conducted prior to each entry under the RWP c. The total estimated man-rem for the task is less than 1 man-rem l: d. The total estimated man-rem for the task is greater than 10 man-rem l Answer: 5. 8

Reference:

ANO OPAP 1000.33, Rev. 5, Pgs 10-13 p 194001K104 ... (KA) Comments p This question addresses ALARA procedures for review of RWPs. The vast i majority of operator duties are covered by standing RWPs for general operator activities. The question requires the RO to have memorized details concerning ALARA reviews that do not'significantly affect the [ performing of his job. QUESTION #69 Which one of the following correctly represents requirements for access T control per OP 1000.19, Station Security Requirements? a. Individuals responding to an emergency but not normally authorized 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 with 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: d.

References:

ANO SAP 1000.19, Rev. 17, Pgs 10-15 194001K105 ... (KA) Comments L This question is not related to safe operation of the plant nor is it L related to a significant part of the R0s job duties. The R0 spends < 1% l of his total job time escorting visitors in the plant. 1 l l 9 l l L'

h ,1 f +, ' !. ~ n .,Q QUESTION #72 t Which one.of the'following analyses is performed on the secondary system DAILY or more frequently during normal power operations? ? a. -- Total iron. l. b.- Total copper h c. Boric acid d. Tritium /Flourine L' Answer-l- k d.o y b

References:

AN01 LP AA-51002-023 Table 23.1 194001A114 001000K100 ... (KAs) .i [ Comments This is an SRO level question and was addressed in the initial comments presented at the exit. It-falls into the category of irrelevant at the - RO level in terms of differentiating between daily or weekly samples of the secondary system that is performed by plant chemists and the results reported to the Shift Supervisor (SRO). QUESTION #74 Match each load in column 1 (a-h) with its closest (immediate) power supply t in column 2 (1-10). If a load has multiple alternate power supplies, select the normal (preferred) power supply. No credit will be given for selecting l a power supply which indirectly supplies the load through its closest power supply. Items in column 2 may be used more than once or not at all, a LOAD POWER SUPPLY l s a. Battery charger D03 1. 1A1 b. Core flood tank T-2A outlet (CV-2415) 2. lA2 . c. CRD 480V supply 3. lA3 d. EFW pump P78 4. lA4 EFW pump P7B 5. B5 1 . e.. -Fire pump P6A 6. 86 f. g. AFW pump (P-75) 7. MCC B51 h. IA compressor C2B 8. MCC B56 9. MCC B61 10. MCC B71 Answer: L a. 7 e. 3 b. 8 f. I c. 6 g. 2 d.. 2 h. 9 10 s L ^

jf.

t Yl l

C Comments Questions like this one need to be moderated to include memorization L of only vital or important equipment. The choices should not require L differentiation between 851 or B52 as the power supply but rather B51 or 5 B61. Only major busses rather than specific breakers should be asked. Operators are not required to have all equipment power supplies memorized. Further, the power supplies for control board equipment are identified on labels attached to the board near the handswitch that operates the equipment. QUESTION #78 h Match the primary to secondary leak rates in_ column 1 (a-d) to the appropriate action in column 2 (1-6). Each action may be used more than once or not at all. LEAK RATE ACTION REQUIRED a. > 0.1 gpm 1. Normal shutdown per 1102.04 & 1102.10 b. > 0.35 gpm 2. Trip reactor c. > 1.0 gpm 3. Notify NRC through plant licensing d. > 10.0 gpm 4. Shutdown at - 5%/ minute per 1102.04 & 1102.10 5. Shutdown at 10 ~ 30%/ minute per 1102.04 & 1102.10 6. Go to 1202.01 TUBE RUPTURE tab Answer: a. I b. 3 c. 4 d. 6

References:

1203.23, Rev. 5, Pg. 2 194001K100 000037G005 ... (KA) Comments This is an SRO level question. The RO on the boards combating a tube failure is not concerned about notifying the NRC through plant licensing l at >.35 gpm. This is directed by the procedure for the SRO to perform. 1 I l l L L 11 i

3 f., y. k 'OVESTION #79 i Match the critical air-operated components in column 1 (a e) to the r.! appropriate loss of air pressure failure mode in column 2 (1-3). Failure modes may be used more than once or not at all. s COMPONENTS-FAILURE MODE a. Letdown orifice block valve (CV-1222) 1. Open b.- Pressurizer level control (CV-1235) 2. Closed L c. Main steam isolation valves (CV-2691/2692) 3. As is i d. RC pump seal total injection flow (CV-1207) e. SG-A atmospheric dump control valve (CV-2618) i t ~ Answer: a.' 3 b. 2 c. 2 d. 1 L. e. 2 r

References:

L 1203.24, Rev. 4, Pgs. 13-15 194001K100 000065A208 ... (KA) Comments The RO should not be required to have the failure mode of all or even the significant air operated valves memorized. The A0P lists the valves and the failure modes. There are 28 valves listed in 1203.24. It is not reasonable for the R0 to be expected to have all of them memorized. p The following questions have individual concerns which will be stated for each question separately. QUFSTION #10 Which one of the following will most likely result in an increase in source range N1-(gamma-metrics) indication following a reactor trip? a. Release of corrosion products from RCS internal surfaces b. Purification demineralizer resin retention element failure c. Rapid uncontrolled depressurization of the RCS d. High reactor building temperature and humidity Answer: l C. l 12

.] w I

References:

L L AN01 LP AA-21008-009 Pgs 1-4, STM-1-67 Pgs 2, 3 Tables 67.2-4 4/ 015000A103 ... (KA) i Comments The response that is correct assumes without stating that VOIDING is 7 occurring. A rapid depressurization to l' subcooled with no voiding is I i possible. L QUESTION #21 I ', If pressurizer pressure is 2100 psia, quench tank pressure is 5 psig and initial ERV whil. quench tank temperature is 90 deg. F a leak across the pressurizer e at full power will cause a downstream temperature indication of p about: a. 162 deg. F-b. 228 deg. F c. 318 deg. F d. 640 deg. F Answer: b.

References:

Steam Tables THT&FF Theory 000008K302 000008K101 002000K105 ... (KAs) Comments There are no control panel indications of RCS (pressurizer) pressure that read out in PSIA. Therefore, this is a trick question in that the RO must pick out the PSIA in the RCS pressure and the PSIG for the quench tank to obtain the correct answer. QUESTION #29-When starting the RB Purge System with a negative pressure on the RB, open the purge inlet valves before opening the purge outlet valves to prevent: a. Damaging RB penetrations during sudden pressure change b. Inadvertant release of radioactive contaminants c. Damaging purge discharge due to reverse air flow d. Reverse air flow through stack sample monitor (RE-7400) 13

F -I i k-i g I' Answer: c. 1

References:

AN01 SIN-1-09 Pgs. 4-6, STM-1-47 Pgs 6-11,19 029000A401 ... (KA) Comments 1 As per the pre-exam review, this question was to be modified to include the word " filter" as part of the correct answer "C". " Reverse air flow through the discharge filter". ) QUESTION #56 F Which one of the following actions is required to balance RCS inventory if l a pressurizer steam space leak is indicated and pressurizer level cannot be maintained < 290. inches? a. Stop all but one RCP b. Isolate letdown c. Close RC Pump Seals Total INJ Flow Valve (CV-1207) d. De-energize all heaters Answer: ' a.

References:

1202.01, Rev. 17, Pg. 19 000008A106 ... (KA) m-Comments -This question was identified in the p're-exam review but was inappropriately modified when " Balance RCS Inventory was added. This modification makes the answers inappropriate. Refer to exit meeting comments. QUESTION #70 Excessive water level is of concern in affected areas since the integrity of safe shutdown electrical equipment is only verified for an actuation time of: a.. 10 minutes b. 20 minutes c. 30 minutes d. 60 minutes 14

e i -a h. .s Answer: j b.

References:

ANO DAP 1015.07 Rev. 8, Pg. 2 Comments L Without reading something into the question, this question does not stand alone. The actuation of a " Fire Suppression System" must be read into i-the question. L (; The following Questions relate to a deviation from BR0122 and ES401 as indicated for each item. QUESTION #22 s The loss of which one of the following DC panels would directly impact the automatic operation of pump P34B? a. D11 b. D21 c. 015 d. D25 Answer: b.

References:

AN01 OP 1107.04 Pgs. 28-31, STM-1-32, Pg. 28, STM-1-05, Pg. 4 006000K201 ... (KA) Comments In conflict with BR0122 Page 4-13 Item #9. The logical sequence should be Oll, D15, 021, 025. l' QUESTION #25 l l According to Technical Specifications, which one of the following RPS trips is NOT specifically intended for DNB protection? l. l. a. Power imbalance - flow L b. Low pressure c. High temperature d. Variable low pressure 15 1

i k, Answer:

References:

AN01 STM-1-02 Pgs. 17-21, AOP 1203.121 Pg. 49, AOP 1203.03 Pg. 1 014000A102 ... (KA) Comments In conflict with BR0122 Page 4-10 Item #5. "When possible avoid using negatively stated items". L QUESTION #49 Which one of the following is an INCORRECT statement of the requirements L: for Reactor Building Integrity per 1203.05, " Loss of Reactor Building Integrity?" a. Both doors of the peisonnel lock are closed and sealed b. One door on the personnel airlock is closed and sealed during personnel access c. All non-automatic reactor building isolation valves are closed as required d. All automatic reactor building isolation valves are operable Answer: d.

References:

1203.05, Rev. 5, Pg. 1 000069A201 ... (KA) Comments In conflict with BR0122 Page 4-10 Item #5. "When possible, avoid using negatively stated items". QUESTION #38 Once the hydrogen recombiners have been started following a LOCA, signifi-cant hydrogen recombination will not begin for about: (Att C to OP 1104.31 provided) a. 1 - 2 hours D. 2 - 3 hours i' c. 3 - 4 hours d. 4 - 5 hours L t 16 [

i, n 0 Answer: C.

References:

AN01 OP 1104.31 Pos. 2, 12 028000K601 028000A401 028000A202 028000A101 ... (KAs) Comments In conflict with BR0122 Page 4-13 Item #10. Avoid overlapping answers. 1-2 hrs, 2-3 hrs, 3-4 hrs, 4-5 hrs. t QUESTION #45 Which one of the following is a correct statement regarding condenser vacuum and reactor operation? a. If reactor power is at 40% and condenser vacuum cannot be maintained above 24.5" Hg, then the reactor must be tripped 4 b. If reactor power is less than 30% and condenser vacuum cannot be maintained above 26.5" Hg, then the plant must be shutdown per OP 1102.10 c. If condenser vacuum decreases to less than 17" Hg, then reactor power must be reduced to less than 3%. d. If condenser vacuum decreases to less than 5" Hg, then the reactor must be placed in a subtritical condition within 6 hours Answer: c.

References:

1203.16 Rev. 4, Pg. 2-4 000051A202 ... (KA) Comments In conflict with BR0122 Page 4-6 Item #3. " Don't present a collection of j true-false statements as a multiple choice item". i QUESTION #69 Which one of the following correctly represents requirements for access control per OP 1000.19, Station Security Requirements? a. Individuals responding to an emergency but not normally authorized access to a particular vital area may piggyback with an individual i with proper access and then report to security af ter the emergency is controlled. 17 j a

q., t 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 with 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 t is monitored by the escort. Answer: d.

References:

l ANO SAO 1000.19, Rev. 17, Pgs. 10-15 1940001K105 Comments In conflict with BR0122 Page 4-8 Item #3. " Don't present a collection of strue-false statements as a multiple choice item". QUESTION #55 Which one of the following correctly completes the paragraph below? Following a reactor trip, the SPDS CRT ATOG displays will show a normal transient window with the minimum and maximum expected post-trip The small box inside this window shows the expected for normal hot shutdown conditions. Two boxes show expected during natural circulation, a. T-hot and T-cold, average temperature, pressure and temperature b. Pressures and temperatures, P-T relationship, T-hot and T-cold c. Pressures-and temperatures, average temperatures, T-hot and T-cold d. T-hot and T-cold, P-T relationship, pressure and temperature Answer: b.

References:

1202.01, Rev. 17, Pg. 28 000007K203 ... (KA) 18 l L

1 .e: Comments In conflict with BR0122 Page 4-7 Item #2. " Avoid the use of too many blanks. Use no more than two in any question". QUESTIONS RELATING TO PROPER TERMIN0 LOGY AND LABELING: The Procedures Writers Guide emphasizes the use of proper and consistent terms for noun r,ames of components. This terminology is used in training and required of the operators while operating the plant. Questions should use complete and accurate noun names of equipment as used in procedures along with i the numerical designation for a piece of equipment. Training requires accurate identification of equipment by either a noun name or a numerical designation. Either designation is acceptable. Since either is acceptable both (name and number) should be referenced in a question. QUESTION #2 l Group rod motion is stopped at the full in or out positions by: a. A cam operated mechanical switch b. A magnetically operated mechanical switch c. A magnetically operated solid state electronic switch d. An optically operated solid state electronic switch Answer: b.

References:

AN01 LP AA-51002-010 Pgs. 18, 19 001000K602 ... ( KA) Comments The correct term for this device is a mechanical REED switch. QUESTION #5 Which one of the following choices represents a correct cause for and preferred response to a RCP 1P32 SEAL COOLING FLOW LO alarm while at full power? a. ICW flow to any RCP < 30 gpm, start standby ICW pump b. Seal flow to any RCP < 3 gpm, adjust valve MU-28 (A-D) c. ICW flow to any RCP < 30 gpm, trip affected RCP d. Seal flow to any RCP < 3 gpm, trip affected RCP 19

py y z m. M. ~. mqs p !R o i Answer:

a..

{.,.

References:

l' h AN01 AOP 1203.12G Pgs. 6, 7, AOP 1203.31 Pg. 6 003000G008 ... (KA)- Comments --- e The correct answer in part "A" is standby _ICS " BOOSTER" pump. _ UESTION #15 Q At full pc er with condensate pumps P2B and P2C running, breaker 152-111 )3, is shut resulting in a CONDENSATE PUMP TRIP alarni. Which one of the r f following will-be' the result of this event? a. P2C-running with_ runback in progress j b. P2A starts in standby and P2C remains running c. P2A running with runback in progress -d. P2A starts.in standby and P2B remains running v Answer: a.

Reference:

AN01-STM-1-20 Pg. 8, OP 1107.01 Rev. 33 Pg. 12 056000A204 .... (KA) Comments-152-111 is the startup transformer #2 feeder breaker to A1. a- 'W QUESTION #14 Which one of the following condensate system parameters affects control signals to the main feedwater pumps? a. Seal water pressure b. Low pressure heater AT DischargepressureA c. d. Hotwell level Answer: C. 20 4

f, j9: h

References:

1" AN01'STM-1-19 Pg. 4, STM-1-20' o 056000K103 ... (KA) Co$ments The' correct answer is a feed pump." TRIP" condition not a parameter that "affects control signals". K & A RATING CONCERNS: In general, many.of the selected KAs have only a vague relationship to the questions asked. Realizing the difficulty of referencing specific plant equipment and procedures with the generic KA catalog, a great deal of latitude was taken into account.- The following references either do not apply or question and KA have differing objectives.- -QUESTION #1 z Which ONE (1) of the following statements describing the design of the fuel transfer tube.is correct? a. A blind flange is used to close the transfer tube on BOTH the containment side and thc spent fuel side b. A valve is used to close the transfer tube on BOTH the containment side and the spent fuel side .V c. A. valve is used to close the transfer tube on the containment side and a blind-flange is used on the spent fuel side d. A blind flange is used to close the transfer tube on the contairment . side and.a valve is used on the spent fuel side Answer: - d. e

References:

AN01 STM-1-51 Pg. 7

034000K101 034000K402

... (KAs) Comments. Referenced KA is not appropriate. The KA which should have been used is 000-069 EA1.02, " Ability to operate and monitor: Blind flanges as part of containment isolation". This KA-has a rating of 2.2. 21

![ y ? i WT t.

cy LQUESTION #101 Which one of the following will most likely result in an increase in source

[ range NI.(gamma-metrics) indication following a reactor trip? a. Release of corrosion products from RCS internal surfaces b. Purification demineralizer resin retention element failure c. Rapid' uncontrolled depressurization of the RCS r

d. -

High reactor building temperature and humidity l f Answer. C.

References:

-AN01 LP'AA-21008-009 Pgs. 1-4, STM-1-67 Pgs. 2, 3, Tables 67.2-4 015000A103 ... (KA) Comments Referenced KA is not appropriate. The question should deal with the ' monitoring of the nuclear instrumentation system to prevent exceeding design limits. The question should be a generic fundamentals exam question under the components section. The generic fundamentals exam -KA'is 192002K1.17, " Effects of Core Voiding on Neutron Detection". QUESTION #15 -At full power with condensate pumps P2B and P2C running, breaker 152-111 is shut resulting.in a CONDENSATE PUMP TRIP alarm. Which one of the following will be the result-'of this event? a. P2C running with runback in progress a b. -P2A starts in standby and P2C remains running c. P2A-running with runback in progress d. P2A starts in standby and P2B remains running -t Answer: a.

References:

o AN01'STM-1-20 Pg. 8, OP 1107.01 Rev. 33, Pg. 12 056000A204 ... (KA) Comments-KA is the ability to predict the impact of a loss of condensate pumps. The question refers to the load shedding of condensate pumps when shifting to startup transformer #2. 22 >v

k' % D g [l$;Q y ~ lf N L 4 /hg j {??@4' 1 QUESTION #29 v When starting the RB Purge System with a negative pressure on the RB, open i the purge inlet valves before opening the purge outlet valves to prevent-g . a. Damaging RB penetrations during sudden pressure change. I .b. Inadvertant release of radioactive contaminants c. Damaging purge' discharge due to reverse air flow ny x, d.. Reverse air flow through stack sample monitor (RE-7400)' o-L Answer: p. .C., uu

References:

S; -~AN01 STM-1-09 Pgs. 4-6, STM-1-47 Pgs.-6-11, 19 4! 029000A401- ' Comments-Since the question deals with a reverse flow across the reactor building purge exhaust filters', the correct KA should be " Knowledge of CPS Design 4

Feature (s) and/or Interlock (s) which p'rovide for the following:

Use of filters for purging to the atmosphere. 029000K4.01. This has a rating m' of 2.4. QUESTION'#35 Aside^from improving plant operating efficiency, the Circ Water Waterbox Vacuum System is important to: a. Prevent lake water from entering the feedwater system as a result of =small condenser tube leaks-i b. Reduce circ water pump discharge back pressure to keep pump motor 4 -temperatures within limits 'c. Prevent damage to condenser tubes which results from steam impacting on dry tubing .d. Remove dissolved gases from lake water which interfere with anti-

• g fouling chlorination treatment Answer:

c.

References:

AN01 STH-1-40 Pg. 2 075000A203 ... (KA) L e 23

V g II g .ce - Comments Incorrect KA: referenced. Correct KA should be 075000K1.09, Knowledge of y~ the physical connections and/or cause-effect relationships between the circulating water system and the following systems: Vacuum priming". <lv This rating is.1.5. QUESTION #39 p U On ES actuation the.0HR coolers are protected from overpressurization ' by: ) Shutting:.theIinlet and outlet valves and opening the bypass valve f a. o" - b. Check. valves in-the core flood injection /0H removal lines c. The automatic closure and interlock system 4 d. Nothing since the coolers are designed for normal RCS pressure - Answer: - b.-

References:

i AN01 STM-1-5-Pgs. 2-10, P&ID M-232 ., ~. 005000K603 ... (KA) Comments Since the function asked in the question deals with the check valves, KA .s ould be 005000K6.04. " Knowledge of the applicable performance and h . design-attributes of the following RHRS components". The rating is 1.9. QUESTION #78 Match the primary to secondary leak rates in column 1 (a-d)-to the appropriate action in column 2 (1-6). Each action may be used more than once'or.not at.all. LEAK RATE ACTION REQUIRED l a. > 0.1 gpm 1. Normal shutdown per 1102.04 & 1102.10 b.. > 0.35 gpm 2. Trip reactor c. > 1.0 gpm 3. Notify NRC through plant licensing d. > 10.0 gpm-4. Shutdown at ~ 5%/ minute per 1102.04 & 1102.10 l S. Shutdown at 10 ~ 30%/ minute per 1102.04 & 1102.10 o h 6. Go to 1202.01 TUBE RUPTURE tab l t 24 l l

r, l::*_ t t. e< Answer:: o 4 a. J1l ? b. -3 c.. 4- . d. - 6-l

References:

1203.23 Rev. 5, Pg. 2-1 L

194001K1003 000037G005

... (KA) 7 L ' Comments (_ Referenced'KA. implies the "use of the' response instructions" not the L memorization of the followup actions of the abnormal operating procedure for;"High Activity in the Reactor Coolant System". 1 o QUESTION #79 Match the critical air-operated components in column 1 (a e) to the appropriate loss of air pressure failure mode in column 2 (1-3). Failure 1 modes may be used more than once or not at all. COMPONENTS FAILURE MODE a. . Letdown orifice block valve (CV-1222) 1. Open b.. . Pressurizer level control (CV-1235) 2. Closed c. Main steam isolation valves (CV-2691/2692) 3. As is d.- -RC pump. seal' total injection' flow (CV-1207) e. .SG-A. atmospheric dump control valve (CV-2618) Answer: a.. 3. b. 2 c. 2 d. 1 e. 2

References:

1203.24'Rev 4, Pgs. 13-15 194001K100 000065A208 ... (KAs) Comments . Referenced KA " Ability to determine or interpret: Failure modes of air operated equipment". In order to utilize KA, candidate should be asked to determine"the failure mode (i.e., indications of failure, piping dr' awing, etc.) not simply to memorize the failure modes from an attachment in the Loss of Instrument Air Abnormal Operating Procedure. 25

' ^ ~ ga p 4Q + nM k SPECIFIC QUESTIONS w c These are the comments from the original letter presented at the exit meeting.- QUESTION #30 1 9, Which one of the following spent fuel system parameters or conditions-l produce abnormal condition alarms directly observable in the control room? s a.: Spent fuel pool recirculation flow b.- ICW flow through the spentifuel coolers c. Spent. fuel cooler filter differential pressure d.' Fuel transfer tube gate valve not. fully shut Answer:. e a. ?

References:

AN01 STM-1-07 Pgs 2-6, OP 1101.02 Rev. 8, Pgs. 16, 18 .033000G008 ... (KA) Comments It is requested 'that this question be dropped from the exam. This question requires memorization of plant computer alarms as listed in 1101.02"Setpoint". .This computer alarm is not referenced in 1101.01 " Limits and Precautions ' - nor is it referenced in 1104.06 " Spent Fuel Cooling System".

Further, P&ID M-235 ' identifies the borated water pump P-66 as a " recirculation" pump'which has no flow alarms.

Spent fuel pump P-40A/B is referred to as a-circulation" pump. This question was identified as a problem during the pre-exam review where the concern was stated. The current R0 license training does not require-the memorization of plant computer alarms to the point of discerning one point our of a list'of four parameters where three are not alarms on the plant computer or annunciator. QUESTION #56 Which one of the following actions is. required to balance RCS inventory if a pressurizer steam space leak is indicated and pressurizer level cannot be maintained < 290 inches? a. Stop all but one RCP b. Isolate letdown c. Close RC Pump Seals Total INJ Flow Valve (CV-1207) d. De-energize all heaters Answer: a. 26

pm

if

ML <c M y; l'

References:

g 1202.01, Rev; 17, Pg.- 19 i .000008A106 '.... (KA) Comments. 1 It is requested that this' question be dropped from_the exam. There is no correct answer to'the question as stated. The question is misleading' e in that thv correct answer (a) "Stop all but one RCP" (leaving one RCP fs running) is performed _in the. HPI cooldown. tab to "... promote mixing of the cold HPI. coolant with RCS coolant". This is not required to r " balance'RCS inventory". Answer "a" would not be correct to " balance .RCS inventory" as all.RCPs.are tripped on a loss of subcooling margin. ls,c '{ .. + l [' QUESTION #72' i ' Which one of the following analyses is performed on the secondary system j DAILY =or more frequently during normal power operations? l a. Total iron i b. Total copper c. Boric acid-I

d.

Tritium Flourine- -Answer: d. e

References:

i AN01-LP AA-51002-023 Table 23.1 194001A114 001000K100 ...~(KAs) j 1 . Comments 1 i It i.s requested that this question be dropped from the exam. This question does not have a correct' answer. The stated reference for the question is a table from a lesson plan that is out of date with the current secondary sampling frequencies. As noted in OP1000.42, Att. 4 and 1042.01, Form 1042.001GG, none of the choices given in the answer are performed as a daily ?~' . analysis. 4r } c 27 + . m.

{TT 3 5

7. [

~ 3 ,i g f " M ' SIMULATION FACILITY FIDELITY REPORT x 't:' - Facility Licensee::l Arkansas Power &' Light Company Facility Licensee Docket No'.:' 50-313 1 Facility License No.: DPR-51' 3 0perating Tests Administered at:': Arkansas Nuclear One, Unit l' = 0perating Tests given on: November 14, 1989 ~ During the conduct of the simulator portion of the operating tests identified above :the following apparent performance and/or human factors discrepancies .were observed:- NONE-1 This report should not be construed as an evaluation of the performance or j capabil.ities of the ANO:1 simulation facility. Only two scenario sets were required to' conduct the simulator portion of the operating examination. This is too small a sample to provide-a meaningful evaluation of the simulation facility.- i I4 : s ? c, \\ k ', t h S d + s z ,}}