Text

Exam Rept 50-321/OL-87-01 on 870420-23.Exam Results:Eight Senior Reactor Operators Passed Written & Operating Exams. Exam Questions,Answer Key & Util Comments Encl
	ML20215J915
Person / Time
Site:	Hatch
Issue date:	06/19/1987
From:	Brockman K, Munro J; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	;
Shared Package
ML20215J907	List: ML20215J904; ML20215J915;
References
	50-321-OL-87-01, 50-321-OL-87-1, NUDOCS 8706250150
	Download: ML20215J915 (63)
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{{#Wiki_filter:T 1 1 8 l 1 ENCLOSURE 1 EXAMINATION REPORT 321/0L-87-01 Facility Licensee: Georgia Power Company l Facility Name: Edwin I. Hatch Nuclear Plant Facility Docket No.- 50-321 and 50-366 l i Written and operating (oral and simulator) examinations were admin-istered at Edwin I Hatch Nuclear Plant near Baxley, Georgia. 1 Chief Examiner: j te euu' /6

" - ME

/KenE.B%m[ Date Signed I b I/ 87 Approved by: v1 John F. Munfd, Section Chief Date Signed Summary: ) Exan.laations were administered on April 20 -23, 1987. i Written and operating (oral and simulator) examinations were given to eight Senior Reactor Operators (SRO). Eight SR0s passed the written examination; eight SRos passed the operating examination. Based on the results described above, eight of eight SR0s passed the overall examination. Of the five technical comments to the examination made by the facility, two (40%) were due to inaccurate / insufficient / outdated material provided to the Commission for the examination construction. This low number indicates the improvement made in the accuracy and completeness of the facility's training materials. i 8706250150 970622 ADOCK050g1 PDR V

1 1 REPORT. DETAILS 1. Facility. Emolovees Contacicui: J. T. Beckham,-Vice President - Hatch 3 H. Nix, Site General Manager - Hatch C. T. Moore, Manager - Nuclear Training R. S. Grantham, Supervisor - Operations Training R. Berry, Simulator Instructor Attended Exit Meeting t 2. Examiners: K. Brockman, Region II i C. Casto, Region.II F.-Keeton, Region III

Chief Examiner 3.

, Examination Review Meeting: At'the conclusion of the written examination, the examiners provided your training staff with a copy of the-written examination and answer key for review. The comments made by the facility reviewers are included as Enclosure 3 to this report. The NRC resolutions to these comments are listed below. l SRO Examination l -5.06 Comment not accepted. ) i The word "WHAT" in the stem of the question is j capitalized in bold type. This should be sufficient to 1 focus the examinees' attention to the requirement that 1 a definition be provided. j 5.11 Comment not accepted. The intent of the question was to determine if the examinees have an " appreciation" for relative absorption cross sections of common poisons in the core. Grading was based upon the candidates description of the concept of poison retention in the core. " Key words/ phrases" were not required for full

credit, m

e 1 5.15 Comment partially accepted, i The statement in Part a. is word-for-word from the GE BWR Academic Series, " Heat Transfer and Fluid Flow," Chapter 6, page 6-100, item 3., with the exception that the words "less.than" were' dropped as a distractor. If, however, the. examinee states the proper -i assumptions,.then TRUE would beHan acceptable response. i 7.04 Comment accepted. The: answer key has been corrected and the question revised, as per 34AB-OPS-045-2S. i 7.09 Comment not accepted. Parts a, b,'and.d are actions that an operator must be-familiar with if immediate control room evacuation is i required. Part c would only. require familiarity with -i the procedure in knowing that " Fuel Pool Cooling" is not addressed. 7.14 Comment acknowledged. j The intent of-the question was to determine if the examinee could recognize a " loss of secondary. containment" and have a " general" idea of actions required for this event. Although the answer key lists specific actions, the exam was graded accepting answers that'could be identified as " reasonable 1 actions", as per 34AB-OPS-018-2S and supporting procedures. The answer key has been annotated to more l specifically show this. 8.01 Comment partially accepted. During the examination, the examinees were instructed to state their assumptions if the intent was unclear. The answer key has been revised as follows-: -{ ..] a. No (Yes with the assumption of TS applicability for ) both units stated). d. No (Yes with the assumption of TS applicability for both units stated). 1 l

l 1 q o. 1 1 J The staffing requirements as stated in the Technical Specifications are not clear, in that the potential exist'to interpret these staffity levels as being unit specific, as opposed to being' site epecific. Neither. Unit I-nor Unit-II Technical Specificat ions identifies Table 6.,2,2.1 as i being the minimum staff required for Unit I and Unit II. Subsequent conversations with the Resident Inspectors at the site confirm that the specifications are being consistently interpreted as site specific, and that there is no reason for considering this to be an~ item requiring further resolution. 8.02 Comment partially accepted. i The term "Open Air Gap," although only used in: Hatch material as stated in the comment, applies'to pulled fuses, open breakers, open disconnects, racked-out breakers, etc., in any electrical circuit, An SRO, -responsible for the safety of personnel, should recognize that this condition is necessary for-work on any high-voltage system. The statement is i I correctly referenced to LP 3.1. The EO reference is I incorrect and was removed from the answer key; also, the specific voltage (277 V).will not be required for full credit. 8.03 Comment accepted. Part b. - The answer key has been corrected according to the revised procedure 34GO-SUV-001-OS. Part c. - (or local) is in parentheses indicating it is not required for full credit. 8.04 Comment acknowledged. The stem of the question and part (a) clearly state I. that the examinee is the OSOS. Therefore, any of the titles or names suggested (other than OSOS) are acceptable. In part (b), any responses indicating that the examinee is familiar with the ED duties would be acceptable. The answer key was annotated to more specifically show this. 8.05 Comment accepted. The question was deleted as recommended. A review of the ALARA Procedure substantiates that memorization is not required, because reference material is readily available and the administrative criteria for staff actions does not require short-term operator retention. u.......

r w a v, - i f 1 8.07 Comment accepted. The question was deleted as recommended. A review of o the Hatch reporting requirements and operator responsibilities indicate that the items listed in the j question-would not be considered the responsibility of an Operations SRO. 8.09 Comment' accepted. MCPR will be included as a correct answer. This is based on'the utility recommended references as well as the 5th paragraph'on page'3/4 1-2,in the Unit II Technical i Specifications. i 8.12 Comment not accepted. 'The; requirements for entry are considered to be of significance. They are' presented in the lesson ~ material withLenough emphasis to justify using them as a tool for' measuring the examinees' knowledge. j

4.

Exit Meetina At the end of the site visit the examiners met with representatives of the plant staff to discuss the results of the' examination. 1 There were no generic performance weaknesses noted.during the oral or simulator examinations, i There were four weaknessee noted during the operating examinations 't which, while not generic, were significant enough to bring to the attention of the plant management. a. In using the Emergency Operating Procedures-(EOPs), one j candidate took a wrong action path due to the human factors-1 construction of the flow path charts. With the great quantity of information which the utility has decided to include on the-flow charts, the action paths which go from step to step often are so close together, that the potential for mistracing the proper path is very great. The utility was encouraged to continue their evaluation of the symptom-based emergency procedures from a human-factors viewpoint. l 4 i

JJ 4 b. .The operators, in two instances, were hesitant to utilize'HPCI i or RCIC as_high pressure feed systems, when they.were INOPERABLE in the automatic mode of operation. The E0Ps asked i

the. question as to whetherLHPCI or RCIC were AVAILABLE; the j

systems were1available and would have helped to mitigate the

consequences of the transient if they.had been used.

The i training department was encouraged to ensure that all i operators understand the difference between available1and operable, as.they apply-to system operation. .c. Procedure.AR 602-325.only. lists one of the three Technical i Specification 1 relationships which exist if.this annunciator ' illuminates (TS 3/4.6.3). TS 3/4.3~.2-1 and 3/4.7 are not i listed as.' applicable in the procedure. These TSs should be included at the first possible convenience.. d. The Terminal' Blocks for the fuses.which control the solenoids i forLthe Main Steam Isolation Valves (MSIVs) were not labeled and could not be verified..This could cause operational ) errors if1the fuses were required to be pulled, as is possible. ~ during utilization-of the EOPs. There were numerous instances of simulator weaknesses during the examination. All'were of. minor'aignificance and posed no challenge to the integrity of the examinations. Specific software l shortcomings of note were: a. When estab1'iching RCIC flow for performance of the full-flow Surveillance Inspection, only 390 gpm could be established, as-opposed to the required 400 gpm. b. Cycling of the Minimum Flow Valves within the Feedwater System caused an unrealistic reaction on feedwater flow when power was less than 70% and three Condensate Booster Pumps were in operation. o, The RCIC -022 valve hand switch must be held for approximately 5 seconds after the " red light" comes on to attain proper valve operation. d. SPDS'did not reset when Initial Conditions were changed between scenarioes. The trace data which was being tracked from the last scenario continued to be displayed until the time retention period expired. e. The Cause - Effect Book for the various malfunctions needs to be updated to ensure that both utility and Commission personnel have accurate descriptions of the simulation activities. LL

>~.: + l c. The cooperation given to the examiners and the effort to ensure an' -atmosphere'in the control room conducive to oral examinations was-noted and. appreciated. ,1 The licensee did not-identify as proprietary any of the material provided or reviewed by the examiners. j i t.

.v ,g4 \\? 1 f ENCLOSURE 2 I-l~ U. B. NUCLEAR REGULATORY COMMIGUION GENIOR REACTOR OPERATOR LICENSE EXAMINATION FACILITY: ,_ I_I A T.C. _H. _1 7. ', -... _,.. _ _ _.,_ _ _ .m REACTOR TYPE: _ B W R___ _G F. 4_ __... -._.__.. _._,_ _ l DATE ADMINIS rERED: 0^7/04/20 EXAMINER. .J.E E T O N J. 1 CANDIDATE: INSTRUCTIONS TO CANDIDATE: Use oeparate paper for the an t.wmr c. Write answerb c, n one nide only. Staple questian sheet on top of the answer sheets. Points for each que n,t i on ar e indicated in parenthesen after the question. The passing gradG r e q u i r v-at LOA 5t 70% In DGCh CSEOgarV and a findl grade Of~at least 00%. Es arni.n a t i on papers will be picked up si (6) hourt after i the b terhinatien starts. % OF CATEGORY- % OF CANDIDATE'S CATEGORY .._YOlds .10166 .. _ _. E 0 0 B E _ _,_ _,M O L L E __ _ _ _._ _,_._ _,__.,, _ _ G 8 1 E G O B L _ _,,_ 25, b'l 26.00 .. '. T T 5. ~l H E O R Y OF NUCLE AR PONER PL. AN I L OPERATION, FLUIDE, AND THCRM0 DYNAMICS 2 6, '#> l 23 50 l 7 6. PLANT SYSTEMG DESIGN, CONTROL. 3 AND INGTRUMENTATION gg,50 26.31 PRCCEDURES - NORMAL, ADNORMAL, l.E9 a.. n _._ EMERCENCY f.ND RAOIOLOGICAL CONTROL 23:75 23 87 _.a w _ _ _ L a .__ _ __ c. non tme rnAuvc r'ROCEDURES, CONDITIONS, AND LIMITATIONS 100s] { ,,'+'\\ n .L , b h1. I' ( t All wor k done ca n thle o amination is ny own, I ha m n e i t. h e - given nOr r O C O /Od d i Cl. f-

u. m e a t s

-, we i i

e I 1 1 J 1 [ \\ NRC RULEO AND GUIDELINES FOR L.ICENSE EXAMINATIONS During tha admiru strati on of thlm e, amination the following rule opply: 1. Cheating on the e< amination means an autor ati c denial of your application and could result in more se mre penalties. l 2. Restroom trips are to he' limited and only one candidate at a time may leave. You must avoid all contacts w:th anyone outside the utamination 3 room to avoid even the appear ance or possibility of cheating. Uso bl ack ink or dark pencil gnh t o facilitate legible reproductions. i 4', Frint your name in the blan!< provided on the cover sheet of the examination.

1 Fill in the date on the. cover nheet of the e< amination (if necessary).

6; Use only_the paper provided for answers, j 7. Print your-nam'e in the upper -ight-hand corner at the first page of encil .sectxon of the answer sheet. l 0 8 Consecutively number each anrmer shcet, w'ite "End of Category i" an appropriate, start each categor y on a Oew page, write only gn ogg sidq of the-paper, and write "Last Page" cn the laat answer chee&. 9. Number ach answer as to category and n u rr b e r, for enample, 1.4, 6. ~5.

10. Skip at least three linus between each a n s war

11. Deparate answer sheeto from pad and place finished ansucr cheet; face down on your desk or :able.

12. Ue" abbreviations only if they a.re commonly used :n facility l i t erat ur e.

13. The point val ue for each question is indtceted in parentheses after the question and can be uced as a g u i rJ e for the depth of armwer s 'equ1 r ed.

14. Ghow al l calculations, nethods, or assumptions uned to ;btain an anuwer io mathemari.;l proo:1ee whether indicated in tlie question or oct.

1 1 15 Partial credit may bo given. ~l h er e f or e, 4 HEWER ALL PARTG Of' TlE OUESTION AND DO NOT LEAVE ANY AN M R Bl. ANK i i

16. If parts of the.e: aaunation are not clear as to intent. an questions of the e..am) rior en;y.

.i l '7. You must sign the stetement or thL.: o v e r dur e t t t,at i n d i c c.t e s that the j uork i> your own und you have not received or be::n gi mis assistanto in the i n ami nat i on has l completing the eaamination. This nuit to donc ef t t been ComplOtGd. ]

i e e t I a 3 1 1 10 '. When you complato your e' amination, you shall-a. 'Assemb1c your enamination an f01 aus: j (1) E' a m qua ts t i on s on tc p. i (2) E;am alda - figurec, tablea, etc. 1 (3) . Answer pages including figuren which are pait of the answer, I b. Turn in your copy of tho c::ami nati on and all pagen used to answer the e;(eminat t oo q v ca t i on s., j c. Turn'in all ccrap paper and the balance of the peper that you.did j. not use for answering the auestions. t. d. Leave the ex ami na ti on area, as defined by the examiner. If a-f t er leaving 3 fou are found in thin ar ea while the examinatlon la still in prngress, your license may be denied or revoked. 1 i ) 1 S

1 f ) l 1 j ' S.f_. _T.H, En.R_Y_.O_ _F_ N._U._Ct.E.A_R. POWER PL AN T .O.P_ E_R A T..I O._NL F_ _L,. U.I. D 9. L A N D PAGE 2 T.HE,RM..O D VN. AM._I C. S { } i l q OUESTION S.01 (1m00) . Critic 4lity is defined an Ke-f f u l, " f 21 s i r:an chain reaction.is c'el f -sust ai ni n g. " DESCRIDE the process that maken it possible to have a self-sustaining reaction at Koff=U.90? i J, QUESTIOM-' 5.02 (2.00) I l Y ch.t are,Silift Supervisor during a startup following n reactor. scram. The. ) j RO hau withdrawn rodc to Keff=0.79 and the reactor in cooling down'at a rate of 100 degrees'F/hr. I s 'l a. Calculate WHEN the reactor will go critical with no further r'ad ' q motion.(Consider only temperature effects, assume alpha TM m l l -1 x 1 C4~ ~4 Delta K/K degrees F). (1.0) b. IF t he reactor was at 100% power far 60 dayn prior to the SCRAM HOW 3 Would Xenon affect the t i mt? calculated in a. above: .i f l '1 ) D hours s.f t er the scram? (0.5) f: ) 20 hourr M t e-the ecram' (O.S) UtJESTION S. O!. (1.S0) 1 a. ' Define Net Poni t i ve SJcLion Head (NPSH). (O.G) i l; b Expla'n WHAT happen; and WHY to Recirculation Pump NPSH if HPCI i I initiele at '70% power. (1.0) l L i QUESTION-3.04 ( 1., 00 ) During reactor thatdown for r e i tm l i n g, the Statitn Nuclear Engineer tellu you. shutdown margin in O., 4 1 %. CALCULATE,::e f f. I I l DUESTION S.05 (1.00) WHAT could happen if the Core Sprq F utrpt storted with the J oc k en j. Pumps shut down? l l [.

<lA . j '. bs_ IUEOB _OE_,8UCl.' EAR POWEfi PLANT OPiERATION _f3.),J1DOuGND PAGE 3 3 . IUEBdO[ddQUIGO i i . QUESTION 5.06 (1.50) { 1 I .;WHI1T i u. '! Power Coe ( f 1 ci ent of Reac t i vi t y,, " WHICll other; coefficient-DOMINATES the power coefficient during: - a. Startup? l b. Power operation? QUESTION .5.07 ( 2,, 00 ) <l With regated to FCICMR, IDENTIFY the fallowing statemento as TRUE or FALSE, . a., PCI failured are dependent un absolute power, i ric r ease 1.n. p o w er, dt.ra ti on of power increase. previcus.pawnr hiatory, and fbel 'l exposure. I l "b. Regardless of. strsms utate, strain rate,itemperature, presence of i iodine, f.u? d. u t a t e o f irradiation, :: i r c al l oy fuel tuben Will be

ductile, i

q c. If power l'evel is reduced prior to ccmpleting the 12-hour caak, pre -conditioning 13 resumed at either the new power-level or the power level-12-hours before the power decrease, whichever 'i n higher. d. PCIDMR limits are.given in Gection 374.2 of the Technical-Specificatiant i QUESTION 5.08 (1.00) DEFINE " rod shadowing," and EXPLAIN the offacts. i ($***i CATEGORY 05 CONTINUED ON NEXT PAGE

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sf 9- -I L $h.., lUggBLDE Ugg6500_POWEft P!; GUT,OBEB811GL_ELUlph_OUD - PAGE 4 1 IU!iBtiDDYNAMICD i QUESTION-5.09 (1.50) 1 1 ..Dur, n g '. you r> shif t,.an > SRV-inadvertentl y opens at 100% power-and looo. psia. Use the' Gloam Tables or M o l l i ta r Di agr am to answer.the following;; (AGSUME' INGTANTANEOUS HEAT TRANSFER AND A DATURATED SYSTEM.)- I .a. Determine tailpipe temperature, assuming r:eactor pressure remains c on ts t an t and suppression pool is at atmospheric'practure. !:i t .b. I'rs the ! steam e<hausting to the supriress t on '. pool scaturated or i iuuperheated9' 1 1 c. Determine at-what reactor pressure the tailnipe would reach.its i maximum temperature'if the reactor depressurires. ) GUESTIUN 5.'10 -(L 00)- .1 l Match the f ollowing st atements (1 thru 4)' With the pr'edomi nant reactivity cdefficient (a thru'c): (May be used mars than once.) 1. Decames more dominant as nteam flow increases at power, 1 . _,, _ _ _ _, Wi]l i n.L t i e t u reactor power change upon high level-in 4th stage feedwater heater. J. ,,, _,,_. L e a s t responsive to fuel time constant. I 4, ,_ _,._ Taken advantage of during Anticipated Trencient.Without i Scram (ATWS). J 4 a. F1od er a t or Temperature Coeff1cient ] k b Doppler Coefficient i i i. c. Void Coefficien!- I { l ( QUESTION S.11 (1.00) a. GADOLIN1UM was chosen as a burnable painon Instead of DDRON because GG has'a larger absorplion cross :ection. 'I' RUE or FALSE ' -b. Justify your antwor. (***** CATEGORY 05 CDNFINUED ON NE/:T PAUE ***?A)

jy ' .c ,~ e ? f- [6 '- i .a, 1 .34

f 5$.: d1dE9BX 9E_.!)WGLEOb !I9k!EB.El$0dI_.9EEBS110th,,EL(!1DL _6NQ PAGE d3[i,-

IUEB009YtML11GS hi 4DOESIION-5,12 (2.50) ,. :~ Match esch.of'thetfollowing;. statement.n.with the appropriate numbered item: 'I h The :1imi ti n.g. par ameter. that assuren PCT-will not ' extend + '200 degrees F.auring a design basis LOCA. 'I .1 A

Total. power passing through 'a utilt length of fuelirod.-

I j ?,f APLHOR divided by MAPLHOR limit. M ~Saf ety limit that is not analyzed at 4 10% power.or 800 psia, i, s. 4 ^ e.

E'atto of thk-power ~ required ta produce OTB in the bund.le'to

- (- l actn.al'bundln power. -) ,(7 l 1.' ); 1. .MAPRAT 5. LHGR qq l 20 'FLCPR -6. FLPD 3. APLHGR 7. CPR O I 4 MCPR D. -GELX x

b.i

. QUEST, ION 5.13' (1.50)' q i <\\ t ^ ~ period. (1.0) g ) a. Defind reactor b ". As compared to - BOL candi!.i on:s, the mfie.:t o# del ayed ~ t r>Lu_ r an s on reactor ' period at EOL fo# the same reactivity addition will 1 e result in a (SHORTER, THE GM;E, LONGEE, period. Whoose one) l. (0.5) l 3 l' r~ l.. > 'OUESTION -5.14' ( l '. 00 ) s T Ghapi ng' c'ontrol rods ~are (DEEP,. INTERMEDIATE, SHALLD O rade that are uned to change the power profile because they (ARE, ARE NOT) 'affected by shadowing. (Choose one answer in sach par en thesi n. ) i l I -($****; CATEGORY 05 CONTINUED ON NFXT PAGE

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n,

f r. J.7, ..a. ffb l hh I.N pv ,.g{,}! eg. c x 3. c ;; n.;, .q. t f ". ?- r, 0, fp NYW$g{lT (Y ' s> f $y. t3:d t..@.,OPY_O_F. E._n. -~4 AR I'OWER PL ANT 0,PEfe.4..T.I. ONt EL_.U__I D9A_AN_D PAGE ,6i ~ 0 d , '.i ym$,TMTBMUDYNAMIC$ J f y rn~ !! \\ p ;,3 ).c y? .1 . g ;. i y,;( ~ t 4 o t i c,JOCESTION' S.1$ ,(2.00) 1 (. a '1 ..l , y(( ;)pd)cerni ng qpump^dharacter Wti ce cia te. whether

l s-j each of the 'following is,

{- t MUEp orts FALUE: Of/Of.. a) The.totaf,braks hognepowsd 'for two~. i den't i cal ~ pumps operat i ng - b.;))',, in. Ppd 11h un tWice the individual brake.. horsepower for-at uingle z W ' t

puTo1 ry pp'192.ng.the same capac) ty; t>

..'iflI' ni murn f Iow valv s3 are provic'ed in all. ECCS cyst.emo to. minimize

,s 1

~ 3, ' ). Ethef time the L pusn.p i a running. ul th tahu tof f h e a d., , r. V'{.EsanlWith.the Heblyculation. pumps off, the jet pumpu will enhance' . e,.. {.. natur'al-ci.rcQ1 ati on flaw. q d.

Rotary. pumps ard used'on' emergency diecels for pumping:viccous.

L1 iicoli ds.(such' as oil, f uel 0111 etc,) because'they are'nimple,- -l i gh t-: wei ght!, lcompac t, and low cast. .l I m ,.n I s W QUEST 10N (c.!. 16 (1 00) cri ticality has been achieved and control rods > During a reactor'etartup, have"beeni Withdrawn to ectablish a 100 sec period. At what point Would you expect 1to'ne period became longer and.WHY? 1 n s. QUESTIDN'. 5.17. (2.DO). E ' Attached Figure # 070 represents a transient that could occur at a DWR. .GIVE!h (1) An SRV.In manually ' lifted at time T 2 min =- -(2). 'The SRV is cloc.ed at time T = 4.5 mi n 1; (3) No other operator act1ons occur a 1 d i vi s i. on 1 mi nute 4-(4) Recorder npeed LEAPLAIN-the cause(s) of the f ollowing recorder indications 2 a. W essure DECREASF (Region 4) l .b. Total Steam Flow REDUCTION (Region D) c. Turbian Ste6m Flow REDUCTION (Region C) =d, Level INCREASE (Point D) e. NEW'CTABLE (1cwer) Level IRegion E> (***** END OT: CATEGORY Ob 454%$)

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o qv p ^ %_ !1BNI3f!5IEt!3EglQth GQUIBL.ONQ_INHIByt!EUIGIlOU PAGE' .- 7 7 1 ~ ?OUESTION' 6.01. (1.50) Fo.);1owing "a reactcr scram,' reactor _ pressure'is'at 900 psi and;the Reactor " Water. Cl eanup Sputern'. (RWCU) Listbeing!used-to control-reactor vessel water c.l evel. With 'reguards ' to the.RWCU: a.,;WHAT:special precaution must<beLtakenT?E(0.5) b. WHYT (1.0): i . i .j e 10UESTION: 6.021 ( 2. 00') [ 'Ind) te.whether each iof.the f ollowing are - TRUE or 'F ALSE. Fecirc'u1Ntion pump-flow'.is varied b'y varying the f requency whils "a. imalntaining a constant voltage. b,, To! r estart a reci rculation purnp' af ter a' trip.at' power, the i d l e' d loop i s L. warmed ?up by thr;ottl i ntj ~- the di scharge va'1 ve. - t -) c- ' AYa115ble' Net Positive Guttien Head for the recirculation' pumps ' i sc greater ; at. '.100% power than at.75% power because of greater- ' feed flow. Id., With the recirculation ~ pump cirive motor windings at rated J - temperature, two starts are allowed during a one-hour ~ p er i od'. i QUEGT. ION 6.03 (1.00) (Fil1-in the D1anka) l (a) LPFiM detectors serve each at the APRM channel s on RPS Dus A,- i p [. ,and (b) _,._ _. LPRl*'detectorc, serve each of the APRM channels on RPS I-Dus D. i I -QUESFION 6.04 (2.00) j I '2TATC thh purpose of the L'JW-LJW GET (LLS) system, and LIDT the canditions j that'will arm the uystem7 j ~ 1 (*44**.CATEGDRY C T ! NUED ON b!EX'1 PAGE

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is 7 j j ,4 j d I -fi_ ZbhMLDIDIEUS DEOlGNt_GOUIBL_GND_INSIByd[UISIlOU PAGE 8. r. 1 - i DUESTION '6.05 -( . 50). [TRUE or-FALGE 7' 4- - I The Standby. Li qua d Control. (SDL.C) system'Will shut down'the reactor from

any, operati ng. 'condi ti on at any time in core life and i s intended as a bac kup f or... reactor.. scram.,

OUEGTION 6.,06 (2.50)' Ma i. ri steam Iine rad monit'arn pravide 5 prat.ective actions at radiation j< 1evels'3XN. LIST THEM. ..UESTIGN

6. O'?

(1.00) Q 1 Each Standby Liquid Control (SDLC) pump is uired 'to inject :the nolution into the' reactor in 50 to 125 minuten. STATE the reacons for the MAXIMUM and MINIMUM injection rates, k-

DUESTIOrk 6 00-(3.00) a.

STATE the purpose of the'"18-inch e:4 cesu. f l ow i sol ati on dampers" on the Gtandby. Gas Treatment System (SGTS). suction line and HOW this function:is. performed. (1.5) . ti. ~ STATE'the purpose af the activated charcoal filter bed in the SDTG, ar d HOW and WHY it would be affected if the electrical heater is last .following a LOCA. (1.3) i I k i 'OUESTION -6.09 (.50) { j; ) .TRUE or FALUE '? 1 l '11'a LOCA and LDSP accur simultaneously, all RHR pumps will start 12 q l --sucands after the LDSP to allow the d i e :>e l generators to first tie to l. -their respective buses, f I I I ] -(***** CATEGORY 06 CONTINUED UN NEXT PAGE

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it..

k ^ E... e. r [. I Oz..$6DNT,_QySTEMS L DESIGN - CONT [396_fND INSTRUMENTAT ION PAGE-9 1 e Ij -OUESTIDN' 6.10 (2.00) 'U-i an'd'U-2.use nitrogen to~ inert'their. primary containmento during a.- ' op e r a t i on.'..Other than preventing an' explosive. mixtdre f ollowing a. LOCA,.What is the. reason given for inerting Unit'2?- (0.5) ,j b2 .The nitrogen la heated pr or to reaching containment. Identify f .TllREE adverse efftcts.,that loss of heat'ing could have an the'systemui -j or plant ~during inerting. (1 5) i i i 1 ..J . QUESTION 6'.11 (1'. 50) .i I Vou have-just.rslleved the affgoing shift during a plant startup. Ths -j -reactor is at G5. thermal power-.andlyou notice the mechanical vacuum pump .l' .i e running. In this a problem?. WHY or WHY NOT? -QUESTIOM 6.12 .i2.00) You are Ehift Cupervisor on'Un'it 2. An a nstrument technici'an' in f oPms you that he needs to per-form maintenance on an Analog Transmitter Trip 'j Gystem1(ATTS) cabinet that requires deenergining one of the 120-V ac' power'

l oupplieu.

WHAT effect will thtu action-have on the fallowing: -] l a. .PCID Group I b. PCIS Group II.and V i c. Gecondary Containment d. RPG. trip systemu ( l QUESTION' 6.13 (1.00) -Concerning the Cantrol Rad Drive (CRD) s yst!em: a. Identify TWO sources of water. I b; WHICH cource is: preferred? c. WHY'1s this the in ef erred source? (****t CATEGORY 06 CONTINUED ON NEXT PAGE

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%._ f lLO U I _ E X E I 6 t!E l E Q l g N __Q O N I B O (s t AND lygIB(JUEMIQIlON PAGE 10 t y 1 1 l 'DUESTION 6,14~ (1.00) 1 Which ONE'.of the following most accurately describes the PRIMARY concer n j

if a' tube leak develops in a RWCU Non-Regenerative Heat Exchanger in.

a. Release of radianctivo material to the environment, b. Calder seter being. injected into the feedwater system. c. Contaminati on ni the RBCCW system. .d. Over:'pressuri n at i on o f the RDCCW system. 'OUESTION 6.15 (2.50) 'During'a fuel load you are required to veri f y proper ori ent ati on c.f. the 3 . fuel ascemblies. -SIX visual indications of proper orientation are lipted. Dive FIVE of t h e m,. QUESTION .6.16 (1.00) Which of the-following lists of responsen (e d) CORRECTLY describes'the main turbine's responso'to an Ov'ERSPEE u condition? RESPONSES SPEEDS (a) (b) (c) (d) 102% " Master" A13 ICV's All ICV'c "Menter" ICV's began begin to begin.to ICV's begin to thr o t tl e-throttle throttle to throttle "Sl ave " Slave" ICV'c begin ICV's begin to throttle to throttle l' All ICV's Al l ICV"s All I CV ' *. A)) I C t"' - Ful1 C1oned Ful1 Clcued Ful1 Cloned Ful1 Clased 110% Mechanical El ectr i c al Mec han 2 c a.i E) ectri c a] O'Spd Trip O'Opd Trip O'Spd Trip O'Spd Trip 1 J 1 ;. 5 % Electrical Mechanica.l El et rr ic Al Merhanical O'Spd Trip O'Spd Trip O'Spd Trip 0"Spd Trip '(***** ENDOFCATE}OORY

- }**)

06

af 5

n

,c-u.fDNOBi h_Er1EBO[NGLOND PAGEL '11

7.

~ FROCED!)RES ' ; NORMAL j RADIGUOGICAL CONTROL n e . QUESTION -7. 01 - -(1.50) t Jhe. High Prescure Coolant Injection (HPCI) system in being. shut'down l hliowing'survekllance. The operator han' started reducing the turbin speed;in accordance wi th 3400-E41'-001 -29 but'was called to the other unit ~ to assist. pith a probl em., You notice HPCI turbine speed is still- 'decreening. Accorcli n g to the procedures a, '- WHAT speed i s-of concern. ( 0. '50 ) b. -. LIST-T;WO.re r.

onc er n. ( 1. 0)

I . QUESTION ~ 7.02 ( 2.' 00 ) .In accordar ce wi th. U--2 Procedur e J4SD~D21 2OO1-28,'" Automatic l ' Depressur;i n ati on System (ADS) and LOW-LOW Set System (LLS)," j ..the ADS may-be initiated MANUALLY only iF4 conditions exist. -l ' STATE these.FOUR' conditions. l 'OUESTION' 7.03. (.50) l TRLIE or FALSE 7 t In preparation for plant startup, the' operator lining-up the Plant Service Water (P5W) system informs you that a val ve must be changed. f rom i ts l normal position. Au ShifL Supervisor,'you'can authorize thie change, p.r i o r to clearance being 2suuec, to expedite the startup. -QUESTION- '7.04 (2.00)

a..

.You have just recei v-d the f u11 awi ng al arms, " Rod Out Black," " Heater Trouble," and '4th Stage HlR BOO 74 Lovel Righ." S~ ATE the immediate action which must be t aken (no <eactor scram). STAFE the reason for 1 thi s acti on. Lb. .It'becomes necessary to insert contral rods to r.t a v below the 100% sc

load.line.

WHAT chould you tn11 veur reactor operator royuarding cbre flow and rod i n ser t :. on cautions and notes" l i i i (***** CATEGORY W7 CONTINUED ON NEXT PAGE

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f' Z,_Ef30GEROBE0_: UQBtl0!.k_GDNOBdOLJ, fide 6ggNgL6dD PAGE '12 00D19L001086_G9dIBOL ~ .DUESTION 7,05 (2.OOf i In -accordance.with_34GO-OPS-OO1-23, "Pl ant Startup, " the Reactor Water Lovel ' Oelector swi tch, is, selected to "D." STATE FOUR reasona,for r;el ec t i n g "D." OUESTION 7.06' (1.50) LDeleted. .i 1

D LIE S T I O N '

7.07' (2.50) Given thct f ollowing general EDP conditions,-IDENTIFY the correct flow path-l '.to fallow in accordance wi th 31EO--EOP-OO1-25, " Emergency Operating. Procedure Inside Control' Room Lini t 2." Hi gh radi ati on, 'l oss o f ' cool ant, control of primarj contaihment i integri t:y. b. Fil gh steam 'li ne.redi ati on, loss of vital power, st Uck open relief v :11 v e.. c. Low power:trancient or 'faj-lure of vital equipment. d. Malfunction of Rescti vity Control System. e. .High power reactor tranuients or' failure of vital e qu :1 pm en t. QUESTION 7.08 (.50) J l TRUE or FALSE ? Aft'er a reactor scram occurs the Shift Supervino-determines whdther ARPn 3 and/or-ADPc Will be perfarmed I ) Iq } -(***** CMEGORY 07' CONTINUED ON NEXT PAGE

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BODIOLOglG9(__ggNIBOL ^ . Pf4GE. 13L NORMAlQ ADNORMALdl"j[ROMGLAr D 7.

PROCEDURES i

r QUESTIDN 7,09 (2y00) l 1 ' Ap 'Shi f t. Supervi scr on. Unit 2 during mid-shift, the reactor is in Mode D and 'you - are r' equi red to i m:nedi ately evacuate the control room. AncWer each of the following statements Tf"UE or FALSE. Ja, Since the i mn,edi ate ac ti ons of 34AD-OPS-055-28 cannot be performed prior to ' l eavi rig the control room, the same results Will be accomplished by apening and reclasing the RPG breakers, and opening breakerL2N21"F113 at MCC-2C, and opening 2N21-F113 et;147 TDT 18. b. Decaune the RPS tripped if the breakers were opened, you would'be requared to enter 31EO-EOP-007-2S. i c. .The.aubscquent actions of '4AD-OPD-055-25 require that you verify { Fuel Pool.coolin'a is established in accordance.wi tih 34SO~041iO1-29. d. According to SD-OPS-04-1106, upon enterino the reactor building, you-are requi r ed to clone valve 2T48-F111. .I OUESTIDisi .7.10 . ( 2. 0C0 Actnrding t o 34 AD-OPG- 024 --2, "RPIS Failure," STATE the FOUR indications you would expect if the RPTO f ail ed wi th the reactor at 20% power? DUESTIGN 7.11 (1.00)

t You have entered 31EO-EOP-001-29, Path 5,. and a key parameter previ ousl y

.eddressed changen Your immediate actiar) in-(CHOOSE ONE) a. Rcturn to that key par ameter,i readdress, and continue from there, l

b.

Ignore the change nince subsequent acti on s have atmured p i sin t safety. c. JWturn to top of f J ow chart d. .Go to End Path Manual :2 n d follow procedure for that pammeter,. i l 1 1 1 1 (% *** CATEGORY 07 CD ' r ? N .D ON NEXT PAGE **tif)

f . d -1 I 1 l f '7. PROCEDURES + NORMALn,,f)DhlDRijhEfj[~RGENGy AL4D. PAGE 14 R_ A_ D I O L O.G..I_ C AL... _CO. N.. _T.R.O. _L. 4 { I 1 QUESTION 7;12 (1.50) 1 During plant startup, in accordance with 34GO-OPS-001r2Sg " Plant Startup," ')t ep J 29.a.) " Turbine and Generator Startup " the generator ' cmci tation is established. l l 6. WHAT at.t i on muut-be taken if the generator' voltage does'not immediately increase.to 60%'of' rated?. (0. 5 ) b. Ident if y TWO possible reasoon of f ailure to establish

exci tation.

( 1. 0 ) - . QUESTION

7. -l 3 (1.00) l=

Yatt are maintaining cold shutdown.in accordance with 34GO-OPS-015-29, " Maintaining Cold Shutdown or Refuel Condition," A CAUTION states.that heatta may occur in the core area with lio temperature increase at the recirc pump nuttion or RWCU inlet. State the TWd conditions that can tause this. -QUESTION 7.14 '(2.50) During power operation as the Unit 2 Shift,Eupervisor3 a PEG reports that both doorn on u Reactor Duilding access were damaged by a contractor moving equipment through and neither door can be f ull y cl osed. STATE } FIVE actions you would take?- l I I- -OUESTION 7.15 (1.00) (Fill in the blanka) j During Pce,t -LOC A cp er a ti on, the Hydrogen Recombiner Sy n t ern shall b r> i:n i t i at ed per 34SO-T49-001-2, " Post LOCA Hydragen Recombinor," wtwn ' hydrogen concentrataon reaches (a) The reconbiner cystem Will be operati?d to mai nt.ai n the hydrogen concentration belcw L w _3 and the anygen concente m aa ta ow (o _ _ x. l -(***M CM EBORY'07 CONTINUED ON NEXT PAGE

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3 o 1, y, 4 n 1 4 . c R. ' t Zi_200GEDUQgS. ~ NORM %;,,_GEUQBL18Ld_EdEB@@UQX,,6ND PAGE-: w B00106001G06 39NIBOL- ~ F 'fjuEST ION /7.16' (1.30) According to 3430-L47eOO1-2, "Plsnt Fire Protection System," after the' .3 ire in'"out and the fire pumps are shutdown, the ManualDReset Switch >must be' reset by the PEO. ta. JWHERE is-this swi tch li.7cated'? ( 0. 5 ) ' -b. WHAT.woul'd be-'the consequenceo'of not: resetting th6l switch? _I.1 Ob l 1 j 'UESTION 7.17 (2.00) p Q i Entry into a HIGH' RADI ATION AREA is required..'To: complete the. task, t h e-j ~ l, - operator wi'11. receive an estimated 70 mrem,whole bad / doeie. You have-the' f oll owingc i rif ormati on en avail able. operators. Time constraints"will.not 'j permittauthori r ati on - a f a*1 increase in administrative. limits (above your.. 1 p. l evel' as - Shif t Supervi sor). NRC Form 4c are an' f ile unless otherwise L-indicated. Gi ve 'your ' reasons.f or accepting or rejecting each;aperator f or; thegjob. 7 l! ' Operator 1' 1 4- .i 1 l \\. Seki Hale Male Female Male Age: 29 30: 24 20 \\ 200 mram o mrem 5' mrem 98 mrem LWk/ Exposure \\ 1190 mrem . 1960 mrem 435 mrem 420 mrem Qtr / Exposure. p '. Life / Exposure 53370 mrem 273S mrem 9970 mrem. Remarko I li.st or y ' months l( Unavai1able fr e g n a n t -

p.,

Signed Prenatal Document on File e e (***** END-OF CATEGORY 07

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Wesuk'ug-'ll ruR11 rgiir gi-

h:7! 6-s 1 .\\ gig AD M I N I S T R AI I_ y!CPBO QQQljBEQ S,,C OND I T I Oh"3 u AN D L I M I T A T I O NS PAGE '16' i - QUESTION. : G. 01-(2 00) .j m. ~ You:are U-2 ShiDFt-Cupervrcor on back chift. U-1 in operating at ' power 3. "' - ' Un2' i s.i n.11 ode 5, Fuel movement in progrecs. Beccuse of a Flu epidemic, if ,your_' crew composition'is-ocheduled rn follows-q '50L 2 + 1 Fuel ' Handling Supervinor i DL 3' ? .Non-licensed 3' GTA 1-4 1 .] =The STA,..J OL, and FH Supervidor have called :t n cick. The STA and OLE i have just. completed a double shift, the FH Supervisor operator'hb.n worked (! 14'f)ourn. I a. ' Con the STA from the previous chift satisfy your requirements? { 1 Lkn. 'How 1ong do~you have to meet your.requirementa? l r t. Who can authorize deviation f rom overtime guidelines? j i d. Can'you anq1gn 1 of your SOLs to FH Gupervinor to meet that r equirement? I i .y , ~ ' QUEST 10N. .I 0402 (1.00) TRUE'ur FALGE ? A clear ance can be i ssued without an "c. pen-air-gap" to work on Drywel'l ] Cooling Fans. JUSTIFY.your answer. 4 'QUEGTION 8.03 (2.00) You are verifying a valve 1 i n e -u p, STATE. how you confIre, pomition af each j I of the following: a. C1osed valve. i b. Open valve. c, . Motor-operated valve. .d. L.oc k ed thr'ottle valve. -(***** CATEGORY 08 CONTI.NUED ON NEXT PAGE

- - 44)

f ~ ~ ' h'"; b. .G J ( l., PAGE 17- !% 690101GIB6IIMfLEBOGEDUBESuG90DII19Ugg AND LIM 110110MD l .l j 4 3 >-QUEST: ION :6.04 (2.25) l e. a'n alert. As On-Shift

A' situation. occurs requiring declaration of l

Operati:ons. SQpervi sor:

ll- ~ Who Al'11.- rel i eva.'you as. Emergency: Di r ectcr? (0. 5 ) - 1 a. 1 ,b. LISl SEVEN'of yourirespanoibil'ities until r el i eved'? '( 1. 75) 9 i m 1 I l 1 l ..RUF.GTIGN D.05'

11. SO) :

'l 'Daleted. Y QUESTIGN G. 06 ( 1.' 0 0 ') '. 1 1 l STATE the.,condi Lion-that munt enist f or more than"ONE MWO number to j be.placed ca.a clearance? 1 i l Q U E. S T I O N..G.07 f1,00) ~ i '. Del e t ed. i 4 j -DUESTION G.08 ' ( 1. 00) l I y . Unit.1 Technical Specifications ctate that "'I r r a d i a t ed fuel shall not be handled in or above the reactor prior to 24 hours after reactor shutdown." -WHICH aneLaf the following most accurately describes the reason? I; eL a. This is the minimum time it takes to set up for fuel. handling. l. b. Decay heat must be bel ow a speci f'i ed level. ' 4 -h odr decay. 2 c. Fuel handling accident analysen are based on .d. . Uhutdown margin'cannot be calculated untij Xe in on its decay cycl. 'O'UED T I Ot.-} 8.09 (1.50) Wi t h' respect.to Unit 1 Technical Spec i f i c ati onS Safety Limits, WHICH 3 s Hspeci.fication requires periodically checking scram time and WHY? 7 7 L., _(***** CATEGORY 08 CON INUED ON NEXT PAGE *****)

J Lg 1

z:-.

.'.5, 4.'^ s j x, ,m' f p Q,890lbIhISBIIVE_f 60GEDWBEL._GO SDIIIOL%_BN D_,Eldllbilgy3 - LPAGE 18L, i IQUESY10N l0.10 ( 1. 50). s i

Wifth respect to Uniti1'and Unit 2 Technical Specifications, STA'TE the'

(- ' differences between the sa f ety lirnits,. f or the,tWo-Units. i i i j -QUEU.T. ION 8.11 -( 1. 50 ) . f' ,u . In accordance with : Techni cal > Gpecification, Secti o.n 6 8, - and s j 10AC-MOR-00bOS, " Preparation and Control of Procedureu,". temporary j <changen tof sa f et.y-rel ated procedures can be made if-TFlREE conditions'., j arb met,. STATE-thoun-conditions. 1 I LOUESTICN -0.12 ( 2. DCO al Enttytinto primary conteirmont is neverned by. temperature / time- ~ 1 limits. ~5 TATE those limits as gisen in 31GO-OPS- 005-09, "r'r i mary. Cohtainment Entry." (1.5) .b. . T RUE or FALSE : . i Following a one-hour rest outside caritainment, re-entry.can[be j made. (0. 5) ' . l 1 1 QUEdT10N 0.13 12.50) - l

On bsc!' shift, a fire is reported in une al the maintenance shops:

1 a.- STATE.the PRIMARY iand'ALTERNATC persons (position t i. t l e ) designated to assume Fire Brigade Chief. (1.0) b. .What ia the minimum number of perscos who should show up for the 'iire.-briged W (0,D) c, !!aW~ mariy of t6 we persons should have c:ompet ent kreowl edge of s o f 'e t y r j 4 systems? (O.b) d. ,Are those persono responding to the fire still counted as part of -the-shift r.r e w ? (0.5) i R ;A ? (***** CATEGORY 98 CONTINUED ON NEXT FAGE

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a

J

t a,

'g i .i & _ 09dINISIBBII E EE9CE.DUBEL._CONDUrIUN b_ BUD _11dIISIlgMS PAGE 19 j 4 duESTION B.141 ( 1. '00 ) l l A' Technical Sp eci4 i c a ti on Quarterly. Surveillance for a Unit 2 ECCS cyatem was due July let,, Because of an LCO on the system, the.curveillance wan not completed until July 15th. i a. WHEN will the next quarterly surveillance become due? i- .b. ' DEFINE " Grace Period" for Unit 2. l i QUEGTION B.15 ( 2. 0C0 .With regnrdu to Recirculation System: l a. STATE the c on d i t i on ( E,) that ac t ua t e (1: ) the End of Cycle RPT trip. 1 b. . STATE,WHY. thin trip in neccessary. t UESTION-8.16 (1.00) t [, [. Uni t. 2 i n in HOT OHUTDOWN wi th a. reactor prescure of 805 psig. Operabili-ty SI(o are performad on all of the MCL Radiation. Monitoring System Chenneln. Channels A and D test UNSAT, while Channels D and C test GAT. Maintenance has no estimate of repair-time and will not be able La commence troubleshooting and rep air" for 16 hours. Which pf the following entions most accurately d ail the allowances and/or limitatlans imposed by the Technical Specifications in this instance? a. No action required; function not required to be OPERADLE. b. . Place one Trip System in the tripped condition, within one hour; no add i t i on al actlan i s required. -c. .De in Cold Ghutdown within the next 30 houro. .d. Place one Trip Gyctem in the tripped condition, within one hour AND be in Cold Shutdown wtthin the n m>. t 'O hours. } e. Lock the Rr: act c.r Made Ewitch in the Shutdown Pcsi t a an, within one hour. s .(t***t. CATEGORY 08. CONTINUED ON NEXT PAGE

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4 [ '1 1 i< -( ; '..~ 4 N,% ,d 1 Di A9dlOISIBOIlYE_.CBQggDUQggi GQNDITIONS, AND LIMIT 8TlgND- -PAGE' .2 0 - j l 1 . QUESTION E J17 - (,.50) 1 r 0iven'the fol!1owing conditions on Unit 2: t ' Mode Gwitch. 1~ Refuel Tremperature 100 deg F i . Pressure O psig clevel - 'OS-inches -RHR SDC Mode . T h, e H. e a d Dalts to.the RPV are DETENGIONED' .5 TATE thefabove described Operationr1 Condition. l i', QUESTION 8.18 ( 1.'00 ) -Uni t 2 has been r ecently chutdown and placed in COLD SHUTDOWN - l. Operational Candition 4. The shutdown /ccoldown was necessitated.by a requirement t'o drain and visua11y inspect the Supprension Pool. conditi ons/ requirements have been establi shed: The following' plant C5. system.is allgned to.the CGT Reactor. Mode Switch in lockr_ in the Shutdown Position No maintenarice affecting the reactor vessel i s - i n: progress-Thdre'i.s one outstanding deficiency: s h. D/G 2A Turbocharger is undergoing repairs (D/G INOP) i.. !ND'TE : APPLICABL.E TS's ARE ENCLOSED FOR REFERENC,E n -Which,one of the -following most accurately deccribes the allowances / limitations imposed by the T ot.i n i c a l Sp ec i f i c a t i on a'> n. Suppression Pool draining may commence, since all TS LEO requirements are met. l b. Suppression Pool draining may commente as soon as the Sh i -f t Supervisar ensureu that NO POGITIVE REACTIVITY changes will occur in this condition. c. Supprennion Pool draining rn a y commence ne soon es the shirt Gupervisor ensures that NO POSITIVE REACTIVITY changen will occur AND that or,e LPCI subsystem .n OPERADLE in thls condition. d. Supprescion Pool draining may commence ON'.Y AF TER the D/U 2A 4 Turbocharger is repcired and th; D/S is decl sr ed OPERABLE. (***** END OF CATEGDRY 08

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_u_wmuumm u

i D o (. \\. t l i i s1 t ^' M. s,)

====. !g I 3 w-s, 4 1 I 1 e j ,a I i I I J i. 's 's e I i 4 g I !.' i W \\ s' o 1; g i1 1 u e I N i 2 W i e e w e V M h h U 1 I d r, EA 2 l e e a E R E 1 i i i l . c3 t s r = ~ ) Jh fa a a m.W t t e e

m, . ~ _ - _ _ _.,, _. -, ? f' r 4 A - 1 N,..,. b Nl} ; I +J!.

p

" t h eldEQB1,,.QE;N[LQJOB,,C.Q[gB_ % QNI,,,gEggellgNdEbylph_OND f .PAGEl '21-IBEQd99XNOMIQg e ,s .ANSWEFS.+ HATCH <1&2' -87 /04 /20 -KEETON,. ' J. S '3. 3' ANSWER' SJ01 ( 1,' 00 ) o'l !Subtritical Mul;t i p l i r.at i'an f 0. 5 ) uses source neutrarm such.that the number of neutrons.ilast in oath generatian i n equal. to the number of. neutrons 'produted(f rom ' the cur ce (i. e 7 cource' critical) (0.5). JREFERENCE" .EIH: Reactor. Theor y3 Chapter 3, LO'#1(2,-1.~6 . 292OO3K106 ...(KA'G) - l f/:iNSWER 5.,02 (2.00) La.. ' Delta K/K

Keff-1/Keff-;' O.99-1/O.99 e

'j 0.0101 Delta K/K must be incerted- ' ( 0. 5 ) (Delta K N =1(AlphaITM)' ( De l. t d T ) - ( T iihe ) 0.0101 DeltaJK/K *, @lX10E 4 Delta.K/K. degrees F)(-100 degrees T) (Time.hr ); Time (hr.)==..( = 0.0101. Delta K/K )/ (-1X10E-4 Delt a K/U. 'Degreen F) (4 00 Degrees F). = ' 1. 01. - 5 r'- (O.S) lb. l ') S hourc bfter sc"r nm.Xe 'i s increasing co time would bellonger.. ( 0. 5).

2) 20 hours after scram Xe>1s-decreasing so time would be shorter.

( 0. 5 ) - E' Longer'than in a., but-shorter than in b.'1) i s - ac c.ep t abl e, because the examinee may assume that a., Was Xe free.:J .REFERENCt Elli: ' Reactor Theory, Chapter 4, LO #2.4; Chapter 6, LD tti.5 l 292006K'107 292OOOK105 ...(KA"G) i' .j i I a E J,' - 4 I1 > + - r .-I.' b

( i .t.', 33 g,y q 9

-y 3-q l

P AB'E ' 22-1

Q,.gf THEORE OF ~ NLjCLE AR ' POWER PL ANT ' OPERGHOth_EL111 DEjd,G@

. TtjEf3MODYNAM],Cg ] . ANSWERS.--HATCHL1&2 .i m -07 / 04/ 20-KEETON,. ' O. .I '] 1 .f ANSWER' c5i03 $t1.S0) 1 ) ) .? d. NPSHrin the: dif f erence between : total' pressure at the eye of the pump j and ; satur ati or). pressur e f ort the li quid. (0.5) CMathematical i -definition is-acceptable for full. credit.1 j b.- The,NPSHJwould' increase (0.U) because~thel temperature of'the q l1 feedwater would decreace, thus' increasing the subcooling ( density, weight,: pressure, etc.) at the eye of,the reci r cul ati on puinp. (0.5) lREFEREr.lCE Flow, Chapter 6',LLO #10.9, 10.10' 'EIH: Heat.TrsnsFer'and Eluid L 293004 K,1 12

L'9 3 O O 6 K 1 1 0 -

....(KA'5) I A. 1 =, 1 ANSWER-5.04 (1.00) ) 1 SDM' mci-Ke f f:' ( or 1-Kef f /Ke f f ) (0. 5fD E TSDM:dLO 41%/100%

O.0041 E

!Keff'x61 10.OO^1'=;O.995c7 (0.50)

REFERENCE" I

. E1H2 ' Reactor' Theory, Chapter 1,.LO #3' i 292002K113. ...; (KA" B ) I ANSWER 5.05 ( 1. 00 ) - i designed to keep the discharge 11oe or the core spray. The Jockey' Pumps are -full lto prevent waterhammer. Waterhammer could cause severe system damage and ' reduce. t he ef f ectiveness of the care spray system. C Any response'

implying luystem damage due to WATERHAMMER 2.s acceptable.1 (1.0).

c i !PEFERENCE l .EIH: - Heat Tr anuf er and Fluid F1ON, Chapter 6 LD #8 E EIHr 3R ~201,. LP O.1, L.O #6 209001K402 293OO6K105 ...(KA'B) f-l )- (. o t Y r. 51, i , q.....i.....:........

.c m-f h.

.h_T!j[ORY OF 'NOGLfiOS_[Ol E8,_PLONI_OPEBOTJg[s.,,E6[.JJDL, SUD -PAGE .23 j . pjQ3f10 D'v'N AM I CC

ANSWERS HATCH'1&2 iD7/04/20-KEETON,;J.

j

A'NSWER-5,,06 (LI5O) v

~ ~ Power Coef-f i ci ent. of Reacti vi ty is the change in reactivity for a 1 */. change in t.eactor. power. C.Wil'1 also accept the-GUM of reacti'vity .'i n ner t i on f r om MODERATOR, DOPPLER, and-VOID coeff1cientu at power.3 (O.5) ~. Dur,ing reactor startup, Lhe moderator temperature coefficient' a i s domi nant. (0.5) b. At power 3 the void coefficient is dominant. (0.5) REFERENCE EIH: R attor Theory, Chapter.44 LO #1.1 and 1.3 292004K114 (KA'G) 1 . ANSWER 9.07 (2.00) n. True b. False c. ~True .d. False REFERENCE E. I H : Heat Transfer and Fluid Flow, Chapter 9, LD #8 .) I 293009K136 (KA'51 i 'l l.: t l - ANSWEP 5.00 (1.00) l -(Insertion or withdraual of adjacent central r odr,) 'hangeb the relative i niorth of'the control rada, changes zone of control, changen number of neutronn available from adjacent cello, ett. (Any annwero showing that the candidate can er. plain the ter m will be given full credit.). ( 1. 0) l l; REFERENCE j Elli: -Reactor Theory, Chapter 5, L,0 #2 292003K104 ..., ( K A B ) l 1: l 1I-L l' i l I

...m, m .s y.- i ^5. TUEORY OF NyCLEAR POWER' PLANT DPERATION-FLU DS AND PAGE ' 2' 4 l [U($55E5958EICs~~~~~ ~~~ ~ ~~~~~~ ~ ~ ~ ~ ~~ -) ANSWERS '- HATCF 1&2

07/04/20-KEETON, J.

1 .j -ANSWER. S.09 (1.50, j ( .'95 degrees F.( + or 115 degrees F) j 2 a, c th -Superheated: .c. 450 psi a. (' + or. -50 poi a) (0.5 pts each) .j REFERENCE EIH:' ' Heat Tralafer ahd Fluid Flow, Chapter 3, LO #1,2 1.4 e 3 293OO3K123 ...(KA'S) ) i i l f ANSWER 5.10 (?. 00). l i } 1. C. I 2. a. 3. ba

4..

.C. (O.5~ pts each). i" i REFERENCE Elit: ReactorJ Theor y, Ch ap t car 4 LO 41.5 16, 5.5 l 3 3 292OO4K114 ...(KA#C) AblGNER. 5.11-(1.00) at..Tr ue (0.5). t]. If baron were used it would r emain an

t. h e fuel for o loriger period 1

of tirne bec ause of the smaller cr os s --sec t i on adding negat.tve reactivity (0,5). f i REFERENCE .EIH: Reactor 'T h e o r y, Ch ap t er 6, LD #4.4 292OO7K101 ...(KA'5) i i

y m I. p ;,, (. 4.'- 1 t x t..., + 4G1.. s ~ ~ ,ic s. 1, .,l', t ..i 691dl[jgQBT DF NUCLEAR,,,CQ(![B_E66MILOBES91,10& _EljlGS _ASQ PAGE 25' 1 JIUEBU90XN00lGSS -*. @S(4 ERD' :- " HATCH: 1&2 487/04/20-KEETON,..'J. i w. ,3, L'

c.-

ANSWER:. '5.12 ( 2. 50 ). l;. W

b.

-p . c '. -

1 -

"d. 4J l e. < 7, } '(Q.l5 ; pto each ): o ! ~, : w '. JREFERENCE-Elth Heat-Transfer and: Fluid. Flow 3.' Chapters 7, Lo #4.2, 3.1,.4.6, 5.10,. -and 542 -29300?K105s 29300?K106' --293009K111' 293009K115' - 2$3009K118 ..,. ( K A ',5 ) ' 4 ANSWER 5.13 (1 50)- 'l a. The~ amount of time required for reactor power to increace by j y

a 'f actor df e,

-(1.0) b. Shorter. -( 0. 5 ) 1 l REFERENCE j - E I H z. . Reactor Theory,-Chapter:3,'LO #3.'1,-5.6. 293OO9K105 ?.93009K106' . '....(KA" 5) 4 ANSWER 5.14 (1.00) ~Shal1oW '( O. 5 )' ARE (0.5) REFERENCE EIHF Reactor Theor y, Chapter S, LO #3.7 and 3.5 .-29200SV.110' ... '( K4 " 5 ) i A 4 t i t- .I

w.,...,. .c l s V t

y ' ~$ 1+j i
,q -4 : y, -1 r .<, d l.t@E'aprY OF g ^,.. NbCLE AR ' Puk,EB;CLQNI_ GEE (BOIlgu3._ELylpguGUD - PAGE1 27 l J IUtIBbogyusdigg j i... 1 [ LANSWERS i HATCH1&2' -07/04/204tEETON, J. ' i .l d . j. '_ '. 1 iANSWER 5.'1:7 (2.50) l L Prensure decrease.'io irom the reduced head.1osses ascociated.
G
. wi th: the *iteam, flow.(flow through the'SRV requtres lens driving-if fforcel. - ( 0. 5) [( 1 M Indicated total steam flow is. reduced since less. steam is E "neen"' by? the f l ow rest rictors. The SRV is upstream of the f low -sensors, - OR - EHC reduces flow in'. response to pressur.e decrease. 'Ltn s-D ew is "seen"..by'the flow restrictorni (0.5) 1 I c.
Turbine steam flow in. reduced by the EHC nystem proportionate' j
to the..SRV release (interacti ve, with. presuure control). - ( 0,5 ). 'f 1 . d ;.. :. Level increase.ts experienced in..the annulus as the. pressure reduction causes void formationn'in the core. (0,5) ) e. (Level reduction i s. con trol'l ed ' by t.he ' FWCS). Lavel'is-l stabi'li' zed at-a point where the level' error matchen-the~ steam. jflow/ feed' flow mismatch signal. ( 0. 5) ' r REFERENCE- .) EIH: 'GPNT, Vol.VII, Chapter 10.4 23900A105 '239002K101 '239002K104 ...(KA'S)- + .i f i 'f I h h I l 1 l l .u I t
s W, 1 4 t;, ..y. v :p j.. g',' i, I l i j7 4 ,2flj$tMJIjy(sIGL1@ihhMIdth1GQNISdbg8Mdi1N@lBydGUI6110M-PAGE 20L h L j J / '... ~87/04/20-KECTON, J.' 1 t ANSWERS HATCH.,102. j e t V. q i s / ANSWER. 6w Ol' (1.50).
i..
['. "a,'Non-regenerative;heab exchanger; outlet temperatureLmuut be close.ly' ] ~ monitored; (O;5) ~ , ti.:-.- Decause, water i s :bei ng1 dumped to 'the candenser and no cooli ng. water. i s riawincathrodgh the regenerative heat exchangrar ( 0., 5 ). 'R W C U w i l.1 ' _i col ate if non-regenerative. heat' exchanger outlet reaches,140: degrees y g' ' F C ~ ( 0.' 5 ). 'E Other technically correct. responses are.also acceptable.'5 y 1 REFERENCE. j ! EIHii - SR-201~, ; LP ' 3.1', LO.' tt B. .,(KA'S) { j 1293OO9K105 293OO9K166 . 293OO9K111' i
I
'ANGidER 6.02 '( 2. 00 ) H a.: " Ff a1 s e - s t- . b',, .True - i c. -' False l d.
Fal ne j
!( 10.5 pts each) I i , REFERENCE.. .E IH: j SR-201l3 LP'4.1 {293OO9K10$; .293009K106 ..e(KA"S) j [ nNswEn
5. o 3 c1.oo)
.i .(a) 17. i. l(b) 14' l, (0;5-'pte each)' .REFE,RENCE i Enfi DR-201, LP 1 2. 's., L.O M9 L- .~21500SK104 .,,.(KW Si } i e
I PLANT SYSTEl+ tsEDIGN uC O NT R OL d N D _] rj g T R lfj E tj Ti,3I I Qtj FAGE 29 DN5WERS - flATCH iL2 -07/04/20 {EETON J. 3 AiCWER 6.04 (2.00) Trn? purpose af '. h o LLG 1s to ini ti gat e the postul a ted higi> fraquency 1aado on containment aiid thrust loadc on the SRV.dischargt linu that may occur during subsequent C:RV cpenings (1.O). Ar med by higli r ea r_ t or pr assure - -l [i 1054 psig] (0.5) and any ORV open E: 85 psig on tail pipe 3 (O 5) l Euetpoints are not necemary for full credit.J REFERENCE EIll: BR-201, LP 14.2, LO 1 and Ob. 293OO9K10S 293OO9K106 (kA"C) ANSWER 6.00 (.30) False. (0,5) REFERENCE ElH: GR-201,.LP 1 1.= 1, LO #1 2110000004 (KA'S) ANSWER 6.06 (2.50) 1. Reactor atram '2. Or4 1 i s ol a t.1 on Main con tr ol roam vrntilation switchec to pressurintstion made '4. Mechanical vacuum pump trips and isolates 5. 01and f: e a l enhauster trips and t :.: 01 at e E ( O.5 pts each) REFERENCE ElH: OR 201, LP 14.1, LD tt2 293OO9K105 793OO7F106 N3OO9K13i ,(KA"S) ANSVER 6.07 (1.00) ' aron gets 2nto the r eac t or qu i c i:e r k Minimum rate limit anuures that th; u r-Ibn.. le cool down rate (0.5). M a:: i mt i.m r ito limit assur e, cu f f i c i r:nt thit M.i h g to prCVefit tnPVOn C ' 1 C t'n t r a t '! O n L frUm ci r cul at i ng throt:gh the cort a-cemsing c yc m p om., cnzn m <cnemung). ma REFERENCE ~ElH: UR-201 L. P 11.1, LO 14 4 211000A107 21 10 tXW20^ '11000MO .. W Y S)
di-Q h, J,.. 4., 1 0 s / ,~ .u r. s 4 g$l_ (, hywf b ik[ '",;. .2 4 Q;fRf:.- ~, %y 9. g.,' [j y
l -
1 ;
T.,.., n c. M .MQ:: ;;), a 1 ~ 3 9 4 V' ..... 1.J .. l. _ _..t PAGE.S030 W 9] m a yT SY9TEMS/DG. SIGN' . PL t CONTROU.~' AND L INSTRUMENTAT..1DN. : n t L +O.~g:? ANSWERS
HATCHf1&2
,Q.' . \\. n' v 9. -07/04'/ 20 iKEETON,: c J. 1 ,.., ~ -. O g pH M ' g.} M' s t 4 ,r ~- r ; ,1 'C N. > [ ..ir 73kOOE CA'NSWERD, !6.003 gg J '.. wS o - n Jfaj: cT!stserdampernpreventM LOCA; press,ure. spi ke f rcim causino damage, to" gy Eth.e7fil tersi duegiofhi gh fdp' ;and possi bl e > i ns tantaneouu-rel ease - of ' y_ ' radioactive 1 par.ticl es out;o f f the estack '(1 LO). (The dampers are spring. N' j cadsd / open;f dnd) L cl oseJ ~cn' hi gh. 41ow-(O.Sh g "g-q. pWo of the. charcoal.is:t~o adsorb radioactive'iadine:(0.5)i. N#'
The?iodi'neiadsorpt! ion? efficiency of1the charcoaljfilter bed wi11'be
' T,, sreducedibecaune.of the ad. sorption cf-water'in the charcoal it the $ Qr , ; heater s i s; l ost.. (1.0), -? REFERENCE' 4 Q NGPC NuciearcTrainincy Manual', ; Chapter 3.3:andLE1H: SR :201, LP 30.1 . 29,Cl001000T. . 290001K104.' .,,. - ( K A ' S ) 9 o m, y,- e 56.69. '( h., 50 I MNSWERL V j ?Fi1~se'. (0.50) 1 .g 1 < ryEFERENCE, t, '(~ E I) h L G R - 2 0 1,) L P 3 4.."1,^ L O 't!1 4 l:203000K4Cr7 , 203000K601" -(KV O' -i W. i . n.,.. 1 1 MNSWE..y..R L6.10.. C(2. 00 ): p q
gj Unit f 2Tirerts the fdrywell f or.1 fire protection of the recircul ati on
. s
pump" areas.in-.'lleu of installing-a uprinkler nystem.
(D. 5)' ~ E. 1,'
Line ciould if reeze and stop the fl.aw o f N2.
(Can't i n e r t' ~ cont ai nmsnt 2 l, Piping coulr.] get no cold it could' brittle fracture. to Tech Spec requirement) '2.'. H3. Containment' may!get cold enaugh to cause cracking. (Loss of ' f' Primary' Containment) '. 4. ' Li qui d ni troGen 'coul d ' enter containment and damage equ2 pment. g responsec are equally acceptable.] j t Otiher.t:ettinically carrect - x-L(;any"3:3 0.5 pts each) y q 4 c.. t R E. F E R E..N C. E t J ^E'I4HatchyLesson Plan, Vol. 5 Chapter 3.1, page 3.1-14 and IE Dulletin 3 je4h01 S223001K3b5 223OO1R600- 'KA"S> i 9 1 i l ). h'2 <.. ) i l b
,,.e y
Y a f,.. [' i < M ?..;;r
p, i
2 a i 4!
t .C l fA P L..A. _N T_.G. _Y. S._T E M D..._D_ E. C....I.. G, N_. A C O N'1 R O L.2. _A_ _N D I N_ S _T R U.M E N.-.T.. _f;T,I._O N._. PAGE 31 ANSWERS - lifiTCH 1h2 -87 / 04 / 20-f EETON, J. 1 l 1 1 ANSWER 6,11 (1.50) Yes. (D.5) Operation of mechanical vacuum pump above 5% i s n o t1 illowed. Any radioacti vity callected_in the main condancer-ia being released dir ett 1 y to the environment (O 5) and sufficient hydragen ru a y be call ected 'in-the condenser to cause an enplosion Wu:n heated by the vacuum purnp. (O. 5) REFERENCE EIH: BR-201, L P "' S,, 1 2710000001 271000K111 271000P404 (KA'O) ' ANSWER 6.12 (2.00) a. Half a Group inolation-(0.5) b. Half-Group II and V isolation. (0.25) Helf the valves (i nboard or outboard) close (0.05) c. One SOGT startu ( 0. 25 ) ' Loose R/D ventilation (uupply end rmhaust fanc trip and valves cl ose ) (0.20) .d. Half scram (no rod motion) (0.5) l.- 6EFERENCE l EIH: BR-201, L.P 44.3 LO M7 3 216000KL19 216000KT10 (1A'B) 1 1 ANOWER 6.17 (1.30) i a. .bn C b Eh d t b b[Stob s'i n d cCndO'n$bt( UbCIahd t Ml'! Ov A t. ( !), b. Condensate system is profcered c oi...;r c o (0.S) c. m amm the m u en se d_m_m u ~ e m mer 1m and ccn m ns 1CLS diOOOlN '7 d 0:' y g PM (0.5) f f Il gha purity W -it a r le
!i nisol s'ed s o.l i d a,
y etc, aiu,o acceptable ! EEFERENCE EIH: SR "01, LF' 1.1, LO itu 1 j 201001K101 201001Kli.C ... ( U A ' ED t l l f p., 8 J I c., (l.O) l
w, wa,.. M. M OUl_@l@lfidE._,GEEl@Us.._COdit h _6SD ltdgIBydddl8110M PAGE J.2 ANSWEF<S - HATCH'1M -87/04/20-KEETON J. 3 fiEFCRENCE LO #1 l ~EIH: GR-201, LP ?.1, 204000K104 204000K601 .,,, ( K A ' 3 ) ANSWET: .6.15' (2. 50 ). a i l l
1.
Channel f.m ': e n e r in center of r.oll -l 1. ID lug pointo to center of cell ~ 3. Gpater but tann.adj ac.ent to contral rod i 4. Derial numbere reudable f r om center of cell l ( 5. Cell to Celi Symtoot r y 6. Location of Gd rod and plugs ( An y 55) O. 4. p t a,' e a c h ) q REFERENCE EIH: GR-201, Lf' 1.5 LO $111 1 3 2340000001 ,,.. ( K(i ' G ) ./ \\
l
} . ANSWEff - 6.16 (1.00) l .a. .l REFERENCE I 1 Elli: EPNT, Vol. VI, Chapter 5.5-2; Yo l '. VII, Ch apt er 9.4-17 20; L-+ RQ-7 05 .) 3 i 2450CK) GOO 7 "24 5 0 0 01'::4 0 b 245000K409 ... ( }c: A ' 5 ) I 1 1 1 1 I i 1
p 'f ,, :o.'...'
7.. P_RO..CE D,,...UR.E.~9._" _NO_RM A.L.al.. A,.BN__O_.RM_ AL._E_.M_E{tGENCY A ND '
PAGE 33 ~ _ .2 J 6021LLO9.lCOL EOb!1BOL AIGWERS -- HATCH 1 &2 - -87/04/20-KEETON, J. 1 l i' l.! I /4NSWER .~7. O 1 (1.50) a.: The procedure c atiti ons egeinst prolonged operation below. 2OOO RPM i Ewill accept 2100. RPM? (0.3). l b, To prevent Lurbine exhaunt. check valve chatter, (Oc5), and to ensure adequate oil prosaure for turbine governor i . operation and bearing lubrication,Enunillary.all pump'does not start i r. until turbine speed cecrease,s below 1500 RPM],. ( 0. 5,) l REFfIRENCE .G P C.: ' 3 4 5 0 - E 4 1-- 0 0 1 - 2 9, Rev. 2.. G et t. i oi ) 7. ",,, 1 EIH: SR-201,- LP 5.1, LO #21 206000G010 206000KSO1 ...(KA"S) i i k ANSWER 7.02 '(;;. 00 ) l '. ADS connut..' initiate automat i c al l y 2. RWL < -101 inches and not increasing. l 3. Core Spray or RHR or Con d ernrat e. s yst e m is running and capable of I l'nj ec ti lig. 4. Reactor' pressure i t. 330 psig. (4 0 Or5 pts.each) REFERENCE .GPC: 3490-B21-001-25,.B 1, Bection 7.2.1 EIH: .GR-201, LP ~50.1, LO O 2100000002 218000G010 ? l 8 0 0t.W 4 0 2 ,.-(KW S) l ANSWER 7' 03 (,50) l Fal w. (0.5) REFERENCE GPC: 34 S1 -P41 -901 - 25, Rev. Oect1on D.2 ( !"D T E ) 294001K101 29 4001 K 102' (KA'S) l j
e n.; e 7_.o_EBQGE00EES.__ E B00Li /waORMatm ;tigeggggLebig RAGE 34 r R@QlgLOGI C/L GO((Tij(L ANSWERG -- HATCH 162 ~87/04/20-KEETON, J. 0 1 1 3 I i i ANSWER 7.04 ~ (2.00) .pa Redute core thern,al power by 20% o.f 4nitial by decreas.ing recira F l ow (0. 5 ) to limit fuel over power (0.5). by. b. Do.not,i nnert challow rodt; until core flow is reduced 10 10E6. ( 0, 5,5 If necer:aary to insert shallaw rods, do ao continuously. (0.,5) PEPEFiENCE i GPC: 34AD-OPS-04S MS, Rev. 2, lection 3.0 4.0 (Caution), and 4.1 ) 3 EIHe SR-201, LP 15,1, LO tl10 7590910001 2590010010 259001012 ...(KA'G) .ANGWER 7.03 (2.00) 1. " /9 L C" t r an sit i t t c>r s une the >ame reference leg (would regate 2 of j 5 tripo) 2. Would not get' Lurbine tra n on high level if "A" Het e selected and ASC were failed law. 3 I -f "A" i u s erl et t ed and fai1ed-1oW, a falue nignal would cauce 1evel. Increare and level would c.an t i nLe to increase until terminated by operator. 4. With'"B" nelected, failure at "A" will still allow 2 al 3 tripe on high l e ve:1. 5. W2th "D' teletted -f a i 1 ur e of "D" sti11 al1oWo ' of 7 3 trips f roni " n t:c o-( bfIy 4 h Oa b [) { r f.c a c h ) REFERCNCE GPC: .s 4 G O - D P G - O O 1 - C r, Stop D.1.d. -4 ECH: DR-201, LP '::. 2, LO # :: 2B90020010 259007t414 ,,.. ( K A ' O ) l ANEWER 7.06 (1.50) Deluted. R E F ERE.N CE De l e t. ed. l .' 0 0': % l': > ... : K I4 ' E > 26tnXJOA J 02 20W'On MO 1 _ J.L Y)' i,10? l l 1 l
~ 4 .,,j. n. 24._ _[jBQgEDUBED e NQBMOL,,,,ADUDBM[}{u._.EMEBggfjgy OND PAGE. 35 4 !.GDJ.9690190Ll9dIB06 LANGWERS - flATCH 1&2 -07/04/20-KEETON, J. f I, i 1 ' ANSWER 7.07 ( 2. 50)-~ J i u. Path 5 b., Path:4 j
c ',
Fath 2 1 .d. Path'1 Le. Path ' l (0.5 ptu'each) j REFERENCE GPCs 31ED-EOP-OO1-23, LP # L T - I ll--20101 -00, LO tF7 '29S006G012 ,,.-(KA'S) i l. ANSWER 7,,08 -( .50) True ( 0.' 5 ) ' REF CRENCE l2 'GPC: J1EO-EDP--001-25 l.- Elfi LP # LT-l H-20101--OO - EO #11 i 3 27S006G0051 ...(KA"G) i 1 ~ ANSWER-7.09-(2.00) I M. IIuO b, False c.- ' False-i d. True .( O.5 ptn each) REFERENCE / GPCs J4AD-OPS-0 %-25 and OO-~0FS-n4 -1106 295016GO10 29501dr2M' 295016KJ.01 (KA'D) 1 I
n-n b 1 - 9, ; e ' ZA, C89CE9dBEE_;._.UOBbGht_GQUQBt!9t,x_[dEBfjgdCLOUD PAGE 36 R AD I D!,.,0G I C At u.COUIRO!g . ANSWERS --' HATCH 1&2' -07/04/20-KEETON,JJ. = ANSWER. ~7.10 (2.00) l '. Loos of four rad diop1ay- '2.- Rod drift-indication on all roda J. Select rod black-4. .RWM rod black ( 0.5' pts,each) REFERENCE ls GPC: 34 AB-OPS--024-2, Dection A EIH; GR-201,.LP S4.2, LO #2 2010020010 201002K103 ...(KA'5) ANSWER '7.11 - ( 1. 00) i l C. ( 1. O ). REFERENCE j =GPC: -3.1EO-EUP-OO1 25 E1H: LT-1H-20101-OO, LO 45 275030G012. ...(KA'S) AN5WER 7.12 ( 1,. SO ) a. Tr i p the field breaker ( O.. b ) b. Failure of manual voltage regulator (0.5) or lose of 125 Vdc Cather -faults that could. result i r, loss of 125 Vdc to the field (d13 be acceptab]e.] (0.5) ' REFERENCE GPC: 34CO-OPS-00.1 -25 ETH: Volume 6, Section 7,1 EIH: SR-201, LP 17 1, LD #12 26200100ff7 262001G014 262OO1N102 (KA"S) 1 I ANSWER 7.17 (1.00) RWL 53" (0.5) cin d core -f l ow '700 g p rn (0.5) s REFERENCE GPC: ._s1 G O - O P S - 0 1 5 - 2 0,., Sect 2on 7.J 205000G001 2050006010 ,,.. ( K A " S ) l [
t i
6 s e -
~7 P.R_ O.C...E. D...U.R.E_9_.' N O R.. M_A.L._ sA_.B NOR M, AL_ x...E.._ME R_ G., ENC Y _- AN. D PAGE 37 - -~ BODIOL@jlG86.,,GOUIBOL ANSWErm - HATCH 162 "87/04/20-KEETON, J. 1 a 1 ' ANSWER 7.14-(2.50) 1. Reter to Tech Specs
e...
Establish 4 hr. LCO 3. 'llave' PEG attempt to reatore containment 4. Natify HNP management 5. Refer to Emc'rgency C14~.sification 6. Natify NRC l l L Any reasonabl e pr ocedures1 at ti on wi11-be accepted.] i (Any 5 iii O.5' pts.cach1 L REFERtNCE GPC::34AB-OPS-010-25 EIH: DR-201, LP'13.2 2900010001 290001G003 .290001G011 290001G015 ...(KA*S) ANSWEf t 7.,15 <1.00) { a.
3. 3 (0.4) b.
4' (0.3) c. 5 (0.3) REFERENCE 'GPC: 34S0-149'001-2 EIH: SR-201,-LP 30.1., LO #3 223001G014 223001K404 223001K510 .,., ( K A ' S ) AN5WER 7.16 (1,50) a. Fire Pump House; d i ec t r.. c Fire Pump Contral Panel Eelther or both answers aufficient for full credit] (O'),d b. If the switch I r, not r met, the makeup water will be tiepl et ed, i.a3 al l. ~ water galna to fire syutem, dem t nar ali z ed water last-sanatary water l o s t., (11 t er ed wate-Fank l evel lost, etc. (1.0). REFERENCE GPC: 34SO-L43-OO1-2 ). EIH: SR-201, LP
1. 36 LO 4t 1,36.1.
3 206000G001 2 0 6 0 0 0 Ed.3 0 9 2 0 0 0 0 0!-: 4 0 1 (KV )
7.< PROCEDURED 'NOBljGL1_G@NORfjekt EMEBCENGLOUQ PAGE 30 BOD 106091C86 GOUIB06 j q i 'ANSWERG -ilATCH 1842 -07/04/20-kEETON, J. i 1 ANSWER
7. l'7 l
'(2,00) Operator 1 - Rej er;ted - Would exceed'10 CFR 20 limit 1250 mrem /qtr with no Form 11 on'fi1e (0. 5). Operator 2.- Rejected - Han already exceeded 3. i mi t s that require approval l above shift superviser 1evel, (O,5) Operator 3 - Rejected - Would exceed pregnancy 1imit of 500 mrem (0. 5) Operator 4 - Accepted Would not exceed quarterly limit.cf 1.25 rem whole J l body. 5(N-10) Ib 1imiting on1y when it-in dentred to enceed 1,25 rem /qtr whole bada. (0.5) j l l' l l ' REFERENCE l GPCs 60AC41PXO1-0, 10 CFR 20-2 ~ .EIH: DR-501, L.P 300.3, LO tt4 -) } '294001K10? ... WA'G) I l-i 1 ) 1 I ) i ) p 1 l l ) l t 1 l l l l 1 (
t
<c, r
l,;., 3.... I -_DM.I N_I ST. R AT I VE.#._ ROC.. E D. U..R..E_.G A C. O. ND..I.T_.I_ONS AND?L.I M I T A.T.I O. N.S P(M3E 39 ~ (iO n-- A ' ANSWERS - liATCH 1?<2 ' -07/04/20"KEETON, J. T y ANSWER' O.01 -( 2. 00) a. No, wil1. accept 'yes wi th ; reasonabl e. assumpti on stated concerning applicabl1ity-uf' Technical Specifications to both Units. (0. 5 )' b. ? hourn. (0,5) c;= General-Manager-Pl ant Hatch or his Deputy (0 '5) d. No, will accept yes with reasonabl e annumption stated concerning applicability of Techru cal Specificatiana to both~ Units. (0.5) -REFERENCE' CIH: U-2 Technical Specification, Section 6.2 EIH: CR-301,'LP 500.3. LO bl 234000 GOO 1 ...(KA"S) ANSWER 8.02 (1.00) Fal se (0.5). An openwu r gap i s r equired on any high val'tage cystem (277 volto or greater. DW fann are 600 volts.) ( 0. 5 ) [ -REFERENCE EIH: BR-301, LP 3.1, EO # 3.1.7.1 6 ,294001Klu2 294001K167 ...(KA S) ANO.WER 8.O! (2.00) a. Turn valve in closed direction (1/4 turn m a :< to coat) b. Turn valve in closed direction (1/4 turn max then return to open) c. Verify at remote (or 1ocal) parition indication d. Can+irm locking device operability (by -uttempting to n; ave val ve) ( O.5 each ) REFERENCE E1H: SR-301, LP 3.1, EO fl ?.1.3.5 294001K101 ...(KA'9) 1
l' ese, ida._5Dt!!NIGIB011RbSOGERUE%jgNQIllOUQ. AND kiUllOllON{}; PAGE 40 -AIR 1WpRG'-- HATCH 162 -07/04/20-KEETON, J. 4 . ANSWER U.04 (2.25) j.. a. Gener al t1anagar. or designee, i.e., Operation Manager, Plant M.an a g er, ' Pl ant-Suppor t Man a ger, VP of Nucluer Operations, etc. (0.5) .b. Formal cantact for Gener a l Office, NT<C,..Btate or ather organizations 2. Activate corporate retponse 3 Develop recovery and mitigation' plans l 4. Identify and coordinate supplemental recource requirement.c 5. Establish Security 6. Overall management of accident respanne 7. Protective action recommendations to State G. Declare proper emergency cl assification '7, C1ose out or reduce emergency c1 ass ( Any other roosanable responne equally. acceptable.) [ An y 7 ' 5) 0.25 pts each) REFERENCE EIH: GR-301, LP ". 2 EO 63.2.2.1 and 3.?.2.2 294001A116 .. (KA'S) ' ANSWER 8.05 (1.50) , Deleted. ' REFERENCE Deleted. 294OO1K104 ...(KA'B) 1 ANSWER 8.06 (1.UU) 1 4 The required a scd o t 2 on boundarie: are identical I. t o g s ma, be added within the boundartes if bound sr r sn are identicall. (.1. 0 ) l REFERENCE EIH: SR '01, LP 'nO.4, l.D #C.O i 29400.1KlO2 ...(KA'S) I i i 1 ANSWER O.07 (1.00) i i -Del e t ed.
-l 4 ' 8 e e i h ! Y .h..,., /} L e l AtEWERS - HATCH I? - 07 / 0 4 / 2CH.Cr 10N,,, J., = Delatud. -\\ \\ 294001K10.P ,.. W fe E ) ANOWER U.00 (1 00) t, (1 W REFERENCE Un1L 1 T cec t in i c a l Speti f i cat i orin f. 10.H, De al 3 Ill H : GH l01, LP 4,1 2340000001 JM0000005 .(G'B) ANOWER O 00 ( 1., 5 0 ) Power Trerm1 tat: Lwill a c c c:p t FK.,f R ' (0.',) 'fety 11 mat The nAfely an al y ;e s, have .a h,: w n that c,c. r a m s caused by e :cecc'i ng c G e t L.i n C} S Will st 5 tM tu D J..li iD t y i i iTi l l ' a Or0 NGL U -: C U C d L > d pFCVidCd (fir, e t r, up l i rne W.1 tIII fl 1 i Ull t ie, (l.O) ] ' > Uni l. 1 Technical S p e _ > f 1 t 3 L a o n n :, B +- 0 1.1. f [.1111: O R- ?.01, !.P 4.1, CO Wi. ) 1_1 and 4.1 1.2 2010(.'10006 .(KA"C) AN C,0E fi D 10 ( 1., S O > 1. Unit i l' a t r, addiL co.ai Prc' 1;r v o t., L2mib i n -s e !,1 n g thL r ahuLdavn t oc1 i r q) mr de ( G., 5 ; c t d L 1 ~ f.. ; 0, ,.1 ! ', E O. l t :if L n t : fi thO I13WLi I f LA h E. t 6. Il t lin i i. } h s tr Y j I Jd ., ; f U l
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T... t 4iO O I." ' ' ' i'hGn ' ! ' [:: C' C 5 i ).. L "n1ny C c) 1.l '1 i Cdu30 ( '.' ) 'J 9 is C l L P~ I d u l i.." t ~ .! E. / i/1 ' s d i f f t:1 ' U I' i l 3, l' CI'O.' /i' f'-33U O! and Ur i t i " n ta iW - ' A4 si R E F E ilh C E. Uni t 1 cnd Urii t f rx h 12 al tp c !tcaLlt,e 'A.'i
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e ee e j n. A m1 n: I m rmT I vt Pna cE nm m, _:.orTD._I. T._I..DN_ D_._, _A_ N.D.L.._I M_ I._T_ AT I.O.. N.,.S_ PACE 4? I ANSWERO IIATCH l t> T -G7/04/?O-iEETUN, J. i l ANSWER O,,11 (1,DO) 1, Inter.F of ttn> original precod;ce tu nul altered. C h a; n;..- re<1ewed by 2 mecibern Lf ope r xtaog st a fi, orie auct b t-SRO on a f f ect ed unit. C h a n (p. in documentod, rt n oWod by PRD, and appr oved by GM ot' d e b 2 t;p e e within 14 dayi af charge. ( O, [)t 5 f.> t c h ) i REFERENCE Unit. 1 and ' T -c c h n i c a l Sp e c i -f i c a t. i o o n, Bettian 6.0 GPr. 10 AC - MG re- (XO - Ol.') Elli: GFe 01,, LP 300. '., L.O O2 210CO&iOO1 ...(KA'3) ANEWER D. l '" CO) 1 i nn ! (0.5) a. 1. ,5 dtgreer f-No tir ~. 95 degrow '10 d.c g r e e s F 4 houra (0,5) ~. 110 degre F hr. ut ok t.a r rn i n e d by HP ( 0. 5 ) b True; (0.5) REFERLNCE O!i:
1 GD -OP' S--DOG -OS EIll: Bfl 101, LP I O O 4,,- L O t!C. ?
m.::O O t 6 0 0 1 (FA"9) ANOWER B. '1 D (:.50) u. U-J Bhift C up c ' s-l u or en 1 1, m >r t to f ; r t- ]. m Lhlut if h* 1.- r s C K.31 1 f 1 e d ;; f fla L < l...! - ) ' a ' 91 a 1 - "i Chili (I.O) b. . ( 0. 2' ) c (0.5) d. N G). I. i. ) REi O <t NW. Of C :- 'pitic F[ ' 001 Elli: i t'l,
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_j ~ _ - t n 162 - B 7 / 0 4 / 2 0 - F. E E 1 0 N, J., l',N 31, j E R S HATCH 1 4 l l l i i1N9WER O.14 (1.00) f a. The n t:x t uuivnillance wi11 he dur October 1 (or 92 d e,y s ). (0 tid b. T l u.' grace pertad to ?t% of the f requenr:y not to e:ceed 3.25 fCF C Of i t '3 C Lt t, v e Ur Vtfi l 1 itnc DL. tO.C) ~ REFERENCE Unit. Techni t. ;) '3 p m f i c e t t or,c GPC. 4 0 AC --RCO 001 EIH: OR-301, LP ~;O O, 4 LO n D.D 3 l 2(EOOOB CKm ..(lA'0) 1 l Auswm o.as a.om I t l c1 l i t t.' E.O C RPT t.r 2 p 1: actueted 1f 00?. power (O. $4 ) 2 on ti trbi ne trip (O.'3) or loud reject [ T C 's' -f a c t c:1 as ar e] ( O. ' I, ). l ) b. Fhl w i n T. o ins'ro ufficient llega !. i ve r e a c t. i v i t. y in added in i 1 C OIlj unC k l On W1 tl) the control r od': whi ct ; in i l l ( r i c, u r e t il ce rtia l tiydr auli c I limtLs (MCPP) are not e:cueded (1.0). l ra cneuce l L q e 5 202OO1K407 t'02OOil:4 L J (17i 'R' I l l ANSWER O.16 ( 1. 0 0 ') d. (1.0) 1 1 REFEROJCE l l [ I; 1 H : U ;. ' T c' .1 2 l T/2OnOr;r:u 3 " ' W)O F.' G M (l%'0) l l l l h'$ 5 1, ) ',. e l l 5 m o F u r l a n y 's l I acr Enr.Ncr l lhIll: U2 TB, 1_.i. f Li ..? ?. l
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I 1 N r.. _OI2!11bjl91Bfjlly[,_EB[2GEjl2UBf g1_Cor@lT IObigt _AND L IMIT AT 7 DNS r' AGE 44 l ANOWERS -- IIATCH 1.L2 -87 / 04 /20--KEET ON, J. k ANSWER 0.18 (1.00) d. (1.0) REFERENCE 1 '2 ba T' 55 )a [1. O y bi, {li^I(j I [')(g O r t.l e t>- 04--35 9 2230020005 ...(lw 0) j r i i i
l .h U ) '. 1EST CROS2) REFERENCE FAGE 1 f2UES T I ON WiLUE liEFERENCE -..... ~ O*.;. 01 1.00 KMJOOOiO/7 05,02 2.00 L:11d OOO 1070 0G.03 '1. SO KMJOOO1079 05.04 1.00 KMJOOO1000 05.05 1.00 KMJOOO1001 05.06 1.50 KMJOOOl%? 05.07 2.00 KMJOOO100f 05.OB 1.00 KMJOOO1004 05.09 1.50 KMJ0001085 05.10 /.00 i:11J OOO 1036 0 5, l'1 1.00 KMJOOO1007 -00.12 -. 50 KMJOOO1000 0 5, l '. 1., S O F.MJ0001039 00.14 1.00 KMJOOO1090 05.15 2.00 KMJOOO1091 05.16 1.00 l:.MJ OO O 1092 OS 17 2.50 KMJOOO1139 w L 06.OL
1. '".J O KMJ OOO 10W 06.O' 00 KMJ0001094
{ 06,03 1.00 KMJOOO1095 06.04
/. 00 KMJOOO1096 06.05 50 KMJOOO1097 06.06 50 I: MJ OOO 1090 06.07 1.00 KMJOOO1099
[ 06.00 00 1::N J 0 0 0 1 1 0 0 06.09 50 KMJOOO1101 06.10 2.00 R MJ OO O 1 10 06.11 1.50 KMJOOO1103 0 6. l ') ' 00 P..MJ % Q 1 10 4 06.13 1.50 L:MJOOO1105 06,14 1.00 KMJOOO1106 06.15 2.50 RMJ0001107 06.16 1.00 1::MJ OOO 1140 25.50 07.01 1.50 KMJOfM1109 I t 07.02 2.00 K M J O O O 1 :;. 0 9 O'7. v3 UU 1:.M J U001110 07.04 2. _:e O pyJ CK':01111 07.06 2.00 KMJi>OOlJ12 M' . i i s, , _. - ~ ) L') I k, k. 0 t e o 07.08 50 I-:MJ N O 1 1 i t 0 7. OE . (K4 KMJ00011!6 07.,10 ,.UD 'JMJiN O1.'17 07.11 1.00 KMJUOO1J10
I 1 1 TEcil CROSS REFERENCE PC,GE 2 QUESTIGil W41.UE REFERENCE _. ~... 07.12 1.50 RMJOOO1119 l 07.13 1.00 L.MJ O OO 1120 l 07.14
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p* ENCLOSURE 3 PLANT E.I. H ATCH, UTILITY-COMMENTS SENIOR OPERATOR LICENSE EXAMINATION l WRITTEN RESPONSE REQUESTED APRIL 20, 1987 s-1 5.06 Utility Comment: )1 While the definition of the power coefficient is objective based, the' stem of the question requires three responses per the key, the definition itself and the "a" and "b" parts. However, the question gives the appearance of a two part ("a" and "b") question; this -is confusing and the examinee may not have realized,that the definition is part of the required response. Suggested Resolution: If the grading process shows that this was a problem, consideration should be given to deleting the definition of power coefficient as a required. response. l
Reference:
L GE BWR Academic Series, Reactor Theory, Chapter 4 5.11 Utility Comment: Part b: This portion of the question not supported by objectives. Additionally, the question statement may not elicit the desired response in that the justification for a TRUE answer in part "a" could i b'e that Gadolinia has a larger absorption cross-section. Suggested Resolution: i It is recommended that the "b" portion of the question be deleted.
Reference:
GE BWR Academic Series, Reactor Theory, Chapter 6 N k . or s Page 1 of 8
F W.. PLANT E. I. HATCH LICENSE EXAMINATION ' COMMENTS 5.15 Utility' Comment: Part a: This could be answered either TRUE or FALSE depending ~ on th'a assumptions made. - Mathematically it is TRUE. Total Power = 2 x Individual Power. If two identical. pumps are operating in parallel, the sum of their EQUAL powers will be the total power. However, if the assumption is made that the question is asking-the KEY point, that for a GIVEN flow rate, it takes less power for two pumps in parallel than it does for one pump, the answer, would be FALSE. ~ Suggested Resolution: It is, recommended that part "a" be deleted. j
Reference:
i GE BWR Academic Series, Heat Transfer and Fluid Flow, Chapter 6 l 7.04 Utility Comment: l Part b: The answer key is incorrect in that the procedure states: " shallow rods should not be inserted without a PRIOR REDUCTION of - cr)re flow > 10E6 lbm/hr", not " shallow rods should not be inserteci ,j WITH a core flow > 10E6 lbm/hr". Additionally, the - response "If n-ry to... do so continuously." is a note, not' a caution. Since the question asked for cautions (plural), the examinee may ' have ~ answered with: 1. notes, or 2. notes and the only caution, or 3. the only caution listed in the procedure. Suggested Resolution: Part b: It is recommended the key be modified to require either notes or cautions, of which there are three in the 34 AB-OPS-045 procedure, or require only the one caution for full credit. The key also needs to be I corrected to correspond to the procedural caution. '\\
Reference:
s 3 4 A B-OPS-04 5-2S Page 2 of 8
i I I PLANT E. I. HATCH LICENSE EXAMINATION COMMENTS I l-7.09 Utility Comment: ) [ This question requires a level of knowle. se of the procedure bordering on memorization which is inconsistent with performance based testing and the Plant Hatch philosophy regartling procedure memorization. The l Abnormal Operating Procedures lesson plan as approved by the Managers ] of the Operations and the Training departments is attached. This lesson plan was developed based on the input of a consensus group consisting of subject matter experts, and training specialists. It was written to ensure the operators are sufficiently familiar with the abnormal procedures such that they can perform th,,em without excessive burden on their memory. Part A: Without explicitly stating the conditions in the TRUE or FALSE statement, incorrect assumptions are likely on the part of the examinee. In other words, the distractor as worded may not elicit the desired response. l Part B: Does not state the breakers that were tripped. This causes same problem as part A. Part C: This requires memorization of SUBSEQUENT actions, which is inconsistent with performance based testing and the plant's philosophy regarding procedure memorization. Part D: Same comments as part C. Suggested Resolution It is recommended that this question be deleted.
Reference:
34 AB-OPS-0555 2S, SG-OPS-04-1186 's N,NN Page 3 of 8
PLANT E. I. HATCH LICENSE EXAMINATION COMMENTS 7.14 Utility Comment
The question requires verbatim knowledge of subsequent operator
{ actions, which have been determined by the Operations and Training { departments to be an unnecessary burden on the operator's memory. l Refer to question 7.09 comments. l Suggested Resolution: i It is recommended that this question be deleted. ~
Reference:
34 A B-OPS-018-2S l 8.01 Utility Comment: The wording of the question is such that it implies the manning for each unit is that of the minimum shift manning for both units. This may lead to confusion as to the manning levels present at the beginning of the scenario. This will make it difficult for the examinee to determine the correct response. 1 Suggested Resolution: It is recommended that parts A and D be deleted. Additionally, part B j may have been affected by this problem. If during the grading this becomes apparent, part B should also be deleted.
Reference:
30AC-OPS-003-OS, U2 Tech Specs, LP 300.3 +m 'NN x Page 4 of 8
p PLANT E. I. HATCH LICENSE EXAMINATION COMMENTS 8.02 Utility Comment: j Open Air Gap is normally thought of as disconnects used on a very high voltage. The 277 voltage maximum is found in 34SO-S22-001, 500 KV switchyard and is not mentioned in _ the clearance procedure. Additionally, the reference on the key is the Emergency actions lesson plan and deals with the location of the MET towers. The 300.4 lesson plan discusses clearances and switching orders and does not refer to or cover by objectives the topic of this question. This is not the terminology used to require racking out a 600 volt breaker. As such this question may not elicit the desired response., Lesson plans 300.4, Administrative Procedures, and 3.1, Emergency Actions are attached. Suggested Resolution: It is recommended that this question be deleted.
Reference:
34SO-S22-001, 30AC-OPS-001-OS 8.03 Utility Comment: The key is incorrect. The procedure has been revised. Suggested Resolution: It is recommended the answer key be modified as follows: Part b: Turn the valve in the closed direction no more than 1/4 turn and return to full open position. Part c: The response "or local" should not be required for full credit.
References:
34GO-SUV-001-0S (attached) s ,\\ Page 5 of 8 1
c l PLANT E. I. HATCH LICENSE EXAMINATION COMMENTS-l 8.04 Utility Comment: Part A: The question of who will relieve-the OSOS as ED could be answered in other ways. The designated-alternate is the typical relief during ALL drills. _ The plant's philosophy is to relieve the OSOS as soon as possible to allow him to direct recovery actions in the control room (typically this is the TSC manager who is the manager of Operations). Part B: The 73EP-EIP-004-OS procedure, Duties of Emergency Director (Attached) lists additional duties. These duties are correct E responses, though they may be more specific than,the broad categories listed on the key. There.may be other reasonable duties not listed in the procedure or lesson materials that should be allowed for credit that would fall into the categories listed on the key. Additionally, I the listing of duties of the ED rather than an application of the i procedure may not be an appropriate application of performance based testing, and places an excessive burden on.the examinee's memory. Suggested Resolution: i It is recommended the key be modified as follows:. Part A: The OSOS should assume Emergency Director (E D) l responsibilities until relieved by: Primary: Plant Manager (Harvey Nix) lst Alt. Plant Support Manager (Dennis Read) 2nd Alt. Manager of Operations, (Lewis Sumner) 3rd Alt. Vice President of Nuclear Operations (Tom Beckham) j j Accept any of the specific titles as an acceptable response for i " designee". Part B: It is recommended the key be modified to accept any of the -j additional duties listed in 73EP-EIP-004-OS for credit. i d
References:
73EP-EIP-004-OS s. 'NN N Page 6 of 8 I i
E PLANT E. I. HATCH LICENSE EXAMINATION COMMENTS 8.05 . Utility Comment: The question is inconsistent with performance based testing and is not covered by objectives. To test in this manner places an unwarranted burden-on the operators memory and is not consistent with the nature of i their job duties. The objectives referenced in the answer key deal with the restrictions placed on access to high radiation areas, not the. spacif'im involved in the issuance of RWPs. To correctly answer the question,' memorization of a flow chart in the procedure is required. For comments regarding procedure memorization see question 7.09 comments. y Suggested Resolution: It is recommended that this question be deleted.
Reference:
60AC-HPXO9-0 8.07 Utility Comment: The question requires memorization of several pages of a matrix of reporting ruplirements of the 40AC-REG-002-0S procedure. S comments j on procedure memorization for question 7.09. None of the choices i provided fall under Operations department responsibility for reporting. Additionally, our objectives don't support identifying the type of report required without using the procedure for reference. Procedurally, the correct responses are identified as "immediate notifications" rather than "I hour reports". Suggested Resolution: ~ It is recommended that this question be deleted. ~
Reference:
N.s 40AC-REG-002-OS s s Page 7 of 8
~ PLANT E. I. HATCH LICENSE EXAMINATION COMMENTS l 8.09 Utility.' Comment: In section 3.11.C., the OLMCPR is stated to be a function of scram time. The basis for the OLMCPR also states that compliance with the i OLMCPR will prevent violating the Tech Spec Safety Limit for MCPR. This demonstrates that MCPR would be an acceptable response. Suggested Resolution: It is recommended that the key also accept MCPR for full credit. Also, greater specificity as to the desired response wou,1d be preferred prior i to usage on future exams. l
Reference:
Unit 1 Tech Specs, 3.11.C., and 4.11.C.2. 8.12 Utility Comment: i These requimments should not need memorization, 'as HP and procedure j will be referenced prior to this entry. The time and temperature limits are included in the lesson material for familiarization and are not identified as required by the objectives. The objective requires the use of the procedure to identify the abnormal (oxygen deficient ' atmosphere) entry requirements. As such, this test item does not meet the intent of the learning objective. Part a: Does not specify the number of responses required. / Part b: The question may not elicit the desired response since the initial conditions were not specified. The one hour rest requirement only applies if the temperature is greater than 95 degrees. Suggested Resolution: It is recommended that the question be deleted. ) l ' N, Reference-s \\ 31GO-OPS-005-0S j i e.** Page 8 of 8 1 e e}}

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