IR 05000322/1987021

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Exam Rept 50-322/87-21OL on 871201-03.Exam Results:Four Senior Reactor Operators Passed Both Written Exams & Operating Tests
ML20196E378
Person / Time
Site: Shoreham File:Long Island Lighting Company icon.png
Issue date: 01/22/1988
From: Florek D, Lange D
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20196E355 List:
References
50-322-87-21OL, NUDOCS 8803010061
Download: ML20196E378 (65)
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V. S. NUCLEAR REGULATORY COMMISSION REGION'I OPERATOR LICENSING EXAMINATION REPORT EXAMINATION REPORT.NO. 87-21 (0L)

FACILITY DOCKET NO. 50-322 FACILITY LICENSE NO. NPF-36 LICENSEE: Long Island Lighting Company P. O. Box 618 Wading River, New York 11792 FACILITY: Shoreham Huclear Power Station EXAMINATION DATES: December 1-3 1 I(987

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ACTING CHIEF EXAMINER: ,

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!N Donald J~ Florek, Senior erations Engineer / Opte APPROVED BY: -o 4W J -/8'-77 David J. Lange, Ehief BWR% ection, Date Operations Branch, Division of Reactor Safety SUMMARY: Written examinations and operating tests were administered to four (4) senior reactor operators (SRO). All SRO's passed these examinations.

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' DETAILS-

' TYPE -0F EXAMINATIONS: Replacement EXAMINATION RESULTS:

e l SR0 l

I ' Pass / Fail l l 1 l' . I I

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I I I I -l l l0verall l 4/0 l l l I 1. ACTING CHIEF EXAMINER AT SITE: Donald J. Florek, Senior Operations Engineer 2. 0THER-EXAMINERS: -D..Lange, Chief BWR Section, DRS M. Bishop consultant USNRC T.- Fish, Operations Engineer 3. Due to the limited number of candidates no generic strengths or deficien-cies were noted during the operating test.

'4. The following-is a summary of generic strengths or deficiencies noted from

.the grading of the SR0 written examinations. This information -is being provided to aid the licensee in upgrading license and requalification

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training programs. No licensee response is required.

STRENGTHS a. Knowledge to xenon effects on rod worth and reactivity following a scram.

b. Knowledge of the recirculation system pump seals, response following a LOCA and the E0C pump trip breakers.

c. Knowleage of LPCI valve motive power supplies.

d. Knowledge of the effects of loss of instrument air on the feedwater control system.

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I e. Knowledge of the cautions on HPCI for low flow and low speed.

f. Knowledge of the Watch Engineer duties as an Emergency Director.

g. Knowledge of the Report of Abnormal Condition (RAC).

-DEFICIENCIES a. Rtlationship of thermal limits to failure modes.

b. Flow path of the offgas system 5. Personnel Present at Exit Interview:

NRC Personnel D. Lange, BWR Section Chief D. Florek, Senior Operations Engineer T. Fish, Operations Engineer F. Crescenzo, Resident Inspector M. Bishop, Consultant, USNRC Facility Personnel W. Steiger, Plant Manager J. Scalice, Assistant Plant Manager L. Calone, Manager, Operations Training Division C. Thayer, Manager Ops / simulator Training Dept.

H. Carter, Training Instructor B. Nazzaro, SRO Lead Instructor D. Smith, Compliance Engineer 6. Summary of NRC comments made at exit interview:

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The chief examiner thanked the training staff for their preliminary work

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to ensure that the examinations were conducted in accordance with the Examiner Standards.

The chief examiner also made the following comments: The location for the written examination was adequate and noted that the written examination review only generated minor changes to the answer key. Formal written comments on the exam should be submitted within five days after the exit.

No generic strengths and weaknesses were noted on the operating examination. The examiner did comment that the facility appeared very clean as a result of observations during the operating test.

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I Certain procedures submitted to the NRC only' contained every other page and this should be corrected in the future submittals.

The chief examiner informed the facility that it is a goal to provide the exam results 30 days'following receipt of the exam comments.

7. Summary of facility comments and commitments made at exit interview:

The facility staff expressed their appreciation for the cooperation from the NRC prior to examination administration and requested the results to be provided as soon as possible.

Attachments:

1. Written Examination and Answer Key (SRO)

2. Facility Comments on Written Examinations af ter Facility Review 3. NRC Response to Facility Comments

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U. E. NUCLEAR REGULATORY COMMISSION J-SENIOR REACTOR OPERATOR LICENSE EYAMINATION

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FACILITY: SHOREHAM REACTCR TYPE: BWR-4GE DATE ADMINISTERED: 97/12/1 EXAMINER: BISHOP, M.

CANDIDAlE: _____________________,

INSTRUCTIONS TO CAND!DATE:

_-_-_-----__--___________-

Use separate paper for the answers. Write answers on one side cri .

Staple cuestien sheet on tcp O' the a95Wer sheets. Points 4Cr ea "

cuest2on are indica *ec t- paren-Moses deter the cuestion. T h'e pass:~.

grade recuires at least 7 'i" . ** each category and a 4inal grade c4 a-leas * E O */. . E> a+i r et t e capere w: !3 ba Ricked up six 46) hours e+tr-t he ev a-: n a t i c, c:ar ts.

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~ A T E C- C R '-

. D' C A h. _. ! O A T E s C A T E T_ ; i VALUE TOTAL SCO:E Va_.- CATEGORY

___. __-__. _ _ _ _ . . - - - . . _ --..-.-.- -----------____----___--_._- . .

24 9 25.00 25..fn ; 5. THEORi C' NUCLEA;I * OWE; .. -

-__-____ _----- --------- _ _. ---..

OPERATION, FLUIDS.AND THERMODYNAMICS 24 . 9 +,,

25.00 2,' t. A_ ANT SYSTEMS DESIC-N, Cole ._

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fg AND INSTRUMENTATION 25 46q, 25.G 25.447; 7. PROCEDURES - NORMAL, ABNORMe_.

---_--_- ------ _-_--__-__. --------

EMERGENCY AND RADIOLOGICAL CONTROL 2 4. t4 25.00 -2 5 . _O =

p 0. ADMINISTRATIVE PROCEDURES.

_____-_. --____ __----_____ __-_--__

CONDITIONS, AND LIMITATION:

100.Oc re

  • /. Totals

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F : na' . Grado

All work cone on th:s exa-inats:- is ev can. 1 ave nelther c ve-ner rece:ved asc.

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Cancidate't Signature

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NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS D'uring the administration of this examination the following rules appl y:

1. Cheating on the examination means an automatic denial of ycur applicaticn and could result in more severe penalties.-

2. Restroom trips are to be l i mi ted and Only one candidate at a time mo, leave. Ycu must-avoic all centacts with anyone outside the examinat: 0-room to avoid even the appearance or possibility of cheating.

3. Use black ink or dark pencil only to facilitate l egi bl e reprocuc ti c"c.

4 Print your name in t he bl ard prcvi ded on the cover sheet of the examination.

5. Fill in the date on the cover sheet of the examinaticn (if necessary ,

e. Use only tne pacer pr ovi ced 4cr answers.

7 Print your na?e in the upper right-nanc ccrner c4 the first page od each sectic, c4 the erswer sheet.

9. Consecutivaly nummer each artwe- sneet, write "End c4 Categc y __ ac apprCDri3te. sta e a c c a t eOc' Y c' a new paQC. w-ite only c- Che S; c'

04 the pape , a^d writc Lat* Oage' cn t c last answse sneet.

C. Numecr each answar as tc cate;ory and number. 4er exatale. 4 c.3.

. '; . Et :2 at tecs? tnrce lirei cetwee$ ecch a swo .

.'. Sepa-ate amcwe- sneetr 4 o- 727 a"t p. ace 4 1 ishec answe- s*c M c * ,:: c UCW" en your cesi c' *a*IC.

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11. Use aOOr e'.. S ti end c"}V ! 4 thr, a-e CCm*c.l'. usef in 4ac!..ti 1;te-Stur i'.

13. T~e s ci e t value 4 :~ ecch cuest:cn :r indicated in ca ent ese- e1 -  ?--

cuestlo- a .' d ca" t r- stec as a ;ulce 4ce the cento c3 answe' -cc_:-rt.

14 Show all calculations. methccs, or assumptions used te cota:n an a r xe-to mathematical problems whether indicated in the question or et.

15. Partial credit may be given. Therefore, ANSWER ALL DARTS D: T-E QUEST 10N AND D NOT LEAVE ANV ANSWER SLANK.

I 16. If parts of the examination are not clear as to intent, ask c u e s *. t c r '

of the examiner Only.

7 You must sign the statement On the cover sheet that indicates that t?

work is your own and ycu has? not receivec or be  ;;.e- ascistance 1-complet: g t"e evactretion. This must be done a-te- t- eracinat:c-

! has ceen ecmaletec.

i 19. When you complete your examination, you shall:

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a. Asse+cie vcu- examacat
c, as 4ol!cws:

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(18 Exat cuCsticFC Cn top.

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. , (2) Exam aics '- 4iqures, tables.-etc.

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(3). Answer pages including figures.which are part of the answer.

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b '. . TurnJin your.~ copy of the examination anc all pages usec to aaswer the:examtnation quartsens.

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<Tu-n in all scrap.papec -and t*ie balance.c ~the paper t h a t' y: cci-

>not-use fc- answering the'cuestions' .

d. Leave the examinatten1 area, as defined by the examiner. *+ e4te-

. leaving.,ytu are;founc in this area wnile the examinatice is c :..

in progress. your license may be denied or revoked.

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5. : THEORY OF NUCLEAD DOWER PLQNTcOPERATION,

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......................... i QL'ESI1ON 5.61 13.001 With the reactor'eperating at 100% rated thermal ' power with recircu} ati on flow control system in manual, ex tr ac ti on steam is lost to e first point heater. Assuming no operator-intervention.

HOW ce the fc11ching pa-ameters change? (INCREASE, DECREASE, 09 REMAIN THE SAME7 A. Core inlet subteS1 19q.

B. Neutron flu".

. C. Feecwate- 41 c.i .

D. * c a c *. o # procsu#e.

E. Reci'culatiom c o r :::co ' .

c. Peacto wate- l e'. c i . (.S eacna CLEE! ION S.0L 12. 0.-1 Litt t~e three "tcha-isrt. CRDC'H OF PREFERENCE. that attu e adeouate co"e coo'.ir'g wit *i the "eac t c- 59utdchn.

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CUEE:10U 5.02 12.002 A. As reactor power increases, what happens to the inlet feedwate-e subcooling (INCREASES.DECREAEE5. OR REMAINS THE SAME)? BRIECLv EXPLAIN WHY, ( ; , q3 i

B. For a given electrical output. does the plant operate more eff-i ciently with HOTTER OR COOLER inlet feedwater terperature?

~BRIEFLY EXDLAIN WHY. { } . O'

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QUESIION 5.OG 13.001 Frovide ansi.ers for the b l a n >: s (A thecugi F) of the folicwir; t ab' .r :

LITil LSSE GELdGS MCEE PARAMETEP Average Tetal MONITORED (A) Fuel Pin Eu9dle Power Power in a Node LIMITING Clad Temp CONDITION (E) >2200 F (C)

IN REACTOF MODC OF FAILURE 'D'e (E) (F CAJEE 0; r ue. c e.let Semst ; e anc Lct: ;-

FA: LU5iE Extcarir- Decay Heat t:;ci e : . -

Due tC E'te:r Lcl.cwing E=: 41--

~ cat ' ' c .9 ; c t I O - a LOLA E .v c e t-Hea; ..

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'CUESI1ON 5.05 12.001 Concerning fuel-preconcitteninc

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A. Fuel preconcitioning. places restrictions on WHAT fuel limit' .b-B.'WHAT effect is minim::ed by 4cilowing fuel preconditioning recommendatiens? t.S C. HOW'coesJan operate- assure that the fuel preconditionirq limit are not exceeded? BRE! FLY ANSWER. (.5-D. When following the fuel preconcitioning recommendations and operating acove the threshol e values. power changes should be limited to 15'/. p er -:nute. TRUE OR FAL5E (.S-

> QUE51100 5 . '.% - 22.001 From 50'4 p ov.o r a b =crce~t stec c.*ange increase in recir +Icw c: L' r anc rea:ter acwer increaur .

A. L'E SC 915 E the chan es : n *e vc:c Jraction te cause tac t r:re . .

E. Wun' c re3 + : c: ent-f c) ster t"c cower increase? < ,

C. HOW t. . ' 1 incicutc~ .evci ret ac.907

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QUEEIICU S.02 11.501 90iv cces f. e - o - co>:ent-ation a+ feet ce-ipheral rec wcetr e c l l e .": - - :

ser a* f ec- n: ;' c ower 7 951EPLv EXPLAIN W n' tnis c: cure. '.L.

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. QUESIION 5.08 13.001 .

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' Assuming the;same centrol cod withdrawal secuence is utili:cc.

critical 2tv can occur'at_diederent control roc cecitions tn start;rc during-the cDe-atin; cycle. LIS1 four reasons why thi s' can ' occOr .

(3.0)~

QUESI1ON 5.0c 12..Q01 i

A. While operating at 80%~=ower you are indormed that feedwate-experienced a sudden increase in chloride concentration anc

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then. stabilized at a higher l evel . If the reactor water cleanup syste.m WAE NOT operating during this time, will i reacter wate- chterace concentratfor aise stabilize at a misser level' ,

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. E. HOW'does coloride content c4 the feedwater affect concuctivity' '

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C. >H Y 's a concent-ation .im:t placed on chlorides?

D. pH will always iricreate n en concut t i vi t y increases. TRUE OF 5' ALEL (.S each>

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I OUE51*da b.10 12.SC;

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lhe reactor rias teem ocerating at 100*4 ocwmr for one month warm a scram cecurt is w* i c" seve- 31 control rods Fall to Fully inse-t. Eno -

Poet I/O Intert ' o .f 2 3,7 Or'ng tne reacto- suOcrit1 Cal at the t1N OJ

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snis t door . If react?- moderator tempe-atu-e is maintained CONiTAN' arr  ;

control reds a-e not c.cvoc. 15 subc-sticality assurec for an  !

incefinite perloc? ExcLalh voar answer. (2.5- t

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.6. PLANT.5VSTEMS. DESIGN, CONTROL, AND INSTRUMENTATION.

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GUE51106 6.01- 1;.004 Answer the f ollowing -in regarc to tne CRD Hydraulic System.

A. With the HCU's :n normal oceration, why is'the accumulator nitrogen pressure less than charging water pressure? (1.0)

9. If both CRD pumps are net available while the reactor is at

, 50%' power..HOW can the reactor ce shutdown? (1.0)

C. What are the two design purposes o' the CRL Dump minimum flow line? (1.0)

.GUEEI.OU h.02 12. ul Answo- tne 4ollow:ng : -

rega-o c the Re::rculatsen Syster.

A. WWAT c es i ca- test -o 04 tc ccircu!atic- pumps lim:ts leakage t e :ent ai n+cn'-  :- en .r caen seals fail, t' '

E. Brie *;y Er"Lc N WCW t*< "o :-cul ati c7 Systet Des: cn / Lo*:co-o : t 411cwc nc cerc te te et;oceed 4:11cwl,g a 054 LOCA. t!.!

C. E te:1v E).Pu Al'4 t e reasca 'c- t~e 1e:otten ce tac Eat c3 Ci..

Rectreu.ation c u rti 1rso Oceakers' ( ...

' QUE511CS 6.0: 12.00 You have just ordered tne Standby Liquid Cent-ci System initiate:

in acccedance with the Eme gency Procedures. LIST six control r oot.. ind: cations yuu could use to veri 4y crcpt- initiation. (3.C.

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QUESTION 6.04 . (2. 00)' -

Will the f ollowing cause a hoc 1. i sol ati on?

A. HPCI steam' supply pressure low. ,;

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B. HPCI turbine high exhaust pressure'  ;

i C. HPCI turbine exhaust diaphram h:gh pressure  ;

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D. HFCI booster pump los suction pressure  ;

E. Reactor vessel high water' level (.4 earni

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QUESIlON 6.05 13.001 i i  !

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I A less c4 - , o- c. a l powe- t: all c; t he 4MV emergency cusses has e::s.-e-anc t h e d e s'.  : 6,s*er ;at a siled. T n e s l o,. t-ans4cr was succes- . .

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4 wha! a-e t"e 4hr tar breate- positions from the f ol l er.i ng? ..; !

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I E. WwAT e-w the status c- the ere gency caesel gener a t e s *

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i QUESliCb  :.0: 12.004

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Answer the folicwing ir regard to the LPCI Mode of RHR.

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A. WHAT two RHR medes c4 Oce-atien will not reve-t to LPCI j mcde when a valid ini ti ation signal 15 received. ( 1. '

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B. LPCI MG sets 110A and 1139 are out of service. If a LOCA occur: .

< HOW will LPCI valve motive power De supplied? (l.i h

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QUESI1ON 6.02 12.001 A lous of instrument ate to the feecwater anc feed < Ate- c c,t r ei :s has caused at LEGE1 t e reacto- 3eeowater puma mi-t e- flow recirculat:en valves t0 cptn.

A. If the less of instrument air occurred curing a startup when startup level control valves IC32-LCV-OO7X/Y were Controllinc.

HOW would reactO- Wate- level change? EXPLAIN your answer. ( 1 '.

B. 14 the loss of instrument air occurred at 2 0 */. p o w e r , HOW wculc reacto water level change? EXPLAIN your answer. (1.0)

GUESIlON 6.QB 12.001 Antwer the #cll wsng in E;a-: to the 'D5 system.

4 W:th the rus:*.:- cpe ct: ; at l ': , c t e ; , s t a t e , the cre ate-manually are- ac ct;-ertre oth cnanmelt c4 both ADE lcgic divicicci. W!LL t .c LDE val.<es coe at crDLAIN your answer. (.75'

E. k"A' 2s tnr au cee ;+ tne ;' 5 srcc,c e delay ~ ' .

c. !* c- 9Cv cpe - e: . c a: c .v e - > <w w: ll reacter rower 70 geme ater r e g a .u a - *. cutpu- recno r :nitiall, anc cace t e t' . t-t I NCRE..sh D F.; G E M E ': M. ' A ! ' T-E S h 'd E .' ossere ne scra . 1 D. WdV are ope-at;rs c A .' t : _sso ,0- .c en ::nely manua l . y coe-at, aa SRv t Clear a Lea'^

E. W"Y ar e Op e a t er s CLU T ICh'ED net tc crerate an ERV wit- F-V Oressure less t"an t "_' PEI7? .I

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QUESI1ON e.09 12.001 A.oLACE the folicWing cc DO ents of the c4+goss system in ' ' ?- ra*-

o* c er .

1. Cooler condenser 2. Recombiner 3. 04fgas inlet cocster ejecter 4 Preheate- '

S. Sacr: 4ical bec e. Main ccnceaser Stese Jet Air Ejector Ractatien N0 miter t '~ i . .

7. Charcoal A:sorber Tan's B. Main Conde,ser Of4 gas System Effluent Radiation Menite- < c 'e t '

C. Drye- Decs (1.8)

5. WrAT w:11 Se t e e-4 e:t ce lots of the Radwaste Building HV"C l c :ne charccal a:no-be- tankst (.2)

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7 PROCEDURES - NO9 MAL, ABNORMAL. EMERGENCY

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AND RADIRwCG3 CAL CD' YRC

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QUESIlON 2.01 12.501 LIST the f i-vc ente v corci t: ens 4 0- Emergency Precedu-e 20.027.07. Peire v.Crata:nment Control.(betnotets Recuired) (2.'-

( Z. 73 b CRE5llOU 2.02 Ji m ;

Fe- eacn ce tno 4c11on:,; setr 74 clo : parc-eters. DETEAM!t-E Ir ---

ECO i- : ar;c c-' t ~ e .-I c - s"cule ce as 9; i e ge-cy crececu-c 20.023.01. Level Comt-e! te s.acill:e the clamt. If the an:we- : ves,

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CRO>'DE tc c <:: .: c a t ',- :- c.t::- (pa-a-ete- a-c retze -ti.

A. Dr yv.e l ' O * es c u-C- !!

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E. f#- a : n SteC* P 4 C7 ;-S tru?t "! -ea^" . l '. Ps: 0.

C. beu-*C" W3:ce levC! 't . C- "'a r r o w "ange.

D. hea:to- p r e s t. - t> :e .5- p. ;

E. Na:- Etea- . tac a ca .-o: e : c. te-ce-stare : ::' ceq. ~

r. CO-cc-nc- va:au- :t ' :nt ee 6; '

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QUESIION 2.03 12.002 The reactor is in RErUE_ "'JDE wit * refuelarg ir Orc-ress.

A valid REACTOR SU!.DINC- DIFERENT I AL CREEEJRE LEW alarm is receivec. LIST the 4 cur IMMEDICTE AC !ONS recut ec by E MER GE NC '-

PROCEDUF E 29. O !!. '.12. Lots c' Se:enac y Containment Integrity., C.-

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GUESIlON 2.06 12.001 A. During sta-tues c4 the Srorenom Nuclear Plant per EP 22.001.02. ^"CN ' i s tne reacter considerec critical by tnic procedure' Sysg 4 2, 7f g/#g ,

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E. During plant shutccwn ' rem full po ver WHY are operators Caut: 0-not to use the Main Condenser Vacuum Dreakers except curirc a Emergency Condit:cc~' '

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QUESI1ON 2.05 12.001 In at:c-dance w:tn E r' . 2 . 01 ;. 0 . . Hactatten WDerk o nrmits, cc t-c 4cilowing clant conci t: ens /si tuations ecul-e an RWA te be issue:

p-ic- to Dectrn:ng v.c-<'

A. Calibratica c4 o M a : ." S t.e a m 2rsteurent in an area with a roc:c- --

4 : e; c4 '. --e- re- " C .i .

E. T ube sneet : 2:e::::- c- A '? We A.

C. Inspect;cm c4 a hats cu-t .v n e e -ad.atten fielc 2 s E- aret -.

O. Ins;er 2c- ca ;: tur=2-0 .v"c-c .cce is ecnta-inate: at -

.

10' :t s c.

E. ko-*. 0- a- Shv c:scro ae .;"o supac-t ir a neutron rac. 4 : r l :- -

4 * em/" .

. *1-07 1rtpectic" 24 c~ yw(?! ! a t* r acl at t on airDo-ne Cc9:e"t'at: -'

a-c 1 5 . C * M"1 .;ste: 1r l '.' C E A 2C.

(.5 ca: '-

,

_ _ _ _ _ __ ___ __ .__

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C

.

'QUESIlON 2.Qc~ 12.001 Answer the following cues; ions cer Procedure SR C7.OO9.0;. :ue; Hancling A:ctdentsi A. WHAT are three sy*ptoms 04 a damaged fuel Duncle iFuel Handi t r ,

Accident)' D o n o +. list notif ication. (1.5 B. WHAT see three immediate arttons recuared if a Fuel Hardlinq Accacent has occu'* ec7 ( '. . L QUESI1OU 2.02 12.001 A. Using the attachec geschs of the Heat Capacity Temperatu"e L:m2t (HEIL) and the Heat Capa lty LPvel Limit (MCLL) (Figu"e 1)

DETERMINF: the suppression pool water l evel for which a controlle:

RPV ceareesu-::stion woule ce r equ i r ed am accordance .sith tne ce2 mary Coata:nment Cont ol Emerge :y crococur? ( S P - T' . 0 : 7 . t. '

.

SHOW 4LL steps and calculatto"s usec to aartve at your response.

.

. b'

GhEU: Roa:ter p essu e '  ! *. ::: : q bup p r e s'il o" L oo t e *lt e' a l J" O e 70 Oeg C 5. 9P 1 fd l y E)DLA!N le v oce'a'toF W: thin the "egion aDove tar .; c > . ~

4 L' - thO Hed* Cace: It. I e r e ' S ". J " E .. *;t 19 "o* P e C o m t e ". 0 c c . .

u. 'la : ntalm ' 5;- ece.;c9 O c)c - c * me level c: t', e tP' cursr *. *

Wes* C 4 0.9 0 *' . wreC. 1. *;*. ;" U"CC W"A7 11*1t will "ot 'e c' t t  %

e e O

-- - - _ _ - - - _, - - - _ - - - - - - - - - .- - -

-_ - ,-

._

. : ac

.: o-

. >

-

v-- .

i *

QUESIlON 2.05 12.QQL

,

-Answer ~ the f ollowing in-ceccedance with Proeecure SP O2.001.0 ..

5 tart-up- Cold Snutcow, t t' 20 percent.

A. WHAT are three tenditions ne:essary foe a system to be ce lo e.

AVAILABLE FOR SERVICE? ( 1 .' .

B.- WHO may autno-tze a deviatien fecm the rescribec secuence c4 eventt? (. ?:

C.- 'WHY-are operatorc CAUTIONED to minimize the use of Au>111ary 5 *. e t - -

to-support the_maan turb:ne sealing system, radwaste off-gac' o .

radwaste evaporators? t.75;

.

QUES!10W Z.09 42.C01 Answe- the 'cl:owinc in c:cor:r.mee wl:n Frecscure EP 22.004.0;.

Operit::n betweem 20 P:t ame 100 3:t Power.

A. L'U" 2 n g Pl aa t Sto- up 14 te- a Lee vel:m; Uuta;c witn tme cc-+e;- --

ce-t-e-tet, k"i N "ust *~e :c-ta:- cat exvgea ren:ent-at:e- r- ;r:-

t .an 4*. ' t Ev i e.-c cc D:c- c t : ca it cleance) 2 B. We arc Sporat: - 307;;'NFr' -Ot te c:::ce tac BO'<. roc .:--

u a l e r. t te*a: co c 41:n :t reate- t n.e" !? "terr ar? .

-

L. Dv-:nt a Fla-t inu*,ccwn. Wh ' " ET ce veri fte: a+ter c '. t v ,

t: -e ue: mg rewe- celcw 20'I ' .:

GUESIlOS 1.10 J L .9's.

Answer the following in reguarc to Peccecure SP 23.202.9;. Hign Pressurc Inject;or Syster.

A. WHY are operaters Cau*:ened against ope-atic witm flew less t :-

576 gem? f:.

B. WHY are cperaterc Cautionec against operatier at less than : 01 rpm' ( .

t'***= END Or CATEGORY 7 **=**)

f

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, 8. ADMINISTRATIVE PROCEDURES. CONDITIONS,

. . ..----------------------------------------

AND LIMITATIONS

QUESIl0a E.01 12.501 As the Waten Engineer at02OO hours you have Just been informee by the Watch Sup er vi sor tnat he has indication both seals have f allec on the "A" recirc pump. Attempts to close the recire pump suctic" valve have been unsuccess4ul, the primary containment is 1solated and he has no indication of drywell paessure. Drywell temperature i s approx 4 matel y 22S ce;"ces C. The appropriate EOP's are ceing implemented and all other syste*t a p p e .se to be functional at t"tt tire.

A. As t*e E*e gem:y Th c tcr . WWAT t"ree outier cannot be dele;a*:'-

(;.'

B. WWAT cet of percecu-et wo...e you initially refer to 4er ge cance :- vc .- ade? t: o* c - c! ci .S.

C. CLASE!cv t,: t e~er;c- - .5 n. ,.:. -.

. .- i . s. n .

-4

-

. ...r....

,

vou a r e t n e ic t c - Eu::c s 2 s er and *"e Operatiens E'g:ner- 5ss jur*

In'c--ec yet tna' tme w e.i. l v surve:llence on the rain turbine st -

valves was not per4c med last week and mes exceecec the mart a-all owabl e ex tens c - :nterval. ANSWER USINC, TECH SPECS.

A. WWICL LCO ac applicable?

B. HOW may the valves be returned to operable status 7 C. HOW long do ycu have to comply with the Action Statement?

D. ARE the 7eovisions c4 Spe: 1 4:catie. 4.0.4 applicable? (.5

_ - _ _ _ _ _ _ _ _ _ _ -

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.

QUESI1ON 8.03 IL'.S Q A Answer the f oll owing in egare to Tech. Specs.

A. W:th the ree-to- .t '. SOP Ocwc- cur! ; MSL Rac. Me,itor Survei..: -

Tenting, 15 2t re=at-ec to place the channel being testec :n t-TRIP condition? BRIECLY EXPLAIN. (;.v.

5. With the reactor at I QV*, Oower WHAT action 3s recuired by i t." .

Specs. 1 4 oae M5L Ractat:en Monitor Fails Downscale? '

.t-C. With the reactor at 100% pcwer, WHAT action is recutree av ic--

Specs. 14 one "5L Ractation Montter in each Trip System f a le d own s c a l e*' (1.0 QUE511La k J. ~ 12.001 an t ..e- tqe + '.cr : n; . ' r e:c- 9 te ic- . Epe:s. with tme rec::c- - -

SHU7DCr J.

a. W-G: a .- : e - :t -ncuace: +

t~e Div. ! D/G cay tank +uel lese:

s - e
: c - r c - *: vct tc te 25. galloms anc a visibie hole :s ;n tre taai .' u s * acove the p-esent leve!' (1.

B. WrAl a: tic- :s reca: ec 1 4 tre 125-velt D.C. Dist. Bus A ts '. c o t ~

C. Tne R'E Ma :c- a c +c re or -c- te . , asse? :y at t,c Overvelta;c 1: 7 :

-

re- the a<secolv is not tr: ppe?. .

. .-..**na G,, .a . e. a. 1;.....--.

-

For each o' the + :l l e v. ! n g condittens. statt viS or N: wnetner a Lifte Lea: anc Ju-cer Permit 25 re uirec per 5: 12.035.01, Centre Liftec Leads and J ump er s, .

A. A jumper is inctallec t an rcrevec in the ne>t step of a r- ap -r station procecure that has a sign-off for each step. 'ac procecure will re com.,letec prio- to shift change.

B. a lead is menentarily It'ted to initiate an al ar m then reple. ."

C. Recoval of a circuit toarc from the LCPS logic authort:ec e, .-

N .,s .

L. L: 4 ting u ecrae. .:ces to eplace a capac2t=r in a circatt, (.5 eac-

n m;

,, _. #

3.s ..

. ..

!

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.-

GUESIlOW 8.06 -13.001

' Answer the f ollowing in regard to the Emergency Precedure Guicli-ess

!

A. LIST two. reasons WHV _i s i t- oref erable to spray tne suppress: c-chamber rather than the drywell? tl.v ]

5. At WHAT Suppressicr-Chameer Dressure is the Containment ,

'

vented, irrespective o4-radiatien release anc WHY shculd the reacter building be evacuated prior to venting? (1.04 C. WHAT evolution is in progress when you'are concerned with the-

'

MAXIMUM ACCEPTABLE CORE UNCOVERY TIME? (1.O?

s t

GUE5110W E.02 a2.001 ,

A. WHO is rescens:cle fer ceter-fring wnetne- a AAC (Rep -t 24 .

Armeree! Ce*::t*en) enouie de taitiated? (2.

B. If no Ela it en c:4: 4- w c, a RAC event occues. kHO w L. c t e xe * :-

Eagte.eer. net:fy : rstcee 0 4 the'STA? '. 0-C. ' ! 4 the ENS -Oti:ne it inoperaD2c. WFERE could tFe Waith Er.g t net-refe- to 4 0- tretruct2:9r c- alternate metne:c 4e- ra : aq t~n-e a: -ed neti<icet: Ort' <

..

.

<

.

T CUESIICW E.0E 22.00; A. In ac:c-ca-ce w:tn Prc:ccurc L .f.?!.02. Operatiemt 4c r t, WWEN :: e Lee:ter Trt: Repe-t net ec=J: red o c arest:- tr:r' *

g .i . e. x

'

B. Price to Reacto- startup f ollowing a reactae trtp, WHO must rev:c.

the Reactor Trip Repert? (.")

r

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_ QUESI1ON 8.09 '13.001

. F (TRUE OR FAL5E).

A; _The Shift'Tecnnica! A vise may be designate: to assume tne conteci room commanc Junction an Operational Condition 1.

B. The-Operator."At the Controls" may. leave the "At the Controlt"

area for Non-Emergency Reasons.

C. The person pert'o-mirg the control room command function must

,.

remain within f41 Q h t o4 the operator at the controls.

, D. When-you give instructions to the NSO/NA50 he must repeat them back "in the same terms."

E. You can use a pertable racic fo- monitorinc purposes while t- >

the shift engineer's o8fice. 'E F. Dur i ng Lu"o-mal Plant C:nciticos the N50/NA50 has the i responsibility to take the immeciate a:ti cos necessary f or i Reacter Sa4ety.  !

I (.S each)

,

l I

,

! GJEE!!ON E.10 12c.O. l

!

4 tcrein; te !C C: A 50 tne < toc-t:"; recutremsat of DNE "004 - :- * I

,

icllowin: . rent:: rms ;t a c r '.1 : c o ' e . LTRUE or RALSE2 .

!

4 The plant ts i n a OOnditiC" n:t Cove"ed by ope"atinq G"O ene geniy pr cecuees.

B. The loss 0+ the c44 site nntification system.

C. A valte autcmatic initiation of the Reactor Protection System (RPS).

,

D. A shutdown was commenced Decause the plant was i n violation  ;

of the Technical Specifications. (.5 each)  :

l I

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(*s**s END OF CATEGORY 8 *****)

'

(s**a****** END OF EXAMINATION $$***** sat) .

?

,

W I

i r l

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l

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f

,

. , , ~y y ---,y-, ,.-

,,,,i e ry-- - . . , , , , , -,,e4y- y y y- e e.=w ,----+w w- ------4 w

'

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. ,0 --

-

l ,.  % .e ve- .m

--

.

- .;

1, . y - -

.-

.

.X -

-

l /? x * '

n. ////g

, 9 - -

l 4, /////A

- / //////k

.,,, ////////>w ' " '

l///////////

/s,o wor' oram in rurs ucrow//A

////////////7n .

.,00 0 a 10 ra a u

////7r ,x

, a a a a A t' EC (MC yb A T HC is determined by subtracting suppression pool teeparature from the West Capacity Temperature Limit (HCTL).

.

HEAT CAPACITY TEMPERATURE IJMIT e ,'" M///////////////////

l '" N////,*"*"'**"""/7)// "

'

l'" NL// / // / / //////

l IN '" ~4/////////

\

F 4J ^//

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fH K rn tH

< '*

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IN..,

,

I If0 IN O It0 200 300 400 800

'

000 TH 000 000 1000 If00 JU*V PMSSUM 931Co FI6URe

m

.. -_ , _ . . _

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=  !

'5. . THEORY OR'NUCt.EARlPOWER PLANT OPERATION.- D l

.-------------------------

Ib y l 1

'

FLUIDS.AND THERMODYNAMICS

.

ANSWER .5.01 ( 2. 0(0  :

A. '!, create .

i

'

B. Increase '

C. Increase-D. Increase  !

E. Remain tnc same  :

F. Remain the sa*o

_

( . 5) eacn RECERENCE

'Sherenar u -11n : W Heatr's. Extractio9 Eteam. Heater Dra:ra aad MP' Cg 17 . -c c:or< Sc-*:on 154.1.E.

29~005t!!1 ..(LA'e

.----..-- - . ........ ........... .... ........ . --. -.....-_,

ANSkER S.0; G. 0 0 1. RPV W/L above tcp of active fuel (most cet.t r ab l e ) .

C. E t n 21 c - E;;5 nw c: e* at :"; a - e : *.i e: t ; "i,y o A o** C S M/ *f '~g g /%s f ca.

,. -coa- -- !:"q i t # 4 i t i e .t stre- I ', c r thee.sch ea-b t t . " .: . a -

ree e-. ;;p r .,e; te- .eut cet t -cr i e' .

<- .S4 0- r o:;t;i e.; ; e Amt O. b 4 ce c e .9 e r RE=EHEM E Snorehaa: Etucent Harcout. HL-9E0, Mat: gating Core Ce-a c.

. .etec- he. - Faget leM (Reco;m::tng Adecuate Cc e ~co.: cs.

NL 9H -3 NL A%. L ff, ts.

. c y , , p . ,. ,;.

..-. ~a.,..i

. n.

..

~ -9

- e e, 36 o-

- ,

..tyn <.,

.--. ..-.--- --.----.---.------------------------.--.

ANSWER 5.07 (2.00)

A. It decreases. (0.5) As powe* Increases, more ex tracti on steam is availacle for fee 1 Water heating. (0,5)

E. Hotter. (0.S) Cocler fecewater will re cu:re ade. t: ena; core neat to cuppcet a given electrical output ( 0. 5 )

REFEREfJCE

$NFS Wrat ~rcatfee 'ihrecocyna*:ct Mccule, pc 4-75 6 4-72.

259001A102 ..O A's5

. ---------------.-------.------.--

'

NASTER COPY

- __- _ _.

. s .

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.

.

  • ANSWEw 5.04 (3.00)

4. Local Fuel P1n Power in a Node.

B. :*/. P!ast:c Stra: 9 on C;accing.

L. Tr arsi t i on Retlac; c- DNE.

D. Ciad Cra: Anna Due to Excess Stress.

E. Gross Clac Failure Due to Lack of Cooling.

F. Clad Cracking cue to lack c4 cooling.

(0.5 eacn>

RCPERCNCE Shorehar Lessen Plan No. 904 Thermal Based Limitations Mocu.e Rev. O F1gure 1.7

[43009 1*6 2 2 4 c" 4- :;C 29:00u *1; . 293C09K109 .. m i

___ _______ ___ ______ _____ ____ ______ _____ _______________

ANSWEA 5.05 t .' . "-

A. Rate 03 : n . - e a c r- :- fGH W Cg 4#44 @.5)

B. Dellet c l .t c trte a-tte m t.5'

C. W s : s e ; e <. : - so  : c:tc c. bca:::- e ;; nee t r.; 4.5)

D. r e.: se <

.-s r, E r E q N g S*c-eraa ' r e~ c ! Ecsec Li.:taticrt voc le L esser 4 ::c s 7. '.

--

myep. m 4,. .. i1,.

. w .t .ir,q,

.e.

. . _ . . . . ...._ . ._... __.. _..,.. .___..,., __.._.

__==.....__-a.

l l

l

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_ _ _ _ _ _ _ _ . ._

. . .

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.

.

ANbWER S.0e(3.00)

.

A. Void fraction decreases initially (due to boiling boundary ce!"c moved further in the core) (.5). due to increased modeaatto-anc positive reactiv:tv power increases (with vcid 4ractic" returr[I tc aDout the s a '* e value)(.5-B. Void (0,5) ano doppler <0,5)

C. Decrease ini ti all y ( . 5) anc the return te normal level (.5)

(by 4cedwater systc~' OR p w) . . _ Lhc sens- (o.5) f,,. $y ), . g f . L _,f /, y. fa, (c_

.

  • REFERECE Shoreham Lessor L" o r PL-650-SHl. Reacter Recirc Flow Cent-c! = age 26 : tem t.

RECERENCE e

_ c,

_ u.. . ... , c. . ,...

,-. - _,, .p

. ...u. _- o _n s p a- . . c

.,

. . I ' 60 ' C

_____.___........._. .__... --.___-_.._-.._ ___.__-______...___._.

ANEWER 5.07 .1.5.'

Gr ::"c ci  :- , :- .s : .. . : c re. .t. +:q* pc-:- c: c-- --

t cre..: ...- :c : ec- e-t-2.- ;c- :c 04 tne co-c . :c; ce

'

the tne *ai ne,t :- .

-

.u- - * hat

. crt:c- c4 tre c c- e are - - -

flu ~ 1-to tne -c ;c;;.,

'

.c Ocre- -c;;c- t:er: :~e-a. .

'ne.; .

cess s at tne pee: ;rer, c- *e : -e cause n:q'ce roc wcet~. .

.

_ r g. - - r , _ .

w- un x.:

LaSal.e C>. R 9ys:c. Ec.:es. W ?v. .

c ug. ICU5 :: 1E'.;...

=

Shoreham Lesson Plan No. 13, Fuel Loading, Control Rocs anc Surnacle Petscos pp. 7-212 292OO5K!Oo .. (PA*t)

____________________________________________________________________

+

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,

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AN5WER 5.09 -(0.00 A. fuel cepletion B. c: 44erent mocc-ator temperature C. depletter c4 E-10 : r- co-trej -ec D. ci3ferent xenon coacentrat;c":

E. gacclina burnout F. different samarium concentratton G. fission preduct ouildup (any 4 9 75 each)

REFERENCE Snore 5a* Reacter Dhysics Mccule ogs 7-112,145,155.169.176.216.

292 Ore.10; , .<.t'-

..----------------...------.----------. ---------------------------

AN5WER 5.04 < 2. O t -

r A. Ne t.6-U. ConCJCt1 i! wt. .' t # s * > s. C 4

.

'

L. C - es y g e e v . c.e e 3- ry-cm : .a,, s; ,,?

_

'. F a . 9 (' ."

REFE4F.NCE Sherema+ C h e . s t r '< . Mcc et 49: -

1: or ai r Kccale Lessca . 0 ;r-t2vc

- Oc??- 2 Ocje00.vc t 2O4'JQP74,'l 25*:O'a.'A}U .' FG*...

..-----..--------------------------

f

. . .

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.

.

  • f4NSWE R 5.10 82.50)

No (.73) Xenon Will p tr a r a~d than decay afte" the scram. Tne Or*:* r rea- : v: tv interte: by t5m ce:w,' of xenon will o ver c orre the -cer.

t ; . :' 5 :

FECERENCE Shcroha* Lesson F'la- No. .1, Fisc:en c>rocuct Pc: son pc. 7-157, 29290ek107 .. ' Ga .

e.... Et , r;, r t - { rj -;- g e,, .

-

- - - -,

, . . .

> e e

.

c. PL6NT E-57 EMS DESIGN. CONTHC . AND INSTRUMENTAllON d

___ . ... .___ . ... -_.. .._ .. _. . __..

ANSWER c.Oi ( ~ . ' .C )

A. Initial .m i t r og en :na gt ; 0-essu-e is not encuch tr' prevert :t Oist:- fr:m cett0m:n; out due tc charging water pressu-e. .;.

E. Througn o rea:to- scram. (1,0)

Prevent pump eve-heating :r the event the discha ;e sc..e

~

C. 1.

~~

inadvertent 1y shut. t W (I.d)

-

..

._ _

c. . . - - , .- _. .--.... ,_ _____

.a .

..

r. ..

u m

:: c ,< t.. ,.

. ..

r-Shere,a* L i.2:e.- s m : :. ; M. : . :: - - - ! . CRD -v::- s . ::: Sys -

\ ca;c t a : ...

L t.' 10 . t.. ..

,.c  : ( . :. . .. 't/'s)

. . . . . . . ._ __. . . . .. . . . . . . _ . . . . . , . . . . . . .

.%: t . .' : .

u. B r e a r c e .s - r- 'rrett.e en ;r: . .t'

E. "'o jet .m : ce me.ce: t o - e c r. i e :1 ate i. . t t ': -- : ,,:

--

t-r n t : : c -- c - c .. - c-ee .. te . 2:e .53 : : t~n .:: r

.i e t pum:v a L : '. :o-r *o;;~- . tv.t ( thebL I desEt- f.,. du ca na.: s9 0 /<o.s bomf ddelterr e vuls s- clar 7)

a C. RAT breave- teolate t h e MC- set f e c m. One pum:: (O.Si p eventing the "4!vwheel c'#4e: " w*: le the O u t.? 1e ::'asti g 0"-

a ster a trip. (O.b' s. sp or'* d

& g /s e teis~l fs e tr.fth'Cd Ek*8*7 y$ dS~ fo*'.d'aj h~l.//. e!*ch.d /(O. S) fr., f e s rtN (0. S REFERENCE Sho-ehar Stuce-t Wanc ut 6-L - ; ? >- E n . Reactor Re:te: Syster "c .

Pages 4 ,, 6

"

Enab]1ng 00je:t;ves "N" er/ ,tet'4 'f#1 /8>0 y /f.

Q r t hm / s< h . ,'y* h 5 S $. l a r.. . Up}6 .g

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@

ANSWER o . '. 7 13.00;

.

l '965

A. Continutty indicater 1sc;s w tinguish.

B. Scuib valve continuity lots a"ranctater.

C. Pu~c discha'ge preen. R >, Pret2v e.

D. Fame rum-ing lign: ca.

E. Storage Tane Leve. Decreas:ng.

F. R< power cecreasing.

G. RWCU isol ta" -s tAmy e & v . '" s a c -_1.,/

{. S*yu;b VsIn 9 m h a f y mp r1 r +.> dum ./w RECERENCE Y Shereham Stude-t '-a cca L-127-S'fl. SDLC Syrtem Rev. t ca c .-

L e s s :'r Ce;c:tive r.

21 1 v00CrX'! . . I V (4 ' :

...... .... . - - . . . . . . . . - . . . . - . . . .-.--... - - - - . - .. ... - - - - . . - - - . . - . . - . .

et :S u '. .

.. *s. ...

4 *er b. he C. ~er . s- s

'

.. N:

. NO AEPEGE' TE Snc-ena~ Etucemi Harce : " L - I r. 2 - S L ' . s=c! ys.e- re.. 1 page 21-2', Lesson ODjective CG and CH.

206000K402 206000r402 ..( n's'

-- --..------------------- ---.. -- --------------------- --------.

_______._____.______,

-- _ _ _ _ __

.. .- .

e <

.:

.

. ANSWER c.05 (2.00)

A. EDG Breaker ccen ( . 5)

RSST Breaker closed t . 5)

NEST Br ea t:e* caen ' . 5 .-

B. Running t.S:

C. Service wate cu os A(.2). B(.2). C or D (.21 CRD purs (.2)

RB5VE an CNAL ue: ts thet were ruamtng t.2)

n = c c rs= v. r s:

- -

Shorenam Stucent Man:out +.~7C;-Sw2. Emergency Electr: cal Distr: ru -

09-21 lessca ceject?vec C a'

262Ovin3u2 .62OO:t201 .! c 2 0 0 ! t . 0 c ..ket

.-.----....------. .--..--------------.------------..

ANSWER e.0L +2.u0)

A. 1. whe- : -- E! Coc.:ng M:ce. ..t)

. W9e- in Fuel cc:1 Cool: a; *cce.<0.5>

f. . '!

. . ') v- - ... ' .5 .?!. Oceca !"e ac!c0ta*C0 Durcet RC 5 f.:EN e Sha-enam St ce : unc: t n ~~o4-EH: LPCI S ys t en. Cev. '-

Ite- - a-d ri; arc -2. c :en 0:jective CC.

2 0:et; c., ;. .; -t nov .: 0 .. ( h t ' ._ ..

-------- -------. .-.---.......-- ---...----------- --

-

. . .

. .

e

.

  • ANSWER e.07 ( 2. t. 0 )

A. Decrease s . 5) Startup l evel val ves f ail closed en lost ce a:- ' .

B.No Change (.5) With -: r- .or valve ope- tv-asce s eed wt1; i": re to maintaim level spo 4 2- : *. w2th:n the capability of the pu : $ -

the min val.c fully cpea. ) ( . 5)

REFERENCE S*crenar Stuccat HandO_t H:.- 1 09-S Hl. Feecwate- Syttem Rev. 0 ca;e 27-20.

259001K601 .. (KA's)

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

ANiWER 6.UE ( 2. OO ' e C. b. : 4

. J S w CO e 12 -- ~

_- '!' runn r~ e t ce *urma.; t.5:

P. A '. . C r. " ant n Q *- Cr9: 4. ' C Gytter t0 -eStCre level t0 e.CtC unnecessary blCACCWF.  ;.Di C. 4P 4 0 *. 0 - "J 0 . e . ri: : t,-- o n c e . :e a- :ne. retur- - : : -a: .

..cac 4: r- -e;aaa:- .~ t c e : - e a : ., i . .. : .'

'

f D. e va..a e a r e . c: c , .: ( 1-Cf( be slh Hj Mnfs gj1 '

.

o

\

E. 'ne :a! ve is, ca ca~ ace . (i .2- u hs" fL 3/Jyo~&d RL cE RENCi Ce.. "

5*:-ena- Etuce . -ance t mL-20:-F- A';E ' E R v Estte-page 13 Lecson Oc]ective 3 anc B.

2180'.05010 .. (kA's)

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

,f L .- . .

e *

O

.

, ANSWER e 09 (2.001 A. 1. Offgas Inlet booster ejector 2. Preheater 3. Recombiner 4 Main condenser stea* Jet air eje: tor rac moniter ( 0.r , 7 -

b. Cooler Oc* censer b. Sacr \'tcal cec 7. D yer oeos 8. Charcoal a d s c r * f. -

9 Main cercenser C+4gaz uvstem e4divent rac mon 2to- tREt3; E. Ee: teroe sture v... :r:recte (bed helca: time will cecrease).

(.2 ectn artwer)

REFERENCE She-eha=* Etucc t *,c7Cout -714 Gasscus RaOnaste og 12 a r.0 .

an: ".-97.  : *

. 4a0 '< ~:t -: c cgs IS-16

..i,..-

.

.-. . .. c. -

-

. . , . s, .

. . . c. ,.

. . . . . . . . . _ _ _ . . - - - -....._..... ...---........~.....___...... __..

aN d k'E E- r... ." .

.

2. b; i' .. . .' ; ^9('t.

~

. E' / . ' " 3.' * ! !.t 4 C; .'3. 4 7. RE r e * ut ; .ese, eN".LJi* r aC h '~ TR *-/hr.

4: . RE ce; e o r s's 1. : c v. v. :ncnet water mel ew M1.

i . .t c a : : r:" . .t retac:nt)

REFERENCE

Shoreham btuce-t wanecut (L-412-Sr: Rev. O page 19 ite- C.;.

Lessor Ob;ectise D.

2COOO2E401

'

..(' ~ t.

'***** E N .' - Cr C ATEGCra , c ... ,y

-

,

. . . .,

a W

'

,

'7 PRQCEDURC5 - NORMAL ABNORMAL, EMERGENCY

.

~~~~hNb'khbibLb5 EEE Cb5TkbE"'~~~~~~~~~~~~"

..... ...................

ANSWER 7.01 (2.50:

.

1. Average Suppres<.te- coo! Temperature above 90 cegrees F.

2. Average Crywell Te persture above 145 de;-ees F.

3. Drywell pretsure a=ove ..e: RSIG.

4 Supprescien Poc. Level ateve +6 anches.

5. Suppression Pool Level below -6 inches.

(0.25 +or oc a-eter anc O.25 for the value) ,

REFERENCE Enore on E e gemi. m et e: en O 't. ': C . ': ~ . P :+ary C e n t a : r.t e - .

Cent 01 Res. 12 : s c r. 1.

2050!OG011 29502090!! .'95024G011 295028G011 29500:U'.

. 9. A ' c

_ _ _ _ _ _ . . _ _ . , . _ _ . . . . _. . _ . - . . ._._. . __. . . . . _ _ _ _ _ _ _ _ _ . _ . .

2.1.5 Avs w. - 7.... ,_.

A. No, t >; . ; 5 )

5. ves it .25 Isol at c" w-i * recu:-es o- :m:ttates t. scra- i .;- (to * /5' d

. . :: A y's.S (0. tS) (PU W.-f + luv/ < 12. 5 ilJ a.> (c. L s)

. Nes. (0.25) 90/ Presture Greater than 104;
s:q (0. S?

E. v c:. (0.2S4 l u o l e '. i c a wn;:n -ecutret or initiate: a scra- ( ._ (155'F)

F. Yes (0.25) Isolation wntch recutres or initiates a scram t.S (gy"#p-MECERENCE Shoreham Emergenev Procecure 29.C:!.O!, Level Control Rev. O pp 1.

Shorenam T.E. 3.2.2. d d. dd d f. Z . 2.

95020GO!! 2C50240011 2050 5G011 2950
100!! ..ta-

. ..______________. _ _ . __ __. - . . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .

en. _-amm _

,. . _ . _ _

. . . .

. .

.

aNSWEC 7.02 (2.00)

1. Start the RB5VE 14 not alreacy operating.

2. Suspend hancling c4 scractatec fuel in the seconoary corto:n-e t.

3. Suspenc core alto atiens.

4 Suspenc =peretiens e,2.n a actentio: fer cra:ning the gr,.

t0.5 ea.)

RCCERENCC Shocena? Emergency Pro:ecu-e 29.023.02. Loss of Se:onca y Conte: m Integrity Rev. 7 = ace NO. 1.

293075G01O ..(FA's>

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

AN E k E.H /.04 ( 2. CT.-

A. W c .- -cutren -vs + i s o r. e. i t r a c:nstert (stable) pt :cc ( .t) withcut accit:eaal ::"trel ro w2thdrawal.(0.St

d. Er t et s r vc . '

10- v ?: i .~ - :1~: :- *~? :stt s '. o g c 7; O r ?.1 :~ ~~'

tu"7:re. 1C c:cc

- - .h u N 't--

~'

Sno-ena- Pr :t e,: - r !!'- 22..t...2 Res. :o : . Sta tu; : J.

E . C . *. ' . : o": Su 21. .* ; t . 0. t? C v .10 p r .

292VUP*.lt7 ..(*A C

---.------------------------ ---------------------------------------

F .

, , .,

. .

.

'

.

.

ANSWER 7.05 (3.00)

A. Yes B. N e ".

C. No D. No E. Yes F. No (t d '. 5 eacn)

REFEREN~E Shorehaa Procedv*e 3r 12.012.01, Radiaticn Werk Permit Rev. . .

2c400!K105 . . ($ A r:

.o.e. .. _ e . . .__ ..._-.. .. e_. .._..._.......__._...e. e. ..._e . e _.

' *

ANSW.ER . O ee t .F 4.

1. \'a sua ::. n e '. a t i t -- .' ta; :uct.c c c g, t a g tr:~ a ta cre.

4 a*se.t.v.

2. m eas:ric act: ..t- . e .- 1 5 rr alar s c- re4uc; - ; c: -

.. . : e a t : > ., act: s.t, :r.c.: c~ a l e r .~. ; :

J e.a ras;at: m ec .t:- ala-ms

-

ve-t:lat: : e .

-

g

& t? ASUS r'* *U /E d - B er..><-

( ? at 0.5 ea.)

E. 1. 1: tme a. rue' Wan:;; i ;

.

2. 1.m=lemeat ; 0:a. a r e.s evacuat:o c* '; a e a::;4ent ares.

!. Nott i y Healt'$ Phyti:9 section ( ! at c.5 ea.)

REFERENCE

-

L Shoreham Precedure SP 29.009.01 10.1. /r .

-

e ns s. ,.,.e 3 C,. ,C. %

. . . n c. e. >

e se . . gmem se eme == o. em me e == = e .* ee an enwe en on-e re - e e-e e e. . e e ** e en*-e e i em * . e, um e. ee. e se e e .e-***.-e o ee .,,e e

-- __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

. . . . .

. .

.

ANSWEA 7.07 (!.00)

.

A. From th'e HCTL, if Rx pressure = 550 psig.

Sr ter.o a 175 to 177 ce; 5 (....r.

telta ' H: p SP Terr, <4rc+ WCTL)- actual So tems 17e - 170 ce;.F" e ce;.F. (+ or -

1 d e ; . c .* .-'

From HCLL. if ac.ta T H: = 6 (+ or ~1 deg.F). ADS shoulc be aritiatec p-:c- to reach:"; -20 :r.(+ o- - 4") ( <. . ! -

D. 14 ADS actuat:c- te- E*c cenev Depressurization) cccu ;t.f unstae:e stea- concea s* 'a 'A.202 may c:cu- at er near t*e :

cis:* a ;c cov: c er (~ ". 1- -e 2) CO.2*:

C. HC'L .29 ci qu,f bL S/m wk - n~ (O. 5)

R E C E G E n, _ :

C. r-r .3 - 2 -:: e r. r t- ." . ..

293 e; J r,i ;ie f;;. ? ;.'5 , ; ~ . ;, ,_

.

, , ( y (, ' 5 i

.._________ -____... _._ .._. ._. _ _ . . . _ _ _ _ . _ _ . - _ _ _ _ _ . . . . . _ . _ _ _ _ . .

l l

i l

d m

7-

. . c .

. .

.

.

' ANSWER 7.OD (3.09 A. 2. Valve liceu; cemplete: 0- accepted as comcleted.

c. Pcwer surelv :"e *-c'- snrtets : mpleted or acceptee at CO*D1eteO.

3. All necessa v co ::ae'tc are Operational for the svete- ::

perforn its intencee function in tne requirec manner.

4 Tno system wi.1 rescenc pre;erly to an automatic i ni t i a t . :-

signa; :- wren tm t::.tcr le system prececure is t*:In i- --

tc tia-t te tyr:p , P...I a , L ivc 7-5. f.,kt,,r c,,,yt. n (siar y r 61.- ,Y ,

fas r ap, i.h

'4*v 2 i O.5 eatn)

E. Watch Engineer (.75:

C. The concense; avv211a-. "rt.r- ttea aces to the centamtno:c:

. sate- 1-'e- : r at ": ::::: ~. t . ' 2 (FL.fg'] s c n N+ & , ' g ja ), 's ,

  • A .l ,* ' '

det Nsseh f* f ~ lto.~* ~ ~. s e.

.

  • .Pf y n r u l.ro .)

R E F E R E N'_ C Shere a* F-::e. -c 5: ...

'

.. .. : tart Lp, Co.c Snutce.sr *: ..

pe-cent. Pes. . e. pa:et ~ er :te : .' . 2 . 7.4 and 4.b. dry 9 71.nr.n /,.,,4,.

Sh .,es amykes dne w j;, rm ;.t ,fa x ll g j d ps 2 2, w. 0 I ,Q , it., y g.o ,

I ' 4 ." > .' . th. . . . . l-

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

. - _ . _

.:.N e. E ;i ~. + 4

~_.-

e. W:tran  ; n, c. e- ;y- R4 c- i r e- v 3 ; cene- n #:%: eser, ,.

E. i.. e::: 'c 'r.*c- .. ~ 0: t: .cs 1 ;- ma, Occu . 0

.~:

C. Re Pattern :s corre - i. ; e - Reacter Engt cering.'(0,5)

REFERENCE bhe-eham crececure ::. W . l. C;e-atic" Betweea 20 P:t. aac 16 F;t. Pone- Rev. E. ;4aet 2 anO 3 ttets 4.5 and 4.7 2010'.W 5v; ~. e . 0 . t a t.: . . : i- :

_____.. ... _. ..__ _ . . . . . . . . _ . _ _ ___ ____.___._____ ___.-___

- . _ - _ _ __ _. _. _

, e ' '~ 0 t e e e

ANSWER 7.3C (0.00)

.

A. crevent Minimum rica Valve (MOV-026) 4 rom Aute coening 3: .-et .

CS' water into tee Baccress: 0, occl.(1.0)

E. Preven: Stcom Lxraust D: t na ;e Che:> Valvo caeage.(1.v*

AEFERENCE Shorehae P-::ecure 5: 7 . 2 ': . . n l p:.' an: Lessen olaa "' -:32-E" ..*;'.

Syste :: t.

206000v:418 206000A:Oc 206000K60S .. (KA*t)

- - - - - - - - - - - - - - - - - - - - - - . - - , . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

.

..... : '

. .. c. . tr.gu - ? ... n>

,

i I

t I

r

r o . e 4 9 C

9. ADMINISTH47!vE PROCEDU,lES, COND1110NS.

.

.

. ____ .______ ...___ ___. .___________._

AND '. IMITATIONS

___________ ___

ANSWER 8.01 '2.!O)

A. 1. C1 ass)f catao" c' Eme sency

'

.. D:retizac t"e rot: 4.:at:en cd ode site off1:1a!t.

2. Ma.ang c4 4 s: t e r:rotect 2 ve ac ti on recommencatione.

( .'. at O.I6 GaCh'

U. E V' : ' ' t V.2 4' jf,h > ll. <l*asi<~ L **'~b Y' Y'

(g kw.s J., sn**/ /?CM N 5- "**

C* n '- l R '

- (C*v'

4,,, g ,. ,7 f./ . re A O *f> ** />'*'< h l

t, , fyj,, .r s oll frey b sd psy pslus*.s.

CErtpcN r Snocemam E~e-cenev P; am l mp l e + r.- t t n g Pr oc e::u- e 1-: ke.. :; o:,t- .

Eno-ema- Lecce c 2 ... . . i. 1 . St a t t o- L' g e - t : a t ; o - a-c

Ge sonre! Les:maar: 1:i:e. He.. c op. 27. Item E.25.7.. / # 6/ S*7 /" */

. .es....; m.. ... . - n.

. .,- . ..

, c. , ,

.

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

AN5NEC 5. O' t O. ;i:o A. 2 . .' . d . r E. Per.nem int :.pse2ilance.

C. 6 nos-s D. No (0.5 each)

REFERENCE Snorenam Tern. Specs. 3.7.8 pa;e /4 4-99

.10003005- .. (vo's)

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

d

f

. s s s

. .

.

-

ANSWER E.O! '2.t:0)

.

A. h c. (0.50) Not recutroc Dy 1.5. Table 3.3.1.-1 :0.tu)

6. Place the Trio Chanrei in tae TRlFFEDCmd1tica. ( '. . S .'

C. Place one te: p systr.- :" 74!PDLL cenett;cn wgsn:n , move a-;

ce in STARTUR witain d neurt (M51v's eleses) er at least :-

HOT SHUTDOWN with:m 12 meurs. (1.0)

( fn Cid $bs 1b 0 a.fbA IN r'i l 2 4 km Shorenam T.S. 7.2.1 Tacle 1.2.1-1 Shoreaa- r,5, 4:. : Ign g gTE mErp 2,;,1,a, a n e 3, 3,1, g: ,

^':

. e ': , . . t v . .' ' ?

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

A N E .< E h E.Un 2.

U. Pe r 4 c- - 4.E... ...c ri ;* .f.......a.a +y. car ~ c ; t. s t ; W i t *. t r c-hCu r anC D"CG per t. ,, c urs ;nerna+ tee. RcEtore in Car. Cr Oc i' ".*

e- ,

. . - , a; .p, . * c. , 0.'*g 14 '

.

'

MM .t it's [ 2 4*J

't s.o J.y-t n t*~ me -*:' r ** GG * *~,f 7 f ~ 9S

, ,-* - * l w* Ms

m ..

ii.r'.it

  • o s sp+.

p . ; ..

'YNs ,.-;'efbrmps ' p su

<>r u__ ._

.~re :. ta r_ r s._4, o ed e slk~

s.k,, t) f. I'L. o l f;l

[., , ,. 6.,. . . - - . .

ac , ,

  • e

., . - ,e '

+

- +e . ,;;,,tr- ... .g, ,,,

C. " r t * r r L>

  • -

, ' ' p r . r '. e v. *

..

  • -

. Or re*rve '

~

  • 'r* :or s W =E RE N' .

'

E*OPaa* ' O ~. h . . . T. f ' * . 0 ", C . ! *

9 ~ :.

. i..E.E.7'.2/~ E*. '..h. . ..

/* E-14 (2.E.3.1.D.i.)

Oc40M 410: ..(>r*t-

. _ ______. ________ .. ___ ......__ ....___. ..__. __.._____.__ .

r .

. . . . '

,.

?

/*

t- ,

.

ANSWER G.05 (2.00)

,

A. No S. No C. No D. Yes (4 at 0.5 each)

REFERENCE Shcrehan Procedu e EP12.O!5.01. Control of Lifted Leads and Ju :c Rev. 12 page 3 Item 8.1 294001klO2

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

ANSWER 6.06 (C.O'

s A. The e it less cm.arer :- ec::ptent :.amage .i.' a": centc;rme t

mplos.cn(0.5)

S. eC asig (0.5) Becau: e tc leatne- c c u;: . : ;, (E.9' Last) r.

uotures . . . ? a- ct{ Gu ws- of y siiblu b lh j f r _J. %.J.h& s (0. 5)

C. Rev s n;e: . c- .=. c .~; ate- :: ce- . _

'

cita
: - 2 c a. o- .:

,

..r. ..

,

r 1 r, . " '

- s.s rr_ ' . ,i r ..me

.- :s s

. ... .v . . :- . ,

REFERENCE S dOREHP Etutent ranccut WL - E 4 -SW- ; E M-~.R G E NC V PRCCE DUHi.t. C- L' I c .

pp.10 AND Id. _ E S SO:' UEJECTINE CC. f04 /_ yd $g d.!BEIC 2 7.00.V p'w.tf yP, 295024G007 . . (Ko's)

-_--------..----------_---_-------- .----_-----------------_--- --__

e

. s: .- e,

--

,

, ,
. ., .

.

A

.

I

-'? ANSWER B.07- (3.00)

,

UA. Watch. Engineer +: O n 0/f /A7e~c W/ /E y ,,. S frfe k l * y'4 p w ' h-

- E. Minagement on Cal Inc vidual (1.0)

. .

-

'

L

'

c. SP 12.0009.O', Report of. Abnormal Conditions'(RAC) and L t' e t t i n..

-Cone: tic,'for'Cperation. ( 1. O n EXACT TITLE OR NUMBER N0 t .~ RE'.tu !; 5

.il4 w ace y T J ff.,- with J .,fola *d ~rf f~/ .

" RECERENCE Shoreham Procedure SP 12.009.03 , Report ~of Abnormal Conditiontt;cC.

' ant L;miting.Corditic, of Operation. Rev. K p p . ~h-3m 4, G

t.

.,

cc ou.15c<:.: . , ,s c.c - ,

_ _ _ _ _ _ _ _ _ . . -_ .._ ...___ -..._____ .. . __ __________ _ ____ ..

ANSWER. L.09 ';- . t.s v ~.

4 '4 plsnne: t a t ect e- M. b e - as a r e n t.1 * c4'st-veijlance.testt*g'(: .5'

wne-r ro coc raati on a s c c ;.:r r ec . ( 0. 5')

.c. . ;. .g_. ..s

.

. .

.

.s..,...

.

e p, ).-

2 "*Tci ar"t

. s. cp =--.r : : -

"#

'

+ w :;'; do.m -r- 1 rs- --t-:. st: -

'

f , _ -)'

Snorena.- :rorecu e EF 21. W . C . .' Operations ~Repc-ts. Rev. "

pape . tc- e..', page .' iten 9.2.2 g p / ,

.

/ 2. ,

29a no ; % rg ..5 .c

-.... . .__.._ __ __ _ . _ . _ +

_. _ ..._...

-=

,,,'I

?

,

,ne-

T 4 se a s 4

.

. ANSWEP. 8.09 (3.00'

.

A. False E. False C. False D. True E. True F. True (.5 efeni PEFERENCE She-eham P-aceau-o EP 21. C'04. 01. Mat, Control Room - Concurt c4 Personnel Pe.. 11 . tem 6.1 .. Item B.2.3, item 8.2.3.1, item 8.7.2. and item 8.9.1.

294f>0iSGO ..*As

___________ __-..__.____..____....___ _________.________________________

AN5kCu e. t r . . . .u: s A. t"ue C. ta.Er E. true C. truc (.O E ?. "

R E' E Riw_^ E 1r. Cvc u_ s , . .r .-

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

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[fEg"O , LONG ISLAND LIGHTING COM PANY

__ _ _ SHOREHAM NUCLEAR POWER STATION P.O. BOX 618, NORTri COUNTRY ROAD e WADINO RIVER, N.Y.11792 JOHN D. LEONARD,JR.

VICE PAESIDENT NUCLEAR OPER ATIONS SNRC-1400 Mr. William Russell Regional Administrator U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 Post NRC Written Examination Review Shoreham Nuclear Power Station - Unit 1 Docket No. 50-322

Dear Mr. Russell:

l Our Operator Training Division, utilizing the expertise of

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several Shoreham SROs has performed a review of the NRC written i examination and answer key. The attached comments, along with supporting documentation, are provided to assist you and your staff in evaluating the responses to exan questions provided by our license candidates.

l If clarification is needed on any of this material, please do not hesitate to contact Mr. L. Calone, Manager, Operator Training l Division, at (516) 436-4046.

l Very truly your ,

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J O. . }1 cm e' /

onD. Leonard, Jr. '

s Vic President - Nuclear O erations

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Attachments cc: R. Lo l Document Control Desk F. Crescenzo D. Lange (Region 1)

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' * ATTACHMENT TO SNRC-1400

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.. Question: 5.02

    • Response (Answer 2) Also accept single Core Spray pump operating and injecting.

Referer.ce: HL-944-SH1 Rev. 1 page 12.

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Question: 5.05 a.

    • Response: Delete "Rate of increase in" The question asked about what fuel limit is restricted by fuel preconditioning ra 3 than what parameter is limited.

i Reference: n/a

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l Question: 5.06-c.

    • Response: Also accept "Remains as is" for steady-state to l steady-state response.

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' Question:- 6. 0'1 E c.

    • Response: Delete answer'c.2,~ increase point value on c.1 to (1.0).

Re fe renen: HL-106-SH1 Rev. O page 5.

Question: 6.02 b.

    • Response: Also accept for partial credit: Recirc. Pump Discharge Valve Closes.

Reference: HL-204-SH1 Rev. O' page 19.

Question: 6.02 c.

Response Also accept as correct:-they provide dual electrical protection required for electrical penetrations through drywell.

Reference: Technical Specifications 3.8.4.1

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t Question: 6.03

    • Response: Correct answer "A" to read "lights" instead of "loops". if Also add Squib Valve continuity AMP Meters as answer "H."

Reference: HL-123-SHL Rev. O pages 8, 15, 20. i;

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    • As previously discussed.

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, .. ATTACHMENT.TO SNRC-1400

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Question: 6.04 Response: Also accept a listing of just'the items that cause a HPCI isolation; the answer would then be: A and C.

Re fe rence: n/a .

Question: 6.10 i

Response: The setpoint in the answer key show GREATER THAN and LESS THAN signs as they are listed in Technical Specifications as

"Trip Setpoints". Delete these signs or also accept with the opposite sign-l Reference:

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ATTACHMENT TO SNRC-1400'

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Question: 7.02 c.

    • Response: Change answer to Yes. Entry condition is reactor water level < 12.5 inches.-

Reference: 'SP 29.023.01 Rev. 7 page 1.

Question: 7.02 b,e, f

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    • Response: Answer key missing setpoints.

References _ Technical Specifications Table 3.3.2-2 Question: 7.06 a.3

    • Response: Also accept RBSYS Proceso Rad. Monitoring.

Reference: SP 29.009.01 Rev. 1 page 1.

w Question: 7.07 c.

Response: Accept the same answer as in B. The limit is no unstable steam condensation in the suppression pool.

Reference: SP 29.023.03 Rev. 13 Figures 3 and 9, pages 16, 22.

    • As previously discussed.

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Question:' 7.08 f - --

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, '** Response: ' Accept also prerequisite checklist in place of answer ~Al and

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Reference: Any SP 23.XXX.XX-Question: 7.08 c.

Response:- Recommend partial credit be given for the following answer:

Aux. Boiler steam could cause damage to the platinum catalyst in the offgas recombiner (due to phosphates). This answer is found in SP 23.701.01. Question referenced SP 22.001.01. However SP 22.001.01 references SP 23.701.01.

Reference: SP 23.701.01 Rev. 11 page 3 and SP 22.001.01 Rev. 16 page 20.

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Question: 8.01.a.

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Response: Also accept:

4. Makes the decision to evacuate the site.

5. Authorization for workers to exceed 10CFR20, emergency radiation exposure limits.

6. Approve all proposed press releases.

Reference: EPIP 5-7 Rev. 4 page 7.

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. ATTACHMENTLTO'SNRC-1400 f , , ~ "Ptga 7 of 9

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Question: 8.02 Responses a. Surveillance' procedure SP 24.127.01, RPS, RPT AND TURBINE OVERSPEED PROTECTION; SYSTEM FUNCTIONAL TEST FOR THE TURBINE STOP VALVES, simultaneously meets the requirements of all the following Technical Specifications:

1) h: 4.3.1.1 - 1 (9) (RPS)

2) M: 4.3.4.2.1 - 1(1) (EOC RPT)

3) W: 4.3.8.2.a.1.a.1 (Turb. Overspeed)

4) W: 4.3.8.2.a.1.b.1 (Turb. Overspeed)

Therefore,.the candidates may consider three (3) Lco's to be applicable:

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1) 3.3.8.b (already in answer' key)

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2) 3.3.1.b and Action 6 (15 minutes)

3) 3.3.4.2.e (1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />)

LCO 3.3.8.b is a required answer, as listed in the answer key. However, recommend that credit be given for these other answers.

c./d. Key should be expanded to reflect the most restrictive answer that matches the LCO given as an answer in part a.

! Reference: SNPS Technical Specifications SP 24.127.01 Rev. 3

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,. . ATTACHMENT TO SNRC-1400

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.a Question: 8.03 Response: b. Actually two (2) LCO's are applicable:

1) 3.3.1.a (already in answer key)

2) 3.3.2.b.

c. Actually two (2) LCO's are applicable:

1) 3.3.1.b and Action 5 (Already in answer key)

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2)- 3.3.2.c and Action 21 Recomnend that credit be given for these additional answers.

Reference: SNPS Technical Specifications Question: 8.06 b

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    • Response: Accept "Due to radiation conditions" in lieu of "Because'

the leather coupling...may rupture."

Reference: SP 29.023.03 Rev. 13 page 8,

HL-944-SH1 Rev. I page 10.

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Queation: 'e - 8.07 a

    • Response:- Or accept: Anyone who is a station' employee.

Reference: SP 12.009.03 Rev. 6 page 4.

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Question: 8.08 b Response: Also accept:

-Watch Engineer

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-Operations Engineer-Operations Manager Re ft.rence: SP 21.003.01 Rev. 9 pages 5, 12.

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, FACILITY COMMENTS lAND NRC RESOLUTIONS FOR.THE GHOREHAM

SRO LICENSE EXAM OF DECEMBER 1, 1987..

QUESTIONE5.02 ,

Fecility Comment:

(Answer 2) Also accept single Core Sprey pump operating and injecting NRC Resolution:

Comment is valid. Answer No. 2 will be. changed to read as follows: "Single ECCS pump operating and injecting OR one CS pump at rated.

flow to the core". Point value remains unchanged.

QUESTION 5.05 A Facility Comment:

Delete "rate of increase in". The question asked about what fuel limit is restricted by fuel preconditioning rather than what parameter is-limited.

NRC Resolution:

Comment is valid. The answer will be modified to read as follows:

"

Rate of increase in LHGR OR LHGR (0.5)".

QUESTION 5.06 C.

J Facility Comment:

Also accept " Remains as is" for steady - state to steady - state response.

.NRC Resolution:

Comment is valid: The answer will be modified by adding " OR remain the same (0.5) for steady-state to steady-state".(0.5)

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QUESTION '. 01 C.

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Facility Comment:

Delete' answer C.2., increase point value on C.1. to (1,0)

NRC Resolution:

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Comment is valid: It is reasonable to assume that the operators may become confused between the valve and line the way the question is worded. Answer C.2. will be deleted and 0.5 points will be added to the value of answer C.1.

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Quaction 6.02 B.

Fccility Comment:

Also accept for partial credit: Recirc. Pump Discharge Valve closes.

NRC Resolution:

Comment is valid. It is reasonable to expect the operators may discuss this feature since it attemps to isolate the leak to assist LPCI to reflood the core. The answer will be modified to indicate that partial credit will be given for this discussion.

Point value remains unchanged.

Question 6.02 C.

Fccility Comment:

Also accept as correct: they provide dual electrical protection required for electrical penetrations through the drywell.

NRC Resolution:

Comment is valid. The following will be added to the end of the answer: "OR they provide dual electrica; protection (0,5)

reo.uired for electrical penetrations through the drywell.(0.5)".

QUESTION 6.03 Facility Comment:

Correct answer "A" to read "lights" instead of "loops". Also add Squib Valve continuity AMP Meters as answer "H" NRC Resolution:

Comment is valid. Loops will be changed to Lights and new answer

"H" will be added as a possible correct response and will read as follows: "Squib Valve continuity amp meters downscale".

Point value remains unchanged.

QUESTION 6.04 Facility Comment:

Also accept a listing of just the items that cause a HPCI isolation ; the answer would then be: A and C.

NRC Resolution:

Comment is not valid. The question indicates an answer is required for each item with a point value of 0.4 for each response. The answer will remain unchanged.

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QUESTION 6.10 i

Fccility Comment:

The setpoint in the answer key show GREATER THAN and LESS THAN signs as they are listed in Technical Specifications as "Trip Sotpoints". Delete these signs or also accept with the opposite sign.

NRC Resolution:

The comment is not valid. The values are listed as they appear in the referenced training material. The signs are however, confusing and will be deleted. Point value remains unchanged.

QUESTION 7.02 C.

Facility Comment:

Change answer to Yes. Entry condition is reactor water level

< 12.5 inches.

NRC Resolution:

Comment is valid. Answer will be changed to read as follows:

" Yes.(0.25) RPV Water Level < 12.5 inches.(0.25)

Question point value will be increased by 0.25 QUESTION 7.02 B,E,F.

Facility Comment:

Answer key missing setpoints.

NRC Resolution:

Comment is valid but this entry condition does not require a specific setpoint. Credit will not be deducted for use of setpoints and the setpoints will be added in parenthesis after each answer.

QUESTION 7.06 A.3.

Facility Comment:

Also accept RBSVS Process Rad. Monitoring.

NRC Resolution Comment is valid. " OR RBSVS Process Monitor Increase" will be added to the answer. Point value remains unchanged.

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Fccility Comment:

Accept the same answer as in B. The limit is no unstable steam condensation in the suppression porl.

NRC Resolution:

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Comment la valid. Since each figure has an explaniation that

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talks about Unstable Steam Condensation, this answer will also be accepted for full credit. Answer for 7.C.

will read "HCTL or Unstable Steam Condensation (0.5)"

Point value remains unchangad.

QUESTION 7.08 Facility Comment:

Accept also prerequisite checklist in place of answer A.1. and A.2.

NRC Resolution:

Comment is valid. Since this checklist is normally used to satisify these two items, credit will be given if this is used instead of the A.1. and A.2 answers. Answer 5. will be added to the answer sheet to read as follows :"5. Prerequisite checklist complete.(Acceptable if answer No. 1 or 2 NOT used)

Point value remains unchanged.

Question 7.08 C.

Facility Comment:

Recommend partial credit be given for the following answer: Aux.

Boiler steam could cause damage to the platinum catalyst in the off gas recombiner (due to phosphates). This answer is found in SP 23.701.01. Question referenced SP 22.001.01. However, SP 22.001.01 references SP 23.701.01 NRC Resolution:

Comment is valid. Partial credit will be given for a discussion of damage to the recombiner.

Point value remains unchanged.

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Fecility Comment:

Also accept:

4. Makes the decision to evacuate the site.

5. Authorization far workers to exceed 10CFR20, emergency radiation exposure limits.

6. Approve al?. proposed press releases.

NRC Resolution:

Comment is valid. This procedure was not supplied prior to the exam but it specifies these additional non-delegatable duties which wi?1 be added to the answer sheet as possible correct answers. Point value remains unchanged.

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QUESTION 8.02 A.

Facility Comment:

Surveillance procedure SP 24.127.01, RPS,RPT AND TURBINE OVERSPEED PROTECTION SYSTEM FUNCTIONAL TEST FOR THE TURBINE STOP VALVES, simultanerusly meets the requirements of all the following Technical Specifications:

1) M: 4.3.1.1-1 (9) (RPS)

2) M: 4.3.4.2.1-1(1) (EOC-RPT)

3) W: ,4.3.8.2.a.1.a.1 (Turb. Overspeed)

4) W: 4.3.8.2.a.1.b.1 (Turb. Overspeed)

Therefore, the candidates may consider three (3) LCO's to be applicable:

1) 3.3.8.b (already in answer key)

2) 3.3.1.b and Action 6 (15 minutes)

3) 3.3.4.2.e (1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />)

LCO 3.3.8.b is a required answer, as listed in the answer key.

However, recommend that credit be given for these other answers.

C./D. Key.should be expanded to reflect the most restrictive answer that matches the LCO given as an answer in part a.

NRC Resolution:

Comment is valid but not necessary. No credit is deducted for additional CORRECT information when answering a question.

From the information given in the question the candidate may or may not know this surveillance satisifies all three LCO's therefore it would not be reasonable to expect all three be given in the answer. As long as 3.3.8.b is listed, full credit will be given. Answer key will remain unchanged.

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QdESTION 8.03

_ Fecility Comment:

b.' Actually two LCO's are applicable:

, 1) 3.3.1.a (already in, answer key)

'2) 3.3.2.b c. Actrally two LCO's are applicable:

1) 5.3.1.b and-Action 5 (Already in answer key)

2) 3.3.2.c and Action 21 Recommend that credit be given for these additional answers.

NRC Resolution:

The comment la partially valid. The action'for 3.3.1.a and 3.3.2.b are identical and answer requires no changes. The answer.for 3.3.1.b and 3.3.2.c are not the same . The answer for part C. of the. question will be modified such that the following will be added to the end-of the answer:

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(and cold Shutdown within the1 next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) Point value remains unchanged.

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QUESTION 8.06 5.

Fccility Comment:

Accept _"Due to radiation _ conditions" in lieu of "Because the leather coupling... may rupture".

NRC Resolution: 4 Comment is valid. The answer will be changed as requested.

Point value remains unchanged.

. QUESTION 8.07 A.

Facility Comment:

Or accept: Anyone who is a station employee.

NRC Resolution:

Comment is valid but the procedure is not clear on this. The answer will be modified to also accept " Anyone who is a station employee". Point value remains unchanged.

QUESTION 8.08 B.

Fccility Comment:

Also accept:

-Watch Engineer

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-Operations Engineer-Operations Manager

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NRC Resolution:

Do not accept. Plant Manager is the required reviewer. Answer key will not be changed.

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EXAMINER CHANGES TO THE EXAM DURING GRADING QUESTION 5,06  :

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Answer _"C" was modified to enclose "with void fraction returning to about the same value" within parenthesis. The wording in the question did not solicit this part of the answer.

- QUESTION 6.08 Answer "C" modified to read as follows: "and then return to normal OR ba slightly higher than when the SRV opened".

Power will actually be slightly higher but may be hard to see on the instrumentation. The operators should not loose credit.for stating actual plant response.

- QUESTION 8.04 Answer "A" modified to add Action "c" of T.S. 3.8.1.1. to answer key as a required response. It was missed when the exam was written.

QUESTION 8.07 Answer "C" was modified by adding "Also accept any other method utilized at plant". There are several places this information is avaible to the operator and credit will 1x3 given for listing any of these.

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