Text

Exam Rept 50-395/OL-85-02 on 851119-22.Exam Results:Two Candidates Passed & Two Failed Written Simulator Exams. One Candidate Passed Simulator & Oral Reexam
	ML20151R997
Person / Time
Site:	Summer
Issue date:	01/03/1986
From:	Douglas W, Wilson B; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	;
Shared Package
ML20151R995	List: ML20151R991; ML20151R997;
References
	50-395-OL-85-02, 50-395-OL-85-2, NUDOCS 8602060362
	Download: ML20151R997 (111)
	v • d • e

ENCLOSURE 1 EXAMINATION REPORT 395/0L-85-02 Facility Licensee: V. C. Summer Nuclear Plant P. O. Box 88 Jenkinsville, SC 29065 Facility Name: V. C. Summer Nuclear Plant Facility Docket No.: 50-395 Written, simulator, and oral examinations were administered at V. C. Summer, near Jenkinsville, South Carolina.

Ch'ief Examiner: O. h. 9mb W. G. Douglas O 12(26/85 Date Signed Approved by: m , Uk w Sb Brae A. Wil' son, Section Chief 'Date Signed Summary:

Examinations on Novemoer 19-22, 1985 Written, simulator, and oral examinations were administered to four candidates; two of whom passed.

A simulator and oral re-examination was administs red to one candidate who passed all areas.

0602060362 060108 5 PDR ADOCK 0500

REPORT DETAILS

1. Facility Employees Contacted:

T. Matlosz, Nuclear Training Supervisor

J. Heilman, Nuclear Operations Education and Training

M. Williams, Nuclear Operations Education and Training

H. Babb, Nuclear Education Training

B. Williams, Operations

M. Browne, Operations / Technical Support

2. NRC Employees Contacted:

R..Prevatte, Senior Resident Inspector

P. Hopkins, Resident Inspector

Attended Exit Meeting 1

3. Examiners:

W. G. Douglas W. M. Dean

Chief Examiner

4. Examination Review Meeting At the conclusion of the written examinations, copies of the written examinations and answer keys were given to the facility representatives for review. The following comments were made by the facility reviewers:

a. R0 Exam Facility Comments: See Enclosure 4 for facility comments and recommendations.

NRC Resolutions:

(1) S0P-118 is in contradiction with the refcrenced system description. Answer key changed to accept OPEN on inactive loop and CLOSED on active loop as correct answers for Part b.

(2) Agree with facility comment. Answer key changed to accept not available as correct answer for Part a.

(3) Facility did not supply reference on pressurizer safety valves -

l acoustic leak monitor in material used to prepare examination.

l Answer key changed to accept 3 of 4 possible answers for full credit.

I

Enclosure 1 2 (4) Summer's SAP-200 states that " . . . of f-normal operations , . . .

which require signoffs as each position is verified should be present and followed as tasks specified are being performed."

Immediate action steps do not require signoffs. Also SAP-200 does not limit memorization of immediate operator actions to Emergency Operating Procedures. It is NRC's policy that the candidates must demonstrate complete knowledge and understanding of the symptoms, automatic actions, and immediate action steps specified by dbnormal and emergency procedures regardless of where these procedures are located. Therefore, the facility comment is acknowledged, but. is not accepted and the answer key is not changed.

b. SR0 Exam Facility Comments: See Enclosure 5 for facility comments and recommendations.

NRC Resolutions:

(1) Agree with facility comment. Answer key changed to accept calculate SDM per STP as an acceptable answer.

(2) See NRC Resolution 1 on R0 Exam.

(3) See NRC Resolution 3 on R0 Exam.

(4) See NRC Resolution 4 on R0 Exam.

(5) Answer'was not contained in reference material supplied to prepare examination. The facility supplied answer was added to the answer key.

(6) Agree with facility that watch turnover sheet is ambigious.

Part c deleted from examination.

(7) One hundred Rem to save a life is the limit, 75 Rem is - a recommended guideline. The facility comment is acknowledged, but is not accepted and the answer key is not changed.

5. Exit Meeting At the conclusion of the site visit the examiners met with representatives of the plant staff to discuss the results of the examination. Those individuals who clearly passed the oral examination were ' identified.

There were no generic weaknesses (greater than 75 percent of candidates giving incorrect answers to one examination topic) noted during the oral examination.

_ __J

~ Enclosure 1 3 The cooperation given to the examiners and the effort to ensure an atmosphere in the control room conducive to oral examinations was also noted and appreciated.

The' licensee did not identify as proprietary any of the material provided to or reviewed by the examiners.

Document Name:

0LL PROCEDURES Requestor's ID:

PEGGY Author's Name:

shaw Document Coments:

operator license procedures l

1 ENCLOSURE 3 (Part 1)

4. 3. rJUCLEAR FEGULATORf C on nI2 3 I0 rJ PEACTOP OPERATOF LICEt15E EXAhINATION FACILITY: 3UhhER REACTOP TYPE: PWF-uEC5 DATE ADh1NISTERED: E L 1 1 / ~.J li EXAnINER: JERPt DOUGLA5 APFLICANT: _ _M_ _ 5_T_E_R_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

INSTRUCTIONS TO APPLICANT:

Use separate paper for the answers. Write snswers on ene side onl..

5taple question sheet on toF of tne answer sheets. Points for each question are indicsted in parentheses a f t e .- the questien. The passin3 grade requires at least 707. in each tSte3sry ano a final 3r ade of at 1esst 507.. Exsaination ,rs p e r s will de mid ed up si: 4 :i hours sfter the e s a n.1 n a t i o n starts.

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PLANT OFERATION. THEF n X ; N An1C 5 Mii A T T R A r:5 F E s MID FLUID FLOW

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i APPLICANT'5 5IGNATURE

4

1. FRIrJCIPLES OF NUCLEAR POWER PLANT OPERATION. RAGE : i l

T H ER riO D Y N A r1IC 3, HEAT TRANSFER A rid FLUID . L O LJ GUESTION 1.01 'l.00)

During a <enon-f ree reactor startup. critical dats was insovertently taken two decades below tne r+qu2 rec Intermediste'Fmnge IIP level

( L E-lO smps). The :rttical dets S23 t..en tsken st *he prcper IR level 'l E-0E ups: . As um:n3.FCE t e n. p e r s t o r e eno bor an concentre-tien did not :hsnge. which cf 'he following wist+ments is correct?

3. Tne critical roo pcIltion t s t e r. 5t the proper IR level ts t.E35 Tb N the critical :2 ?csition tsken two decades below the pr oper IR level.

b. The eritic31 rod positicn tsken 3t the propor IR level is TF'E SAME A5 th+ critical rod position taien two decades below the proper I Fi level.

, The critical os position t : L er. It tne proper IR level 19 GFEATER THAN the critical too position taken two decades below tne proper R level.

! d. ~here ts not.enouqh i n f e r ai s t i o n 2tven t ,

determine the relationship betueen the crit: cal *od position taken at the roper ~R le el snd the ritical cra position trven two decade; belaw the p r ,p e: IP level.

QUESTICN 1.OI ( 1. 's 0 i Which of the followin3 ststements a e s c r t c. n the rolstienship oetween inte3rsi and differentisi rod worth 7

a. Inte;rs1 rod warth ( t srv, loc:tioni is the slope of t..e differential rod worth c u r .: e at that la_stion.

I j b. Inte3rsl rod worth : st sn. :. a c s t i o n . m - *;e tctal area l undct the differential roc -at tn :iir , e fr:m the eno cf l

the rod to that location.

c. Integr51 rod worth >: st an, I c. c s t i o n ) i s the squar e of the differential rod worth st that location.

c. There ts no relationship between integral and differential rod warth.

(***** CATEGORY 01 CONTINUED ON NEXT FAGE *****)

1 4

1 1

1

1. PRINCIPLE 5 0F NUCLEAR POWER PLANT OPERATION- FAGE I T HE R h0 D t N AriIC 5 HEAT TRANSFER AND FLUID FLOW OUESTION 1 02 (1.00i Which of the followin3 ststements concernin3 ssmarium reactivity effects is c o r r e c t !'

s. The equilibrium st power: value of smarium is dependent upon power level. The p e si. eslue of s a m a r i u rn following s shutdcun is dependent upon power level pricr to shutdcwn.

b. The .e a v i l i b r i u m (st power ' value of : a n. a r i u m is cependent upon pcwer le.e1. The peak vslue of samarium following a shutdown l' s independent of power level prior to shutdown.

. The equilibrium ist seweri / slue of ssmarium is independent af poser level. The pesk salue of I a ni e r t u ra following s Ibutcoun is d e p > n c .' r t ipan - .c w e r le.'el ;: r t o r to inutdown.

,. T '. , e s ~: v i l i b r i u m t poaer ' s e l '> e af ssmsrlum it independent

r. .ower

lesel. -.ne

rest o.oe of -i a m a r l u m f c ,t i o w i n 3 a shutdcun is inoependent of powe, levei ;rior tc shutdown.

QUESTICN ! . 34 .:ci 2hich :( Rs 3: 11:-tn3 : *. s t a i e n t : concerning the resct1/it, eslues af e , c i ; o t u n,

, t p :+2 r 3 r,: : 2nd p e s t. (after 2 n u t ., a w n ' enen 12 cor r ec ti J, 5 a :. .w _- ,coan : : c .s r - f O ra .c g u t 1 i b r t u m c a n d i t l a r,s .

?. Ew11ibrivn. senon i- INDEFENDEU- of poue- level; peak renan i: INCEFENDENT :f :ower level.

b. E r. u i 11 : r ; s n. .enon is INDEPENDENT :i o c r- r level. part .enan

_s 3 E F B:NDENT :n power level.

. E:oi abrlum :enon is DEPENDEtT :n FOver i n '. c . . !

c. e a t :enon

: TEFENCENT af scuer Ic :.1

o. E q u i l i c r i e c. encr. 13 DEFENDEU~ an pwer lesel; gest enon t- CEP~NDENT cn caucr :- e e l .

C A T E G D F '. C1 C O rJ TIN U E D ON NEYT PAGE * * *.* * ,

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1. 0FTr!CIFLE3 0F t1UCLE AR FWER F L ANT C PER AT:0:1, FAGE a T H E R h 0 D Y il A M I C 3 , HEAT T F A r!S F E R AND FLUID FLOW GUESTIDH 1.05 (2.00)

For the followingr state whether the tensile stresses are msximum on the OUTER or INNER wall of the-resctor pressure vessel,

s. Pressure Stres: ;0.5)

b. Heatup S t r e :: s due to delta i only) (0.5)

c. .Cooldown Strees (due to delta T only) (0.5)

d. Composite (Total) Stress during Cooldown (0,5)

QUE3 TION 1.06 ':Z.00)

If steam joes throu3n s throttling .oracess, indicste whether the icllowin3 parsmeters will I tf u,., stn_ - . d E . D-_ etr Em.-.- :- r rt _ , . , - . .n ui .,HE Sn,d t.

s. Enthalpy 0.I:

t. Pressure (3.5

En', ropy 'C.Si

. . Tem crstor= ' 5 T . . IJ.

., {s( ".L _! *1 f t .3. - i ' "' e .*,sT .,

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CATEGOE; C1 C O U~I:10ED OH r4Eii PACE *****

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1. PFINCIPLES OF r!UCLEAR P0uER . F L Ati- u. E: A T IG ri . AGE 5 TH EF n G D Y Na rs IC S . HEAT TRAN3FEP ANC FLUID FL0u OUE3TI0ri 1. C C- (2.00)

A .n o t o r criven centrifugal o u rn p is opersting st rsted ficw. feu then start closing oown on the dischstge valve. How ': I rJC R E A S E . DECFEASEr o- REMAIN THE ?AnE'; will esca ci the icllowing bs : #fected'

's. Flow /O.53 L. ~>1scharge Presure (0.5)

c. Available NP5H (0.5)

d. Motor Amps (0.5)

GUEETION 1.0? (2.00)

An ECP ts calculated ior s -s t a r t o p 4 neurs sfter a snutdown f r o ni !. 0 0 7.

stesdv state power. Indicste whetnat the actus; critical position will ce GREATER THAN. LESS THAN or the IAnE A5 the ECP for the following conditions.

2 , The stean cump lsressure setpoint is incresse_ b, I5 psig. i 0 . 5 ';

b- All s t a a n, g e r.e r a t cg le,el+ ar- m:r;ssed b 5' fi,e ninutes sachac. (0.e.s;

efore :ri .cslit/ i1

c. '.ont;cr :rt : : u u n, is recucec T' "g due to ros11 sir lesL. (0.5) ai ; s._t:r _ : n t o;; : h .syed for 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . :0.5-s s. *

CATEG0F.- 01 CONTINUED ON NExi PAGE *****)

1 1

I. O E DICIF LES OF HUCLEAR F0WEF P L Mi T G F E R A TIi' N . ~ AGE :

T H EF h 0DYrl AMIC i r HEAT TPArJ3FER AM Fi. LID FLC7 G U E 3 TI0ri 1.10 '1.30i ri s t c h the heat trsnsfer process tn : .: 1 u m n A to the equstion that applies to that process i n C o l u nin E; .

CGI.UhN A C LUhri 3

s. E-e t w e e n ccio 193 and hot les 1. ~ = E: AT af reactor (normal FC flow';

2. 0 = 4 m AT

o. Acros= 5 . T- tubes (primary to secondary) 3. G = UA 4T

c. Across 5 /G (feedwater to s t e s n. 4. 0 = m : Ah

5. 0 = maa GUELTIDU i.11 . .0C' For t .1 e Hocerstcr Temr-erst'>re Caefficient :HTC' Ti s t c n the parsneter change in_ Col _nn A to the direction it all c.n zr . ine nTC in :olumn E' . C a r. ider esch case separately.

C O L u ir] A COLUnti E

!. mode at.:r t e c.9 e r s t u r > ineresse2 : Hare % g s t i'. e 2 Earan :oncentrstion i n c r e a s c r. :. Let: N e p s t i '. c

3. .1 rcce in /s. 311 rocs out -

ac Effect

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1. PR.~NCIPLES OF NUCLEAR POWER PLANT OPERATION- FACE T H E R n 0 D Y N A tiI C S , HEAT TRAN5 FEE A t4 D FLUIE LOW GUE5 TION 1.13 (2.50)

Frequent Tiention is made in the Technical Specifications and elsewhere that limits ar e placed on the Departure from Nucleate E. oiling Ratio (DNBR).

s. Define CNBE (0.5;

b. What is the limit on DNBR (0.5)

c. Since the CNBR'is not a directly observable carameter, name SIX p ar araeter s the oper stor monitors and/or controls to-ensure the ENER is not ric12 tad. (1.5)

GUESTION 1.14 : 1.00i Primse systen f l o .a este is .nanv times 3 rester than secondary sy-tem flow rste while the he=1 transfer ec b, the tuo systems is essentially the same. Erpisin how this is pos ible.

aiJ t - i w s! .

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. e. e..

e=.ne the fsllowin3 ' ; r rie s :

s. A ist F l u. D i f f a r .: n c - (0.5i

b. R+sctivit- (0.5>

. ~c'21 Fewer Defect (0.Si GUE5 TION 1.1: (1.50) 3 What is : :01sved neutron? iO.5i

c. Un3 sre oslavec neutrons i m p o r t s r; t ; 0 . 5 .'

. :4h s t happens (and why) to the percentaje of delayed neutrons over core life? '0.5i

i. z a x t

CATEGORY 01 CGNTINUED GN NEXT FAGE *****)

r

1. PFINCIPLE5 0F NUCLEAR POWER FLANT OPERATICr4 PAGE 5 THERMODYNAhICS. HEAT TRANSFER AND FLUID FLOW GUE5 TION 1.17 (1.00)

The reactor is operating at 507. power with the rod control system in MANUAL when a single Group A rod dropc into the core. As sumir.g no reactor trip or operator sctions occur- indicate how the fin'al stesdv state values of reactor power AND Tave compare to their initial values.

QUESTION 1.1G (2.00)

Given the following, calculate the required boron chsnge to_incresse reactor power f r o n. 7 57. to 100". while maintaining constant rod position.

Moderstar Temperature Coefficient -15 pcm/ degree Doppler-only Power Coefficient -12 pcm/% power

.' loid Resctivity change -25 pcm Xenon cosn3e -50 p:m Eoron Coefficient -9 pcm/ ppm GUE5TIOi! 1.1: (1.00)

( . e x c '. c r power incresses from 1000 cps tc 5000 :ps in 30 seconds, what is the 5UP' GUE FION t.20 '1.00' If the Summer reacter is opersting st 1007. powsr with Tsve=Trei, what is tne .:1us cf REE subcoolin3' (tua* END OF C ATEG':s f O !. *

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2. PLANT DESIGN INCLUDING 5AFETY AND EriEFCENCY 5 Y 5TE ri5 FAGE ?

GUE5 TION 2.01 (1.00)

-Accoroinj to 10CFR50.46, which of the following is NOT s design criteria of the Emergency Core Cooling system subsystems.

a. The calculsted peak centerline temperstore shall not eaceed 2000 de3rees F.

b. The msninura cisddin3 0,:idstien shall not exceed 17% c,f the total clroding thickness.

c. The esicul.stad totsl amount of hydrogen generated from the

ladding r e a c t i a r, with water shsll not exceed 1% of the amcunt that aculd be genersted if 311 c1zdding surrounding the fuel rescted.

d. Calculated chsnges in core geometry shall be such that tne core remains arae n a b l e to cooling.

i.t . r. : S J. u N. . e U s,. 'L.OV:

'4 h i c h of the following ficaps ths cescribin3 hcw sawer is normally supplied to i t fFicsl vitsi instrument bus :s :r re:t?

4. 4 3 0 '! A +'. fr:m vi' al bus, rectified +.c 1T lDC* iiverted to 12 0 ',' A C

snd EUppIied iD i ts s i T V 6 :- r ' O t.> :

b. 2 3 6 i) A C f r c .T. i l i 5 '. dVS* I, P i n 3 i ~, F 0 9 'i t: [20 IIACf 3nd SVpp119d to I n s t r ora e n ' b

c. l ~ T 'lO C f r

Ts ;3ttyrv. 20pplied tc c s ', t e r ;gg. jnvertcd tc 1 2 3 '.'A 1 ' snO %Upp1ieC t ;- i n : '. I i1 E r t !VJ, j, 4 3 ~i 1A1 ~ . Th /L*si bes? ie:t.I GG t ^. 120 'l C

Gnd supp1ied t ~, i r. g t + . ,, ? ri fi U i.

t a s 's s " f, T E 3 C p 'f ) [ O N T 21U E C Cs N E!I SAGE 177VJ)

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i-i OUEETION 2.0~ it."O' 4

.; Which cf the t'c I l c u i n j ststement.s describin3 the design ci the '>el

. trensier.tuce is correct?

a. A blind flan 3e is usea to :1cse the trans'er tube :n E. G T H t h e c o n t a,i n ,1.e n t side a n c' tne spent fuel ride,

c. A blind 'Isnge i 's usea tc.: lose the transfer tubs an the I c a n t s i n t.i e n t side and a v.alse is used on the spent fuel side.

c. A .sive :, s used to close ths trsnsfer tube on the contain-ment side and a blind fisnge is used c ri the spent fuel side.

'. A /sl ee is used to close the transfer tuce en BOTH the cen-l tsinmer.1 side snd tne spent fuel tide.

.. s

,-] , C., es . t . . I3 * ' t. .4 6 +lst n/

i ha 12 NC puap sesi leskoff is norosil. collected in which of the

,n...iowing-

, t. C a n t s i n ,ti e n t Sump 1

b. Fretteriner Relief is-J c, '!clume Centrol Tank t o o 2. a n ,. D r s i r,

d. Fes: tor .i E nt.

i 4

J+1E37ICH 2.05 (1.00)

~he ?/G 30FV's -7. s imun, cspscity is limitcd 2 ,> o e ; 3 r. - t c spproximstely i ", c f 'sted s t e s n: ' low. Which of tac follouing ;; the rosson for inis limitatten?

3, S intaina nass dischstge r-to within the capscity of I

t h. c^nien;e- nM eup syrtei...

b. Lianits plant cooldown rste if :i w on: C'V ettens open. :

i :. n i r,1 m i t e s possibi,tity of 2. ._v differenti:-i Prcssure __ s .i ,

if any c r.e FORV sticks open.

c. ni.imi: 3 erosion of PORV valce c c- 1. t : .

t I u. 2 5 4 CATEGGRY 0; CONTIHUED ON NEXT FAGE *****>

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2. PLANT DESIGt! INCLUDING 5AFETY Ar4D EhEFGENCY E Y E T E riE FAGE 11 OUESTION 2,06 (1.003 s An undervoltage on s ,.2 kV safeguseds bus ~ occurs :O seconds after the receipt of a Esfety Injection signal. Uni'en of the fellowing state-ments regarding sequencing of loads onto the safegusros bus is correct?

3. All loads eccept Losd E lod il ar e s tr i; ped anc the E5F Losding iequence is reinitiated once toe CG output breaker is closed.

b. Sequencing stops until the DG output oresker is closed st which time it continues from the Foint st which the under-voltage occurs.

c. Sequencing stops until the CG output breaker is closed at which time only the ECC5-related equipment sequence will be einitisted.

d. All lo sds e.:cep t the ECC3-relsted oquipment are stripped snd only the ECC5-related equipnent sequence will be continued once the DG out. cut bresker is closed.

QUESTION 2.0- t 1. 5 0 :'

Indicate whether the following connecticos '; *Me 12in 3tesm s v s t e rk tsp off UP5TREAH or DOWNE.TREAM of to+ m a i r. stesa isolation esives,

s. 4tmospheric steam dump ssives +v.51 b., A t nio s ph e r i c PORVa .0.5'

c. E.t s e g e i n -seo ' ump stesa s r.e p p l ., < 0 . 5 :-

QUEETION ~. . M ' : . 0 :'

Indics'c u h .2 t h e r t.c '311caing vsi.es - c 2.1 ' EM :: C L C I E D -. t ' a tn. r e ac to- o ;- e r s t i r< : . r. ,

noce 1 It 17 ; " row;,

3. R 4 ': T - t o - P H 9 cene suction us'ser .

ti'.' G - I ~ ;A i E (0.5i

b. C C W - t o - Fs H P Ho: 1 s o l s t i c.n celses i m V P :'5 0 % !. E> (0.5)

.: . RHR 3.estem train crcssccnnect /sives -: M '!G - 9 3 :1 A !. E ) (0.5i

.d . RHF hypess f1w control vsivas (FCV-605A R E) ( 0 . 5 :-

- - - - CATEGORY 02 CONTINUED OH r' EXT PAGE x *. * * * )

2. PL ANT DESIGtJ INCLUDING SAFETY AND EriERGENCY SYETEH5 PAGE 1:

GUEETION 2.0? ( . 5 0 :.

TRUE or FALSE?

The blowdown connections for all three 5/Gs use s common blowdown heat enchanger to cool the blowdown fluid prict to discharge to the Circu-latins Water System.

QUESTION 2.10 (2.00/

ria t c h the RC system penetration in Column A to the correct locstion in Column B.

COLuriN A C O LU riN B

a. Excess Letdown 1. Loot A Hot Les 2, ::: G Hot Leg

b. Alternate Charging .. L o c rs A Cold Leg

4. Loop 9 Tald Leg

.- R H t. Cooldown Euction 5. Loop C Cold Leg

. Lces G Cold Les

d. P:t - Surge Line GUE3~ igd 2,11 it.CO'

t:h

h -: :CF sesi -low 'estas in Column A tc the appropriste design flow rste 2. r. Cclur,n B C O L U n >2 A COLUHte E

, i : u .- e. a f ' n t c. t,c F.C5 1, 10 c.'nt E, 10C cc 'hr

.:. . l~ seal leakage I. 3 gph

, ! 7po

c. I ns; lesisgc ] gym

> > 3pm it**** CATEGOEY 02 CONTINUED Di2 tJEYT PAGE s * * *.* i

2. FLANT DESIGN INCLUCING 3AFETY AND EhEF GEriCY n3TEH3 FAGE 13 GUE3 TION 2.1 ::.0C The following questions are concerned with the RHF System.

a. What THREE interlocks must be met prict to opening the RHR inlet line isolation valves (9701A :. t 6702Al? (1.0)

b. What' interlock will automaticsil closc the RHR inlet line i olation valves? (includt setpoint) (0.5) e What is the bases of the RHR inlet-line relief valve capacity? (0.5) dUESTION :.15 (2.00)

3. GLher thsn the thermal barrier heat exchanger. list THREE reactor building loads supplied by the Component Cooling Water System. (1.0)

b. Gther than relief valves. what festure prevents overpressuriza-tion of the CCu Evstem if s ther mel bscrier hest enchanger tube ruptures? (Incluce utpoint. if spelicables (1.0)

DUE5TInN : 14 (1.00:

W h <. is tho '. i t h i u m h s d r '_ S i d e (LiGHi v3co to cortrol RCS pH made from the isotope lithium ~ in st eaC of nators11 3 s cur r in; lithium which contains the taatope lithium-d' OUESTInt' .15 l1.00i 6

_: 1 TUO relief .3lves that discharge inte the 1/ c l u m e Contrcl Tank.

G UI 5' T C r3 7. ,1 s 1.50) uhet 2 ignal s. must be p r e s e r. t fcr an AUT1hATIC switchcver of h section of the RHF zy; tem f : o rt, tne RW5T to the rasctor buil din g r e t ir cul s t i cri sumps to cccur' Give setpoint(si snd coincidence /s if spplicable.

<**us CATEGORY 02 C0tCINUED ON NEXT PAGE *****)

2. F L A r1 T DE3IGil IriCLUDIrlG S aFE T'- ANC EriERGEr4CY 3Y3TEiis FAGE la GUE3TI0t4 2.L7 (2.00)

Which components of the Reactor Bu11 ding 5prsy zystem are sffected by:

s. A Phase A Contsinment ~ solation 51gnali (1.0)

b. A 3pra. Actustion 5ijnsli (1.0)

GUE S TIO r4 2.18 i: 1.50.i The following question 3re associatec with the normal service gas decsy tanks.

s. How many normal service gas decsy tanks are there? (0.~i

b. Normall,- how often is the ir-service tank switched? (0,5)

c. Why is the w3ste. gas distributed sn.ong sl1 normal service gas decay tanks in=tead ci filling one tank at a time? (0.5)

GUE3TICH 2 to (1,00i List fit)E Icads off cf 7 . : - L '.' bus 10A (IDE). Do 40T include redundant losds (pumps A a n c E: count ei o r.e losdi or feedera to other oosses.

QUE5TIGH ~. 0 '1.:0.

Whst it the porcase af th- Sarsi:e Water boostar pumps?

O l J, G 3 i A. U il .[ . s .L)'

Al ; wet Dhe rC11C% vin] ivest10n3 ConCernin} 1he EUlO"]9hCy Feed R u tli p s .

a. Whst i5 l. h e l i SOrmsl ICUTCe Of W t ?" I 0.5i

. L e 4 '. .: $ h e i r- sch up ;cy~ce ct u 3 t .;; r i i.~

c. Unit rh'fts tr e supplv from the normal 50urCC tC the b5Ckup i*ct v 7 5etRCLnts snd CincidencC DOI reiviTeG. 0e5)

- - - - CATECORY 02 CONTIr;UED CN NEXT PAGE *****i

. _ _ . . .. - -= . - _ . - -

I i

?.

i d

1 Z. P L Ai!T DE3IGt1 INCLUDING 3AFETY AND EMEGGErJC, ~YSTEMS FAGE 15 i

GUESTION :.Z~ : .00s

! Explain-the TWO ways in which the d r eir e l i s c.s i n t a ined near opersting temperature while the diesel is idle, 4

i i

i 4

4 4

f i

i 1

1 K 1 8. *

EiD OF CATEGGr.t 0; erse 4

4 t,

t t

f I

i I

i f

4 J

d i

f r

i

3 IN5TRUMENT3 AND CONTROL 3 ' AGE li GUESTION 3.01 (1.00)

Eank densoci grcup counters receive up snd down signals f r c a, whira ct the following?

3. CRDH lifL coil sssemalles

b. Rod C o r.t r o l Svatem logi: csbinets

c. CRDM A snd E cct1 s a seaclin

d. Rod Contrel E, stem power c :fc i n e t unit TiUE3 TION 3.0 ' 1, M i Indicate ahethat the followirg ccnciticns will cause the Stesa Dump Svstem to A P ri GNLY. ARM ! DUMP- Or H M' E N O EF~ECT.

4 ISVJ dCde. I-I V 3 C h s h n e l Isi12 i lJh d i. -' 1 J s 3* ':er Linute 10sd (educticn. (0.3)

c. i a v:3 Mcde. fir s . stsge press.,re : F i' - J 4 7 ) fails low with Tavg 1.5 d e gr ee s F grester thsn Tref. -

(0.5' 3UFIT:0R 43 / 1. 0 0 ';

Ir.c t : s t e u.i e t h .s r the follcuing 1.stfunctice.s i n .t.; e 3C4LC 3vstem will result'in a LOW. FIGH- or 90 5<G 1 eves t r 1; s:gnal. Assume initially the reacter is at 75% power with 1. ' r, : eve': st pro 3r en.

.; jest p i e l s '.' r e ( G e i I i t ',. C O.% p e n I 3,10 re 3iJn: 3 ? I C 1. 's .n1Jn. 'U. v Y, b N .

b e ,00N. lFdY

( s r s r .* CATEGDF.i 03 COFTINUED GN NEXT F/4GE ***r -

o .

3. INSTRUMENT 3 AND CONTROLS CAGE L7 C.UESTION 3.04 ( I . 0 0 :>

Hstch the neutron detector in Column A to the re3 i on in which it operates in Column E..

COLUMN A COLUMN.B

s. IPM - i n n e r' chsmber 1. F: e c o m b i n a t i o n

2. Ioni:stion

b. srb 3. Oroportional 4 C e l'3 e r

c. PRM 5. Continous Discharge

.i . Incore OUESTI0t4 3.05 (1.50' Hatch the following reactor ,rotection : and control signals in Colunn A tc. their associated logic ccincidence in C:lumn E.

COLUHH A COLUMN B

a. 2 loop loss of flow trip (per loop > 1. 1.':

2. 2/2

e. F-6 5 F n t u t r. - o n c r. Power de:recie: -3. 1/2 J. Z/3 c, PEH higt power rod stop (power in:resse) 5. 1/4

s. 2/4

~. 3/4 00E TION I.0c (1.507 O m : :- c i' e whs' esch of the following 3 team Cump Ivstam status lignt:

.indicite a ' F E R M I 3 '1 5.

atstus light c i .n s .

b. '3TEAh DUHF CONTROL' atetu: li 3nt . '. w., i n = t s : '

c. 'PERMISV C ~B PB-447E' st3tu= li30* c . P c e r. . ~ C . 5 :e iar*** CATE30FY 03 CONTTHUEE 06 UEiT PAGE * * * * * :-

a

3. IN3TF.UMENTS AND CONTPGLS CAGE 13 OUESTION .5.0~ +: 1. 0 G i Describe how 5/G 1evel i s maintained between 0 *: and 15 *. reactor scuer.

Indirste the source of any control signals and a;: pli c a b l e setpoints.

GUEITION 3.03 /1.00)

L i s t FI','E o u t p u t s o f the Fressuri er Pressure msster controller. NOTE:

F:edendant cotpute c o u r.t is one. i.e.. Pump A and Fump E. . .

i GUESTION 3.0; (1.00)

The cold overpressure protection system (COFS) provides an slarm to warn the c;ser ator thst overpressure prctection is isolated. What plant conditions will -: s u s e this alsr2 ~

nLsc: i t,-]a .

.. ..r- _

i

'J .' t h t h .: J essori.:ar leu l : o r.t r o l switch in F c s i t i o n .I .- cescribe how,a hi3h f ailur e of LT-45~ ulll effect setusl pr es tor i: 3r level. Assume novas, c h 3 r -J i n.3 snd letdewn system lineops and m. operster actions sre

+ s i. c r . Cor tir U. thG -je t : ^ i; t i o n ..s n i i l of'C55Uri~_Or leVG1 i s C '3 n s t 3 n t Or r - " I* 4^tGr i #ip ACCU

5* I n .1 '.' .i e - )

l- 1 : ' } ' W 2 rf- * ?1iCS01ee At.W9*y.m . q g at f

?' t- m L 1 NO b $ 6 *d e The *%il. win 3 :ves'; nh a r +. sssocirted wito the Fasctor Control Unit ot' t,. ; o C ent , ,; 5. ten

. W h s '. :

y,313 +re ..ed

. to jenerste the temperature error sijnal~ i.0.5)

'J ': . ? i r t]*il- 3r9 Osei to >J G ri e f S t e LDE POWGr OrrOr fi3nsl? (0.5)

'-i st i - b52 ,- rr,050 Of the / i r i 3 01.. 33ir 3pplled to the power

+ i ! *[a ' ! 3 T, 8-.V.e.V!

+ae*** CATEGDRY 0 3 CONTINUE 0 Gri NEXT F ACE

n .: * * )

3. INSTRUMENTE AND CONTROLE FAGE 1*

.0UEETION 3.11 .1.50)

List IIX cod. control interlocks. 3etpoints sre NOT required. Redundant interlocks only count once, i.e., Channel A hign voltage and Channel B high voltage.

QUEETION 3.13 (1.00; Arrange the following Rod Control Svstem components in their proper physical order, starting at the power source.

RX TRIP 9KR5, CRDh, dG SET, F0HER CABINET OUE5 TION 3.14 (1.00) i 4 hat is the reason for using s wet bulb RTD for tempersture instruments which provide inouts to the Reactor Protection System?

GUESTION 3.15 (1.50; List ALL inputs used to csiculste the Over Temperature Delta T trip setpoint.

QUESTION .3.Lc (t.00i What is the setpoint AND purpose of the 'T AVG HI' sistm?

GUESTION 3 . '. ,' (1.00)

Describe how the F Rii si3nals 3ro ccmpared to give sn siirm on abnormal flu > distribution in each of toe f ollcuiri3:

4 Power Rsn 3a T h s r.ne l Current Canpstator < Si O. Pcwer E s r.g c Dete: tor Current :, n. ; ; : t. cer <

~.E'

(***** C A T E G 0 F 'i 03 CONTINUED ON N E:i T F- A G E ax:ax

}..

4

5. INSTRUriENT5 AtID CONTROL E FAGE 20 GUE5 TION 3.13 (1.50

a. What TWO interlocks aust-be satisfied ,rict to Tianually resetting s ssfety injection signal ~ (1.0)

b. After resettin3 ssiety injection. a u t o ne s t i c sctuaticn is inhioited until whst signr1 is clear ed? (0.5)

GUESTION 3.l7 (1.50)

What siignals will cause a feecuater isolstion? (3etpoints NOT requitec) a, 1

GUESTION 3.20 (1.00) 1 Describe the interlock sssociatec with the resctor tr ip bypass breskers.

g. Ut . .3_ ._u.i - . .

r. , ,.

a. , ..en..f f Pro..oe the R'!LIS indications for ill THREE c a n .3 e s ( 'J p ,s e r . Narrows and u a rir. for e full sessel at 10f, ANI 07. flow.

, g p, . +r T. pJ rg

. J . m-_- g.t . er, ,

Lis! IhEEE : / I ( 41s s f 3r whiCh the A C C U E ". 1 C i. O s , . h;rsitarin3 3 y s t e ns ;; r c '/ i d e s indiC&t13ns F' s l e s i, .

, .,w-i g ,i c- : - L a, *_ r ; -- fa j .e t.z. -}

.e -,

O' N I .5 i3 c 5/m001 ICf th& follCLing

4. A TI O /0,5) a, - t. h. :s. t u . e- ,'

..V e . J I "3 I4 5

.sdlllC1denCe !

O U i. CT.

.! iN*e.J'

**** END GF ATEGOR'( 03 4xsis) l

.= - -- . _

'4. PROCEDURE 5 - NOPHALr ADNORhALr EMERGEHCf A!4D RAGE 21 RADIOLOGICAL CONTROL GUESTIGH 4.01 ( 1. 0 0 :'

Which of the following is NOT a Critical Safety Function'

s. Subcooling

b. He,st 3 i n t.

c. Suberiti:ality 2

d. Inve.ntory GUESTION 4.02 ( 1. 0 0 :'

According to ~0F-2.1 ' Post-LOCA Co:idown and Depressuri sticn'- which of the fc11 cuing is NOT a ptaper i n c;i c s t i o r. of natural circulati:n?

4 RC3 col: leg t.: ais e r s t o r e nesr s a t u r s t i. o n temperature for 5/G prr.ssure.

b. .C3.subecolin3 3reater than 5C Sejrees,

c. Core nii ther moccuplet itsbis sr slowl, oecteasin3

c. Cr .ielt; > # nip e r s t o r e I T: c 6 - T:o ld :n ecoal to full pcuer or.:ta t c nip e r .:: t u r e ,

1

. . n c .: - - m-- :.., ., e.. . , > ,

Unich ;f 5 ;-. 2 fall: .ng :: NOT sn i r. p u t into etermi.nir3 conrcrmance i with ins ea ct s: rar e 5sfsty L i nt i t s i

.: > Y ' >: s 5 0.*^ i : 01 Fr&siure

. . Loe s t :::c atin3 Loop Flcu

, . -,ermet r o w .:. r

.S . H 13 ree J t 3psrsting Loc.p Tav3 1

k*xx* :ATEGORY 04 CONTINUED ON rJEXT F/GE : a***i l t

i l

l i

1 FROCECUREE - NORMAL, ABNORMAL, EhERGENCi AND PAGE ::

RADIOLOGICAL CONTROL QUESTION 4.04 (1.00)

During 3 natursl circulation cooldown following a reactor trip, which of the following criteria determine the amount of RCE subcoolirig r equir ed?

a. RCS cooldown rate.

b. Reactor power history (decsy heat rate).

c. Fressurizer level.

d. Number of CRDh fans r u n n i ri g .

GUE3 TION 4.05 (1.00) i The trip bistables of a failed power range detector are pisced in the trip condition by which of the following?

a. Placing the applicable bistable test switch in the ' Test' position in the Reactor Prctection Cabinet.

b. Removing the applicsble centrol and instrument power fuses an the power range drswers.

c. Flscing the 3ppit;sble Power Hisaatch B pssi switch to the failed pasitisn at ihe N i s c e l l e ris- o u s Cer,t r c 1 end Indication Panel.

4. Flecing the applicsble Comparstar Channe'. Defeat switch ta the f r ile ' c h a ntie l politim. s4 1:.e E e f .- ;

o r Current Comparstor mel .

GUEETIGb 4.06 .1.0:~

Which -: f % folicwing ts - 10 ~ ~ ~i N o: 1. air' 2 3 ien.,,esr - anole bcdy

b. I rem / quarter - whole body.

c. 16. 75 r e a, ,v a r t e r - hands.

d. rem / quarter - akin of anole body.

( c a r s.

CATEGORY 04 CONTINUED ON NEXT FAGE *****)

J. PROCEDURE 3 - NORMAL, ABHORMALr EMERGENCY AND PAGE 23 FADIOLOGICAL CONTROL GUE3 TION 4.07 .(1.00)

Which of the following radiation e:<posures would inflict the grestest biological damage to man?

3. 1 Rem of GAMMA.

b. 1 Rem of ALPHA.

c. 1 Rem of NEUTRON.

d. NOME of the above; they are all equivalent.

QUESTION 4.03 (1.00)

Which of the following describes how the point plotted on the Inverse Count Fate Ratio curve is calculstedt 4 1 divided by the ccont rate st snv specific time,

b. The change in count rste divided by the initisl count ~rste.

c, The initial ccunt rate divided by the c.unt rate at anv specific t i ai s ,

c. The char ge in : o u r. t r ate d i .1 :f e d cy the finst count rate.

OUE5 TION 4.00 (1 50 Which of the f o 11c w in 3 i.ie l f unc t ions will result in botP- a high Tivg ind . :st;;n and a Iw delte T andicatiorJ

z. Hot leg ~rt.fsiled high

a. Hat lag FTD ' ailed Icw

. Cold : ?3 cTC f?iled high

6. :old l e s F. T :e f211e6 low

.:*<.* CATEGGRY 04 CONTINUEC ON NUT 04GE a=***s

4. FROCEDURE5 - NORt,AL. AENOFnAL- EnEFGENCi Ar!D PAGE 24

- ~~~~~~~~~~~~~~

~~~~5:7655EUG5CAE~53i155:0E ~ ~~~

GUE 57IO ri 4.10 (1.00'

'lhich of the following statements describe the cooloown/depressuri stion sequence of E0P-4.0, 'Stesm Generator ruoe Rupture'?

a. Commence rapid cocidown; depress; rice msintstninj subcooling simultaneously with cooldown-

b. Ccoldown to 520 degree 3: -depressuri:e to 1500 psig: complete cocidouni complete depressurication.

c. Cooldown to required temp e r si.or e ; depressurire to required pressure once cooldown is completed.

d. ~ c m aie n c e 'spid :ccidown ind depressurization without limits a oli subcooling.

u ,h- r _.za

..I ,

....t u . v .., )

'Jhich of the below s t s t e nie n t : descriae the FCP trip critsrla (cllowin-3 i EI witt normsl containnent canditions7

s. Lesi than 30 d?3rac: ; b c a a l i e. 3 A rid pr le-el less *han 4 '; . ,

c. , Les s .t:.sn d a 3 r t .e - o bc 0 ;; 17,3 Ar'D II f1:w . c r i f i s.:. .

CI preaavr :eez +. an ' 3C . ,2 13 AND II~ficw serificc.

d. RCE r r e s s.o r e let: thin 1330 pi;j AND p:r lovci less than 4%.

ul,_: i . ,. r 1 -

.. & . m..

!f e :id 2 tst: in *he , : s c t .: r .essel w i ' ,1 sll GCFs itc:: Ped. which of the follow:nj set; uni is used to collspre t c. e scid 3: cording to EOF-

!?, . ' F .s i s c n c s ': '.' c i d s la R e s .: t a r '! a s t e l ' !

] 3. De:rcs c 1 mFerature while m; int 31ning system r- r e s s u r e ,

b. Star t s 3I pump tc .t n c r e a s e :sstem r- r e s s u r e while k eeping t e m p e r -s t . i r c. :onstsnt,

. Inc r os se system : essure using :,ress.ri:er hesters while msintsining ptessoriner level,

d. Fill pressurizar solid and sent the reactor vessel head.

( * * .*.*

CATEGOPY 04 CONTINUED ON NEXT FAGE *****)

4

4. FROCEDURE5 - NORMAL, AENORMAL. EMERGENCY AiJ D PACE 25

AOIOLOGICAL COF'_ROL___

GUE3 TION 4.13 (1.00i In the process af determining if 5I can be terminated- it is d e t e r ri t o e d thst the secordsry heat s i rik is available. In which of the following situstiens could SI be terminatec if sdverse :entsinment conoitions exist?

FZF L '!L IUBCGGLING FRE55URE

s. 2 0 *. 20 d=grees stable

b. 45* IS de3rees incressing

c. !?% 35 degrees increasing

d. 4 0 *. 40 dagrees stable GUEETION J .1 1 :1.~0; Accordi 3 tc the Immediste Correctise Actions for a totsl loss of re cic_ water- indicate whether or not (YE5 or NO) the following s ;ticr : sre performed.

s. Trip the reacter (0.5)

b. haintsin reactor at no-load Tavg (3.5)

c. Trip the reactor ccolsnt pumps (0,5)

GUESTIOtJ 4.15 (I.50

Incicate the nunerics1 valveis) sssocisted with the following precautions.

Ms.;1mem cifterential pr es sur e oetween FC_o anc . . .s,u. u . a .-

s.

c. Ma.:imum differentisl tempersture between r. c 3 i c a r_ 3 , (0.5;

c. Ninamem r ?. E flowrsie prict tc snd ouring RC5 diivtions. iC.5)

d. M s.: t mum rate of poser i r.c r e a s e sbcee 20% reactor power without m s n r: g e m s n t a p p r o v a. l . ( 0 . 5

e. M a a i.t u m RC3 temperature during FHR cperstions. '0.5' 1

1

(**t** CATEGORY 04 CONTINUED ON HEXT PAGE *****-

4. PROCEDURE 5 - NORMAL. ABNORHAL. EMEPGENCY AnD PAGE ~6 RADIOLOGICAL CONTROL QUE3 TION 4.16 (1.00i List the actions required if the sctual critical rcd positicn is soove the low-low insertion ~ limit but differs from the estimsted critac-Il position by more than SC step 3r and less than the m?nimum r ,d aith-draw 31 limit.

GUE5 TION 4.17 (1.50)

Answer the following questioni c oncer nin 3 the requirements.sasocisted with doing s reactor startup.

s. 14 hen mu s t sll Shutdown Eant rods f ailly withdrawn be ,erifted? '0.5)

b. How many licensed ; Ferstors must ce present in tne Cont? 1 Roon; E. e specific sa to what licenses 5. r e reovirec. (0,5) c, If the s tar tup 1 - deleyed. when must the E a t in,s te d C r i t t : a 1 Ccoiition esiculat. ion ce ne.tewe;? '0.5)

C'j E .'IO N 4.1? ,.ac' 4wn i- . * {11 4eq * - .- t , . .e r c -i conte:-;

~ i i r t, o .2 .x u e r a r. e r s t 1 c ri s e $ .

GUE1TI3N 1.L? I.00'

!., C r r e c I,1 *5 L '$ ,~2 U r 3 ,- b]

.1 c . I o r. ' 3 ' + l [ * +~

_Il '$ 1 $ 5 k, r2 ,sl ,i e .4.Il! m 9 C,1 $ b c 'e' 6 '5% a -

Ai '567. Puu97 i n t- f D i l :. 6 : in g i l d f ra s CCCui " . iF ' '. t ' a ' i l '-

' CP A tt Si 5.h0FF rLG HI/LC' 2no ' sci A 4i '. ;F .0'

.C.,* ' i ( *.

. "..-( i*%*d.

U "1 A f. 3re khe $in fl 9 d i a t e ( O I r tt c t 1 e's A c t 13 '"t 8 5- r ~. 2 0 . i 2 0 i I' t d *? .' O f ' ] i n 3 f}OW control <BlVG (ICV-11E fBil: 10 s e d W r' l l e L T, N t M i' 1 : ~ Mtf01 3 r. '" .e L i l not 'espond to 3 'lidrival O in Jn35~

i***64 COIEOGIY C3 C O d I [ilO E[ UN NEY^ PAGE T****

l

l J. FROCEDURES - NORMAL, ABNORMAL- EMERGENCY AND PAGE

~

~ ~~~~~~~~~~~~~~~~~~~~~~~~

~~~~id656E665CIL 66Uf66L f

GUESTION 4.21 (1.50)

An Immediate. Corrective Action for a feedwater oooster pump trip-limits

plant load based on.the numoet of feedwa*er booster pumps still in service. What are the plant losc limiti,tions with the following j n u ,wb e r of.feedwater booster pumps in serei: e?

l 3 3 (0.5; l b. 2 (0.5) l c. 1 (0.5) l

[

QUESTION 4.22 4 1.50)

Other than identifving and correcting the malfunction, what are-the ImmerJiat e Cor r ec t ive Actions for s diesel generstor trip f ollowirig an

[ emer37.ncy start' l

l OUE571GN 4.23 (1.50)

Whst see the Immedi.ste Corrective Actions if Gr20p ~ 1 snd Group 2-step

ounters of E s tJ D roos differ t '. morc than 1-st:F GUE37IGN 4.24 3 . 0 0 '* .

List the Immeciste Orerator Actions for s Resctor Tr ip.~5 s f et. Injpction.

Just list the actico. not how the scii:n :s sc:cmF;1shed.

(***st. IND OF CAIEGOR 04 *24=i)

(**********~s** END 0 EXAMINATION ***************)

/

1. PRINCIPLES OF NUCLEAR ?0WER LANT CPERATIJN. ; AGE 23

! THERHODYNAMICSe HEAT TPAN3FE- AnD FLUID FL0t>

A N ? tJ E R S -- 3 L'h h E R -5 5 /11.' 13 - J ER R f DOUCLA3 ANsuER 1.01 ( 1. 0 0

b {1.0) pt:

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NUS. Nuclesr Energy Trainingr nodule 3 Unit 3 Westinghouse Reactor Fnysics, Sect. 3r He> tron Einetics and sect. 5 Core Physics HBRr Resctor Thecrye 3essions 20 snd 24 - 31 _

DFC. Fundas.entals of tioc l es

Reactor Engineering- p. 236 0 01,'0 0 0-K 5 .13 (3.1/3.6)

ANIHER 1.0: : 1. 0 C .

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. ANSWEF 1.05 (2.00i i

s. IrfdER (G.5i

s. DUTER /O.Si

, c. INNER : 0 . 5 :'

d. INNER (0.54 ;

REFERENCE 4

NUS, Nuclear Energy Training --Plant Performance. pp. 10-1.8&7 004/000-K5.07 ( 3 . ' 4 . 2 )

1 AN3WER 1.06 i'.00)

3. REMAIN THE I A rit (0.5)

b. DECREAEE (0.5)

! c. INCREASE (0.5i

d. DECREASE (0.5)

EFEFENCE

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2

c. INCREAEE (3.5) !

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+. ww r ,- .q:cn:e.. - c . u3 . e, s

d. DECREAIE iO.St i

4 i Pi:FD ENCE j' C3n.eril Fnysics, HT - rF - rioid Flow Ara l i c a t i dr. f ict 3 - s t e a. s a rid C o rn p a n e r". 5

i ') ; , ,'JU. - k, ,J e U 1 *JessJek.I s

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i i _ _ _ _ _ _ _ _ _ _ . _ _ _ . _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ____. - _ _ _ . _ _ - - .

d i 1. - PRINCIPLE 3 0F NUCLEAR POWER FLANT GFERATION. FAGE 30 1 THERMODYNAMIC 3 HEAT TRAN5FEF AND FLUID FLOW ANSWER 3 -- SUMMER -35/11/13-JERRY DOUCLA3 f

j ANSWER 1.08 (I.00) i 'a. DECREASE (0.5)

b. INCREASE ( C . 5

c. INCREASE (0.5)

d. DECREASE (0.5)

_RE.ERENCE General Physics, HT & FF. pp. 319 - 334 ANSWER 1.0? ( .00)

3. GREATER THAN (0.5)

6. LEEE THAN (0.5)

C.

anML Hs (o.c) J

6. GREATER THAN (0.5)

REFERENCE NUS. 'J c l 3 Urii t 1:

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1. PRIi4CIPLES OF NUCLEAR F0WER TLANT O c E P A ~ ! O rJ .

e :-

THERh0 DYNAMICS, HEAT T C:Ar13FER AND FLUIE FLOW Ar15WERS -- SunnER -35 1: ' 13 -J E s t ', ECUGLAS ANSWER 1.14 ti.00;'

In the secondsry systera there is 3 mosse :h:nje ..! :' . A scasc change re'uires

- i a large delt n. W:th tac : rgc- delt3 r. of tne

ecandery, *he s s ci e heat csn be trsniterrea 4 tn .s lower .au rste (0.5 pts'.

PEFERENCE General P h v 'I t c s . HT & FF. Section 3.2 .

002/000-K5.01 '3.1/3.4)

A rJ 3 W E R 1.15 (1.50)

a. D i f f e r e r. : e in ncrmaltzed f lu. 2 3 r. : 1 : ; ,

s : r. +V ' o :: ana ;++cm halves Cf tGe IOTe. ~ .5

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!. PRINCIPLE 3 GF rJUCLEAR F GWEF ? !. AHT 'cFCA :'d. FAGE 31 ;

THERHC0YNAh!CS. HEAT TFAN5FER AND F L 'J IC TLOW i

AD54EPS -- GunnEF - 3 5,' i l .' 13 - J E R F Y GOUCLA3 ANSWER 1.17 /1.00'

1. Fins.1 pcwer = initial cower (0.Yi 2, ~1ns1 Tave initial Tsve (0.51 7 i

NEFERENCE NUS. Nuclear Energy Training - Rescter 03erstion .

ANEWER 1.18 (2.00) isve : 30.4 X 0.25 Y -15 = -114 pcm (0.4)

Fower; '25 Y -12 = ~-300 pcm (0.4)

Void - 25 pcm Xenon: - 50 F:m Total: -aGi pcm (0.J)

E;o r on : -423 -9 = 54.s ppm '52-5e) iO.4)

Dtlotion (0.4) t e r t w. t ri t t We s t ;r.gnoo s e .Juc l e s e Tr sin t o 3 Opor r *. ion s op. I ".27 - 5.26 0 .i,.'

. O ,.e -i, ,; . a_ _

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A r13 4 EP 1.17 '1.0Ci t.4 CFn (4.5 pts. for n tng corr ec t egostione 0.5 pts. for snswor) s.t.v> ,

EEFE Er4CE NOi. Nuclest E ,w r T. ~reinin3 - Reactor her3rion. o. s.4-2 u e s '. i rg n o v r e % s. : . : t invsics. F. 1 a.1e Hb - -s : tar T, e o r . . :essian 43, p. 3

'i P . . r unosment als of Nuclear Eeactor E n ,11 r.e e r i r j . p. 24 0't/000 ':5.40 r . ; . 7 / 3 . 4 'i

1. PRINCIPLE 3 0F NUCLEAR POWER PLANT GPERATION. FACE 24 THERMODYNAnIC3 HEAT TRANSFER AND FLUID FLOW ANSWEFS -- IUhMER -GS.11,13-JERFf DOUGLAS ANSWER 1.20 (1.00)

That = 587 + 30 = s17 degrees (0.33)

Psat = 2250 psis, Tsat = 653 degrees :0.33) 5eocoolin3 = 453 - o17 = 36 de.3r ee s (0.33)

REFERENCE VC3 Systems Lesson Plans. Rod Control System i Reactor Coolant Svstem and Steam Tables 002/000-K5.10 (3.3/4.1)

-A1.04 (3.9/4.1)

2. PLANT DE3IGN INCLUDING 2 A F E T t' AND E ttE F G EN C Y 3 ( 3 T E r15 PAGE 3" AN3WER3 -- $ Urine F ~35/11/1G-JERRt 000GLA3 ANSWER .01 (1.00' s

REFERENCE 10CFR50.46(o) 006/050-PWGf35 (4.2,4.2)

ANSWER :.0 (1.00) a REFERENCE

'J E G F , Training Text. '! c l u m e 3 rm .

15b-3 and F13 16b-1 ! 6

'J C S , GE-:. Safeguards Power system. pp. 27 !. 25 AN5WER 2.03 (1.003 b

FEFERENCE CAT. FC Le s s or, T e;: t . c. 11

'J C G . G3-4. Fuel H a ri o l i n g 3/ sten. :.4 0:4c000-L:,.01 i:.1,-3. +

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ANSWERS -- 5UNHER -35 ' t 1 '13 -uCF F f DOUGl.A-AN5WER I.12 (2.00i

a. 1. RW37-to-RHR suction val /e closed r h y r, - r3 3 0 9 ) (0.23)

2. EHRI-tt-CVC5 1scistion .slse closed (MVG-3'Os> ( 0. r -

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).33

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b. RCS Pressore greater than '00 pt:3

c. Discharje c o rt o i n e d flow of all ithree' : a sr 3inj comF S . 0 5' REFERENCE VC3 A E4 - 7 FHF i s s t ei . pp. 13 1 14 005'000-04.01 .3.0/3.*i

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a. i0,3i Condensato StoraJe T a n k.

b. Service Water System i0.54

c. Low suction pressure in Emerjenc. Feep Foa.r. m ader 0.5 F:E F EF Et3C E

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heater to norn.3} w :: t ar - c o o l e r, can e nnentt. (1 0

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SIX AT 0.25 POItJTS E ACH

1. IRN.Hijn F1.> .

2. FRM Overpower

1. GT Delta T

4. OF Delta T

5. Tieroine Fower 15 ', -

6. E;a rd D witherswal l i a.1 t (220 steps

R EFE REtJ CE VCS, IC-5 Roc Ccntrol, p. 37 ANSWEF 3.10 (1.00) nG SET, P( TFIF E4 G 3 F 0 u E ,1 ': A E I N E T . :F C M . .

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nf4 WCP .) . . V i ..JJ..

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NCRMAL. A E r10 R M A L . EnERGEtCr l ARID FAGE 4' FACICLOGICAu CGNTR0L i Ad5; EFS -- 3UnhER -G5,11/13-JERF( DOUGLA5 1

b i

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i i '

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4. PROCEDURES - NCRMAL., AEtiORnAL. EMEPCENC't At 0f FACE 50 ,

_______________________________.________________ t 5ADIOLOGICAL~ CONTROL i l

AH5WERS -- SurthEF 35/11/13 ,JEFR( 000GLA.i

(

t ANSWER 4.05- (1.00) j I r

! 0 !

RE FER ErlC E :

nN3 AP/2/A/5500/16 Case IV. p.9. . [

CAT, AP/1/A/5500,'16 Case IV, p.14. -!

l VC:5 50P-404. Eaco r e rJI Sys tem e p. 16 l 045/000-A4.03 (3.2/3.9) i ANSWER 1.06 (1.00i C ,

R EFE RErJ C E l 10 CFR 20 101 l 1'

000<040-K1.0; (2.5/3.1) [

i f

i At!E W E F 4.0~ (1.00 i i

1 REFERENCE I I

10CF6:0 052 ,-r5.04 /3.2 3.5)

. I l !

AU9WEF 4.03 (1.00i i C i

. t i F EFE F EtlC E ;

l VCie G G F - A p p e n en a 0, ICFF Flot. c. : l i

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ANSWER 4.09 (1.00:' f I

i 1 ,

i W.

4. PROCEDURES - NORMAL, A E: NORMAL, EdEFGENC'r AND PAGE 51 PADI0 LOGICAL CONTROL ANSWERS -- 3UMnER -55/11/13-JERRY CGUGLAS REFERENCE VCS, 30P-401 Reactor Protection and Control System, p. 17 ANSWER 4.10 (1.00)

C REFERENCE

'J C 3 EOF-4.0, pp. ; - 13 ANSWEF 4.11 (1.00.'

REFEPENCE VC3 E0F-1.0 p. 10 AN5HEF 4.12 (1.00) c REFERENCE

'C3 EOF-13.2 c. 5 A tJ 54 E 0 4.13 ( 1.00) d REFERENCE

'J C S , E0P-1 0 p. 12 000/00?-U3.24 (4~.1/4.6)

Ar!3HER 4.14 i:1.50)

5. rE3 10.5;

b. 90 (0.5)

.: . NO 'O.5) 1

4. PROCEDURE 5 - ff0RMAL, A E: N O R h AL . EnEFGENCi A"E F A C .~ 5:

-~~~---~~~--~~~~~~------

'RI655LU55 EEL'CUiUR5t ANS9ERS -- 3UhhER -35't1.'15-JEU r DOUGLAi REFERENCE

') C S . 20P-11.. Service Water System- p. 3: A H AN5WER 4.15 (2.50.1 (0.5 F0 INT 3 EACH)

a. 160 0 p s i ci

b. 25 cegrees F

c. 3000 spm u.a . - .. , ~ . ,

y-

e. . oegree5

~EFERENCE

C 2

. GOP-Appendi; Ar Generic Operatin3 F r ec sue,te ns. -, 2 3 i 5 AN5 WEE 4.16 ' 1.00

1. Centinue with ? 'U <0.5r

2. Eecal:viste ECC .0.5

..e-r .cr e.c t_ fir. r. .

C5

. GO'-3 p. IC ANiWER 4.1- '1.50, 3, u i t h t r. 15 ntnotes :f : c n.m e n c r j - o n t. r : 1 ::n> ; ; + .M r s a r l . .5, D. I U.t 3 "e i C. I W D C .ii 1*: SEO 11:enIOC.. :

c, u;t:.in # hcur pr;ct tocritic;1i'.. .5 2.

. .t.r- e. ; . p e ru

+

: 3

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. F: ,wc r ; 0 *. A AaJD reREATC A. T H AM life 04

2. A n -j position 15 s t e s. s i c i rit i' '

5 FE EFENCE

'J C E . C0i-4, p. ::

.. a. .

L

. FROCEDURE3 - NORMAL, A B r40 R M A L . EMERGENCY AND FAGE 53 EADIOLOGICAL CONTROL ANSWERS.-- SUnhER -5 5,' 11/13 -J E R R Y DOUGLAS ANSWER 4.19 (1.00)

Close the iCP A seal leaFoff /alve ' PVT-5141A)

REFERENCE VCS. 30P-101r Rea: tor Coolant system. cp. 51 ! 5:

i 2 ANSWEF 4.20' (1.00 1, . Feduce letdown to 45 3pm :0.Si

2. C3ntrol F:r level usin3 (locall FCV-122 bypass valve (XVT-0403) (0,5)

REFERErlCE VC3r 30P-100, C ')C 3 r pp. 37 1 39 ANSWEF 4.21 (1.50'

s. No restriction 80.Si

b. 6 0 *. (0.5?

. Miniwo . m i snt loro /0.5) .

, FEFEF ENCE

'/ C 3 3CE-$1)r E?RIW4$9I 9 / E t d $s r Op. 35 1 3 f ANEVEF 4. : 1. 5 0 .'

1 c> set a e ciu r t : a; r,ersoced, if apptzcsole c c . r .'

~. naent3r: 1, F1sce CACITEF swttch in 5HUTDOWN 0.Si i

3. Deeress SEH ;ELAYG FEIET ovenbottan 3,5i R : r u- t r> C E VC5 3GP-306 E te-T r 3 e n c / Diesel Genersti're p. 5 i

j i

i

e**o 4.- FROCEDURES - NORMAL, A E.NO R M A L . ENERGENC'r A N C- P A C.E 51 55inE5E----------------~~----~~

~~~~5d555E555C3L ANSWERS -- SUnhER -35/11J13-JERRf DOUGLAG ANSWER 4.23 (1.50)

1. Stop sny changes in reactivity 40.51

2. Place rod control system in hANUAL (0.5-

3. Adjust Tavg by sdjusting turbine load (0.5)

REFERENCE VCS, 50F-403 Rod Centrol and Position Indicating 3ystem, c. 14 ANSWER 4.24 (3.00)

(0.2 FOINTS EACH)

1. Tr ip R:: manually (0.1 pts.) and verifv R> Trip '0.1 pts.)

2. Ensure turbine trip

3. 'J e r i f v st,least one E3F bus energi:e:

4. Verify 5I actuated

5. Ensure FW isolation

6. Ensur e NFW pumps tripped T. Ensure EFW pumps running E. Ensore SI pumps running 7 Ensure :hase A Containment Isolatior

10. Ensure RECUs (0.1 pt.) in 'ow spend 0.1 t' .

!1. En. ore ; su pumps (0.1 pt.- :n fast !??cd v).1 pt.)

12. Ensure I SW boostet pumps running

13. Ensure CCW purop s running

14. E r. s o r e H s i r. Iteam Isolation. i' tc 4 Ira.

15. E n s u r e C E. i r r s y J 0 '.1 pt.1 and tha o - I ? c i s t i : r. '0.1 pt.>, if rcquired REFERENCE U C ,r, - Ecr-:, . e. -- .

o p l

f i

ENCLOSURE 3 (Part 2) l 1

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5. THECRY OF r10CLE AP F 0tJEF l'LANT G E ; ?. *- ~ 0 r. . -

.2:. . : : .t: : 2

.i r1

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Of 4 0 0 9 *' m Et 2 diEChE!90 +V 6 :' 0' '_ I ;* '71: 5 *e?!'it i 7 - - ~ T 's e ' II'd.

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. : cense u.1 .- :. t tne +;41osin3 7

s. G ,e 'c:n; cf at sm at 0 ,aII.

c, ~ ne :Oun of E t e 2 r., 5t 300 ps;3

. T-c .cano: :- stesa st : ~.

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5. THEOF't OF HUCLEAR POWER PLANT OFEFATIC'- ; !:TC E . ANC FAGE I i Ht th0D i r4 Ant u :

GUtdiA0.f, c .t- ' .

,t . e u Which cf the t']Ilowing e.:oress the r+1sti:nsnip between differe.tist red wortn (ORW7 and integtsi rod warth :!FW'?

5 "FW :s 'he sicpe ;f the IFU r - :n that lecstion.

o. ;L :s tne src: onder t,- ~F0 cor.( 3t thst location.

. OFU is the sgosce r: ct of the IFW st taat location.

d. Tn+r+ .- no relationship c e t w e e r. DPW and IPW.

uUE 's ' u t' l ~. . o ~- i L . 'i ai9 s' The :- t m o s p h e r i c P O R ') for ' E. ' 3G .srttsliv o ens to a throttling oosition outing operations at 2 5 *. :ower . Unten of the following descr1 Des the state cf the iteam ]n the sownstresm +13e cf the POR')?

a. wet 5 team

c. 5vpurhasteo 5tessa

. Satorsted Eteam

5. 3storste 1. i x. i c JUE57I3: 5.06 (1.00>

The resctor trips from full powerr equilibrium :enon conditions. 51a ncur a later the reactor is brought critic;l st 10E-5 anps on tne inter-mediste rsnge. If pcwer level is maintsineo at 10E-G smps whlen or the felic*ing statements concerning rod motion r eavir ements for the n e :, t two nours is correct' 3 .' t. o d s will hsve tc ce withdrswn : r:c e encn will closelv follow its normsl cuild-irs rsts following : trip.

b. Reds will have to be inserted since :enen -111 closelv follow it s nornsi decav rete following s tr1;.

c. Rods will hsve to be rapiolv inserted since the criticsl reactor will cause a high rate of o'urnout.

d. Roos will have to be rapidiv withdrawn since the critical reactor will cause a higher than notmal rate of build-in.

(****.* CATEGORf 05 CONTINUED CH NEXT F AGE *****i

F 9

5. THEORY OF HUCLEAR POWER. PLANT OPERATION, PLUI:E. AND PACE 4 QUESTION 5.07 (1.00)

Which of the fellowing statements concernin3 the reactivity salues of equilibt10m (st power.' ;enon and peu iafter shutdown) venor. Is corrett?

Assume shutcown occurs r' rom equili' c ries conditions.

s. Equilibrium vanon is INDEPENDEDT of ;cuer ;c.el; peat enon is INDEPENDENT of power level,

b. Equilibrium senon i+ INDEFENDENT of power leveli peai . e n o r, is DEPENDENT cn power level,

c. E quiller ium ;enon :s DEPErJDENT cn :> awe- le. ci t tesk . .enon is INDEFENDENT of sower level. .

d. Equilibtivm enon is CE;ENDENT cn s o .a e r le.el; r- e s t -enon is CEFENCENT cn power lesel, jut 1T N ,

s. v-

.rce the f .: 1 '. c s i n g , s*.ste w o e t :1e r the tsnzile str.3 3es 2re m a :. l a.u m a r.

as ecT__

t 2r . r.. " . tr

-- .:-21 ci. tue - e ac t or treasure essel.

e, ~~ ;25.ra I si: 'v.S D. WC .7 ' i' Si'Ois 1 3 .' 9 tO del'2 I O r.1 % 2.5 C. 2.3 c 1 ' c t.4 n 3tTes3 due 'o

, ~91t3 I' Cn1w $ . 5 l'

a. !;m;O:its '~ ;*.-11' Etres! Qv*;n3 D;l.;Lr O.S'

t " _: T. T--c +'.1 ~. . ' : - . O. n. .

I' . e ~ esc'*- .: ;persting ;* [J*. .cWer s.- e -

FC' *c.

. E 4 ? i s it i n j

.. ~=-*mr -

. -- 'y : i r.e 101. . 1-738 . , . .

m .

r. :

a en, 4.st.- t ?,c ',15

2 ,.1 2 4 i i j

. '3 3rsistere Ai3..1 -..L iff h . n c i

L t L ' L -1 .-L* si 'L' **f. f ~df .

iOW l t. 3:e!2 ting re30 tor C L ' l E r. ,s 1330'2 .r--

3 c-

. ...s . - I - +

'. ' .dk.. % dea' 2 1 desCk3r 915ei de4 3 .3 I 2

~

d. C p e r s t i r. 3 locs stesm gener 2 ter pressera

> s e s t .s Cn,Ttuo-. r1,.c .- . .

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'.c ,s.; E m i 21q .q _ . r. .. . u- . e .-

N 3 I Cii *,e' d 003* f. T i O 5 iaT T ~=. *2 5 3 ;D C 71 V i?i G $ l .: t .'; y 4 q u 3 ,1.: t Ti 6 il 3 t

- 1 . . . - + n. a. ,. .

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-4 i 1 . E . _i . : 11 0 ~5 3 : !t :. *l0 E f f ;. ; t, 4 Il> 5 !.4 p - - al f life 3 tLuardi

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4

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i t2 . e r E E s T 2 u ra .* -* c-PO4Et. r n ,.i.i u- - . n r2 e a

e. i H .r ..O r - O r- N U 6 ::. n ni - c nut 1

QUESTION 5.13 (2.50)

Frequent mention i s a.ade in the Technical Speciftcstian; and elsewhere that limits are pisced on the Departure f r o n. riu c l e a t e Boilin3 Pstro

( D N E. R ) .

s

~

s. Define DNER 0.Si

b. Whst is the l i ni i t on DNBR? *).5-

c. 3ince the DNER is not a directiv coservsble c. s r a m e t e r , name SIX parameters tne operstor monitors and/or contrcls to ensure tne ONER is not violated. I' . 5 ) l GUESTION 5.14 t1.005 Primarv s s t e in ilcw r:te i s many times 3 rester than secondsrv system 4

flow - 2te wnil - ths heat tr atisier r ed by the two systems is essentially the ame. E ; ,: I s i c. hcw this is possible.

,. ,- .: : ,m. . e.

3, uhen r +: t E : ,ith ;aff I. the ihu tdv . .3in / I D ri s hi s t ' con ser:fied w it h i r. 4 nours ;rior tc crit::allt- H i' 1.s tnis veri-

,tca

,s, lon s c c c u. t i s .w o r

.1, ;.

4 c. ':b s t i: the WP l i n. i t with Tr e 250 degrees- t ] . 5 '-

. N :, m e 3D *::t- I thst 3c into 3 3Dh :sici1:tt:n. -

1.5-

,7 t i r 7 ?. ? g p

- . e.*._-

s

,- .QQi. :

.,4 e S $ f g ' e i

i i

i 1

er*** CA EGOEY 05 CorJTINUED ON D E .' ' ; AGE *****)

h t

h i

e I

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

-u 0, t_.

. E u- ni' u F r4,J C L .tn E r 04E.s F L r,oi.. .'-.E .~ ,., l. st - - -. e4 .cw

. .iH T H E F, M O D i ru n E 3 G L,-.p_: ,. 10 r. J -11 .

. 1. v,.>

s. With reactor power grester t. n i n 5 0 '. . anst 1. --

> : . inom 0.ca.5 snt Power Tilt F.stio ~ 0FTF - thtt : s r. c: 1:+ w1*.: -

t '.1 r. y 1 : n. ; t ; t i : . :

cn plant operstians. : ,5

. g-b.

Tn.e tecnnical .s ecificas ioni 4

I. . ca :. : e r :4 < 1ori . 2 - - aw tinie a - ' . . + c, e tericu W i t. 0 3 6

ta,- OT. 1 rester s i g r. '1;+ n -- + , .J..ngt i3

, e_ o_ _ 1 *

. u .3 r.s.e. . - * -( *

. a ,w, ri fat #. .s. ...-

s.As i

,1. {.lt~ c_ *i I Or t e.t.

s e - i. 1 . ,-

i

'h3t W Cr4 the nE ; i :ii U q; E n -; n ; ri ; & U h +,1cusel. ,;[ygg :t as M0:gr3 tar Tem:erature Iceff1:1ent .. h e r. *nc e.o- . crit.:3;7

- . . - . e-

. . U, w - --1.-

r_ J- 4 e ,2

i __

[' 2 1 r- t a". e f:1 1. Tt j i i 7 ;

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~

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'311CwiG3' 31 '< e - *n- . t . .js e,. 4 4 -- + , . - ,_.,+, ,

, :e_ _ .s- . . T - __W6_T

-- 3 v. c.- . 4, ,s 1,...-. .,

-..g. C...- .,.;+ 2,.- ,4 -J, -:.i- -> - 2 4 - + v.-

- j. P 1 -- d a P " - "' n T P. 9 r 3 ' :.T a ,3'f.: ;," 11 ' -- J r ?

- ' ~

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~. 0 _ p i .; - - : r

..- .i ,.

_.: : S- - t .- .snga < _

. g n j rg r , g .; g

. .:. . 4 - . -

_2 .~r T O R _Ge* tlc 100t 4 23 ~- '- "I e.

~"

i rtat* [ f ".; ~~ !, 2 .', T E C. O E ,

' sss**

(

f P

t 9

(

4

it d. eo C, c :. .1G. . .n. . s. ri g u., L . c, 3.u .4.,..,,._., ,. ..., E .-

n _ _ _...ii.

_ r unr .:s... :

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ n t :,i n ,. I o. n GUE3 TION e.01 "1.00i Which of the fallowing flowpaths de s c r i b i n.3 : Tow ower is n o r m a l l ,-

supplied to a typical vital i n s t r a::.e n t bes :s cor r e:t; f 5. 230 VAC from sital bus. rectifiod 'o 125 VDC. Invertea tc 120 VAC, anc supplied te i n s t r u m e r.t b i. . : .

e-and s i.m p ,. t e d

,c,

3. -v ,v. . t, t r c a. <:tsi 003

,rInsic meo to i _. .'. c .4 1 :- i r, s t r v m e r. t bv2.

e, 125 VOC f r o ti b?tterv. supol;eo to bsttery cus. invorteo i to

._c ...r u. .

sno supp.ied 3 to i n s t r u th e n t cas.

l 2, 430 VAC ' rom .its1

' bue. rectifien tc 12C VOC. snc supplied to.in+trvment bus.

4 J

j

',L,E 2.i 2. _ u

_.y:. : - ._ 1....

} T; c ;/- F 0 ~ 'i ' s ms.iitem c:::c * ,

i s l i m t + e -i 0 ; ;. ; L y, to a pp r c.: t mi t elv i

6 *. of sted steam fisw. L ei; : n ei the i c i l w ; r. 3 1= tne .eason for inis 1 kO k ,E CD

5. N31nt3im? %?2 3 d i i c !1 G r 3 9 "ite wi*nic

r"":ci+' -

f tht : 3 r4 C e n i . ? i. : i tek EVile4.

i l b. L l i. l Ni "

-[t ~ ' ' ' 0 0 1 *. 0 =J T

. P 5 '. 9 L[ 50- . = b- . *iT* 5 OED .

I ~. niftimi~.EE 05IIC11'.- T* I ~ di ~- 'Gr.'!' ' I f e ; 3 -If C 51 1i in, c r,0 C :~ E 'l :'.kI C en, (J + .

4 1

. .e - . ,<- .#, s f' *, ; '

a . . t =

7

-a *.._ :

- .6: < '

h J

r 0

4

. g e. ee . ., ..in . y em.. *. y== == -4 .-

o Yt I..'.e f el 6 0 $ eg -mm enb)*- ~ $ N

i s

a i

I e

-t +g-emv--w---,e-. _ye-,w,*vv w e--- %..-m-=w-my-rwm.,-cw-w,,y-,, ..,=,er-y-,yom,----y_-w= .-wre-.-ww-wr,--v,---&~v.-,.-+w,~

.-rirn-

. . . - - . . , et. . my - . el4 F J._- . ,. ,

c. .r L n, b. - - t w. . ,-:, _ .

L,tn ty , n .1 . r ,, v t -

,3 .u r. r. 's T s.u .e. ..-.a ~1...--

An ,ndervoltage an s ~. kV s af e 3c a r d s ous occurs 20 =econds siter the receipt of : Safets Injectior. signal. Which of toe following state-ments re3seding sequencing of losds cnte the safegustas bus is correct?

s. All losds e.-cept- Lose Elo:6 4: are stripped sno tne EEF Loading 3equence is reinitisted once the DG output oresker is closed.

b. Sequencing stops until the DG cutput breaker is closed at which time it continues from tne ;: o in t at which the under-901t~ age occurs.

c. Sequencing stops until the DG output breaker is cicsed at unich time only the ECCS-related equipment Le::vence will be reinttisted.

i. All 10scs e a c e p t, the ECT3-re1ated equis..ent 1 sre strippec and snly tne ECC5-relatec equipnent sequence will be

. continued cnce the CG v;tput rester 15 :lcsod.

tv,,, r e i .T_i p

- 4..14 i...,.-

Which c/ the fallcwing f .c e' r r d i t n .; c.:19 c nen t s ire ,neumaticsily

' P ti

s t e t I

3. 3tud i 9 fe i 10 re e r

o. ' ED Sh;ft Unist;hirig Io31

. U erCing hsChine

c. CC C n t r, :_1 r,3 71;ture C3r r ia3s

- mas CATEGORY 06 CGNTINUED Gti NEXT FACE <r***i

1 9

6. PLANT SYSTEME DE5IGN, CONTROL- AND IN5TRunEr2TATION PAGE 10 GUE5 TION s.05 (2.00i Iridicate whether the followin3 valves are normally OPEN or CLOSED with the reactor operatin3 in Mode 1 at 100% power.

s. FW5T-to-RHR pump suction eslves (hVG-8309A I 6) (0.5)

b. CCW-to-RHR He> 1 solation valves hVB-9503A i Di 0.51

c. RHF system train crossconnect vsives (MVG-13GTA 1 5) (0.5)

d. EHR-bypass flow control vs1ves (FCV-605A & 5) (0.5)

GUE3 TION s.06 (1.00)

Indicate whether the statements below regarding compensstion of the intermediate range detectors sre TRUE or FAL5E.

a. If the detector 15 undercompenestedr- indicsted power will ce higher than sctusi power while in tne lower decades of the intermediste ran3e. . (0.5)

t. . If the tetector is overccncen stec, the rat. af increase (5UR) indic:ted will be lower t h s r. the actus1 rate f increase while in tas loacr decsses :f the intermediate snje, iO.Si G';E E T IG N d . O ,- i2.00)

Ir.d i c s ' e whether t. h e Over Foser Delts Temperature trip setpotat will IrCREASE. DECREAEE- or FEMAIN THE EAdE fer tne ~follswing pstsneter chsr.jes. Consider each copsretely,

s. Incressir.3 Tsv3 :.5'

c. Tsv 3 less *han rsted sewer T z .' 3 : .5'

c. Delts I 's e c o rn . ii 3 ro o t a negative L.5:

4. Freasor;cer Fressore 1ccressing /0.5

(*r*** CATEGGEV M COrJTINUED ON tJEXT PAGE **'***

1 4

i 1

4 e

1 1

3.

e ,_ n .1 e -.(-

3 bi Er.u-v E a I t, N , .od.R~uL-

.- i nND

. r.3ie t i . _rb. E r %. .. to H e ,., b e. 11 t ------------------------------------------------------ -

s 1

i i GUE5 TION 5.03 : 1.00) ;

t

} Indicate whether the f ollowing conciitions a t il csose ..

,r e i+. aim C o ni o !

., y s ,. e m t o n. r. .rt O d L ). , n R r1 c DUH.r+ or H n. , , -,t t; 0 c. r r r_ t e l

i 7n i

1

3. Tsvg Mode, Tavg channel f3: 1s htqh durin: 3 2 - *. ': n as t ro t a ' sd -

TeOUCt1GD.

- ..L

.i I 1

.0. i .3 /1 -

doder r i r .s t st:qe ,ress. : e c - - , .+ rsi.s t t:w attn . ;,-

j ~

l j 1. 5 d e a r e c- s F : rester t..sn T r .:- f . ( 0 . 5 'i ,

t 4

4 I

GUESTION 3-.01 ~ 1.C:

Whv t; the l i t h t '. a. .v. d r : 1u : L10Hi - -o &c :cntr :1 C3 pH tiade f r a. tne 15 10'15 lithium-7 1 h E t E L ". GT *tatOf215% ? :Urrinq lithium which COntGini f;

- E 9

~

1 1

.6 t. .dI, .1. ! -+d .

4 g.V- 1 .s.-J .'

5 1

E b3 h bb b b2 h +

I** 5 sb b 4 4 b b 4e ) *e dV(tlbb g i ~

+i3

~

1,Dk I ) 04 $ I. .4h D15 be * . a 1d1bh Ie i col 5ti b l

+

5- *a ,7 I ~ . *_ c i . .' ' $ i 'e ti ! G t P. d i fi ~ E in! S if a ;i d e' . E if if~.1LC-Eble. r 4

1 , , , . - . 4 . --

l

- t- r_: AJ. !. . 7. .

I 4 'e 2 34 E Ies 8 Y C i. . .. k 4

f f . I *. . - * . [

l

4 . A Phts+ A

~

2 r ' . i r.c e r.t !Icistisr E13n:lT i.1.0) {

>1.U) t , . .

j c. - :,s r 5 4:'.6-..t;n .2 t --J A 4A , . - E 1

) [

t' i

E 1

< f h

I l,

. n..e

. , - - . . . . .- e

( F4 & L, .ly.-1) f ' - *

$Iik$ ,d***. LL[ .,! [" I,,I 8.4 L AIIII 1 4 f

k' l

A. ,

t.

t e

d t

l

) {

3 I

i !

i i

l t

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r'.4.. ,y ,- 3.y

t. a.

t 1. f. gp ..Jr 3 a

rL, a. - o-3-,.U

.T': i . r* -

, d ,.r.

s ..y T.,+I tn sfi. ,i.--

4st l ,-

GUEITIGrJ 4.12 i.50s The follcuin3 zuestion are asssciated with the noraisi service 3ss aecay tsnks.

3. How m a n ;. a c r ia l s e r ;. i c e gas inczy tank s are t:1e r e ? (0.5)

b. Norns11v- now often-la the i r.- r e r v i c e t~ ant switched? '0.5'

. 'J h y is the waste jai districut.ed among s11 normal service 3ss decay tanks instead of . filling one tant at s timei (0.5' QUESTION 4.13 (2.00:

. E;:p l a i n the TWO ways in which the diesel ts matntained near cpersting temperature while the diesel is 1 ole.

GUEn: .L..i i i e . ... t. ..uu, List FI'JE c > t p u t s of the ; r e sur i:e- ;ressure master : cntrc11er. NOTE:

Fedundant outputs count ss one, t e '. . F uns A zna F s ra: B.

GUEITION : .15 :

.. _- cr0Vlae5 s ri 51 E r c, 602 C31C GVerpres*Ure.prCtecticn s '. i t e n. .ur '; tC warn the operster that averPressure prstertion :- isolitec. Wn:t

.e l a n t conditions will :suse thi; 13rn i sq y:-- q 14?.*>, Ji .. <10 v.

c14 s eJ r. ,

O Nibh I O *' Pri3EUr-122r l e '/ e 1 C C ft D r 01 ~, .J i ( C 1 ;* C 2 i P.1 0 - ^_= 3'.._ '04 ~

n i 3 r. 's ili > r e of L T 'T: sill eff9:* 3:t> '

- - ' Te r .s1 4 .e

r. G r .?: 31 :h-Er'ing i- ~~

1 9 t d c. w ,"> - / 3 t S Tr '

< ,e. ,-...,3

.- ; c. . . ,

s . - *1 ' ,

4~ Y -

s- s 4

c-.

4 -

~ ~ '~

..,'t *Lk [.'6 . 54 '- I

. . ". '2'.;db Cf . * . - '

2 -

2 2

-a

, . s. . A

. . + .

. y' =. ;

+.w '+4.4-

.- "T..-s..

3 .....-k...

Ow ..t - *.-.'.n

+~A

>vs2 ~I ORr M ' ; , ' I z U . r. .; .tJ E-I 241T * * *.

s i

i 1

I i

e_._--.

w. . . . : : : i t 1: D t. : . u n, -

U ni . .c_w

. _ , - . s. .:

.-_o

- mt-

.,_c r. , .- :.

3 .

u. ,J t:_i. I u h,. ( ,; . .m. .

6.1,:

What is the setpoint Ar4D corpose c' the A '.' G HI' 31srm; e, t :eJ--4

'o; ..-. 3

. .s, u Dascribe acw the CFai =i 3nsis sm c : a s - + , 5. 0 3tse an sla m c c, sonorms1 f l u. distributtor. In esen of the f o;;;wir 3:

-i . Fower F2c.2e Channel Current C ac=rst:r

'0.5i

- ~

c. rower -

angt v

, e ,. e ,, - _ u r r e ra t t o m : a r c +. c r !.3. L ,

1.. r . .- s. ,. ...r ..., .

. ..,i

s. % s.t T4C intericcts must be = stisfied prior to mano 11v resettin3 2 r. c- +. .3 ..ye .. t..n.s _ 1,3 r. . b. After resetting safet injectt:n. ;'; t .: a s t ; c : c t u s +. : o n :s in?tbited until abst si3nsi is :las*ed' iO.54 3.16, C .; L t., f t : -., . .JL hesCriCe *de . irb@r1CCf 5 3 ' : . '. 3 ' 0 G 4 1' '

he "E3C'CI trip )*.@Esi OresEePI*

d ,wg.....?d*

%: ;. .. . 4...*. ,

1

, . ,, .. ,. .. e .

~d--

I b h . .I

/Uk. it' . b & m i 8

. .* * ^ ** 5 8

~. ( 'e Eh *e s 4 W

4 P

,. g g * =* = es .

e e r -e

'4 4., . I

'a l.$ -O e . * .

k5 )OI

'.H~

l IN555 if

'io. s ' G o" .3h*00 t h r~ 8t 2 C '

. - . d?* ~~~ * ' ' ' ~, 3 3*EtOS 7 I C ' l u '

=

.,5 T a.,..- . g m j- e

. a +s wn.;- ~ _ u .a I

e

. . . An e g +e .e . * = 4 -

l

)

1 1

i

.r n n. L , t.n r._._a a...; n;.. ,

e rr e:

, r Fx, a- - , - . :- - t3.ON..n . . l , . . ,,,.. 4

n.na .. Auv , . ..- _ ,-__--._.,--------------------- -

. u ti t e. t GUESTION .01 : 1.00' Which of th.: f c l l o t. i reJ t; NOT sn t r. i: ot i nta detsrmining :onformance w1th the restter core Esfetv L ir:.i t : 7 5 F e5:-ori:er = r E 5 5. r e Lowest u.te etina . tacer'

b. -

t low

T e O h e.

6. Highest 3rerstin.a Laoc T s .m. .

-ee9 - .e + q

4w

. )i4 )0 0 5. e D i, cutin] 5 n -3 t V T 3 l C i T C U l 3 *,1 C n ' C -21.i C W G #

', llCWin3 5. .r e ? C t C f' . t r i p

Wh1Ch of q,r 4 5 's %d .

." g

1.p I .

36 Y l.A3

I3$ldCUn a 3+* a U. k6iltDT P O wJ E T h l I I 3 r ', .d9CSy O 'l 3 $ f 510'

;e9?5O'i2ar 1OY0l.

G. d ' a, b c ' ;f C I [ ;- f i t. 5 t s i .% r 1 r 3 1, - . ..

.fi.% g.- ) I ,-

E f.- #

-5.. & 4 hY r h 13.5ClO5 -2 I 3 J 31 d' [ 7. W '2 I I303$ .2 2C 5I I O*3C60 1h , *?

t!!" : On ,; ; I ; r. O, wh;cn of the iLI10 win 3'

~ [ 3 : I n .1 td9 39G11C5bl9 b l .5 ', E O l r

~ -

i s t r. .1 In F. n q 743t*

7..,* , .".*

4 . <6{ 6 . fJ ?. .?, .

f

.'v. h

. . J- - 69 . .

a 4

$b$

~

)* 5 ' '.

E r .3 .' 1 3 .#. .O , '2 5 I } $ b'I ' a. $ .U ln5 ~ ' t ")W0I I'

- h' 6 E' k? e > -

9

' l .;a.- ' i r. . s.80 I. i C S O l e EO4er ' l :

t

4 dt.O ~ ' ali 3 W i t t. ," *3 t. '

...,4..,. 4

.'4 * . i. J

. re .

-., e - =

1:a2 , - .; ; 4 - 1 _4s e si4, . . ,

. : .I s ~*.n<a4 .. s* 4t * .9. i-

- t

A (I e +

2.i..AJ Lh4 ifpli:201~ C;GC5 : : - l'iCr01 ~ .~ i ?It EwltCO (O T.5Gn91 FCI111Cn it i ~. 0 [' O t e ; ?.- 3 r C '.' ' r E n t COGP3r3 tor F

. 3n0,L-i

9 fIi12a

.it; . ./ ,r A A A

8- s, ce ! c, s :q N I .

. . v d. e .., , .4. l4 .s . L 4; fl .bp H. - 8**8*)

. 7,c o, u- t- e, ,t .- t_ _ - g,...rm .L, n.-ew, ., e. %. .u.

_ .r-

.t r u tt, 1.

,b,e ...4. eE .

rn. Ew_ , u_ v_ ._ _ ,_ ., L u d T r: O.t

.d___.

t : i 2 0 t.,

. .v4 ( 1. 0. . .0-U n.ico cr. . .l e following is a l '.) 6_

_c +me sur e limit.e

.-s

a. 5 remJyest - whole boov.

c. 1 ;,m/;uarter - uhale acd,.

c. 15.75 remcovarter - henos.

d. ~ remiqusrter - skin of whole bod..

',.vu?

G,s,_

. t s ,+ _2 0 N .sa ..

Whtch of the (cllcaing statements describe the c oo ldewn.'dep r e s sor t:s tion sequence o1. tO* ,,.e. r . stema venerstor _tu be Rupture..

1. C ,: m m e n c s rspid cocidown. a e r. r e s s u r 1: a 3.sintsining succociing simultsr.e vsiv witn : s o l d s u r. .

c. :cc10cun Oc 5'O 4 .3rees: .i e o r e s s i r t : e '. 1500 93tg; c,mplete COOld3Wn; C O ni p l e t.e de?Ie5sof123t1Dn.

, 2 0 -) l d ] W D *C 'equir30

e n p e r t . . r .-

. , de p r a l ii.." 1 2 0 : r egij t r ec p r G E ' U ; :- On e CGOlG;wr' .: 206.-l -tC~si

j. e ~ ..T.Ji e n C 0 rEotd :00 lact A .. i .Or.r 3;,jri 3t10n s ; t el G i 4 t ilbLti O rt IvbOCS11h3 mss:: -..g.

na t su

. , , ~, p ,

. . .A i k. . s a h CW h hs I rI a h ') > 4 b #0l .

1* k. r h h W h lI

=_

OA W1 . 4

e IS O I IJ .~

4

$ 3 rl 5 l n Ut @ n T 6 "OnC1b 1DnI*-

4 4* "Ei t' ;~ JU.. de<ree? IOCCCC[;ng 9Nc .

CZ" ~.0,. ,0ii t th&n * . .

k g ., L1 flow ver1 7 led.

L C* 3 7 t h 3 ra aJ .. QegTAe" 3 U D 0 0 0. . ; h giL Ce C- Mpd Pressure 10?2 t a, a n l j. .c . '. t rj pJ _;A rtow /er i f iGO .

s 's31]

b. L 3 k r O ~2 58ar e 3eIE IIe 3 0 l ,a b, *

p si g n j..ra pfr leve4 .{c55 tn3h 4 ,. .

de 4 c0N.: _.UED u.N NE.T ( e..cruc (lIIII 1. N ) E uo.r.. f ", tr *seasi

i k

a 4

7 PROCEDURES - NORri AL - A E l10 P rf A L , Er1ER GE t4 C Y AND FAGE 1: ,

g ._____________ ____________________________.___--

RnDIOLOuanL LONiPOL i

?

i GUESTION 7.07 (1.00) e

! If s void exists in the reactor vessel with all RCPs stopped, which of the follow 2ng actions is used to collapse the .' o i d accordin3 to EOF-

j 1.3.;, ' Response to Voics in Peactor U+3 Eel [

s. DeCre3s0 temper 3ture while 1.sintaining system rste550re.

b. S t .s r t a '3I pump to increase system pressure while keeping temperature constant,

c. Incresse system pressure ostn3 pressuricer heaters while l maintainir3 pressuri:er level.

d. Fill pr95suri: er sclid and sent the resctor <cssel hesd.

GUE5 TION .05 (1.00' ,

i n . e p Cc9si ; let,9rialhiPJ if II :In 09 t .' r it ; rit t e d . I,f is d0f,Or%iG9d th3t the i fc O 3Gis! y " test ~'35 : II,rClO+ In - ' 1 :* h Of thG f;110 Win 3 7

sitUitiQni Cr'id "I '22

J r ca l n a t e- d !* = /Or"a . ment 20hditt0n3

' t ' r

,i '

k1

1 I U E M " u I +' :GE35UFE 4 : c '. .

m3 oo- -t 31+

j

_ : E *. 5 ce 3r ee t increasinj

'P. *

. J e .: r e c inctessira. <

~

l(* 49 0 9 *] I O *.?

i*.EO1e i ?

t r

4

8* fs CATEGGFY O' C GNT!Utf E O r> rJ E Y T PAGE rs**si i

I i.

I t

'(

T 1

-. _- - . . . . - _ - . . _ - . _.-.=_ __ - . . . . - - _~. ._. .__ - . . _

J i

. FF.0CECUC.EI - r40RaAL. AENGFhAL, E hEF G E N C '- ANC ; ACE :-

J RADIOLOGICAL CONTEUL ;

J l

i GUE3 TION 7.0? (1.00) ;

If the 3vberiticalits Critical tafet. Functicn .adi.stes s 4 saco esth. 1 whi:n cf tne following sctions is requiredi i

s. Go immedistely to the refe en;ed ;<rocadere.

b. Go to tne referenced pr ocedur e as time permits.

c. rionitor ather status trees sno if no ht3her criorit. :andi-tion exists, then 30 to r ef erenced pr ocedur e.

d. ncnitar ather status trees and if no higher pricrity conci- ;

Lisn e:.i s t i, than 30 to r e f er enceo pr o:sdut e as tiras :,e r m i t s .

i

..,a,

! G U t. ,. 2u 4

. p ,t.vy; I Ubich of the follow 1ig mtifunction! -;l; clult in 'c t.. 3 low Tav3 irtic? tion a r,u :. '. o w celte T indicat nn-

{

not l e g c- ,s. .

j 3. e rsiled .ni3h .

c- . ,3. ia3 e i e f51 er , ow

). c. Calc l -+ 3 GTE 'Illed hi3h i 1 C:Id 1.'s c:T: f1; led lo. ,

t

.' CUE rCGH ~ .11 't.M'r Acccrain3 to the Immedtste Carrective Ace.;ar.: f:r : . *:.t31 1- :-

l '

ser. ice aster. i r. -; ; ; s t e whether or not 'YEI mr iC' t , .- ' 311 N ir,3 i

sctions 3re cer arseec.

I i 3. Tc;2 the res ;t :r A.!'

1 0, n;1: tsar 'eacts' st nc-loss, . 1,1 3 cL

. ~ rip the 25c tcr cocl30t ?v hE 3 ~C.S.

i a

i l :***s C ATE GDF:Y O' CONTINUED ON NEYT FACE ******

I 1

4 i

i j

k 1

1 i

4 4

-- . . . - . - - _-..--- --.---. -.- ...-.~_ - . - . . _ _ - .

1 1

I i

4

7. FFOCEDURE3.- NORMAL, ASN0FhAL. EMEFCENCf ANC FAGE is ;

r FADIGLOGICAL CONTFOL ,

f a uuESTION T.12 (2.50)

Indicata the numerical value(si associated with the fo113 win 3 precautions.

l s. Maximum differential pressure between RC5 and E/C. (0.5)

b. M s ::i m u m differential tempersture cetween PC3 loops. (0.5)

' (0.5)

c. Minimun. FC5 flowrate prior to sne durin3 PCS c:1utions.

t-1 d. M a x i .w m este of power incresse above 2 0 F. reactor power without

managemant approval. i 0'. 5 i

) e. d a::imum EC3 temperature durin3 FHR operations. (0.5)

GUESTION ~.15 (1.00)

List the sctions required if the sctusi critical red posttian is sbove ;

~the low-low insertion limit but differs f r om tne estimateo critical t position by mere thsn 50 steps. ano less than the manimum rod with- 1

dr aws1 limit.

t 4 :

GUE3 TION .14 /t.E' t i

Answer the folicwinj questicns concernin3 the re quirements ssacciated i uitn doing 3 res: tor sisttop, i (0.5) 2 uhen must all ihotdown Bank rods fvils withdrswn be ,erified?

I

b. Haw c. s n v licensed operators must be present to tne Contrcl Room?

Ee ;pecific as to what licenses sre re,; ired. <9 5)

c. If too itsttoo s delsved, waer. aest the Ertin: ten Critics 1 '

i Ccoditten c s l i '; 1 s t 'i o n b e revteweC 0.5-1 1

4 GUEETION ~.1~ (1.00' I C o r in.3 powe r opersticns, when is it alloweo tc .c e r. h e rod control 4 system in automatic?

1 i

.xxxes CATECORY 0~ CONTINUED ON NEXT TAGE *==**)

i i

j j

1

- - -. . . - . _ _ - . . . - - _ - - - . . . ~ . . . - . _ - . -. _ - _ -_.-_

9 1

t, i-t Y

4

. PROCEOURE5 - NORMAL, A D N O R ri A L . EMERGENCi AND PAGE 1?

i n e2. ,. - , O L u t., i t A L t 0 h. i r', Oim ,

+

E 4

I.

1 GU'd'i20N t '.lo'

< ( ' . v~ u~ ,-

1 Indicste the Immeditte Corrective Actier.(si required if w.1 t l e c r-e r s t i n 1 -

l j at SOL power tne followin-3 s;? mi o : u r- sirultaneously. I

'RC? A il 3L L'-GFF FLO hie!.0' and 'RCF A 41 IL F LO'

O ,v, E: _ _. 7. O N,

. .1- . . e u .i Whst sre the Immediate Carrective Acticnts. required if the char 3tng 4

flow contrci vs1ve (FCV-1~I) fails closed while i n s. v t o n. s t i : contro'

,i snd stil oct respond to s nanual c 'o e n stansl~

i 4

i Lper s :.-- 1411IJ

< . - . 1-;: 4 1 . r-,) . 1 An ! % M -; [ i '. e ' rIec'1 : A c " I c c:

cr s *zg,wg* - tc0-tar -- y ;;, p +7kg 1 tait 3 i&O L-ter ;;3;tcr r. . ne .ot gt;11

.;i007 - # 17, 1 Plant lOiG ilifd 03 thC '

3'T ,ic9. M i'. 6

l ' ~: 'd~ p1 int ic3d 1i%ititicSi 41td thG

c I l c w ; ~, ;

r. u r. c. -s - c- f fe W iter .ar-int evno; i r: tereite ~

- e.

, .a* .

1

~

v ,3 $

t s . r. .,

4

]

' s

- VU-.__.,

- ct .

I . .

D, *. O 'd J {D

. : d 9 D *. i i ;Gj 5Gd .: G r r e C *, i n *] *he ra i l f u r,C t t ". n = a /16 t ITo t*e

. IIt- '. 3 T 7 .t I A!t1Cni 10' I dies 1 1,nei i- t tr;- f o l l ~m ; ri a ?n I *.4 3. t-

. v e .3 I q ; ', - + 2 i~

..., ._ ,. . r-

. . r.

se av>

h drb 4e n Ie b ,e br6 h 'e e 'I - k J [. 5 h # ).i 9 , I h . e!' ,

' - w G G .-

4 i

d IIIIM

l. P1 i C Q fj f 'je 4, I ,k b

b, e

..N 6 6

i b $- $If 4

1 11 1

+

s

{

1 4

I P

i ~. P C:0CEDUEE5 - NORMAL. A E N N+ A L . EME :Itc Apt r A .E :0

! RADIOLOGICAL CONTFOL j _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _

t I

i i

? 03ESTION ~.21 (3.00*

List the Immediate Operatcr Acticns (cr 2 Reactor Trip /Safetv Injection.

I Just list'the action. not now ins action is act:nplishec.

< GUE37IGH - .22 (2.00: ,

List the FOUR possible siternate sctions that cn be ts)en if during a response to s o n o r ra s i power generation ATW5) the turbine had not auto- .,

, astically tripped.

j GUESTION 7.23 (1.00; ;

. 'Jha t p lant ccnditiani j e t ir .w i n e when 32.erse Containaent conottions J :crackets in EOFi are used in t.e Emer3ance Gpar atir g Pr ocedures l

L i

h k-

}

1 i

[.

f f

i

}

h r

i.

4 I

i J l 1

1 9

I 5

i I it#$84 (TI (' Cf

4 7 ~ ' ) E 't [~ &81 ke l

l 1

4 i t I

i 1

f i

I i

i ?

f 4

}

ii 1 , w e,-,-----,w-w,,

,--.m-..,_ _+.-r...w. w-.,w-,-m_ w.--,,-ye,..my,-,,.-.w-,--w,--ce, _.

i t

=

l 3

1 i.

1 4

i

- - . - ~ - ' ~ - ~ ^*

d. .,gn yA. A 5 e n. n a . , -

._.._,t W. u t. E. '0 U n" t . J t w~ '4 - .t e r4 i . n" r > ~i ' 'tn ~i n' ~. ~.iJf : F A' - t. .. ;

i j _-,.________..__________________.-______.._.._._..____'. i .

I t 1

u U E _2 > I s, t, o.v..

'.a.W' ..

Accceding t' : the Techntcal 3pecifications. three cancitions 1. u s t exist !

for the RW57 to be operable. Wnicn of the follo;1ng is t10 T one of these 1'

three conditions ~

1

! a. Leia th3n maximum water 'emperature.

b. Greater thsn minimtm water volume. (

i'

! c. roper ocron concentr at ten.

a

}s -j . Greater t h s t, m i i i m u n. water tenperature. .

t l 4

! UUEITIOil 3.2: ~1,30i '

I 'J h i c h c f L:.e a l l o w i n g L the correct definition for Hest F10:' Hot Channel Factor?

3 The ratio of the inte.3ral af linear power along a rod with

! tne hi3 hest integrated power ts the aversge rod power. ,

I l t b. The mani1vm local heat f l u ': :n toe suri=ce of s fuel rod at l i

core elevstion divided o. the esers3e fuel rod heat flu-. '

1 i

j c. ene nstra af peil ccwer 1 e rrxit tc svirage rcaer s density in !

! the h :.r 1 : o n t a 1 F1ane st c or e 21. . s t i s r. ~.

d. Ha ;two e.. ore det=.ta; c sil' e r a ted cur rent dtvided o 'v sver33e e :or e -j e t e c t o r calistated Ourient. f or the upper or lower r

] .h '. e : t e r s , whichever is grester. l l

i a.,ite. ua - . a. - ' ' . s ,s .'

I

rtar to unaciting the rescter vessel hezo, the m i r t wy. a a r ; n concentr:- l 1

L1cr r_. ; ' .i .:. . +

.::- af the followin.a enirer2nt~ ,

! m , ". : 0 ', ,: .:. Os enouqa to e n .,ia r e -

.. f r it less taan s. '. w a t : n e .< e r l 4

l 12 wt _d: _,

E l 3. 2000 apa .dITHOUT regarc tc keff. f

. Enougr to ensure leff II less than 0.05 U!THOUT regar d to c a r. -

i centrstten.

2. 2000 ppm OR enov.jh to ensure ,eff 13 leis t.>sn 0.;5 woichever is G F E (, T E F .

1 iaaaaa CATEGGRf OG CONTIrluED O t1 uEXT PAGE :****f

R r

i 1

4

~

f G. ADMINISTRATIVE PROCEDURE 5, CONDITION 5 AND IMITATIONS FAGE !

j l

GUE5 TION 5.04 (1.00i The piccess of determinin 3 an i n s t r u c.e n t ' s ac:vrze, n v i su s 11. ecmparinq -

the indication to other independent instrument channeli ,t e i s e r i n 3 t n e same parameter is defined in Techn cal 23ecific aticn a as s' 2 s. . Channel C s l i b t a t l o r.

b. Channel Check j

2 c. Channel Functional Test t

i d. Channel Verification ,

i GUE5 TION 5.05 ( .00i I

9mich of .t h e tellowinJ is the best: f;r t c. e hi 3h 3ressert:er wster level ,

l reactor trtF

3. Fre,ents solid cperstions 4n11. '. n e .; a c *, c . t: eriticsl.

l

} b. Frevents exceecing cantain.wnf aessjn Frei wr4 in e s e ri t of a l

LOCA with s11 :C3 fluid asa:c3 .a ut 1. .

c. Fresents lost f p r a t r, o r -- i m. tral v. e a;r n c. c : : 1 . bein3

'i e c ia e t jtd.

d. ' f r ; t .f ... t . ', h e 3 :.;i+;;9 - ;et ;[ . 3;1 nit ., :. t e

1,ci, j

c.,

i'

- G ,J - . , _ u- ,1 i e . v e. . v ;-

! tr :perstte] st M 0 '. ther >;l 34. - -1 E +w *.3:' c sN wa.n in :: Q1203 97? Rn O!'3* in ihG C'l: 0171.00 ~l C 9 5t i. ' l i l l * " O'i f i t' 7

d e . L 4 ', 1 0 n I lili e . ~ *.51 .itiCn s ? O w 's *4 01 w f

. - "O3'.I d= 1i!LC5 $154

' *. 25 hout i d e t i r. ; *ne irevi305 10 0: or" 4: : * 'a' i r 3

thf ri -1 LOG T ' ~ iFi i '31 se~; fir i .205 JAich Q*

i -4 11 '<tDC *LChi 15 " " JV i r e 3 7

~..

I' tilt i r4 1 a 0. i ' i ete . u _64-

+ - e -

' i - i. h !. f- *'

-4

d56 . d!3 t ,l 11 is .,i

). ..tkh.n M .2 V % 16' ..II . a ? V dYi 4 * '1 u '

I i

. W i t h i r. c ," Ge i n U t E i . '?d:. t' '

l i. ' FO4* ! 'J lifi U' i ri 13*.i 4

) . O p e r S t i>",n 3 la i / CCntinue st l O O *. E' lon] ~~ ' I' " 15 + -ir l i n t

i i - 1 1

u i t h ; r.

the tar 3 t bend. ;

r I

I

(*an12 CATCO.( 0 :3 IGHTidVED QU NO* i V,E at,sai i

i !

.i !

I i

t o

3 4

I

! 5. A0ri!NIETR ATIVE PROCECURES , CONDITIONE. AND L!riIT A TIGif E EAGE : -

i i

j GUE5 TION C.v it.004 i

j Which of the following is the Technical Specification minimum shift crew q composition requir ement .41th Unit 1 op e r a t irig in node 17 i

i s. 1 $$. 1 CRS. 1 RO, 2 AG. 1 ITA i

{ t. 1 E5 1 CR5 PC. AO. 1 ETA 1

i c. 1 is, 2 CRS, 2 F 0, 3 AG, ! 37A a

4 t

d. 1 E5 : CES. 1 RO, 3 AD. 1 5TA ,

(

GUE3 TION G.03 1.00)

I which of the following 15 the basis for the upper c o r, t a i n ss en t temperature ;

limit 7

s. Prevent eaceeding design r-ressure during steam line cresh.

b. hinimize hydrogen generation in containment foll~owing a LOCA. f I r

! :. hinimize coolinq requirements :( containment coo 11og systems

) durit.3 notmal plent cpi-rsticn.

4

c. Frevent eaceeding teg er:ture illcwed t -a r continous duty of :

ecoipment inside contsinment. r l

a i

i 'eU E I T T:3 0 ?.S? ( 1. ',0 )

El -h af the falic ing correctly describes the ma: :imum allowable eatension I t;p for Technical 5pecification tur'.eilanca t r. t e r s a l s ! ,

s. clue 25*., not to e::ceed 3.5 tisier the specified interval for 4

sns 2 conse:vtive i rit e r v a l s .

i 4 c. Flui ~ ~ *; . net to oceeo 3.25 timer tae :pecified intervs!

l for an. I c ar.iecutive inter 5.1.

I

) c. Fivs 50%, no* to e::c e e d 3 times the asecified interval f -a r j j any I consecutive intervals. j i

d. Fivt 50%, not to e.eceed ".5 t i a. e s *he specifted intervsl for n r. y: consecutive inter *.als.

4 i **eaaa CATEGORY CG CONTINUED ON NEXT FAGE a*ss) l i !

I i 4

1 4

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

t a

5 i

G. ADriINISTR ATIVE PROCEDURES. C ONE ITIGt4 5, ANC LIh!TATIONE FACE .1 i.

I '

, GUESTION S.10 (2.00)

i. Indicate WHETHER or NOT the Technical 3pecifications require sction to.be I tat.en within one nour for the following conditions. ,

l a. In Hoce 1 with one full-length rod immcvable cut within 12 steps j of the gr ouF countcr d e n. s n d positian. ( 0. 5 )- l F

j b. 'In noce 5 alth .: n e oreisvri_er code isfety valve ino.erable. 'O.5)

c. In tiode 2 with one Fi tiur: er F 0 F '? blod valve inoperable. (0.5) ;

d. In rtode 1 with onl/ cne :perable c h a r 3 i n g p u.tip . (0.5) i OUEETION 5.11 (1.50;

! 2. n u e r TRUE ar GL3E to the follcwin3

! a. Entr. inte ar Oper sticnsi M o d c- may be perform +d if the condi-i tiana fcr 'he . i t. t t i n g 'cndition (cr Operation (LC0! a r e r40 T i

act :>rn: del the ACTIOrt r equir ement s are subsequently satis-1 (=ct rily :ompleted. (0.5;

o. If s LCO is NOT met and the ACTION statement. are NOT spp11-i ; 1,: l e . then 'ae 3enior :es:tcr Ope.ator has 6. a .- tuthority to I ',15 : 3 3 3 r -j t.h 2 t Far'ic.Isi LCO. ;0.5)

. :tlw e to ccoplete 3 lur<eillsnee P e a v i r e m e n *, within the i spe ifieo time interval (plus sny ellowsble e:; tension) shall 4 :anititute 3 failure of the system tc meet its opersoility feau:rements, (0.5; 4

1 J -I 1 -!

l v L, t_. a +i . a n .35,. + ., .- r ,) ,)

l 1

Inci:ste.wnether the following Ire c .p. t r e c *:

. a . m c i e t. . SEF0FE or

ArTEF w3tcn t t. r n o . a t bv tas Contral ~: 9. Emr .1s -

1 i

i .. I.esiew Re.tuirso Readin3 Ecok .5 i

l o. F.esiew Etstion O r d t- r ! -perial In s tr uc t ion _: i:.Ci

~

eview s n .> 3TFs in prc3ress "5 i'

1 3 '

i

c. err

CATEGOPt 02 CGNT*.NUE0 3 ra r'E x 7 FACE t**is'

)

1 l-I i 1

4 4 e 1 I i

I

O *

3. ACh!NI3TPAT!?E crncE tF E3 r;NEI- :u:. A n :, ._ - n I . A T I O N S F A C ;- :!

OUE3 TION ~~.15 . .00i datch the RC5 leaka3e tve: in C: Inn A t; t ;~. e Teconical 3 ecificstien limits in Columr. B. ( A s s e n. e n i s ri t ti at re o r m a l press / tempi C O L U h ti ; CGLUnd 5

s. Thr,v p p t F O R ') .t o FFT :. O 3pm

. 1 3pm

b. F r o n. R:5 ints c o! . Ic3 a : : U n.u l s t o r 3. 5 spm 4 10 gpm

c. Fran. nntnown location 5. 33 spm

6. 500 spd

d. Nonisolable fsult on FTD ov. pass line .

GUE5 TION G.14 tl.00)

The most l i m i +. u. ;ondition for 3Dh reavirements occura at EGL with Tav3 at r. c load :, erstin3 tenperstere anc is esec on e steam line d r e s'. r accident.

3. Uhv 13 E 2 L M G e' e . i .h t ( t n . ] than E0L" ( 0. 5 )

1. 21 + i r. 3

h 3 r' full lO3d

~

b. 4 n ,. is nD 10 3 . .' t A n47 E r '-t . e nOr a

ea.; e r ;5.:r. ~ '; . 5 .s

/L t: .

. tar ,

. . ..se ...e..

1. Wh3t 13 the T O c '" r t c 3 1 3peCLficatlan 33fety L. i m i ' for E C 3 - p r e s s.J r e a - ,t - .;- '

Whl,ae ir f13 G e i '

D. Wh3h t- the r casirEG 3cticn if t; 15 limit 15 /tclsted' Onl, in* luce irt1Dns

e q '.' I r e d w i t h i r, . nou*. i 1. 0 :'

t.N,,___. L Td A.UL..

t. : c.Ia 3 r.c e ; o t e c .: of equipment is c an 3er * : -] G e o f:r : 13rticular $stntenance w r6 re: vest, ne otner wert can be. per f or meo on tne isolateo equipment sniess either :( twc re ptrements are vt. ', ha t are these TWO require-ra e n t r ?

': a s * *

CATEGORY 03 CONTINUED ON NEXT FAGE :asasi

t E. ADMINISTRATIVE PROCEDUREEr C0tJDITION5, AND LIriIT A TIO M 5 PAGE Zi GUESTION E.17 (1.00)

With the exception of certain electrical breskers, what are the required qualifications of the individual responsible for second verification of danger tag placement?

GUE5 TION B.13 (2.00'.t According to EFF-001 indicate the LOWEST level o f. E a.e r g e n c y Action Level -(EAL) that requires the followin3 sctions.

3. Notify Fstrfield Pump itorage Facility <0.5)

! (0.5)

b. Activste TEC/05C '

c. 3ound Racisticn E::.ergency Alsrm (0.5i

d. Activate E0r sv.Si 4

GUESTION 3.17 *1.00 List the iccaticns cf the 5cuth a r. : 'J c r t h Mclot ; A eas useo in the event of e p l a r. t e w e : v a t : :.r c.. n.m ae : f . ,J y e

-,.uc) ,

o

,c s a

' i :i t tie TWG sc= stole essemol. ':ints f :r ' ,s

_ , - t r .- E , t 3 5 .t .- ,,p o n recetyt of a fire sistm.

c. q_.c. : i y, :s,. . -

Whs' sr+ .. . s .

~ Ce l a : a.e r 3 a n c +-n::are 1: -ta '

. :5.e .usin life AND te c. . t 3 rt t = s a m . :e .

eitsi e c : 1 : n, + r. ' ~

o ,.,.

. t < o r , 2.... 1 L. " -

Uhst TWO ccndittens : e tera: . *w c . e r s a t i i t '. : r' the prezsvrt:er while tne plant .c in node 17 i arrr CATEGORY 03 CONTINUED ON NEXT FAGE *x***)

l t

r h

e i

E. add!i4ISTF.ATIVE PROCEDURE 5 C Gi1DITION 5 AtJD LIn!TATI3tE 2 FAGE GUESTIOt! 5.22 11.50*

List the THREE PC3 chemistrv parameters whose lis,its are given in toe Technicsl Specifiestions.

ul -:et

- , G r. 4 c.- ( 0 u .-

List the conditions required for opersallit. ef *ae ECC3 sccumulaters. .

1 : : :

ErJD OF CATEcarY :? .ie: e siaa stis**** END OF EX AdirJ ATI:ri a ss******a45se

3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE (AFD)

LIMITING CONDITION FOR OPERATION 3.2.1 The indicated AXIAL FLUX DIFFERENCE (AFD) shall be maintained within a 25% target band (flux difference units) about the target flux difference.

APPLICA8ILITY: MODE 1 above 50% of RATED THERMAL POWER

ACTION:

a. With the indicated AXIAL FLUX DIFFERENCE outside of the 15% target band about the target flux difference and with THERMAL POWER:

1. Above 90% of RATED THERMAL POWER, within 15 minutes either:

a) Restore the indicated AFD to within the target band

! limits, or b) Reduce THERMAL POWER to less than 90% of RATED THERMAL POWER.

i

2. Between 50% and 90% of RATED THERMAL POWER:

a) POWER OPERATION may continue provided:

1) The indicated AFD has not been outside of the 15%

target band for more than 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months penalty deviation cumulative during the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , and

2) The indicated AFD is within the limits shown on Figure 3.2-1. Otherwise, reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within 30 minutes and reduce the Power Range Neutron Flux-High Trip Setpoints to less than or equal to 55% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

b) Surveillance testing of the Power Range Neutron Flux Channels may be performed pursuant to Specification 4.3.1.1 provided the indicated AFD is maintained within the limits of Figure 3.2-1. A total of 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months operation may be accumulated with the AFD outside of the target band during this testing without penalty deviation.

b. THERMAL POWER shall not be increased above 90% of RATED THERMAL

, POWER unless the indicated AFD is within the 15% target band and i ACTION a.2.a) 1), above has been satisfied.

SeeSiecialTestException3.10.2 I 1

SUMMER - UNIT 1 3/4 2-1 1

! l

5. THEORY OF NUCLEAF POWER PLANT OPEFATION- FLUIDE. AND .F A G E :E q .

y Arl54ER3 -- SUMMER 35/11/13-JERRY 00VGLAS ANSWER 5.01 (1.001

-c.

EEFERENCE Pump Laws AN5WEP 5.02 (1.00) ,

I b

REFERENCE- ,

General Physics. HT a FF. p. 229 002/000-l'5.01 (3.1/3.4i ANSWER 5.03 (1.00) 9EFERENCE 5 test > Tacles

\

l ANSWER 3,04 (1.00) l

[ 5' l

l REFERENCE l DPCr Funosmentals of rinclese Resctor En 3inee r in 3, p. 138 l WNT0r pp..-I-5.36 - 43 l

001/000-K5.0 i: 2 . ? / 3 . 4 )

RAGE c

5. THEORY GF r4UCLEAR F0WER PL Ari T OPERATI0rl. 7 L U I D ': . A r4 D 4154 E R S -- 3UhhER -55,11/13-JEFRt COUGLA3 MJSWER 5.05 ( 1. 0 0 '.'

b REFERENCE

> 54eam T k\es ANSWER 5.06 (1.0u; a

REFERENCE W r4 T 3 r pp. 1-5.63 - --

MJ54ER 5.0' i1.001 c.

AErERENCE Westinghouse riu c l e a r Trstnin: Operations. :. I-5 :: - ~0

.,, ,1 . t).

s v, r.- }ses .9 .

s -s.e 's.',-

I 5 .

ANSWER 5 . J .3 ~;.00)

3. It!NER G.5'

b. OUTER {G.5'

. INrlE F .5 e

o. 1r :

. i ti e-

EFEFENCE 10-1.~ 5 PJU$ r Nuclear E n e r '3 y Training - ? l a n +. ?3' tcr', nce. sp.

L

5. THEORY OF fluCLEAR POWER PLANT OPERATION. FLUIDS. AND PAGE :I THERh0D YtJ AhIC 5 AriSHERS -- SUhhER -G5/11/13 JERRY DOUGLA3 004/000-K5.09 '(3.7/4.2)

ANSWER 5.09 (2.00)

3. INCREASE (0.5)

b. INCREASE 'O.5)

c. DECPEASE (0.5)

d. DECREASE (0,5)

REFERENCE General Physicsr HT 1 FF - Fluid Flow Appitcstions for 3ysten.s and

-Components 002/000-K5.01 ' 3 . L .' 3 . J )

Ar15WER 5.10 f.1. 5 0 i

s. 1 (or 5) (0.")

+

L. \ p.- .e-a .'

u :

. s ,,>.e,,

, a r: r. t t,. r:' N L t Ganer31 P:wsics. HT ' r~. r. 9 1H s ia c til 0 : 1/ 0 0 0- t.5. 4 7 (2.4/2.i)

-ANSWER 5.11 ~~.G0>

r, s := u. . v. .

. c w .. . r. -

i...,

W

, s E te en -. tr .it a

.uestinghcuse Nuclesr Trsining Goeretter.E. pp. I-5.- - 16 v v 1.< v. v.% . ,,. i.e.,e s ts so.,,2.-.

-N5.26 '3,~/3.6)

- y,e

-a . .,. g a. . .e ..s.,q .

01.'010-K5.29 (2. '3.4i

5. THEOR't-OF NUCLEAR P0uER FLANT GTERA !04. F U I D '- /, n 3 *ME :

THERMOCYNAMICS

, . . .i

-t fl ;_ M, h r. ':.. -- 2 U n,1E r n.. :. m. i; sensr . o t, u u ,. ..:

H N :,,J E r_ e.1, s - t ..vu 3iOC9 3 3113 T' i d .it i i 3t3d10 i 50t19e 0.5 **4.

d c t. h 'h6 i r

d J C +, t C T4 3tf 3 rt *J f & m C '.' 11 TEta E T E ' F f C P O T t '4 3ni. t* FOudi 14% 91 (L.! Pti).

F=~ or ~.cdte _

~c j

.95 $

inghCU1e NUClesr t rining Oper3,1 3 Chi. .

(t . _A ,2. __

g UV 1/ U .%* - f . ,_. s . .;, ,s t..,,<. 4 .

a tg_ . emr p r. e.la-s- to . e- .3 .3

s. DNEF = Heat #19 (cower) *c Cruse Dr4 .

sCtual heat flua (poweri 70.5)

b. IsreEtET .t h 3 r# 3r squ&l i U . 2 ,Ft5' iG 1 . *> 0.I fiS' '0.5)

.: . ( 5 n .' s st.C.25 pts es os It.5, 1 RC5 pressefrE . *:5 19QperitO*e

_z.

_* L 's

. f1cu

. k* *. ;- w e r L. MF_c : . U-in

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l s .".

..__.* PC5lt10A

__l.___.d I L LQ h __

m, U l b, _.-t. g? *: 0 .,E > m

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+:wr r .c_:. .a, .ry %-

'9 * * .' s > *e h ?s ! ,5I * " *

'8

{'** 2 $lY r b $ ($*

wr.

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y.

AHw 4 4 R .h 4 O c; g.. ' ' -

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j . J '1

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d ')F_ . _ _ .f . A -

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En t.iG E 9 0 O r. d 3 7 < 4 '.' : f,9 fra ther9 15 6 9si5 i e C 0 ~ T 30 ~ 5 ,. t 3 ! .

A .sh3E0

. 7 ;*, 3 G

G -S i > I T 01 ; 1?"30 f3GitE h. With ti.

^

'33" ~' !* l t 2 n Of th&

14 2 CIPr? *- . 'T 0 lea t -*30 DG t T -2 0 3 f - 'r ed a l

ii i leuer t' i c . *:tc r ~

As.a .es. a >. .

.wwee _p g m y

[ b. 9

. E. I b. . - .

.3@((1Cb

J d O U I 5 ,a ~ 13'/ 3 1 C 3 ? b. 1 _ F.

6* P .J e a.

-n_ , . . ..

3 VV6-' V U V

h.e.J+Vl t d6 i / .J e v I

i I

l

e. _ L, c -un r .u,n- re T ,.-

.i ..w.t -u F, ., ;r o u t_t ,. t.-n, R. _

ru ------d.

srtesimu --cdw:- -s r

T H ER riO D Y N A nIC S

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

c'.Jum. a:.

. - Rd e,Nb4 t _ - - 3 ,_,.n n e.n . - a t r . t< .

AN WER 5.15 t3.00)

2. Tne redteted critics; rad tosItion i

.5 .S t 5 1 t5 a t t .11 a :cr'. oi rcd : nsertion 11.u ts - .5 eta >. or CalcJake SDM (per STP). 1.-

O. L U i> U f- C m .-8L

. :=nv o st 0.25 pts each) 1.Si

1. F C .3 coron concentratton :. Control roc position

3. PC5 Tev+ 4. Fuel burnup e.

2 senon :. 3smsrtum

~. Power leal

. : .: _ F r .>i t c-VC5 75 pp. _2 1 :- a. 60 P- 3 , 7 7 001 v00-h5..a .~ 3 . s - 2 , 4 )

001 M 0-KS.12 / 3 .1 ' 3 . .

. ,s 1,m. e.

. .. .-. _ e. y ,. i .c u. . .: . .

- c ,

et a = = r- - .- s.

. * , .,s U 'd.I ll 1 b bb 'v' hIJ b fl . h #

~.. Ete;tl.e I D 3 t r U li. E n t 3 t l O r. - l '. i i -

r. - r r. . . ~; _ - t ; t. ) r 3 rs j 9 .5

3. 2 r G E E u r 1 ~. 9 i : 3P3014

Gding 099F201~ .25 -ts.

s W i *. O 3 itE3a D. fa- l t- '~.2E -t.' *

~.5'

, ' d * - 4 4 k 8*..l

I.E'~E:EU~E

+., , . -

,a * - -

a e e p. * .

'I

' ' " + - -

r.*e= , e - 4

. ,0

1 .* H f. R J .k a ._]

o

s E ..-

C. A GW CORT 9;tlOr '. B re G df?t&Ct 1 .c _

1' , 1; ; , .

_ m. I l ; 3 ri d ,

Gotrol rGd. ii n t--- t L E. r _ U L' E

<n. c_ . i :. -e e _. )/'4 .. c s

'a J'

. ^* * -

0OA<,.,e.'..)*Iu .

s n lv'."/

. \ . '" /~'M*

1 I

I.

i 1

5. THEORY OF NUCLEAR FGWEF FLANT GPERAT 3N. FLUIDi. i. c - FAGE 33

~~"~~~ ~~~~~~~~~

i ~~~~IEEEEOD7sA55C5~~~~~~~~

n tlc u. . r_ F <: -- .a u rt r'ittc. .:vs< li* t. :: - ..kr .e t t.

u_,Ucm n' a-4 i ANSWER 5.1S (1.00.'

_ :: c m / c e 3 r s e 9.c.- s

. pcm/degrse ..e' ;

.t i

4 REFERENCE 4

,,C

, z_ , 1: .

.e. a- ,-4

! 001,050-P4G45 ( 2 . 9 .' 4 . 3 .'

AN5WER 5.1? II.50i 4

s. - iffer-ence in normalized flut si:nal; cetween tne top snd Jottcm j nsive3 of tne :Or e. (0.5)

a. cra.:ticnsi :.i s a g e in neutron taculaticof cor jenersticn GR f

fractions 1 ce'.iation from ertti: s;2t3 t0.5-l c. Tne e ctivtty issactated with 3cing f r a a. HZ' tc 4FF. (.. 5) i d

,I

r. t. t P t_

/:34 71* O l-1 3DL M93tinja'GOsd nucle r I 31 n t r i '

"s p e r 3 t 10 r. E ' Sp. I-3.2

,C.~.,

, L s *. >,

.. . - F u .~. .. . a , i > ". >, .

4 -le.ev-

., . .3 o. ,s . 1

-ie.,,. v - ..,.;..e, a ..i n, il ; tJ E ,.r. ; . _ e. .. ,.

(c.VC. *

~

{ l W 4

~1$ = -l14 cm 4 4

_w_,

r . . . '! .15 r .., n. .,.n c.

,- J.

. , . .s ,. .

l _..r.. - SC ; r.-

i 3.. . : . ,

.C *. 5 . . . ~na1 -s c 'in 4.-

EGtOn" -4EI -? = 54.E pPi i 52-5: .i . 4 011eticn 4'

(; tt

_ _.tr - 7_ i3LL -n

- - g .

..-*,4 3 t i n'10 0 U 5 e N u c l e 3 r t r 2 i n t n 1.. U'asr3t1005 50t A es . .- - -

. . J .:

001/000-K5.29 ( .5~5.E:

3

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T .

d.

l

.,-- - - -n, ,,w..,---,,-.m _ . _ , . , _ _ _ _ . , _ , _ ,n,..,e .,,m,-.

.: . t ri a c t : ;t, H , .. O re T K O L . s r. ,, e

. ,,_ .-,. .,1to.n.

c. _

r-,

. n. ri . _. _

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ArriW EF $ -- BU:1hER -35 ' i'- .tFP ANSWER c.01 1.00 3

h e r e n c 0. ,.u:

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,,:1

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t, . _ . _:. ; t e 3 _, 3 r c a .r o .m r _ y s ,. c m - p __ . . c.

A ts S W E R : . .: : i . 0 C 'i u

L-FEFIRENCE '

'll :

i6-2* d 5 i ri 3 *, d 5 m I '/ 5 t. A 7 . . I5 .rd O]

!. A: 1 d e rit , A ri E /5iIe e,. 4_ ~3 J .re.a . 3 r, V - V O.V-. g.

. . + .3 +a '

Ari3WER : .'2 1.-

ri

.; E r" f_ .:. P *..' j .. P

'- - :t,..

JC I . G: .. - f .s y . . a r ; - -

,.4 N . . . _;~ t : :. . . .-.,

trtotN.. -

,i:.

, r, -y :3.. : :. . t, . . . , ,

w.-. .. ;r - ..

o : . .: E E ' ON AC.Tl U E LoFP j OPEN ON /N4CTHIE LOOP

FEN ' "

a. CLO: SED

.; c t. c:-.;;. E rJ r. e 1;ci. AE-! . . u: - : + .;m. . : 4. SOP-I n 8, 8%cLe.A I A, pp. 4 +9

. . . ~ . -. .- -. .- - - , - - - - - . - . - _ = . _ . _ _ - . - .- . - . .. - .. . -- .~ -

1.

i j e .

i e

I j~ i j .

I I

i !

t l I i

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p> t .- , . ., 3 . - ..v.- 1,. - e>>n u c 4 i - . 1..,4

, FLnN

. i i a , a e t. .ra .2., "T".0L. ~' ,N. r i < 4 t,- -.. ;.e.

/.63MERS -- iUnhER -5"/11'13-aERRY DGUGLAi U U t / 0.,. 0 ~ n, ;,; e U u \._;.?- '"e - ).

i f

, ANSWER 5.06 i t.001 i

i

s. TRUE (0.5 1

-D. ra' MLLt ,' e' s

ret te cri t.1 .-

.,: .'.. I8.- . Nuclesc nstrumentation ! v i t o t.

ANEUEF e. 0 ~ (2.00'

! :. DECEEASE i.0.25) i h.E M n,. .t .rJ . ..

' v, . , ,s ,

b. .He anne i

l c. EhAIN THE 3AnE (0.25i ,

4 L

F, t n n ,e d 4 He :..n, t_. t v. . . . ' . -

i l- .: EFEREriCE

!, lF . Tsv3 Delta T. and i .t. ;;, . cp. ic ?. i~

sor r s. -In s tr ument a t ion nano:1 .

j .nect. . -

p. A k. ,. , . -.

.J 6b H , LP _ .n' e a c

a r 'cclant , +t.p e r t t o r e i n s t r v ti e n t a t i o n ,

p. a ;

- mF d . - u - p. ~.

t. ... ter +t.,- ,

'! ; ..-. .. e s c *. , - _

- r c t e c t t o r, 3nd Lo 31c t

.- . , , , c., _ p di. l t , ,- .: 3 t4 . ..

I

. N: - 9 E P .02 '1.00' ,

i i~

! s. HAVE NO EFFET., tv.!>

t ,. -

i s. t,. r. , o. p t ; ie.,' >

1 1 F EFE;EHCC j . - -

- s. t ,i . e nnalv4t+. - -. ,

1. ; . cntrq.a .- -' :, .

p.

I r,N5uEF :.c' (1.005 t

4 f

'm, ) I O \ j ' '. i l %. , 6 d NII j produces t r i t i v ri, . , 5 pts.! f 1 . '.' !

I J

r 4

h i

v i

I r

i 1

4 1 ,, - - - 1

c. - L sn .Ji . ..- r,3 p : ..- ,--_c..

.; a i u 4 . nu r 3in,.

.. - n. i_ - .< n t. :. j .- ., , . .. . ,i

. r ., u E -;:

ArsIWERS '-- 3 U h.1 E A -35 11 1 3 - J ~ .' - ~. 0 W J, .

r. E r__rte _ tJ _LE

.,,, C c . n.E. J.

L ,., L -: t .-

PP. o % i<

004/000-F4.06 s ~.3J .')

ANguER 3.10 1.50

.atats -t n j e c 4. t o n : .13nal to.; ts. A rJ E . ..; .,3

_. 4 t v . ., :ts.*

RW5T le,el (0 I, ets. less ,in 1 0 *. .3 cts. 1 . 5 '-

FEFEFENCE -

,J C e . ,c,. nHF, 2 s ; t .n r p. 16 OCe'0:C-A 01 < ..:/4.3i ArJ - W EF :.I1 '. ~.00-

5. 1. ti s 0 H incisttan ;s l' a s apen (0.5-

. 1, c r e y- ciscostge iscirtion .s..es 'open> 'v s-

b. L. F4II suction alves open? (0.5-

.~.. 5pr,c p u m ,: s (statti t .5' LEFEFENCE

.,en .n -

~- c; -

.c nc a r c 2. r2. -2 ; s ', e m . ,. .

0 u t, . vuv n..c

u.a: -. .s

-rs U Er . i, .- - 1 . e. v, . i

+ v . ,s >

s. .

O

_cct _ 03.- 'v. s -

c.

- 3 ecco: - -a eite o'ovncsrv oose tiu t a.. ,3.

tr s :. i n j l e t a r.1 'ottures. ' . ..

- E c.c- _r1 t c.._

'/C - - AS-1:r W e s t.: Gss 3vstem. ra . 1,

P1'000-E6.10 ' . '_.3/2.5i

"* I uuJva / Je .. ').s sr e____________.__

s. FLANT SYSTEM 5 DESIGN. C 0 rJ T R O L , A r4 D IN S T R u rt E N T A T IO N ,'E 3-Ar454ERS -- S urih ER - 8 5 - 1 1 ' t .: - ..; E P E 1 DOUGLn; ANSWER 6.13 (2.001

1. The lube oil ra r e l v b e system circulates cti 6. n r e , 5 3 s oester ta normz1 Ivoricstion components. 1.?i

2. The c: cling water 'reep warm system :trc':13te w: +er t n r :. . ' 3h heater to n ci r m a l u s t e r - : c o i e r. : o n. F o r. e r. t s - .0' REFEREr4CE VCE, IE-5, Diesel Gener a tor - pp. 34 .

35 064,'000-M1.0: (3.i'1.s.

-Al.01 '3.c/3.1)

A tJ E W EE 6.*J 1.0;

.. ,- . . __ r ..! 4I r- #

-rl y -,,t t.- n' . . :. , t ri 1 MT -J.*40 ( F D P'.'

Z, utja Fressure Alsrni I. D.'U Hester Contral J. ..c w Fressure A l a r n.

3. Fro ort:r.nsi Hester C o ri t t e,1

- F.y-aaa C ( c. i ( 3 r, r :

PEFE;FNCE VC5 TC-i, F:- Fre-sur, c .; Le..I : : r, * - .

~

. *25 r- ;. ,

4 TC:.-

n. t , a G, u- _ o .1,. a.:. '

-999*

Lou + .: t t a n e e r -a d uiy r s r. 2 e To or Te la.. 'iac .2r : aD srn

El 5.;: t ; m e, 'J s l e m nt (v153 0ser,. 55o 9

E R; E r!C E

,,I.-*

1'. ;- * - ^' _ '

P- -

r 3 r, O ,.2

. .L .. ~ . , . 'r ,, . ,

Ai1 E U E F o.1: 1.3':

EU 1 ester c o rn e on >

.' n'.- 2nd :n 3 r 3.n 3 f.u- r . 'l ti- :, t r w c. .1 Ft+.) . Level o e : r es a s e s ~1 t. it l ' *. ..! -* . 1. 1 i.'x-a 1 31stes 0.1 ,t. ; . ..e c er turn aff 0.1 .t.i. _a ,

31srm 0.' -t .

Lese

Increase + 0.1 tt. . Hiyh 1cce s i e r a, '

1 .

st ' ' ' . f.v.1 t. .

High le,e! trtp ..' .t . . st i ' '. '.1 pt. .

i.

s 4

s. PLANT SYSTEME DESIGN, C O N T F:0 L . Ar4 D ItJ5TPunENTATION FAGE 22 i

ANSWER 5 -- SUMMEP -35/11/18-JEREi DOUGLAE.

f I REFERENCE ~

3

'J C S , Control Svstem Fatlure Analysis. 9 1

a l

ANSWER 6 17 (1.00)

Direct iaimer s ion (no weld) decrosses the time it takes *ne PTC tc respond .

l to a temperature enan3e.

REFERENCE

'/ C 3 r IC-6, Temperstore Indication 3 vat,em. p. 14 i

i AN5WER 6.10- ( 1. 0 0

i. 5?1 de3rees F (0.Si D. Warns operator he is approaching Dr1E; LCO. (0.5>

FEFEFENCE

^

'/ C 3 , IC-6r Temperature Indication 3vstom. s. tr i AN5WER s.13 (1.50)

L 2

3. rii th t .: Lcw . C. 5 i (0,5i

b. Fed : e s e n :i to li v e r e 3 e e

a PEFEFENCE VCE. IC-5, HI5 pp. 3? E 42 A d i L E F. 2.20 (1 50s I r. t. 60 seconc time delsv :1. 5 )

2 En Trip Ei r s operi (P-4; 2 0 . 5 '.

j

c. F :: Trip Bi r s closed ( F - 4 0,5) 1, i REFEF'EtlCE .

,,I...!P r II, * * . h f, csf @ e- u.

j 4

e

[

]

j-h

. FLANT 3'!!E13 :E3IGN. CONTFCL. A r4 0 :NiTsinENTATION . ,'. G E 3:

A ri 5 W E R S -- EUrnEP -3 5 /11 c' t 3 -JE R F 'iUGLA3 ANEWER 6.21 (1.00i i h t.*, t i n g o n e seno: 3 trip signs! to the ether. E'atn cannot be shut et the same t i n.e . >

t'. ca ~t ". M C. N.'-- --

C5,

. IC C, EP5 c. Ic ANSWER :. i. i . 5 0 '>

(0.25 FOINTE EACH) 1907. FLOW ) *. FLO4 UPPEF :S tc0-70i 100 (?5-105i NAPF0u tLS 110-120) 100 (75-105)

'JIDE In3 5-105i JO 25-25 FEFERENCE

'J C L: . :C-13 F '.' L I S , F i p; r e. IC12.-

o d- a, ,s cY ._

L- . : '.1.'U' M 3 kI O.6 M N

i. S b' 9 5 3 1 4&6d '! 9 'i *. '. . $ .'

. D 'i i T. EOeOWCtf~ ~6.5)

~, E .Tr e r , F09GW5t@T '0e5)

d. F Po3 9 0 c 'Sgeh v.Wes f,E EFE9CE

'> c 3 IC-;;. Ac a.;; t i c _cs, r.c n t t a r i n g , s. 2.1 OperM en & Matalenante. N%.1.por TEC. Mode I tilt ~1- 04) 1

s I

t f

4 T

'. PROCEDURES - NORnAL- A B r+ 0 E n AL - EnEFGEt!Ci Aim FAGE 40 i PADI0 LOGICAL CONTPOL ,

i y ____________________ ,

, ANSWERS -- 30tinER - 9 5 . 1 1 / 1 5 - J E R F t' COUGLA3 !

k 3

n i

j A'4 5 W E R 7.01 (1.00) a 4 i a -

r.c_-,.NCE r ene ,

i CAri TS, 2.1 VLor es, _.1 f

I ANSWER 7.02 (1.00) ,

i d l t

FEFERENCI

~

3 ttry, EF-1.02A- p. :

' %N, El-0.i. ra . 5

--..,1 4 . w, :

,i .i l- *-_* LUr .r*

"){ 0 / 0 0 ? -K ' . lc *4,4/J.5) f f

f i

% 9 0.- (J r p - . ,,w.-

. ,. 4 . ' . , .

J

] O 1

1 R t t r *.E fit L !

i -d 5. ' AF'/ Z./ A / 5 500 /16 Cste IV, p. .

C A ~ - A' '1 ' A.'5 5 M 16- s ie IV- 7 14-

.i,... .:. s.

_44 .- - ., c.._..

. . . . .t

.,um.

u- .. ., ,

u,,. vu

. ,n,.v.: .,.z a.,-

t

[

n r ) ..:- . . E r- , , i . w, , .>

a

.i

~ ,

. -rec.c.epcE

. - m 3

10 CFF 20.101

., ,s., ,~~; i1,00) c F EFER EllC E VC5 E0P-12.0, : J~~

~~7. PROCECURES - NORMAL, AENOFMAL- EMEF.GE1C( AhD * ?, G E ::~~
- - - ~ ~ ~ ~ - - - - - ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ -
'EdE56E66fC5L E5sTE5t AH5WEP5 -- S uriMER -35 11 !' .!E5F 1 lGLAG At45WEF '.10 i:1.00'
- F e.. t-st E. r. h. r.
VCS, 30P-401, Re sc t :r Protection 3 n .1 :o r.t r c i .
.. :. 15 ANEWEi 7.11 (1.50'
- s, tE2 '. u . ,. '
~~r. v . ,s )~~
~~b. Nu.~~
~~c. NO 0.5)~~
F.E F E F E NC E
- 20s .r -11 . . .:c.vice ,- , r *. e r
,h....
~~,s eew. ,.. .~~
~~M r's..~~
~~d L t . . .JV' s' O . 5 2 0 DJ T 5 E /, C H 'i 1 1600 pt12~~
~~- , . n I~~
* .s c"Jf443
)','
l 'J f f.1 e.. - . s t ,.
..g'.
5, > .u , G e -]t e e s t-
~EFC ENCE lcs. GDF-2.,.,:ca..;t A. c. ., . , a r i c O p a r +. ; , ; ~r- :=i+. .
r t b, _DU !. t.-
~~1- '&*dV'~~
'.' ; i , t [ r*
i+ ,i* *
~~l] .~~
~~s- teIs4C .? I. e 14L l~~
~~pae os re es =. y e [~~
f C I I. " P. e T 'ee b 't P* *
~~I I.gL :.* '~~
~~f {Ag t a . F j. ' , . ' s I~~
l 1
l I
i i
\
> F50CEDURE3 - tiGFMAL. A S tJ 0 E n A L . ~hERGENCi 1. ri r; F AC!: 13
--- iIoi5C35fcIC ?5 rife 6C-~~~~-~~~~~~~~~ ~~~~~~~~
AtsSWEPS -- 3UnnER -35e11,'3-JEFRr 00VGt.As AtJSWER .14 (1.50)
~~3. Within l'5 minutes :f commen:tn3 Control 9ank rod withdraws!. (0.5)~~
~~b. Two. one of w no ni is ER3 licensed. (0.!'~~
~~c. Within J hours prior to criticality. ( 0 . 5~~
R EFE ret!C E
'JC3r G0F-i, pp. 1& 11 AtJ EWE F 7 15 >
1 00i
~~t. R > r. o w .a r 90% OF I0.51~~
. Roc position 215 steps i b a r,6 Ci (0.5*
REFEREtlCE VC5 GDF-4, p. :
Atl34ER 7.16 -
!.00)
Close the RCF A 's e 31 1 -i s k o f f .' a i v e . P'.' T - C 141 A i F EVEF CtlC E VC3 30P-tQi, G. e s c t o r Coelant isster, pp. 51 1 5:
4 t21 W E F .1 :' (1.00)
~~1. ' e d o : -) 1 > tdwn 'o 45 jpm~~
'O.5)
~. C ntrol p:r level using (lo:ali F C '.' - 12 : oypast s a l v r- (XVT-0402) ;0.57 CEFFFEllCE VC3 I O F - l " . C ' . 3 s.. 37 A M e
-_.m
7 FR0CEDURE3 - NORMAL, A B r4 0 P M A L , EnERGENcr A rJ D FAGE 41
~~AnIGLOGICAL CONTROL ANSWE-3 --~~
~~iunhER -35 it.i3-JEFF( 00VGLA3 ANSWER' d7.15 (1.50)~~
~~a. No t-i s t r i c t ion IC.Si~~
~~b. 600 ( 0 . 3 :'~~
~~c. hinimum plant load (0,5)~~
REFERENCE
'!C 3 , 50P-210, Feedwater System, pp. 35 3 16 AN5WER 7.10 (1.50)
~~1. Roset mechanical o.erspeed, if applicable (0.5)~~
~~2. Momentarily place EXCITER twitch in SHUTDOWr! (0.5)~~
~~5. Depress 4EN RELAYS RESET pushbutton (0.5)~~
REFEFENCE
'J C 3 10P-30e. Emer 3 enc. Olesel Generstor. p. 5 Ap5uEP .20 it.50
~~1. 3tcp ins chan3e6 in reactivity (0.5i~~
~~. Fisce rod control system in nANUAL 6 0 . 5 '-~~
't . Aojost TsvJ by edjvitin3 torcine load a
}.5e FEFERENCE
. r. 3 SW-43, Fed Control and Fasit:on T,at 'in3 " 4'.cm. -. 14 i
i i
i l
l
~~7. PFOCEDUPE5 - NORhAL. AENOFMAL. E1EFGE:JC t A rJ O FAGE 45~~
~~~ ~ EZ6i3[3 5 5[EE~E 05iE3[~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
ANSWER 5 -- SunnEC' -G 5. 1 1.' 3 - JE:f,f DGUGLA:
ntJ WEF
., . ( .:, . e - -se-(0.2 1.
F.OINTS .
EACH)
. rtp F. x n a n u s l ,i - u...
-ts.. :nc
.: r i t . _ _ tu .>.., ,
~~2. Ensure turbine tr:p 2 . ,,e~~
~~< r i f v 3 ,. tess. e :ne -.-n as e n e r 31 : o :.~~
~~4. Verify EI sctuated~~
~~_ t.nsure .. W, r tscisttca~~
~~t. Ensure n~W pum r trtrreo~~
. _.nsure t .Fu
., u c. r. : rvnnin3
~~t. t. n s u r r. at puni s t unnir 3~~
. rn s u r

. ;'hs;e ?. :en*:tnment I:a l s t t :r.
10 Ensure F E C 'J 7 ic.1 c' . r. slow ipea. 1 t, t .
t:. Ensura : J - ci : -
- -+
c .1 ,
,e.i 1:. Ensur, : 51 o c. c - t e r p.m:- r u r. r. i n g ti. Enter- : -u,w a r. : r u r. c .1 - ,
14. Ensure n : t r. t e r n, Te- -*
'n- '
ret- ,
* ,+
~~.- c-~~
~~., 1 . ,,n ,~~
.r. ..r. .i 2
- c cs .. . 1
.-1, ,
r- - t , c. . o. .
,J..,__
~~-c. . _~~
t - - .i.. r; i., o, .
-+
.- - ..r.- .
n_ . , L- ' ' ri. - 0
~ r;:. ' -
tr-
.~
r- , : y :s. e ..-, t "9 NI-5 Signa \ prC6e.ok 6EFEFEE E uc ----, EOP L e.as o e) Plan t 9
c.
, . s
- 1 r) : *. ndD- L1:tIr.rt a,r4, a, ._ .. . .
cunits,_ ine, it n.g r R O.L, E D U R t : +
~~t. O rJ r.'-t i- tt r A t, r-~~
- 4 a ri a_ .4 E _,. : -- .: 1, r.n . 4. -.
- t r< ., ,..
~~s, , , , . ,..-JtnRt, e 0 0 L t.n :~~
ANSWER B.01 (1.00
s stetn - .Eth,-. .t E'f r P * .I37 ?. 3/I 5-I1
,.L:.
r o,-
3 e., - l ..
J.Mi4ER :3 . 0 ^ (1.00)
~
EFERENCE
,,Eb
, r 3 -Tt, p, t; J/. c-1
/C3* I '3 ? pi E ~'4 J/ -[
et ND,M t h C e ') O ' 1 e V 'd .I
'aA EFeRENtt
=
K t esCb' I: P F. .- .
g e
4
- '. . a
. . 3 , - .
D.j.,
~~$b e, b & o a~~
~~p=p.e. =~~
~~es e ,~~
~~b m.~~
~~.qe~~
~~,,.,T. .~~
l: * .-
_ . i . .
.c e
u t. s . : . ': ;- ;
'i C '3
~~I '~: ? ?s L-L~~
3. ADMINISTRATI"E PROCEDURE 3. CONDITISh3, AND .. I h ! T A T I O N S : AGE 4-ANSWERS -- SUMMER -35/11/19-JEF ( 00UGLA3 ANSWER 5.05 ( 1. 0 0 :'
d REFERENCE Surry, T5 .3-7 WEN. T5 p. C :-5*
HBR, TS, p. .2-5 VC5, T5 p. S -s ANSWER 2.06 i:1.00) b REFERENCE WBN- T5, pp. 3/4 2-1 e2 VCS. T '3 r p. 3/4 :-1 ANSWER 8. 0, i.1.00) b REFERENCE WBNr ~5r 9 6-t V0 5 r. Tir p. 6-4 ANSWEF 3.00 i1.00) s REFERENCE WBN. TEr p. E 34 6-2 VC3 T3, p, 63Ja .2 -;
ANSWER 8.09 (1.00) b REFERENCE HBRr TSr p. 4.1-1 VCS, T5, p. 3/4 0-2
, e- s G. Aun1N15TRATIVE FROCEDUFE5, E 0 ri D I T'I O ri 3 A ri D m In:T A TI0r4 3 : ., c. E .: 3 AtJ5 4 E R S -- S U rirt E R -55 11 ! .3 - J E F f ( ~4JULA3 At15NER 5 10 t2.00' 3.
fta ' ') . c.s )
~~b. tiO t 0 . 5~~
~~c. ,( .ta * * ! . e..~~
~~6. t20 J0.5>~~
REFEREtlCE CAT, T3, pp. :</4 1-10 1 14 and 3/4 4 -* J to VC5 75- pp. 3 '4 1-10 & 14 and 3/4 4~ & 10 At4 3 W E P 3.11 ( 1.50)
.,. em.L e ...a>
b. FAL5E (0.5) s: . i"~. U E (0.5i
- -t E.
r: r re tt v e.
'J E ; F . T5 pp. 3 'J 0 3 U E r! . T5 rp. I'a 0-1 !
UC3 79 .p. -'4 0-t i ;
1.00 At4 5 W F F 6.1: >&
~~s. AFTEF :0.5i~~
~~,.U . ,; !~~
D. tErd FL- -- "
-~~~
CELETEb P E F E F E tJ C E VC3 3 AF -200, C :n > ' :f 0,seratient. Atta:hment r
~
A ri 5 i2 E i ~ . O C+ !
~~4 '0.5i~~
~~b. : (0.5'~~
,,.e>
a.
4 s
".F.
A_--
G. ADMItJISTRATIVE PROCEDURES, CONDITIONS. AND LIMITATIGHS FAGE 4?
AN3WERS -- SUHhER -9 5 ' 11/1:3-JERF r 000GLAS REFERENCE VCS,'TS, p. 3/4 4-1?
ANSWER 8.14 (1.00)
~~a. HTC more negattve.at E0L I 0 . 5 ',~~
~~b. More mass in $/G at no load temperaturn (0.5)~~
REFERENCE VCS, 05-G, Accident Analvsise p. 31 and TS, p. B 3 ,' 4 1-1 ANSWEP 9.15 (1 50)
~~4. C735 psig (0.5)~~
b. Be in Hot Standby (O.7 pts.i sno notify HRC (0.3 pt5.) 41 01 PEFERENCE-VCS, TS. p. -1 ANSWER 1 .16 (1.00s
~~1. Another sertes of t135 are issued (3.5)~~
2. APF licaol+ in f or p.i t i on 1+ >dded to ist13tnal and yellow copyi Ganger 1 03 Log wet streanv tn efract, ig,5; REFERENCE
'!C S . 3AF-;01 Danger Tagjing, 9 15 AH i.u E F B.1* ,1.90) .
~~t. Suaitfle1 :' a n s e r T M ter~~
~
(U.5)
(Cor*ent UF : ,2- 4 r.i d >0.5)
REFERENCE 9C3 iAP-201, Danger TagJinj, p. 5
c
. .. a i
1 l
~~6. ADhINI57R ATIVE F ROCEDUEE3, C0t4DITION5. AND LIn!i ATIOi43 FAGE 50~~
! AN5WER5 --
SUnhER - C 5 /11/ t E6-J E F E Y DOUGLAS ANSWER G.13 (0.00) i
~~4. 3ITE EMERGEtiCY (G.5i~~
! b. ALERT $0.5>
! c. ALEFT (0.5)
~~d. SITE ENERGENCY 'O.5i REFERENCE~~
( VCS, EPP-001 Attachment III I
l ANSWEP 8.19 (1.00) l
~~t. 3outh - t8'> c l e a r Trainin3 Center <0.5)~~
~~2. tio r t h - Marticello Fe orvoir Exrestional Fa: 111tv 60.5' l~~
~~l REFEREllCE VCO. EFE-01;. p. s AtlS4EA 1.20 ( l.00-~~
~~1. 21:' Level Centrol ~utidtnj t 3 c o t a.> a t t stat well' '0.5~~
~~2. 13c' ' evel T o t .: i n o E.u 1111 n 3 { uc t t End' REFEFE!!CE~~
CI.. EF F ^ . 3
. p. 6 M.TuCP 1, 1 t.Vi
~~1. .. t t' o - t00 ; c .1 id.5'~~
~~. '. " . E n ;' . 5 -~~
~~r2..tr 3~~
~~c. c n < ,,,; y V ,. ;- .;, p. :~~
1 i
1 i
I..a t
i
)
1
\
i 3. A0nINI3TRATI)E PROCEDUFES. C0tJOIT10N3r At t. IM I T A l l C ri : AGE 51
_______________'_____________________________'C ____________.
Atl5WERS --
SurinER -Wt '!!-JERF1 00UGLAT ANSWER 8.22 (1 0:)
~~1. Level ?:% (0.5)~~
~~2. Two groups of heaters (0.2 pts.- each witt, a c a p a c i *. y of 125 iW ' 0.2 9ts.) (0,5)~~
~~REFERENCE VCs. *3 ,.. 3/4 4-7 AtJ5WER 8.23 (1.504~~
~~1. 0.tyjen (0.5)~~
~~2. Chloride (0.51~~
~~3. Flooride (0.5)~~
~~REFERENCE i VC3, i s , r, . 3/4 4-;3 ANSWCF D.24 i .00i~~
~~1. Isolation velve (0.4 rtsi e o r. a n ',.i r, t i <0.!~~
l l :. uitor volonie (0.4 p t s .' o c. t w e e ri 'hi . !;4 3 311 o ri c tr.1 pt (0.5 3, E.orCn co60erstr a t ion eO.4 "*3
,. .:ntwa .s h i ; *;') Or. ~.10 0 7, n. 1 - .I r et> i<'.5)
~~4. ti i t t o p n prersur( S.I c11 b e t w r- e n , ; So p;1y 'O.I pi <0.5)~~
FCFE:CNCE
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s.
.

ML20151R997

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