Text

Exam Rept 50-423/85-44(OL) on 850903-06 & 09-12.Exam results:11 Out of 14 Senior Reactor Operator & 3 Out of 4 Reactor Operator Candidates Passed All Portions of Exams & Will Be Issued Licenses
	ML20136D971
Person / Time
Site:	Millstone
Issue date:	11/13/1985
From:	Dante Johnson, Keller R, Kister H, Kuscitto D, Ruscitto D; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:	;
Shared Package
ML20136D930	List: IR 05000423/1985044; ML20136D926;
References
	50-423-85-44, NUDOCS 8511210400
	Download: ML20136D971 (106)
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U. S. NUCLEAR REGULATORY COMMISSION REGION I OPERATOR LICENSING EXAMINATION REPORT EXAMINATION REPORT NO. 85-44(OL)

FACILITY DOCKET NO. 50-423 FACILITY LICENSE NO. CPPR-113 LICENSEE: Northeast Nuclear Energy Company P.O. Box 270 Hartford, Connecticut 06141-0270 FACILITY: Millstone 3 EXAMINATION DATES:

September 3 - 6, 1985, and September 9 - 12, 1985 b./.

//!4f/6 CHIEF EXAMINER:

0. Ruscitto, Examiner Date

hJe Nh M REVIEWED BY:

0. J6hnson,'ead Exami r

Date L

ilb

s R. Keller, Chief, Proj ct Section 1C Date Approved by:

/47 N if. Kist'e(, Chief, Projects Branch No.1

/Dat6 Division of Reactor Projects Summary: Oral, written and simulator examinations were given to 14 Senior Reactor Operator (SRO) and four Reactor Operator (RO) candidates. One R0 candidate was given a written (first) ratake examination.

Eleven SR0 and three R0 candidates passed all portions of the examination and will be issued licenses. Three SR0 and two R0 candidates failed the written examination, and their licenses were denied.

0311210400 851114 f* DR ADOCK 0500

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REPORT DETAILS TYPE OF EXAMS:

Initial X

EXAM RESULTS:

l R0 l

SR0 I

l Pass / Fail l

Pass / Fail l

l l

I I

I IWritten Exam l 3/2 l

11/3 l

l l

l Oral Exam l

5/0

14/0 l

l l

l Simulator Examl 5/0

14/0 l

l

I I

I i

10verall l

3/2

11/3 I

I I

l l

1.

CHIEF EXAMINER AT SITE:

D. Ruscitto 2.

OTHER EXAMINERS:

B. Keller, NRC 0. Coe, NRC R. Schreiber, PNL L. Defferding, PNL 3.

Summary of generic deficiencies noted on oral and simulator exams:

Minor deficiencies with no safety significances were noted in the following areas:

A.

Knowledge of how and where to trip protection and instrumentation bistables when I and C assistance is unavailable.

B.

Knowledge of the approximate contact dose rate levels present on recently expended fuel assemblies.

4.

Summary of simulator deficiencies:

None.

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.

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i

5.

Summary of generic deficiencies noted from grading of written exams:

'

R0 Exam (Five Candidates)

l A.

Core characteristic changes over core lifetime B.

ECCS mini-flow recirc valve automatic features and interlocks C.

Location and purpose of Radiation Monitoring System components SR0 Exam (14 Candidates)

A.

Bases for S/G code safety setpoints and capacity.

B.

OTAT and OPAT setpoint changes with plant parameters.

(

C.

Reason for loading emergency diesels greater than 50%.

-.

D.

Difference between Containment Instrument Air and Instrument Air.

E.

Basis for pressure and temperature limits on RHR system.

6.

Interface with Plant Staff During Examination Period l

Liaison with plant staff was good and the simulator instructors were helpful in scenario review and modification during the course of several scenarios, which facilitated the examination process.

-

7.

Personnel Present at Exit Interview:

!

NRC Personnel

?

D. Ruscitto, Chief Examiner D. Coe, Examiner B. Norris, Examiner

+

R. Starostecki, Director, Division of Reactor Projects i

.s:,'

Facility Personnel

,

J. Opeka, Vice President, Nuclear Engineering and Operations R. Test, Director, Nuclear Training W. Romberg, Station Superintendent

,

J. Crockett, Unit Superintendent

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K. Burton, Operations Supervisor M. Moehlman, Nuclear Training J. Black, Simulator Project Manager

,

H. Haynes, Simulator Technical Systems Manager

!

R. Lueneburg, Simulator Program Supervisor l

R. Stotts, Nuclear Training i

l 8.

Summary of NRC Comments made at exit interview:

!

Generic deficiencies during oral / simulator examinations and interface with plant staff were summarized. No preliminary results were given.

9.

Examination Review At the conclusion of the written examinations, the examiners met with licensee personnel to review the examination and answer keys to identify

any inappropriate questions relative to plant specific design and to t

'

ensure that the questions will elicit the answers in the key and that they reflect the most current plant conditions. The following licensee personnel presented the comments to the examiners:

!

J. Crockett R. Stotts

!

l Attachments:

I 1.

Written Examination and Answer Key (RO)

l 2.

Written Examination and Answer Key (SRO)

l 3.

Facility Comments on Written Examinations made after Exam Review I

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NUCLEAR RECULATORY COMMISEIGN REACTOR OPERATOR LICENSE EXAMINATION FACILITY:

HILLSTONE 3

_________________________

REACTOR TYPE:

PWR-WEC4

_________________________

DATE ADMINISTERED: 85/09/04

_________________________

EXAhINER:

COE,0.

_________________________

APFLICANT:

_________________________

INSTRUCTIONS TO APPLICANT:

__________________________

Use separate paper for the answers.

Write answers on one side only.

Staple question sheet on top of the a.n s w e r sheets.

Foints for each question are indicatec in parentheses after the question. The passing grade requires at least 70% in each category and a final stade of at lcast 80%.

Enamination papers will be picked up sin (6)

hours after the exanianstion starts.

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MILLSTONE 5

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REACTOR T(FE; FWR-WEC4

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EXAhINER:

NORRIS, B.

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INSTRUCTIONE TO APFLICai;T:

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Use sepsrat,e paper for

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Write snswers on ont side only.

Ettple question sneet on top of the sosser s r.e c t s.

P c i r. t s for etch question are indicatec i. n parentheses after the ques *,1cn.

The passing 3rade r equires et least ' O *. In each cetegory end a final gr&de of st least 807..

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DFERATION. FLUIDS. A b' D T H E R -i 3 C 'r N A n IC E ne

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PEOCEDUREE - NORMAL, ADNCRMAL,

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EhERGENCY I.ND RADIDLOGICAL CONTROL

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ADMINI2TRATIVE FFOCEDURES, CONDITIONS, AND LIh1TATIONS 100.00 100.00 TOTALE

________ ______

___________

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rINAL GRADE

_________________.

All wcrk done on this e:: a n i n s t i o n ts ms cun. I hsse neither 31ven no: received aid.

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THERnGO nan:C3

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Q UES TI0 ri 5.C1 (~.00.

In acecrdance with 10CFR50.46(b,(1), clacains temperature is not pern. tte; to e:,ceed & certsin setpoint.

a.

What is that setpctnt -

0.53 b.

Why is this limit impcsed?

[1.':

c.

Wha'. hsppens to tne :ltcalcy as temperature increases pa st the n. e l ', l o g rcint?

CD.53 OUESTICN 5.0 J.. : "> >

The reacter is c p e r s t i r. g s ', e : c. - s t a t e s t.

50%,:curr. steam gen:ratcr pressure is 102: ps13 How n. u c." w:..lc Tsag have to incr ease 10 causc t h :-

fir st stesm a c r. v.

s t, c r tsfety ssice

+c lift w i t.-

power constant.s t 5 0 '. '

.

Stste all as s ump ti cr;s ans s. n o u sll u;rk.

GUESTION 5.03

<3.CC a.

U p l a r.

why dels.-ec neutrons.ts s e such a large effcct en r 4 a c t,c r operationsi incivce in voor 6:scursacn the produc ti cr.

of both prempt and d e l a,. e c neutrons.

1.5

....

t;.

Wts cres E+ t s-c 4 1eetive chsnac o v ;: : cor e lifei E 0. 0

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3la kfe.

'ssts ter ti,e start-up Rat.e 1.ti c. e c i a t : 1-c.

Calc.;1st.e anc e.. p l e :.-..w c-A following a r es etor trip.

21.C3

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u, u t.:,. A C n

..,. v 4

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.u..t, 1 a

Assume that the p; ant has,ost coc.pletec a n.aintenance perlad cf 70 days, early i r.

cere life; s.

E::p l a in why the i r> t r i n s i c neutron sources alent may not be sufficient to n.e e t all requirements for s reactor startup.

[2.03 b.

What are the installed sources and how do they react to previce neuttoris f c'

s t e actt: s tar tup 0

[1.03 ( A.* * * * C A T E C O R ': 25 CONTINUED ON NEXT FAGE.*****,

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GUESTION 5.05 (3.50)

4.

The re actor ecclant s y s t e a.

Is maintained withir. sp ecit'ica t ton s by use of the f oll ow1 rig che::.i str y contrels, enpla.in each r e acti cri E5.03

'

(1)

Lithium H y c.r c': i c e - pH control (2)

Hydtanine - c u y g e r, c or.tt ol (3)

H y d r o g e r. - cxygen contrcl m

b.

Why is withium-7 used vice r.s t u r a l occuring Lithiup>

[0.53 GUE3 TION 5.06 (

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-6 You ar e i r. the pr oces s cf start:n3 ut tne p l t r. t witn t' e 2.

t o r power at IC smps.

The reactor cparator i n a d v e r t e r. ',1 y moves rods in for

_0 steps.

~

A S s unie roc Werth is o p e::. < 1 ri a n d s ri aveisge neutron p r e t i.i r s c r

.d e c a. y c o r. s t a n t, cf 0.1 see-1; wit:.

c. c forther operstor s c +. i n c :

L.

Wnst 25 the retelting S U E.

i r.inic c i s t e l y a'tc; red r.c t i o n s t e p ~~

[1.25:

b.

What is the p o t. c r stter cu m i n u t,: ~

CO. 52 QUEETION 5. 0

(2.0D a.

Definc cendensate c c p r c : 2 : c c..

C1.0:

b.

Define : s. i t. s t i o n e r.

e :. p l z i r, how it :s c f f :- : t c t' by cterectin3 condensate deptessien.

[0.T5:

c.

How is p l a r.t efficienc, affecte-; c ;, eccessise ennoenstre c e ;.r e : s l o n Co

c-,

4 e. sd 4 (**zt*

CATEGORY 05 CCNTINUED ON NEXT PAGE

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THEOR'r GF r.UCLEAR F 0WER F,_ A ra 7 0FERATION. FLUID 5, A;K

AGE

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GUESTION 5.08 (5.00)

The plant is operating at 5 3 !. Power when the il 5/G nain Stean. Isclation

alve f ails shut due to loss of electrical power.

Usin3 tne below inat;al

.

conditionst calculate the new itead state values for the listed parameter 2 Assume no op.erstor at t i ore. ;;' --

, : ::.

_.. -.. :, and rio r eactor trip.

State a'l assumptions and show all ucrk.

Initial conditions:

Tass = Sc7 F

/ g, /,,,, c,, / u /,r,,, a u /c m,/ec

.m..... - $.cr

"'W r<sec h ' e en /nl.1 < h.m nue. f

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Tur bine power b.

Tav3 (for the affected 1ccp c.

Tavg (f or the ritn-af f ec ted loops d.

5/G pressure 'for the affected 1 capi e.

E/G pr essurc (for tne rian-af f ec ted loops-GUES TIO ri 5.07

,~.00.

-

Indicate at which time in c cr e-life (COL cr EGL) the following a c c i d e r.1, s ar e r.o r e se.e r e. r e sul t :n a longer t 2 n.e spent 5t h;grer peuet

).

E.r t e f l y enplain why.

Main stesm line br ed C1.07 b.

Tetal loss cf coela-t 1;;e

1.D3 c.

Rod wit.7drawal sccide-t frcm Icu in the scurce rsnge pr:ct to-s c..

signifitst.t r e s: tor coolar.t tcmt er atur c increase.

1.03 GUESTIGN

" 10 t1.50)

Explain how incicated reacter scwcr would cnan3e (incresce, 2ecrease, cr ren.ain the same) for the following conditions.

A s s ur.e actusi powtr r e n t i r,s ccnstant at 75%.

CONSIDER EACH CASE SEPARATELY.

c.

Cooldown of the reactor ecclant.

b.

Core aging.

c.

Decrease in boren concentration.

( z s z. x x EN-Or CATEGORi C5

- - .sa

.

4.

FLANT SYSTEhi DI51GNr CONTFCL, AN: INS TRUr.EN T A TIOr>

CAGE

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

GUESTION 6 01 (2.23; s.

What are the cases for *ne first and fifth coce s a f.: t retpcints? C

.5"

,

6.

How niany coce safcty.alvts per s t e e n-generator e c r, be c e c i a.: e c;

gp. p e r a o l e ino during power o p.E r a t i c r. '

What 1 :::i i t a t t a n s tre placed on operatians?

(setpcInts E t i r.i e f r a n.e s r,o t requi ed)

E0.~53 r.* y - T...

c. C,.,

..._;,

t A o r*

=

.

The reactcr ts ope st:ng at a steady st6te 25', power, all contrci systems ar e in attonatic.

Turoine Icac i t.

1r. reaseo tc 100. and ;. n a c ar,tr ol l i n g steac, prestorc cetector f.; r 41 E,' O s t i c i. s s i. tne Z :.. a 'i v.:.

2 ;.p l s i n, in detail, now ana wh. t h a a. L1: 1 e f f e c ". 41 stern gene r stor level - c a s.u ni e no cperator action.

State sli 22:cmpricns ano shoi. ail w o r k..

(A naoner,ea l ans wer is Mc 7 r ef a 'r

DUESTION 6.0:

( 1. 5 0 ',

C e s e r t b e: the location anc purpcse of the labsttnth seal: cc

,b : R e s c t.a r Cool ant Punip s.

QUE3 TION 6.04 (5.C0, a.

Wnat 13 t h -; eignt: icance of the "FZF F E'L TH TEhF rC ' s l a r ai What sctioni shoult y o.i t El c -

[1.03 b.

Why ts r. : t r c y r, a c c e d to t,h e FFTT C1.Gi c.

Give the s e r,ve n c e of e v e r.t - es pressure incret;es r.

t r. e PET - include setacints as spptopr:ste.

C1.03 GUESTION o.C5 43.00e a.

The reactor is op(rat.n3 at SC'; p cwe r when the locp f;cw circuitry for loop 1 1tils low.

Will the r esetor i t 1 p

Include setpo:nt,s a r.d.'o r logic as apprcFritate.

C1.OJ b.

Same question cs above except that power is at 30..

E1.0]

.

S a nie questicn as abcve encept that pcuer is at 87, and loop 2 circuttry Elsc fs11s low.

[1.0:

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C,:i T E G 0 F f ;o CONTINUCC ON NEXT FACE

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6.

FLANT CiETEh5 DEE!5N. CONTiOL, A N L: I N 5 T F. LP,E N T AT I O N FAEE o

________________________________ _____________.________

QUESTION 6.04 11.50)

What three ccnditions are nece:ssary bcfore the s t c s a.

cump control s i s t e n.

sble to admit s t e t.c to thc-n.a l n concense' for cooldown celo. 553 F?

.

-GUE5 TION 4 07 (4.00)

s.

Indicate whethcr the OT Delta-T anc the OF Gelta-T sctpoints will i n c r e s s t-, cecrease, or not change if the f ollowing changes cc cur.

CONSIDEF EACH CHANGE INDEF ENDENTL'r.

1.

Pressursrer pr es aut e de^teasas 130 ps:'.

2.

The N-41 lower c e t.s e t o r fatis icw.

3.

Dserdilutien of the RCE. whicn causes rods to : r. s e r t s ' oi r

to maintain constant lcac anc Tavc.

E,0]

b.

Justify you? answers f or p s: t 1.

accve.

E2.03 GUE5 TION 4.03 (.GC)

a.

Howe i s s r. cperatore c3n you tell if power is lost tc the i n t e. r m e d i a t e ran3e detector prior to a r e r.c t o r stcrtup?

E0.7EJ b.

What kould be the significance ci cne IF: channel ceinj overccmpcnsatec durir.g reactor star tupi 0.5J c.

What Lculd ce the significance of one IR channel bring undcreempenss+cd dur i r,3 a r e ac tor shut oown?

D.5J d.

If one IR channel fail-. 413 n th eir,3 a r e.s c h e r shut 0-n, aca ccn the i

operstor continue to 5.hutdovn?

E i,.

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QUEETION 6.07 (I. 50)

a.

Using Figure c.1 (sttached) describe the preferred and alterr.ste floupaths for eras r 3ency borction.

1.5J bo List the conditions that require emergency boraticn.

[1.03 l

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CATEGORY 06 CONTINUED Oh NEXT PAGE

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6o F L ANT S Y3 7Ed5 DES IGr.. : G ;4 T r,0 ;, AN; IN ;TRUdENT ATION PAGE

GUESTI0tl 6.10 (3.00>

Sketch the flow F.a t h cf clectrical power fron OG A to bus VIAC-3.

Label s11 busses, c o ::.p o n e n t s, ar.d breakers.

Indi ate vc1: ages and show alternate flow paths.

Breaker numbers are not requirec.

1 xn=2r END OF CATEGORY Of a n * z * ',

.

7.

PROCED:JEEE - NCRnAL, ABv0RMALr E i E F C E N C't AND

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Rn0AOL0otenL iONtnLm

____________________

QUESTION 7.}1 (2.50)

a.

What operator actions are rcquitec if criticalitv is achieved prior to t h e n.i n i n.u m rod position on the Estinated Critics 1 Position caleviatior.

(ECP)?

-). 5 2 b.

Wnat if criticality is not achieved oy the m a::i mu m rod position)

EO.52 c.

The Reactor Ccolant System lowest cperating temperature s72.3) is not allowed to sc below 551 F during a reactor startup.

Whzt is the bases for tbis limit C1.53 OUE5 TION 7.02 (3.001 4.

In acccedar.ce with CP3346A ' E.u r g e r.c y Siese' Generator *:

if the EDC ts oper ated at l e s s t h ar. 50;. c e p a c i t y f or 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 2, the d:etel should be operateo at greater than 50% for one hour.

Wh,?

[1.0 b.

When-opetttir.9 the EDG in the e n.e r genc y mode, the sa c ke t Coolar.t Temperature and tae CranLcasc Pressare shatcouns sre cutout cf the trip circuit. 'Wnat a c ti or.s e si any, c e r. tne ope r a tor tste t ni a i n t a i r, tnese p a r a n.e t e r s withir, lietts a r.d therefore minimize dan.33e to the EDG?

A s s u r..e t h t t t h e Iced cannot be o c-c r e a s e d.

[1.03 c.

List the tua autcastic protective f ea tur c s that will alwa.n stop the EDG.

E1.C]

GUE57 ION 7.03

.;5, You are the on-duty '5 C O a r.c a Radiaticn Werk Fore.it (RWF) 11 trought to you f or approval.

In acconcar.cc with SHF 4712, your appr os al z.: 3na tur e signifies what three conciticns with respect to the plant?

(*****

CATEGORY 07 CONTINUED ON NEXT PAGE

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.

7.

PROCEDURES - riC R M A L, AENGRnAL, EriEF GEN C Y AND CAGE

?

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

RAOIOLOGIC:m CGHTFOL

.

GUESTION 7.04 (2.50)

In accordance with EOF 3503 "Shutdcun Gutside Centrcl Rocmr' answar the followin3:

a.

How do you verify the reactor trip?

1.02 b.

Why does the FTCCedure caution e,:41nst placin3 the e r.e t ee n:, switcngect busses in local'

C0.52 c.

How would a cor tr ol voor. oper ator know if contic) hsd been shifted tc the AST C1.03 GUESTICr, 7.05 (1 00 In accorcance with EOP 35ECA-0.0, what are the uimediste actions on a 1 css of sll A/C power 0 GUESTION

~.06 ( 3. " ',

In a ccot t'ance wi t h GF 15 : 'Auxillcry Feetuster Eystem'i a.

What acticn must be t a k 'e n to feed all steam :enerate:s trcm cne motor driver, Ava111er y Feeowawr P un+ i (~/, 0 ]

E'.::

b.

You are feeding the s t s. a m gene.catcrs during a plant cccidown using thc turcinc cravon tunil2xry 1ee5Leter o v n. ;. f011cwing e iost of til A/C power w h e r.

.ov rscet.

the OW2T LEVEL LC-LC alara.

What ections woult you eapect to be teken?

[ /,o,3 M c.

What disadvantases 3e si.sociated with the alternate watcr s.. py lie s ?

,_ __

[p, c us.w.

GUESTIOr4 7.07 (1.00i Answer the fallcuing with respect to GP 3330 ' Reactor Plant Cccponcot Cooling Water' E ADP 3561 ' Loss of Reactor Plant Component Cocling Water':

c.

Why should the shift fi co A cr E train RPCCW to C Swing RPCCW pumF and

,

heat enchan3er be done swiftly?

[1.53

'

i b.

What are three symptoms cf a loss of RPCCW?

C1.03 l

c.

Why must you limit RPCCW ficw to 8100 3pm?

[0.53 (*****

CATECORY C7 CGNTINUCC ON NEXT FAGE

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-..

.

I 7.

PROCEDUREB - NORMAL, A E;N D R n A L. ENERGEt4C1 AND FACE

.0

--- EE5i5E55i5IE 55 i 5----~~-------------------

____________________

GUESTI0t*

7.05 s1.50)

In accordance wtth OP 3319A ' Condensate System *:

s.

When init2 ally starting up the s y s t e ni. why should you ensure proper motor amperage en the pump before letting go of the switch?

CO.752 b.

Prior to placing tne systen; in oper ationi if s t e a ni generator pressure is less than 700 psis, ensure the n.ain feedwater isolaticn valves are closed.

Kny?

CO.753 GUESTION 7.09 (3.53; Answcr the f 11cwing i r, accord 6nce wito AGF 0562 ' Loss of Instrument Air';

a.

The plant 2s opercting st 53% power when you rece2ve the CThi li4 S T AIR FRE55URE LO elarm. ycur pressure indicaticr. confirms that pressure is low.

Ali S ut o n.s t ; c ertions ital to nappen.

What operstor a:tions wavid you enFect to c4 taken to restore air

,ressure'

Wherc can tacse

&ctions be per f or meo ASSUME that each sction t E l-e n fails to r. top the

2 r e s s u r e drop.

C1.52 h.

E:rlefly e;plair. hou the following s y s ten.s will be affected by a loss cf C o r. t a i n m e r, t, A i r if tne p i a r. t is operating at 5 0 ?.

Ir,s /reme&

Feed Water CVCS RCP Seal Water C1.5]

e.

How would RHR be effected by e loss of Contai nn.e nt, Ai r in hode 4) :0.53 i

t,,, / rso aner, /

(*****

CATEGORY 07 CONTINUED ON NEXT FACC

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l l

l r

.

7..

F100EDURE5 - NCRnAL. ADNORhAL, Enti:G E N C Y AHL NGE 1:

RADIOLOGICAL C ; r; F. J L

_-- ----

GUESTION 7.1C (2.75i In crder to n.atntain t, h e plant at 100% pcwer, work must be performed inside the c o n t s i nn.e n t i r, a radattion field of 850 MREh/HR 3 sn,m s a,r.d 3 0 hR A C.'H F.

thermal and fast neutron.

The c.aintenance man selectec is 25 years old ar d has a l i f e t i r.ie exposure through last quarter of 43 REM on h i s N F: C F o r n, 43 additionally, he has accumulated 1.0 REM so far this quarter.

c.

How long n.sy the n.an work in this ar ea without enceeding his 10 CFR l i n. i t

Show all work.

ti.20 b.

During a decisted en.ergency. this indi,1dval

. ol ur.te c t s t :. a r.t c r

'

a high raci stian ar e a cr.d p er f or m work necessar. to,t'e.ent further etfluent ieiease.

In ac c or ds.nc c witn the E t a 11 :ar. F r c et d u r c. what is his cia n i m u r, allcwed whole bot ext.osure3 CO. G e.

Whose suthc.r i: s t ion I r: necdcm in pit t b.

[0.70 l

i I

(*****

END OF CATEGDF,Y 07

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t B.

ADhIiCETF ATIVE F F M EDUF<E5 CDNDITIObE, AN: LIh TATIONE P A ", E

.:

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _., _ _ _

QUESTION 6.01 (2.50, The plant is operating at IC'. Icad anc ycv are the on-shift 5.uft Supervisof.

Enplein what actions. If any, would nced to be caten for the following conditions.

CONSIDER EACH CA!E $EFAEATELY.

s.

Your on-shift E:0 P op e r r t e.t orests his les ir. the plant arid you se nt him to the hctpital for t r e a t rie n t.

C1.052 b.

The on-con.t res ST A calls and u ps be won't t.c in.

C1.!5 j

l

>

QUESTI0ri 6.00 1.75)

'

The Technical Specificatiant, stata that ' E.., c h Evaveillance Requiremer.t.

!

sh&11 be perforn.e6 with1r. tne sFOC;.fied tibc :nterial with;

!

4.

A m a n i m u c. 411cwable entenston nct to er uco 25*. of the servet11:nce interval, but b.

The combined time interval (cr anv t rir e consecutivet sor vc t ilence:

intervtit snt:1 r. o t e,:c e e f ?. 25 tin.cs ths : p o : s f i e r.'

sur.,9211ance intervel.'

What ave the ba, set for the abe'. 9 L

GUESTI0tl 5.00 c;.25

<

In accordance with CF1 01, 'The reactor c o o l a n t p r e s si. r 4 and t emp * * a tur et i

shovid not euceed

______ptia and

..,___r when the Fetidus) Hest E ( n. o '.1 1 syste:m i f, t ri se r vtcc. '

Fill in the blar.ts enc provide the betts for ea:h.

'

OUEST~CN G.0c 2.00i Answer the fc110 wing as they apply to ACF-GA-0.004 'Statten T433tn3'!

i a.

Undet what conditions uovic you authat 1::e ' Or et a t or - 2 n-At tenosi.co '

l tagging?

C1.03 b.

What settons niv e t be taten if the Operator-in-Attendance n.ust leave the area?

C1.03

-

l (***aa C 6 T E G D F. Y OB CONTINUED 06 NE)T F' A C. C

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

I GUESTIGH 5.0L

.:.00s Lofine the 1011cutn3 tern.1:

l a.

Channel Celtdratten l

t,.

Char r.e 1 Or et atser s) To i

!

l G UC 3 f l0tl G.06 (3.00)

I r. accordance with EFIF 40;(A & 4510ft:

As the Entft Supervtscr. ween n.ost you a s s u n.c the ren cnsististics c'

I tl4 Artsi,; ttrc:ter of : t s t t or. C r..c t a e n; y O p e r s t a c r.s i

1.C3

!

b.

Whit c onc t t t eret. Sn*

mv c u s tder when co tei n tr.t nj was ther or nct t)

Of de t i E t t (1 Cr. 4 ; i t' 41 3. 4 re d / o f t%4cuttathi (2 0)

00CCTICH G. i: P

/:.00;

l Ant.use the fallowiny -tth re n ect to Acr-0A-;..cC 'uark cro.rs':

c.

Whteh of the below at rat a rccpc.s.o41st, of the 05,!001 P. 0 3 1.

F1 ace app:cpriato 6 4 f. r..- t 4 -) w 2.

Ids. ret i f y t re. t I ;' * e g u t r p r.. t r, t :

h /w e /.v. e4 J.

f ev tt w t h.e aork Ord<r oge64 y e[Ar erf

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4.

Apptv c ths i tett i e wi c er $ riti l

l b.

Woen mav a ihart " era W;rt Or w ec ot11 :edi 01.51

l OU;Lt:09 L. <.- r (3.0);

fer Technical Grectricettoe, wnen coes,:ontatnn.rt A n ta p i t, e.i t, t *

l 00ESTI0ft L.09 (:. L( )

The safety I t n. i t s for the re4ctwr core are deters.tned fron, a e c na t r.a t u n of resttot toutre pttasuf1:et pretsutte a n t) loop t e n.p e t s t u t 6.

l e.

If a safet,y Inntt in violatede what t pis a d i a t e a c t i o n n u f. t be tek sh i l

CO.53

.

l b.

Wnet are the tasett f or $ttyshj withtr. the reactor safety i n na t tervet"

"" 0 3

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(ssoas CATCCOFI 00 CONTINUCD Cli NCAT l'ACC sasaa4 l

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i OU E S TIO r)

5.1C (4.00)

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The reactor plant is at 05*. power.

rour permts ton i t, r queetted to coniseenee wor 6 on orie of the RCS a:cun.ulatorsi this wori will involve

the partial draininj of the a t:comu la to r !

j s.

Would you authorin the wori?

Eaplair,.

ti.0)

f t

b.

What is the dest 3n 1: 411s for the accumulator volutt.oS C1.03

c.

What 4 tions would ytv tais for an LI ACCunULATOR LEU"L LC (1sta.? L. 00 l

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Equations p=

Q = Mah

+1 tK,ff I +1r e

e Q = mc AT p

SUR = 26 e t' + (5 p) t a = UAat C (1-K ) = C2 (I'E )

,

g

hg = Ky*

.

P = Po 10 sur (t)

3= 3.14 p = pa,t/r i

e = 2.72

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S 1-K,ff t

7 = j ' + S '~ @

1 = CR

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M CR2 1 = 0.693

,,,

,

th 1 = 10 Conversions I curie = 3.7 x 102*dps

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1 kg = 2.21bs 1 gal = 3.78 liters 1 gn/cm = 62.4 lbs/ft*

1.in = 2.54 ca 1 ft' = 1.48 gal 1 yr = 2.15 x 10' sec.

I gal. = 8.3453 lbm.

.

1 MW = 3.41 X 10' BTU /HR

-

.

,

5.

THEORY OF r!bCLE Af; FCWER FLANT OFEEATION, Fuu!OS. AND FACE

________________________________________________________

_____'0DntAMICS ThEnt

_________

ANSWERS -- MILLSTOrlE 3-a5/07/04-NORRIS, E:.

S.

ANSWER 5.01 (2.00)

a.

The limit imposed by 13CFR50 is 2200 F.

CC.52 b.

The 11 nii t is i n.p o s e d t o n. i n i r.il :: e the e f f e:: t t of the srceloy resettori with Water'stest CO.51,which 3 ses off heat and hycrogeny CO.53 i

F "w A.e 6 c ours c lar/</.oj e.n 4n#/r e"e 4 "

(Zr + 2H2O --; ZrG2 + 2H2 + Hest)

c.

T ', e reaction will becenc self-sustain ng (sbout 4320 F-

[0.5:

REFERENCE 10CFR50 46(b)(1)

MFS System D e s c r i p t i c r., ~cp;c 7.

Lessons 1 - 0, page 4 NNE Mitigating Core Der. age. Lessen 1 pages 1.50 &. 51

'

AtJ5WER 5.02 (2.30>

Steam ganera,cr press.ure of 1020 psig = 1035 psis whicn re16t:3 ta 543.7 F (200 psis 544.6 F1

[0.53

=

(1035 psia 0??07 F)

=

(1050 pria 550.5 F)

F t r a t, S/G ssfetv valve lifts at 1155 Ests = 1CGC p:u n.

56?.; F CO.52 Steam ten.persture must aner esse 15.5 F l0.53 (567.2 - 546.7 = id,5)

Therefore, Tav3 must inctsas( by 13.5 F C).52 REFERENCE nF3 System Cescriptior., Topic 1,

Lesscr. 3, pages 39 & 41 H P 3 S y r., t e n.

Des er ip t 2 nri, Topic 1,

L e s s o r.

le page 37 Steam Tables i

r b

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-

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5.

THEORY OF NUCLEAF F0WER PLANT JFERATIOti. F i.J 1 C S. ANC PACE 10.

,

..............._......................................

!

THEhriOD f rurt!Ci

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

l ANSWERS -- HILLST0HC J-05/09/04-NORFIS. E. 3.

!

ANSWER -

5.03 (2.001

,

a.

Prompt neutrons are produced almost immediately after fission 00.253 with a very short lifet.mc (2 x 10E-5 see)(3.253 Delayco neutrons are produced from the cecav cf daughters of fitsten prodvetsto.253with a much Acnger lifetime (12.7 sec) [0.253 Average neutron 3eneration time is approutmatelr equal to th) delayed neutron tern, CO.;53 wM eh it why deleyee neutrons (21&nt.c.11y c :,rit t o f the re sponse F. t e c of the reactoa [0. !]

In pc.r tanc e isttot b.

Eeta-eff = E: e t a - t. r t n Beta-b.ar is a weightN a. era 3e of the Octa's of the different fuel types (U-235, U-256, Fu-;3i (0.2538 as the ccre eges.. the pcreeritt3e of Fu-239 incacases which avses the value ot' Eota-o.sr to decrease ever etre lifet0.053 c.

The SUR immediately following a reactor trip is based Fi the lon3 cst 11ved del eye d neutr or, pr eevr s ot with a r.siflift of "55 sec CO.53 55 s4c/0.673 = 79.3o

00 See C3.;53 i

a e-26.04/T = -26 04/;4

- 0. 3 : 3 c. p r..

[0.053 BUL

=

REFERCHCC tit 3 System Description, Top ic S. ;_c s son

pg ;0

,

Resetos-Theory E.c o L. Topar 9.

p 3 n. : - 4 1. figurt 4

'?

N ' "'/" "J

h *' re '8 4 * W M"*1^!N AH5WER 5.04

<3.C0i Mst /1 ue & * ( theMw G*fl-d

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6cesuse of that, there may be an insufficient neutrer

~~

level te provide the t egoir ec' Sout ce Ren2e indication cr, s t a r t.ip :1. 03.

be Primary source:

Californium-252 CO.053 Reactiont spontaneous fissior, t0.253 (Cf-25;

--?

FF-1 + FF-; + :n)

Secondary source:

A n t int o ny-Ec r y l l i u m to.253 Resettent photo neut r or.

[0 053 (Sb-124 -. Te-124 + G a ni n.a ih13h energy >>

( B e - 9 + G a n.n a - 6 2He-4 + ri)

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THEORY OF i4U CL E AR ~ 0 W o.~

FLAhl 0FEFJ.T10t4, TLUIOS,.:i r> C 7AGC 1.'

__________________..........____.......__.......__.___

T U C R n L C ': N A r. lC G

......... _.

AriSWERS -- r1ILL3 TONE 3-G5/09/04-NORT 0,

C.

O.

RE F E R E tJC E Reactor Theorv Ecol., T Pi:

2.

pgs

4 E, figs 5-11 ANSWER 5.05 (0.5C)

i

(li L 1 - O H d i s e t. s u c i s t s.- s i re witer tc form Hycronyl t o r. s C O.M, which shifts the c or e c ritr a t i ate o f Hy d t o r.1 v n. lores to coritt ol the pH level of the RCS C O.{a (pH 1/CH00+ )

r (;. H y rJ r + ::. r. e t ( a c '. s with c :: r g e r. t c i e t rt. r.2ttc. p r.

a r a.

wtter L O.X *

(.h t. 12 restricte. t.o u s, a o r, s (, a r t y p s t'rca. cold shyf.co.cI

~

(3) Hydtopere ies:t.S with i j.c os.y gers to fetr ueter t {.,7.

wher

.r tac pres.rn;4. at a high gamru f l.n, CO.73

'

G Do (J a t o t a l 11 t h a v r.

0 3rd Bisis L:-o which I o f R. 6 t r a t 1 u n, th-L' whe r<

100J0Cttd to 4 h a y r.e u t. o r.

f lv t.

N. '* ]

R2 r E F Eh'CC rii.3 C y S t e m C E S. r i p t. t a r., I4pic !, Lesson 1, pg)

5-6, d 13-14

-

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-

- -

-

- -

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-

.

k 5.

THEDRY GF NUCLEAf POWEF P_ ANT OFERATION. FLUILE. AND PACE 1E

_______ _

___ _

______________________________________

______________

ANSWERS -- MILLSTONE 2-85/09/04-NORRI5, E.

5.

ANSWER SsO6 (2.00)

a.

one step = 5/6'

==2 6 FCm/in 3.75 pcm/ step CO.12

=

Beta-eff 0.00o9 CO.15J

=

1ambda = 0.1 C0-151 tho = (3.75 p e ni / s t e p ) ( -2 0 steps)

-75 pea or -0.00075

[0,1

=

T (Eeta-eff - the)/(rho)(lacbda)

=

(0.0065 - :-0.00075})/(-0.00075)(0.1)

=

(0.00765),'(-0.000075)

=

-10 CO.5]

=

EUR = 26.3c/T 26.36/(-1024-0.255 dpm

[0.25

=

( S U R 'i ( t 's b.

P = Fo10 CO.25:

-8

{-0. 2 5 5 } -!1 >

(1C )(10

)

=

-6 (1C )(0.556)

=

s

.-?

5.56 10 a ra p s CO.51

=

-

,

REFERENCC MP3 - Sun, mar y c f Core Nuclear Characteristics Resctor Tneory. Topic 10, pages 5-5 MP3 System Cescription, Topic cr Lesson 27 pg 17 MP3 - E1mulator Cur ves f or Intest al Rod Worth ANSWER 5.07 00)

,

s.

The d i f f e r e r.c e in t mperature for the e::: sting condenser.acuun and the teraper atur e o.1 the condensate.

E.03 6.

As the condensate enters the eye of the condensate pump, thE fluid flashes to stean, due to the lower Pressure; as the stean; bubbles travel the length of the impeller bladest they collapse (causing excessive wear).

[0.5 Decr easing conder.s a t e depression causes increased cavitation.

[0.25]

c.

Reduced pl ar t ef ficiency.

E0.25]

REFERENCE Millstone HTF~. pages 152-163

.

5.

THE0R( OF iJUCLEAR FCWER FL A 4 T GF EF ATIOt;, FLUI:3, A tlD i..;E I?

TH E Rh0D r N Ar1IC 3

_----

AtJ5WERS -- hlLL5T0r!E 3-35/0~/04-NORRIS, E..

5.

RIhrnhst u,'Wr *.",s l a,- t,,.. ', aw L <.f -

$/:f4 /// "Le 'B r4 At1SWER 5.08 (3.S0)f' tant re 4 ce</

a.

Turbine power - stays ccns at 33% power EC.63 b.

Tav3 (affetted l o c. p ) - incteases

[0.23 final value - 577 F Ccqual to Th)

CO.4]

c.

Tavg (non-affected loops) - decreases 00.23

' i n a l.elve - total r e a c t c.- Power :u.s cat cnangec; howcVer, the

,t o w. r that ecco of the nor.-ef f e c ted 1 c o p s.1eu s t ti a r.. f e r t c-t h e 5/G has i n c r e s s.i d by a tactor of 1/3 tc c caip e r.s s t c fcr 11 100p.

.

G r :,

=m Cp (Th - Tc1 for cac.. Icop 1, 3

_-_;

-;

y initial Dcits T ws: 2C F,

a r.d ;r u s t t r. c r._ a s e L.- fcctor 1/3

- - -

final Delte i cauals Co.67 7 final Tavs = Tn - Del'.a T/2 577 -._c.c7/2

=

Sol.67 F

[C.43

=

d.

5/G ressure (affectec locp, - increases CO.22 (Ir2tial value - 970 psi 3 = s a tur a tior; pressur e for 555 F)

final salve - saturation pressure for Th = 5~7 F 13:5 pr23 (ssfeties will lift; CO.43

=

e.

3,' C Fressure.ncr.-aficcted iceps; - decreasc CO.2]

final vaive - as with part c anovs, the ap pr op r i t.ts delta-T 'isv3-Istn)

must aneresse by 1/3; iritial De:ta T isvg - Tstr.: = So7 - 555 = ;c F

=

final Tstm Ta.>3 - Delta T 563.67 - 14(4,'3)

=

565.67 - 15.67 545 F

[0.43

=

REFEREt1CE

~

MF' 3 Systen Description, Tcpic 6, Lesson 2 Transient E Accident Analysis, Chapter 4,

page 4.11

.

5.

THEORY OF NUCLEAR F0 WEE FLAUT OFERATION, FLUID 5, ANC FACE

____

_

_ _______________________________________

___________.

ANSWERS -- nILLSTONE 3-35/C7/04-NORRIS, E.

E.

ANSWER 5.09 (3.00)

a.

EOL - MTC is more negative and thus imparts greater positive reactivity from the drcp in coolant temperature.

C/, c)

E+,+1 r.,

4..,

_ -..._ _.

_

_.

ce;_._..i

__r.

._.,_

...

..

_. -

. _,

_

.

impstts less reactivity ficm the power incr e ase.

s'.C b.

BOL - MTC'is less negative anc thus inparts less negative reactivity from the coolant heat-up.

ft. 0)

M

.. -

_ i

._

i

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

,

_. -

_ _

m

.

.s.

...

_. _

._-

_

.

.__.....

-

- :-

1*:,

__

.--

5: 2d

' -

-

53

,

c. EGL - Eeta-eff is less. making SUR g.~ eat.er.

CO.53 DOF C is less neest ive and thus t ra p a r t s less negative ieactivity after i, h c fuel t ei:.p e r a t u r e begins tc increase.

CO.5:

REFERENCE a.

Topic 3 Lesson 5 pg. CE b. Ps. 45 c.

pg. 45 a.

throu3hc.

Reactor Thect/ Chapt. 17 ANSWER 5.10

'1.50)

a.

Decrease CO.13 Less neutron learage due to decreased Tav3

[0.43 b.

Incresse CO.13 Neutr or, f l.u-shif ts towar d the core edges as the cor e rges.

CO.43

.

c.

Increase CO.13 Decreased neutr on absctFtion by boron.

CO.43 REFERENCE MP3 System Description, Topic 6, Lesson 4,

pgs 19-24 Wd N M }7/se a <c ef de e hanje. O G yy*,

e,[f,a A/ perge/ca 0 [c W

!

l

_ _ _ _,

-

.

6.

PLANT SYSTEh5 DIEIC9, CONTRDL. AtJD INSTRUnEt T ATIDF FA.LE 2:

______________________________________________________

ANSWERE -- MILL 5 TONE 3

- 0 5,- v i / 0 4 - t4 C.P i,I E,

B.

E.

ANSWER 6.01 (2.25, s.

First valve (set st 1185 psi 3)

ASME requires the first valve to lift at or below the stesm generator design pressure (1185).

[0.753 Fifth valve (set at 1225 psig)

Ensures that

.s i l

,sives are cren ar.c passing 110*. cf design steam flow

when steam pressure nas esched 110*. of design.

[0.753 b.

Up to three salves per s t c: a n generator.

CO 25]

The p l a r,t 25 l i m 2 t e t'

to ;< reduced power level due to the

.p

_

'

', ^

.

/6}k/,4lNvin) O yacj/y. [

[2.53

'

' '

'

REFERENCE N cc</r.se h u J MF3 System Description. Tcpic 1 Losicn 3 ogs 1E-17 OF 3204. 99 5 TS 3.7.1.1 pg 3. 2

-:

ANSWER 6. ;- :

(2.25'

As power incresse > t.'lta-F

.c le :It.-)

increases CC.353 As power increasesi steam pressure decreases CO.3J

,.-

.

s..

K(P-stm)(delta-F)

m - s. t m =

= = > s : r.c e the s t e s,1, pressure con.conent stays c o n s t a r.t t it sbculd 30 down) while the delts-F increases, indicated stesm fi;L w:11 de higher than actus1 steam flow CO.43 The summing networt f or flou ail' send a s 13 r.c l to tha total c o r.t t :11 e r to open the feed regulating vsl-e.

CO.42 As level starts te intresse, the level error will signal for the FRU to close CO.42 Eventually, the flow error will be tsneelled out by the level error, and the FRV will be positiened such that steam flow equals feed ficw at some higher level.

[0.43 REFERENCE NP 3 System Description, Topic 6,

Lesson 9, pas 18-20, 23 Topic S.

Lesson 4,

pgs 67-75 i

.

6.

PLANT SYSTEh0 DESIGN, CONTROL, AND INSTRunEniATION FAGE

______________________________________________________

ANSWERS -- eILL5 TONE 3-6 5 / 0 7 / 0 4 -N O F, RI E.

E.,

5.

ANSWER 6.03 (1.501 1.

Against the vertical surface of the :mpeller wear ing r ing.

CO.253 To minimize flow to the inlet of the therrasl bstrier nest e:tenanger 1 r.

the event normal seal injection is lost.

CJ.53 2.

Adjacent to the p u nip shsit, below the therms 1 bstrier hest enchen3er.

[0.25]

When the pump n4ust pr ovide i t s curi seal c o ol i r:9 the flcw will be diverted past the heat sachanger tubes instead of cirectly along the shaft.

EC.53 REFERENCE hP3 Systen, Description, L e s s c r.

1, Topic 2, pg 5 ANSWER 6.04 (3.00)

a.

Easts is keeping tiie t a r< k temperature belcu 120 F (to th? tano is the desi d i sgh a r g e)

EG.53 capeble of handlin-a h a lore.gnD'4TJ ha l ca u.rd gs i n g p r i m a r y fml. c,lhe Tany j

t, e Resctor,j oy ad etade water and crain tc Loua n

Plant Gaseous Drs. ins.

[0. J

'

~~

.: _

_ -. _.

_:mj f, prevent tne o,

. ; c -.

_.. -

_

i-.:.:._ '._

.._

'

"

-

tv ts-i 4 5-.--r.

. _, i.- i m - ::..:__,- rn n-

.

hydroger, from'ccn. ng out Of solution which could provide a potentially e r:p l o si v e atmosp her e !'

":

c.

6 psig CO.13 - P C 'J 469 (vent) signalled to closeCO.33

- ' FIR REL TK PRESEURE HI' alarmEO.23 115 pais CO.12 - F o p t.> r *. disks blow outEO.33 REFERENCE hP3 System Description, Lesson 1, Topic 4,

p3s 11-13 i

.

6.

PLANT SYSTEh5 DEEIC.N. CONTFDL. AND IN5TF UMENT ATION PAGE

______________________________________________________

ANSWERS -- MILLETOr;E 3

- C S,' o r/04-NORRIS. E:.

5.

ANSWER 6.05 (3.0G; 4.

Reacter trip - YES CO.5:

power W. '/ F 0 CO.253

'

1/4 Icgic CO.253 b.

Reactor tr ip - NO CO.53 power ' SPC but 107.

0.252

'

,

2/4 logie 4870 CO.253 c.

Reacter trip - NO

[0.52 power < 1 07; CO.253 2/4 Icgic CO.253 F:EF E RE N C E HP3 System Description. Tcpic 1,

Lesson 1,

Pgs 22-23 ANSWER 6.06 (1.50-Steam Dump h0DE SWITCH tc 'STEAn FRE55URE'

CC.52 E:o t h S t e a n. D u n:p I r.t e r l o ;; 6 Euitches to 'E:iPAES INTERLOCM'

E0.53 3/3 Condenser Vacuum (>25' Hg)

CO.5]

REFERENCE MP3 System Descripticr.. Topic 5, Lescon 2, pgs 16-17 & 22-23

,.

6.

PLANT SYSTEhE DESIGN, CONTROL, AND INETF:UriENT ATIO*4 PAGE

______________________________________________________

ANSWEF:E -- h1LLE. TONE 3-85/09/04-NORRIE, E:.

5.

ANSWER 6.07 (4.00)

a OT Delta-T OF Delta-T 1.

decrease oc change

_

n. c /a g e 2.

decrease

':: :: :

'

f,,f,g i : ::::f;gc),g,

E0.33 each]

3.

: _:

b.

1.

OT Delta T - Indicated pr essur izer pressure will be celow the nominal pressure which will insert a negative tern, into tne s.etpoint GP Delta T - nct affected by changes in pressure 2.

OT De:ts T - Delta f l u. -

n o r n.a ll y nesst2ve terno is subtreeted fron, the setpcint (minus :, minus = positive); if lower detector f s i l s.. Delta flu:, becomes positise, which esuses the.setpcint to de:rease DP Delti T -

.. -.- :: :- :-

".. g ffa,y c' he a // 4 7 [Surd w, r+ llg 3.

GT Delta T -

<-

i n _- i-

!!! - - -

- 0 -I '

'_- ; -

-

'-

-

$.:'

21:

.::

'

2 - :

-

- - - '

' ::

_ :

-

__

._-5

..;. +.

i _ _.. _..

OF Delts ~ - '

'-_: - - :_:-

- - :: :i: :

6 F/wp f3

/3 a, / g,,Je / w/

E0.33 for each discuss:cn3 a

REFERENOE N 7" '" /"*7"///

HP3 System Description, Topic 6,

Lesson 5, pas-14 L Topse 7, Lessor s 1-3, pgs 44-52 & RA-1 fS. Yabk J.ht,pp g - 7 M,a gic 61 a(ways reduta -f& Jr frNl

.

F.

i.

6.

F war 4T 5'r 5TEh5 CESIGN. CONTROL, Ar4 D INSTRunENTAT2Cr, RAGE

ANSWERS -- MILLETONE 3-E5/09/04-NORFII.

E'

5.

ANSWEP 6.08 (2.00)

s.

'IR 1(2s LOSS OF COMPEr45 ATING VOLT AGE'

E0.252

'IP LOSS OF DET UOLTAGE'

00.253 There is an electrics 1 signal p?cvided tc the n.eter equisalent to the low scale r e e d i r. g il v 10E-11snps) which prevents the instrument fro-pegging downscale dur ir 3 nee rr sl operaticns.

[0.251 b.

Detector o u t : t.t as loat' t r. c n sett21 rie utr on ;evel.

[ C. 2 5 '.

Indicated level st:1 inc r c a u at s higher tnan actual rate, rising a felse high sicrtuF r z.t c i n d i t z.t i o n.

[0,~53 c.

Detector output is higher than scttil neutron level CO.25]

The source isn3t dctcetors will not suton.ctically ener gine

.1 the affectcc char.nel reeds higher than 5 10 E - 11 a c4 p s CO.25]

.

-

d.

Tne oper stor tsn n.snus11. ener gire the 5F detectors u2tn tne EF E:l o: L-Reset switch.

CO.25]

REFEEENEE nF3 System Description, 7.3 p. c 4,

Lesscn 4.

pgs 15 - 1 <3 OP 3:07 pg 5 ANSWEF 6.09 ( 2. 5.'

s.

See atteched sheets Freterrec path 1.03 Alternate patb

[0.53 C

b.

1.

Rod below the Icw-Icw insertion limit.

[0.2Y each:

2.

All rods fsil to inser-cn a reactor trap.

3.

An uncontrclied cocidcwn c-

-'::t_

i+

i-- ::

.

,__,,

9.

m.

.: 2:

n..; ;.. me :.- _.

;

.--tu

_,.

.

,.

An uncen fu//ed Modedb iic rene.

-

REFERENCE f 4 9,7,f, g, gb MPo System Descriptione icpic 2 Les2cn 2, pgs 32-33 & PG9-PG11 ADF 3566 pg /A ANSWER 6.10 fe.00)

see attached drswing

<

.....

.

i i

l l

!

6.

PLANT 5 5TEMS DESIGNr C o r1 T R O L, AND It4STRUMENTATI0ti FACI

.

______________________________________________________

ANSWERS -- n:LLST0reE 3-85/09/C4-NGRFIG, E.

REFERENCE Millstone 3 Required Drawings 1322 and 323

,

-

-. -

l

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

_ _ _. _.

_,__,_ _

_

i

'1

.

r

J

-

,

.

h, REACTOR MAKEUP SYSTEM

a

,,,,

I__

I sysian V:'

- Letdown so, omV -

[

j o

' r LCV 112A>F0aseous Weste

,

(

<

,

k

-

'

M e.1

)

INa

$Nj,

b Aess

Volume g

,

Control is a

kd 9.

M Tardi

Tank i

.,.

'd

'

, }

",

,

'

!

-

FCV 1108 Borto Acid O

'

l E **"

m. -h[%

-

LCV 1128 @l 86 ender f

,

i

,

.

,,

, ry,,

o f\\/

""]j4

-

L 1120

" o. @J smic o

:

9*

o.2

,g

.

g,7 7-

_' m h"',

.AA r

..

.

- - -

,,

j

,

__

,,CVg

f-M Dorte satcNng

__

,,

8439

-

E g

Transfer Terei h

PW'oe,

-

!

,,

!

f_.CV t 120

-,

_

,

,,

W 8807A f

nl NO M RWST h

,

g ve4saA

'p,g

-

=4RHR Pump A

-

W 85078

,

6 l @ soo

.

- - - -

-

'

Disefierge gy.8(6siil

.,,

$

.___

.

,

i a

u y -

tcvitse

-

,

Nj

n~u l

< 3,,,4k

.

e w si asc.

&fud' F/~pA. 4 i

--

- - -

.

-

..

i

'

.,

-

!

N REACTOR MAKEUP SYSTEM

.

-

Recovery I.

I System

Letdown goron

~

i l

Reco w-f l

LCV 112A Gaseous Weste

$ r J

!

i System

'

<

-

'

"

Volume

)

--

g

,,

fee,g, geg Contrei

,,

a Tar * 4 d

9.

,

,,

FCV 110s Barto Acid

-

"

Aen.

g j

2.

Lev iits

%

_

'

-

'e4s ch.=

'

o l

',

Add R

_-

"

[N/

c

,

nwat = :

tov, iso Tar *

<,

S434 L

"4

-

'I Amat

< r j

g

cend. ; :,

-

"

sorte

0./

,

< r hyging Pumo)s S

^ "Q

^

]

l F

i

,

m.

..

l n+;r

A 9Q

-

N v

eerie seu

-

O

!

~ *

'

Sorte Acad

!

f BatcNng

'M

,9, 843T

"*

!

Transferj i Tar *

-

"

q _... w l

j

--

,

! cv itso j

u

'

-

,

sum

)

, r SAV8807A n 't NO 4 ggy

'

g, g

uV S444A

,

MRHR Pump A

im

-

M@ NO Wee gy 35o73 uv e4ase

-

g

_. _.

.....

.

~

..

-(cvitse f

j-

~ g (N/2r(Nj/

Bra hk n,.. u

'

-

p -, ec n. 9

-

AIN*b Impo

'

.

-

.

}

.

O 4ee erde A (nl v,.,J

.

<.

--

..&q f,

)

..

.

....

.

...

'

. - -...

B u.s 3VC 4/6o oAc.

.......... _

.

.'B ree k u -

)

... ) 3r-esk ~.

.

._.

..

-em n..J -

b. sawn, anc.

T'

.....

.-

%W.

)--

.g _

- -.....

_. _ - -

l

.

. _Bu.s 32-3 7

_

. j3 a.,

3.p. 2 Q

_.

.

.... SAN..

) _-

. ) W P.-- -

..

_] 0etto k!r..

.. -

-

.... _ _ _

........

.... -

- -..

g.y7y

-

.

...

-

. _ _...

....._._ _ _ _ ;. _..

- - -.

-

y.d! fA

.

._

C, ha

.y -

l g

)____kkef_ _ _ _ ) e,k -

.e

/ B u.s 3 0 / A? -2 W

l)3p.__.

'

) 6,1<,-

.

' e ',,a %f A +'ed

-

.r am -2

_

- -.

-

N

..

-

_. _..

_ _

.

y v-3 a.i

< <ack

.-

uade AJ %

.

,)

[

....

.......

,y.gp e.c. -.- -......

.....

_

W'3 Swa r*eA

- - -

- - - -

.-. -..

.-..

.....

'

-Nh

- - -

.h a m

"

- -

- -.

..- 4.10

....

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

-..

.

yi.9c.)-.

-

__

.. - _ _.. _ ___

__ _

_

.__

_

_.

-

. _..

.

7.

PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND FAGE

~~~~IIID5dE5555hL 55sTEoE-----------------~~~----

-

.____________________

. ANSWERS'-- MILLSTONE 3-83/09/04-NORRIS, E.

5.

-ANSWER-7.01 (2.50)

a.

1..

Terminate the startup by inserting all control banks.

CO.5]

b.

1.

Terminate the startup by fully inserting all control rods.

CO.25]

2.

heasure boren concentration and recalculate the ECP.

CO.253 c.

1.

The-moderator temperature coefficient is within its analy ed temperature range 2.

The trip instrumentation is within its normsl operating range 3.

_The P-12 interlock is above its setpoint

The pressuricer.is capable of being in an operable ststus with a steam buoble 5.

The reactor vessel is above its minimum RT-NDT t e a.p c r a t u r e CO.3 each]

REFERENCE OP 3202r Fages 4,

9& 10 I

TS 3.1.1.4.

pgs 3/4 1-6 L B3/4 1-2 Arl5 WER 7.02 (3.00; a.

Fire hazard CO.53 due to excessive oil buildup in euhaust lines CO.52

.

b.

Js eke t - Cool aret Tempersture - incresse the servicc wcter flow to the

. o fh e r4'e Scea lk jacket uater heat enchanger CO.332 4 r7J M rf er A ~

- ensure the 3-way valve is operatinc

~

c c c ejr, /r //(

properly CO.33]

Cr ankca se Pressure - nothins can b e c o n c o_C e n /7,/ go e gg,, f, CO.23]

c.

Low lube oil pressure (2/3)

f #ar 72sc, gg,,,,/

CO.53 naine overspeed

%

4 te ren 4 r ~ h (pri m h /

REFEREr1CE-l OP3346A, para 6.2 & 6.5, pg 4 System Description, Diesel Generator, pgs,42-43 L S X a?t{- f 9 h {' ?'l-U T

")

i l.

!

i

i l

l

!'

i

.

-~.

.

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

.. _ _.-- __

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

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

.

__.

. _. _

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

.

-.

i-t I

-

.

t I

7.

PROCEDURES - NORMAL, A E r40 RM AL, EMERGENCY AN1 PAGE

l

- ________________________________________________

l RADIOLGCICAL CariTROL.

-

______._____________

ANSWERS --' MILLSTONE 3-65/09/04-NORRIS, En S.

,

ANSWER 7.03 (2.25)

'1.

No evoluticns'are planned which could change the radiological conditions as listed on the RWP.

[0.752

- 4 2.

Any evolution that would change the radiological conditions will be reported to HP.

[0.75]

3.

The work on the RWF does not Jeopardine the plant.

[0.75]

REFERENCE

'SHF 4912r para 4.2, pgs 3-4

,

ANSWER 7.04-(2.50)

a.

1.. Rod bottom lights lit

.CC.25:

2.' Reactor - toip anti bypass brealer:- open EO.25]

3.

Digit,al rod position indicators at nerc

0.25]

4.. Neutron flux decrecsing CO.25]

-

b.

" Loss of. automatic actions of

'oth safety injection and diesel generator-c s e qu e n e i r.3 E0.53

,'(affw.yhsk Ma CO.33 cach]

Lc.

' AUX SHUTDOWN FANEL COCR OFEN'

'RHS VALVES LOCAL CONTROL'

m f, f.vt e y, /rc/

c

'SIL VALVES LOCAL CONTROL'

,,.n,y REFERENCE h

ECP 3503, pgs 3 1 5 EOP'FR-S.1, pg 3

.MP3, System Descriptien, Topic 3r Lesson 4,

Pgs 13-14 ANSWER 7.05 (1.00)

,-[ a f h u y ' * # p M p #

.25 each]

' 1.

verify rn trip d

2.

verify turoine trip

'

3.

check that RCS is isolated

-

4.

verify AFW flow e M [#'

'"'J l rr / Sc, & llf lJ A

REFERENCE EDP 35ECA-0.0, pas 3&4 fujenrJe $c in h4 I

.

t

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

.

-

.

!

7.

PRCCEDURE5 - NORMAL, AE40Rh AL, EMERGENCY AND FAGE

_________________________..______________________

FADI0 LOGICAL C0t. TROL

<

,

____________________

ANSWERS -- HILLSTONE 3-85/09/04-NORRIS, B.

S.

ANSWER 7.06 (3.00)

(Manually)cpenthe AFW cischarge header cross-connect valves.

1: 52 a.

b.

Otsy the r-

.= if :-

10: y

~:t--

is ~

';'

'::f"d.

-:.E:

-

C o.. m ;. m m

.1 1..., ;

! !:-

-_

t'-

^

<-

c

'

, ; t e c. cr the

.

n___.2

-

,

2 __.;-.. -

-,,_

w w,

..s

+

,,

.

,,,g,

-

fhift suction to the Concensate Storage Tank T# ~ ~ ~ ~ ~ ',,, _

-

__ __. _. _ _

.,m

_

g j, pf E" 52 T4

_w.r.

.._4-.

.

e,

--

. -. _ - - -

. _

_

,,

,

c.

The CST is aerated

.

fe,5) ::.:52 The Service Water System causes. corrosion (see weter)

(c.y] ::.:EJ REFERENCE OF 3322 p a s.

13-14 E 2:

ANSWER 7.07 (3.00)

a.

There is a momentar/ loss of RPCCW flow C0.52 The service water p u n.p s will be momentarily opereting below minimum required ficw.

CO.53 Service wcter pr es s.or e will be momenterily grerter than RPCCW pressure (possi'le in-leakage of sea water).

CO.5]

c b.

RFCCW Sur se Tank A or B Level (<112')

tany three at 0.33 each]

RPCCW Train A er 5 Non-Safety Header Auto Isolation RPCCW Tr ain A or B Suction Pressure (<15 psis)

RFCCW Header Supplf Flow High RPCCW Pun 4p Auto Trip / Deer current Loss of service water cooling to any on-service RFCCW heat enchanger Any high tempereture/ low flow s l a t o> s on con.ponents served by RPC.CW ce To avoid tube vibration effects in the RFCCW heat e:: c h a n g e r s.

CO.5]

REFERENCE AOP 3561, pg 2 OP 3330A, pgs 6 & 20-21 O

i

_

_ _ _

_. _ _ _ _

_

_ _ _ _

._

___

.

__

.

PROCEDUREE - NORMAL. AENORMAL, EMERGENCY AND FAGE

--- RE5iBE55fc;L C5sTE5L

-

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

____________________

ANSWERS -- MILLSTONE 3-E5/09/04-NORRI5, E.

S.

ANSWER 7.08 (1.50)

a.

When starting the pump, if the breaker has not closed (proper smperage)

the other pumps will Auto-Start if their switch is not in Pull-to-Lock.

[0.752 b.

To prevent seat leat.ege Fest the SGWLC valves.

[0.75]

REFERENCE OF 3319A. p3s 5

' & 15 ANSWER 7.09 (3.50)

a.

(105 psla)-start stancby CIA compressor

[0.32-locs) or c onti c 1 rocm E0.23 (100 psis)-manually cFen the cutsiac c o n t a i n m e r, t isolation valve to admit i n s tr umer.t s2r EC.33-Icc61 only CC. ]

( 85 ps; a )-msrmslly c1cse Service Air Header valvc E0.15]

-msneally open Sersice Air to Instrument Air X-Connect [C.153-local only EO.2]

-,; ' -

.1:

--i nc ef[rc /, mg/,e / f T /1 CO.51 b.

Feedwater

'.1

_

-

f

.

RCF Ses) Lster Outlet Valves Fail Open EO.5]

CUCS Grifice Isc1stion Valves Fail Closed CO.57 c.

RHR

~, hNcl, S u/7

-

(1 css of ten.per stor e controli E0.53

--

" '-

"

~_

-

'-

-

Nl6 7fl ne a

REFERENCE 5 & W Owg Nos. 12179-En-138C-2 & 12179-EM-103A-2 AOP 3562,pg 2 MP3 System Description, Topic 2, Lesson 1,

pg CV-1

!

l.

f

!

7.

PRDCEDUREE - r4 3 R H A L, A E.N O R M A L, E M E R G E rJ C. ? AND FACE 3:

--- EA5i5t5ETEEE E5siE5E----------~~~-----------

ANSWERS -- MILLSTONE 3-55/09/04-NORRIS, B.

5.

ANSWER 7.10 (2.75)

a.

5(N-18) = 50 REM

[0.25]

Total lif etinte to date = 48 + 1 = 49 REh Total lifetime available = 50 - 49 =

1 REM CO.253 Tots 1 this quarter evcilable

=

3-1 =

2 REM E0.253 Lifetime is mere restrictive than quarterly limit 0.85 REM /HR gLams + f.03 RAD /HR)(10 QF) neutr on =1.15 REn/HF. dote Tste 1.0 REh/1.15 REM.'HR = 0.67 HR$ = 52 MIN CG.5]

CO.2 for using tne conservative q u e l i t,, 'artor 3 6.

25 REM whole body one time exposure to.753

.c.

Director, Site Energency Oper ations

0.753 REFERENCE 10 CFR 20 3HP 4700, pas 6-11 & 14-15

_

_ __

.

t E.

ADhINISTRATIJE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE

._______________'__________________________________________

ANSWERS -- HILL 5 TONE 3-55/09/04-NOGFI5 B.

3.

l ANSWER 8.01 (2.50)

a.

You may operate for up to two hours with one less than minimum complement E0.753 pr ovided that immediate action is t al, e n to bring the complement up to minimum EO.52.

t.

The on-shift STA will have to wait for a relief to come in EO.7531 ct if the on-coming 55 or SRO meets the STA requirements, the STA siticr may be vacant E0.53.(C/q,',(je,<,pej,f,y,,,,,;j f he le y r W %p< * * " *

REFERENCE ACP 6.01, para 6.1.5, ps B T.S.,

Section 6.2.2 ANSWEF:

8.02 (1.75)

1.

To allow for crerstional f l e a l t t l i t,>.

(c.E5 J E..

-

:... : i 11 u _ : '. r,.. : : :. c:;

i ;- ::. _

g-

- ;f

a ;.

,

--

-'

- ^ '. l o c. c c _

-

c.

-

'.

T'

~5:

2F4. The tolerances for ir.tervals is restrictive to ensur e the reliability associated with toe surveillance is not degraded.fv ?) E0.62 REFERENCE T.S.

3/4.0, pgs 3/4 0-2 d,B3/4 0-3 ANSWER 8.03 (2.25)

1.

Fressure < 440 psia (fro pren)

E0.375]

Temperature 350 F (f w<i)

E0.5753

,

2.

P r e s s u r'e :

based on-the static pressure of the RCE added to the discharge head of the F:HR pump not to exceed t*t design pressur e of the RHR system.

[0.753 Temperature *

based on the design capacity of the heat exchangers to reduce temperature of the RCS to 120F within 24 hrs after SD.

E0.753 REFERENCE OP3201, para 4.17, pg 12

,

.

E.

ADMIN!5TRATIVE FROCECURES, CONDITIONS, AND LIMITATI0tJC FACE

ANSWERS -- MILLSTONE 3-55/07/04-bCREIS, 5.

5.

ANSWER B.04 (2.00)

a.

Only used when the 0-I-A can assure the safety of the persennel for which the tagging was requested.

E1.03 b.

<1 hr - work stopped a work order in custody of OIA CO.53

>1 hr - valves and/or br ess er s TAGGED as listed on Tss-Log sheet CO.53 REFERENCE ACP-GA-2.06A, pgs 4,

6, S 25-26 ANSWER S.05 (2.00)

a.

Channel Calibraticn - the adjustment of the channel such that it responds within the required range Enc securacy of kr.own values of input E0.53.

The coannel eslibration includes the senscrs anc circuitry EO.53.

b.

Channel Operational Test - the injection of s simulated signal intc the channel ss close to the sensor as pt3ctical to verify cperability of the circuitry E0.53 (Does not include a check of the senscr, deduct 0.25 if the answer indicstes senscr is checked.)

Adjustments msy be made as necessary CO.53.

REFERENCE Technical Specifications, pg 1-1 ANOWER G.06 (3.00)

/76;v e y,

a.

If the emergency concition is classified as anAlert,(Site Area

,

Emetgency, or General Emetgency)

E1.03 b.

1.

W ill assembly help or hinder the situation?

[0.53 2.

Per sonnel dose rates exceeding limits

[0.53 (limits:

210 mrem /hr or I-131 levels : 10 n MPC)

3.

Personnel exposure exceeding limits CO.53 (limits:

>500 mrem whcle body or 500 I-131 MPC hours)

4.

Actual or potential personnel hazar ds e::ist.

[0.53

f.

.

3.

ADMINISTR A TIVE F riOCEDURES, CGNDITIGh5, ANE LIMITATIONE FACE

__________________________________________________________

ANSWERO -- NILL 5 TONE 3-85/09/04-NORFIS, E.

5.

REFERENCE EPIP 4010A. pg 5 EPIP 4 010 E:, pg 3 Nont of ANSWER 8.07 (2.00)

-

ao 13 sthis is the responsibility of the Lead Department Head)

[0.5]

b.

1.

If performing PORC/50RC appr oved procedur es [0.253, th-t require Control Fccm approval [0.253r and work. is documented [0.253.

2.

I t h a s. c e e r-d e t e r n. i n e d that the vori does not affect plant operaticn

[0."53, and does not require DC [0.25] or equipment tagging [0.2523 PEFERENCE ACP-GA-2.02C, pas T

9.

!

11-1l3 g)J6(,.c c ; ja a nd desah

'

~

AN5WER 8. 0 E.

(5.00)

1.

All penettstion3 required to be closed during accicent conditions are either:

CaFable of being closed by an operable containment aito-icciction valve system, or

[0.53 Closed by manosi valves, blind flanges, or deactivated autenatic valves secured in their closed positions.

[G.53 2.

All equipment hatches' closed and sccled.

[0.53 3.

Each sir Icek opercble.

[0.5]

4.

Containment lestage rates within limits.

[0.5]

5.

Ses11ns nechEnisn associated with each penetratior, is cpor abic.

[0.53 REFE6ENCE Technical Specification, pg 1-2

._.

-

_ _

.

_. _ _ _

.

- -. - - _. -

.

_

,.

.

8.

ADMINISTRATIVE FROCEDURES, CONDITIONS, AND LIMITATIONS FACE

ANSWERS -- hILLSTONE 3-85/09/04-NORRIS, E.

3.

ANSWER 8.09 (2.50)

a.

Go to HOT STANDBY (within one hour).

CO.53 b.

1.

Prevent cladding peri oration ;0[. 5:]which would r esult

/. o

,

in the release of fission products to the RCS

. 5:.C/,qJ

"

.

E -et r :t : r :::

.- t'u i-t ; 37

,

m r L;.c i, C

0.5:

t'

.:

,1 -

c--t

-

.

eetmygg _- c. g,n,

, - 1 4 u g +, -

+>,m c.. + i -, 3 +

. ; _ ; - :,; 7

,5,,

_

REFERENCE TS p3s 2-1 & B2-1 ANSWER-0.10 (4.00)

t a.

No CO.253; the TC require 5 all RCS accumulators to be operable when in Mode 1 E0.753.

(An tr ri s we r of Yes will be acceptable with sn sppropriate exp % nation.)

b.

To ensure that an adequate volume of borated water [0.53 is provide.d to the cor e f ollowing a lorse [0.25] RCS pipe rupture CO.253.

c.,

Restore level to the neraal band (with1r. ane hour ) C1.03 or commence placins the plant in at leest hot staridby [1.03.

REFERENCE TS 3/4.5.1, pas 3/4 5-1 & B3/4 5-1 MP3 Systen. Description, Topie 3, Lesson 4, ps 61 t

I l

i r

l l

'

-

-,.-.-..--

., - -.. -.

. -. -..

,- -

. -,

--

- - - - - - - -.

- - = - - - - - - -

-

~

-

g_

namsmasr ummes

]

.,~ _.

,. nn at3.f me es.neM,mmE..$ StEC,mut Conapassy y d U()

y,_

fM1

. -.........

lN4J

......am-,

g

...

me..

.c. u

-

September 12, 1985 MP-S-T-822-85 TO: Doug Coe USNRG,Refon1 Y/b

.

b y - //k /

~

.

FROM:

on Stotts Millstone unit 3 Training SUBJECT: Comments'on Written Examinations of September 4, 1985 Attached is my compilation of comments on your written examinations administered to our operators and senior operators on September 4, 1985.

All comments have been resolved in discussions with Barry Notris, David Ruscitto and you.

This list reflects those agreements.

Thank you for your cooperation as well as that of Mr. Norris and Mr. Ruscitto.

RGS/rm Attachment cc: Training File OT-2.3 M. Moehlmann osto nty 3 a3

.

___________-____.._w

_.....

....

.

,

.

ATTACHMENT RESOLUTIONS TO NRC EXAM COMMENTS REACTOR OPERATOR EXAM 7, 1. l'

10 cycles may produce a slight difference; answer key will l,0 allow for "1 is worth more" if explanation is provided.dg+ps c""~

Ne t ex-<.a pi *A

~*("~ s is d'+*

G

<l'+r % ** k' Lle 1.04 a,b,c Use of the proper term " Shutdown Margin (SDM)" will key

candidates to include +1400 pcm for stuck rod, as the Tech Spec definition dictates; answer key will allow inclusion of this value. p,& m b) ~ p 4 w s p.' k ll McivEs e s> L )rw~

y s k is s+d.

af (@

1.06 same as SRO #5.09)

1.07 a Will also allow Tech Spec Bases for answer. - ?

I 2.01 a (same as SRO #6.04 b) - ?

I 2.04 A & B Rl!R min flows open if less than 555 gpm (references o fc,

provided LSK 27-7E, pLS page 74) /

2.06 a Answer key item #2: time delay is 200 and 210 seconds (reference provided). V o,p *

1 tem #4: feature is completely removed freference provided)( 0,lc.

D q # '2 9 4M (~cv- +,2J 2 - J(,yf gA4 J ttf -1.~ M Key will reflect changes gu-3.01 a Axial Flux Difference Monitoring is not included in the correct answer (reference provided). (nrau G.J-l blxk (Ap to;A

'"*

'

y pt s M (1,.4

%,u.9 rwt ut qM ed.

~

3.01 b Agreed that this switch performs only one function:

" defeats input to overpower Rod Stop"; answer key will allow for this 0. F,

fact.

3.02 Will also accept " output" as label for vertical axis, o te.

3.05 a 1)

CAF = 15 psia 2)

111-3 we use 25 psia OA

'

3.06 The 97.75% trip has been removed; now only one trip called

" low-shaft speed" at 95.75%; we have no P-17; P-7 (10%) is the QK.

only permissive (references provided).

3.07 a 2)

Ansycr key will also accept " excessive kw/ft" ur.

!

3.08 c Correct answer will read " rods out from Tave/ Tref deviation.

O,k,

3.10 Answer key, as written, is correct.

4.03 b,c In both cases, answer key will allow for operator tripping reactor on high VCT temperature. /vD 'T LI)

Ae? 35T/

pg 3-1-i

.

ppyr

--

- -.

.

1 4.04 b.

InboBQcases answerkeywil reactor'onhig(h'VCTtemperatur.-allow]oroperltortrlpping g7

-

,

4.04 b Will accept any 4 from a provided list of shutdown parameters (reference provided).

OI -

4.04 c

" Generator Differential" is added to answer key (reference 7 provided).

,

.

SENIOR REACTOR OPERATOR EXAM 5.01 b Answer key too specific ior required answers. A broader range should be allowed. Concern was resolved.

Some latitude will

be allowed during grading.

{

li 5.03 a Answer key states: "With very short lifetime," "with very kl

long...".

Utility feels these may be implied rather than

'

stated. This concern was resolved. Examiner is looking for those concepts.

Concern that students may use an alternate method for proving c

'

the 1/3 dpm SUR. This concern resolved.

Alternate methods are acceptable.

5.04 a Concern that the first 1.0 points in the answer key were not directly asked for. This concern resolved by changing the l

answer key.

'

b Concern that an acceptable alternative for "photoneutron reaction" and " spontaneous fission" should be the equations.

Concern resolved. Equations are sufficient for full credit.

5.05 a Concern that full credit should be given for writing the equations. This concern was resolved as follows for parts 1, 2, 3.

1)

must include some discussion as to how OH~ affects pH.

2)

equation adequate for full credit and second half of answer key, "this is restricted to use on startups..."

was eliminated.

3)

equation adequate for full credit.

5.06 a Concern that reasonable values for 5 should be allowed.

gg This concern resolved. Any acceptabfe value will be allowed.

5.07 b Answer key should not include the words:

" causing excessive wear."

This concern resolved by eliminating the words from the answer kcy.

!

.

!

-2-

!

f

--

_

l i

5.08 Concern that many variables may occur in the answers given by examinees which are not stated in the question.

For example, turbine load may decrease with stage pressure feedback not used by MP3. This concern resolved.

Examiner will use great latitude in grading.

j

!

5.09 a Concern that MTC discussion should be adequate for full credit.

This concern resolved by changing answer key.

.

b Concern that MTC discussion should be adequate for full credit.

This concern resolved by changing answer key.

t Concern that discussion of Doppler Only Power Coefficient not c

I necessary to fully answer the question.

This concern not

.

resolved. Examiner wishes to reserve j research is completed. Not wpm udgemen untilg5therj7Q l

/

fW pw twu% 0-3'$

!

-fo cessco'S4 - wly r>oPC 04 +k N.

6.01 b Concern that the words "due to the high $ setpoints lowered" should not be required for full credit. This concern resolved by removing those words from the anever key.

6.04 a Concern that the significance in this question is that an abnormal condition exists for temperature, not that_the design discharge capability is affected. This concern resolved as follows:

the words "so the tank is capable of handling the design discharge" were put in parentheses in the key.

Also concerned that the words " cool the tank" should be

.i acceptable for full credit for second part of this question.

Thic concern resolved by enclosing remainder of the answer key i

for this part in parentheses.

j b

Concern that the answer key reflects concerns for corrosion.

MP3 uses a stainless steel PRT and therefore this is not necessary. This was resolved by changing the answer key.

Hydrogen explosion hazard discussion is adequate for full M

credit.

6.05 Concern that answer key is incorrect for P-8 permissive setpoint at MP3. This concern resolved by changing answer key to reflect correct value of 48%.

pg

,g engM 6.07 Concern that answers under OPAT should all be "No Change" since l

Al input to OPAT is set to 0 at MP3. This concern resolved by

'

changing answer key.

(References provided) g(C.

3)

Concern that OTAT will decrease.

(if anything) because of the way Ai input is used by OTAT circuitry. This concern resolved by changing answer key.

(References provided) 4

,

i-3-

.

-

.

_,_-.

-

,-

,

.

,

. - -

-.

HWEEW

-

LS

.

j eScrff 6.08 a Concern that proper names for an nciator tiles should not be f'

required and that other possible indications should be allowed. p " Q p?

This concern resolved. Examiner will use latitude in grading.

g 6.09 b Concern that listing the 5 entry conditions from A0P 3566 should be acceptable for full credit. This concern resolved by changing the answer key.

(References provided) py.

7.02 b Concern that other acceptable answers will be allowed. This o

'

concern resolved. Examiner will use latitude in grading, rd E i

Concern that " Generator Differential" should be included in the i

c answer key.

This concern resolved by changing the answer key (References provided) cy_.

!

7.04 c Concern that some examinees may approach question from the d

point that they are at the ASP and list lights and indications

[@LX seen there. This concern resolved.

Examiner will accept either the answers in the key or an explanation of lights and

'

indicators at the ASP.

!

7.06 a Concern that word " manually" should be eliminated from answer key. This concern resolved by enclosing the word in parentheses in the answer key.

b Concern that " shift to CST" is the only part of the answer

.

necessary for full credit. This concern is not resolved.

0.F -

Further research necessary for full resolution.

8.02 Concern that part 2 of the answer should not be included in the key.

This concern resolved by changing the answer key.

8.03 Concern that certain amount of latitude should be allowed on numbers to fill in the blanks. This concern resolved.

Examiner will use latitude in grading.

~

Also concerned that answer key is too specific for basis on the pressure and temperature. This concern resolved. Examiner will

use latitude in grading.

'

8.07 Concern that acceptable answers should be("#3" or "none." This concern resolved by addition to answer key.-

~

ggg%

.

M A A Act 8.09 b Concern that part 2 of the answer key is not part of the stem question and should, therefore, be eliminated. This concern resolved by eliminating part 2 of the answer key for this question and adding y to each of the answers in part 1.

-4-

' ATTACHMENT 3 R0 EXAMINATION COMMENTS AND RESOLUTIONS Question / Answer Comment

,

1.03 a Comment that 10 cycles may produce a slight difference is not accepted since the referenced training material clear-ly states "...no noticeable change over design life."

1.04 a, b, c Comment that use of the proper term Shutdown Margin will key candidates to include a stuck rod is not accepted since the question specifically ex-cludes consideration of a stuck rod.

1.06 a, b A discussion of MTC effects during these accidents is sufficient for full credit since the Doppler effect is relatively very small.

1.06 c Comment that discussion of DOPC is not necessary to fully answer the question is not accepted since this is the only power turning reactivity effect given the conditions set by the question.

1.07 a Answers based on the Technical Specification for Reactor Safety Limits will be accepted as they are equivalent in content to the referenced training material.

2.01 a Corrosion is not required for full credit since the PRT is stainless '

steel.

Referenced training material is inconsistent on this point.

2.04 555 gpm is the correct setpoint for RH3 pumps as per LSK 27-7E, PLS page 74. Training material is not current.

2.06 a Time delay of 200 and 210 seconds is correct instead of five minutes, as per Emergency Generator Loading Se-quence Fig. 1.

Item 4 is deleted from

,

.

_

-

,.

. _.

.

-

2.06 a (cont'd)

the answer per Dwg. #25212-26915.

Training material is not current.

3.01 a AFD Monitoring deleted from answer as per NI Technical Manual Process Control Block Diagram 10 Series.

Training material is not current.

3.01 b Will accept " defeats input to over-power Rod stop" for full credit since this is a correct answer the way the question is worded.

3.02 Will accept " output" as a label for the vertical axis.

i l

l 3.05 a CAF = 15 psia and Hi-3 is also 25 psia.

-

3.06 The 97.75% trip has been removed. An-swer changed as per revised Reactor Trips table of Topic 1, Lesson 2 which was not current when provided to NRC examiners.

3.07 a Will accept " excessive Kw/ft" as an alternate answer.

3.08 c Question was changed during the exam-ination to delete "Auctioneered high Tave... matched." Correct answer is now " rods nove out due to Tave/ Tref deviation."

4.03 b, c Answer key will allow for tripping the reactor on high VCT temperature in accordance with A0P 3561 page 3.

4.04 b Due to confusion caused by question wording, will accept shutdown param-eters taken from LSK 24-9.3J.

4.04 c

" Generator Differential" added to answer as per LSK 24-9.30.

In addition to the above, the following errors were discovered in the answer key after grading commenced:

_________

-

.

-

.

--

.

..

-

,

4 Question / Answer Comments

- 1.04 b, c Mathematics' error corrected.

~ 1.09 1050 psia should have been 1080 psia (typo)

= 2.01 Due to question wording, safeties and i

reliefs are also correct response.

2'05 Correct value is 375 psig as per PLS

.

pg. 52 2.09 Additional correct answer is " Seal water heat exchanger / excess letdown -

normal flow path," as per Topic 2 Lesson 1 Figure CV-1.

3.03 c.3 Add " blocked when steamline SI is not blocked" as per Main Steam System pg. 20.

4.11'-

A 250 mrem /qtr neutron exposure limit exists as per SHP 4902 pp. 10-11 which becomes more limiting than the beta-gamma limit in the answer key.

,

..

i'

i.

.

t

l.

'

,

, -,..

,

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

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

.. - -,

c-

-.,

-..-

-

_

.

SENIOR REACTOR OPERATOR EXAM COMMENTS AND RESOLUTIONS Question / Answer Comment

.

5.01 b Answer key too specific for required

answers. A broader range should be allowed. Will be considered during grading.

5.03 a Answer key states:

"With very short lifetime," "with very long...".

Util-ity feels these may be implied rather than stated. Will be considered during grading.

5.03 c-Concern that students may use an al-ternate method for proving the 1/3 dpm SUR. Alternate methods will be con-sidered during grading.

5.04 a Concern that the first 1.0 points in the answer key were not directly asked for. Answer key changed to that re-

~

quired by the question.

5.04 b Concern that an acceptable alternative for "photoneutron reaction" and "spon-taneous fission" should be the equa-tions. Equations are sufficient for full credit.

5.05 a Concern that full credit should be given for writing the equations. This concern was resolved as follows for parts 1, 2, 3.

1) must include some discussion as to

-

how OH affects pH.

2) equation adequate for full credit and second half of answer key, "this is restricted to use on startups..."

was eliminated.

3) equation adequate for full credit.

5.06 a Concern that reasonable value for Beff should be allowed. Other acceptable values will be considered during grading.

+

,

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

_ _ _, -, - _

._,.-.ym

,m._

_,,., -.,,

- ~.

.-

, _, _, -.

...

_ _ _ _ - _, _. -

-

5.07 b Answer key should not include the words: " causing excessive wear," since it was not asked for in the question.

This concern resolved by eliminating the words from the answer key.

5.08 Concern that many variables may occur in the answers given by examinees which are not stated in the question.

For example, turbine load may decrease with stage pressure feedback not used by MP3. Will consider other assumptions during grading.

5.09 a, b, c Same comment and resolution as R0 1.06.

6.01 b Concern that the words "due to the high $ setpoints lowered" should not be required for full credit. This concern resolved by removing those words from the answer key and substi-tuting "due to the limited relieving capacity of the code safeties," in accordance with the basis for Tech Spec 3.7.1.1.

6.04 a Concern that the significance in this question is that an abnormal condition exists for temperature, not that the design discharge capability is affect-ed.

This concern resolved as follows:

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the words, "so the tank is capable of l

handling the design discharge" were

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removed from the required answer.

Also concerned that the words, " cool l

the tank" should be acceptable for full credit for second part of this ques-l tion.

Remainder of answer was not

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specifically called for in the question and was deleted.

,

.

6.04 b Same comment and resolution as R0 201. a.

6.05 Concern that answer key is incorrect for P-8 permissive setpoint at MP3.

This concern resolved by changing answer key to reflect correct value of 48%. Supplied reference material not consisten..

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6.07 Concern that answers under OPAT should all be "No change" since AI input to OPAT is set to 0 at MP3. This concern resolved by changing answer key as per Tech Spec Table 2.2.-l.

Concern that OTAT will decrease.

(if anything) because of the way AI input is used by OTAT circuitry. This con-cern resolved by changing answer key as per Tech Spec Table 2.2-1.

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6.08 a-Concern that proper names for annunci-ator tiles should not be required and that other possible indications should

,

be allowed. Will be considered during grading.

6.09 b Listing the five entry conditions from AOP 3566 is acceptable for full credit.

7.02 b Concern that other acceptable answers will be allowed. Will be considered during grading.

7.02 c Same comment and resolution as 7.02 b.

7.04 c Concern that some examinees may approach question from the point that they are at the ASP and list lights and indications seen there. Will accept either the answers in the key l

or an explanation of lights and indi-cators at the ASP.

7.06 a Concern that word, " manually" should

'

be eliminated from answer key. This concern resolved by deleting the word from the answer key since it was not i

asked for in the question.

7.06 b Concern that, " shift to CST" is the only part of the answer necessary for full credit. The rest of the answer was not olicited by the question and was deleted.

8.02 Concern that Part 2 of the answer should not be included in the key.

Part 2 was not elicited by the l

question and was delete.

7 8.03 Concern that certain amount of lati-tude should be allowed on numbers to fill in the blanks. Also concerned that answer key is too specific for basis on the pressure and temperature.

Will be considered during grading.

8.07 Concern that acceptable answers should be "#3" or "none."

Due to poor wording within ACP-QA-2.02C either "#3" or

"none" will be accepted as a correct answer.

8.09 b Concern that Part b.2 of the answer key is not asked for by the stem question and should, therefore, be eliminated.

This concern resolved by eliminating

,

>'s part 2 of the answer key for this question and adding.5 to each of the

answers in Part 1.

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IR 05000423/1985044

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