Text

Exam Rept 50-259/OL-86-02 for Units 1,2 & 3 on 860616-18. Exam results:12 Candidates Passed Operating Exam & 10 Passed Written Exam
	ML20205A915
Person / Time
Site:	Browns Ferry
Issue date:	07/28/1986
From:	Bruckman K, Munro J; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	;
Shared Package
ML20205A891	List: ML20205A886; ML20205A915;
References
	50-259-OL-86-02, 50-259-OL-86-2, NUDOCS 8608110477
	Download: ML20205A915 (110)
	v • d • e

F m[ato UNITED STATES g *o NUCLEAR REGULATORY COMMISSION

,0 "

o REGION 11 g j 101 MARIETTA STREET, N.W.

ATLANTA, GEORGIA 30323

\****/ ENCLOSURE 1 EXAMINATION REPORT 259/0L-86-02 Facility Licensee: Tennessee Valley Authority 1101 Market Street Chattanooga, TN 37402-2801 Facility Name: Browns Ferry Nuclear Plant Facility Docket Nos.: 50-259, 50-260, and 50-296 Written examinations were administered at the Browns Ferry Nuclear Plant near Decatur, Alabama. Operating examinations were administered at the Power Training Operations Center ne r Soddy Daisy, Tennessee.

Chief Examiner: < p 2sdc yE Brodgenf Date Signed Approved by: dadam n F. Munto/Act)mg Section Chief

'//.2r/sc Date Signed

/

Summary:

Examinations on June 16-18, 1986 Operating and written examinations were administered to 12 candidates; 12 passed the operating examination and 10 passed the written examination.

. l 8608110477 860804 PDR ADOCK 05000239 V PDR

r-REPORT DETAILS

1. . Facility Employees Contacted:

H. C. Noe, Division of Nuclear Training

A. R. Champion, BFNP Operations Training

S. Howard, Jr., BFNP Operations Training

N. S. Catron, BFNP Simulator Training

W. J. Glasser, Division of Nuclear Training

R. J. Moll, BFNP Operations Training

Attended Exit Meeting

2. Examiners:

K. E. Brockman, RII D. J. Lange, RI A. J. Mendiola, NRR S. D. Stadler, RII

Chief Examiner

3. Examination Review Meeting At the conclusion of the written examinations, the examiners provided A. R.

Champion with a copy of the written examination and answer key for review.

The comments made by the facility reviewers are shown in Enclosure 3; NRC resolution to these comments are listed below,

a. SR0 Examination - Analogous R0 questions in parenthesis Question 5.06 NRC Resolution: Comments not accepted. While "several hours" is not totally explicit, to address a period of time lasting for over five hours would require discussing both rod withdrawal and insertion. Only answer "a" is possible from time = 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months after shutdown. No change to exam or answer key.

Question 5.08(1.10)

NRC Resolution:

(a) Adequate information is available to calculate bundle CPR, even though the attached P-1 printout does list the elicited CPR.

Stating the end result of CPR = 1.156 will receive half credit; the partial credit breakdown will be used for awarding points.

The need to show all calculations was covered in the instructions given to the examinees. No change to answer key required.

r Enclosure 1 2 (b) Comments acknowledge. Typographical error corrected. Answer key modified to reflect correct units.

Question 5.10.b NRC Resolution: Cormient not accepted. The question requires an integrated plant knowledge appropriate to both the R0 and SR0. Addi-tionally, this happening is specifically addressed in the utilities training materials. If alternative responses are given which are technically accurate, they will be given full credit. No change to exam or answer key.

Question 6.01(2.02)

NRC Resolution: Comments accepted. Since valve 63-500 is isolated during tho SI, the system realignment would be required for both Pump "A" and "B" operation. Answer key modified to reflect additional requirement.

Question 6.03(3.01)

NRC Resolution:

(a) Comment not accepted. The Jet Pump Total Developed Head instrument is in service, and provides indication, during all modes of operation. Simple application of dp gauge operation, combined with acknowledge of the pressure relationships between the taps, allows for answering this question. Just because an instrument's primary use is during startup/ test operations, the operator is not relieved of knowledge about it. No change to exam or answer key.

(b) Comment accepted. Since the High Drywell Pressure condition parenthetically described in the question allows for a potential misinterpretation by the candidates, the question will be graded based upon whether the candidate assumes drywell pressure exceeds 2.45 psig, or not. If the candidate states an assumption that drywell pressure remains below 2.45 psig, he will be graded in accordance with this valid assumption. If the high drywell pressure condition is assumed, the utility provided alternative answer is acceptable. The answer key will be modified to reflect the changes requested.

Question 6.05 (3.03)

NRC Resolution:

(a) Utility comment accepted. The conditions, as expressed, do result in a half-scram condition via the automatic channel (A1) of RPS.

However, since only the manual channel (A3) schematic was included in the handout, it is possible for confusion to exist as to whetner the answer was to be limited to that channel. The answer

Enclosure 1 3 key has been modified to allow for either response, dependent upon the examinees assumption of including the automatic channel in the answer, or not.

(b) 5A-K15 B&D (not indicated on utility handout, but accurate for B channel) accepted as alternate response. Answer key modified.

Question 6.07 (3.10)

NRC Resolution: Utility comment acknowledged. Part "a" of a question deleted due to technical inaccuracy. The "b" solenoid" is not required information for answer; the answer key is, otherwise, accurate and acceptable. No further changes to answer key required.

Question 6.09(2.10)

NRC Resolution: Utility comment accepted. The confusing wording of the utility lesson plan is clarified to provide technical accuracy. Answer key modified as per utility comment.

Question 7.01.b(401.b)

NRC Resolution: Utility comment is essentially a repeat of the answer key. The key words are " directed to take actions". No change to answer key required.

Question 7.03 NRC Resolution:

(a) Alternate acceptable wording used to convey the answer ha. and will continue, to be acceptable. No change to answer key required.

(b) Utility comment accepted. Reference material provided to the NRC included a graph with a drafting error; even though the concept for differentiating between the curves remains valid, the specific difference asked for no longer exists. Question deleted.

Question 7.06a NRC Resolution: The TSC location is more accurately defined as between the U1/U2 and U3 Control Rooms; the answer key was previously modified.

" Shop or Maintenance Area" is accepted as the location of the OSC; specific reference to a particular shop area would receive only partial credit, as the answer key indicates. No change to answer key required.

l i

l

r Enclosure 1 4 Question 7.07(4.06)

NRC Resolution: Utility comment accepted. Even though the utility reference material combines purging and venting of containment as a single reason for starting the Standby Gas Treatment System (01-65,L.0.B), it is agreed that they are separate and distinct operations, as indicated per 01-64, " Primary Containment System".

Individual credit will be given for each/either response. Answer key modified to reflect changes.

Question 7.08 NRC Resolution: The utility comment is trivial in its differences from the answer key. No changes to answer key required.

Question 7.09(4.07)

NRC Resolution: Utility comment acknowledged. Only the TEST portion of the answer was required; the INSERTED portion was additional information for the grader to ensure that credit was not deducted if the candidate answered verbatim from the utility learning objective.

No change to answer key required.

Question 7.11 NRC Resolution: Utility comments acknowledged. Part 2 and part 3 comments are alternate ways of describing the limits listed in the answer key. They would have received full credit, but for clarity have been parenthetically added to the answer key. The part 4 comment is not accepted in that it does not relate to " contaminated areas";

additionally, it is already on the answer key as response 5. No change to answer key.

Question 8.03 NRC Resolution: Utility comment not accepted. 10 CFR 55.22, 10 CFR 55, Appendix A, and NUREG-1021, ES-202 and 404 provide the basis for requiring senior operators to know Technical Specification LC0's. The requirement for this knowledge has been consistent since, at least, 1982 and is still considered appropriate. No change to exam or answer key.

Question 8.04.b NRC Resolution: Utility comment accepted. The question's wording does allow for the interpretation described by the utility. The alternative response requested will be allowed. Answer key modified reflect additional response.

I

Enclosure 1 5 Question 8.06 NRC Resolution: Utility comment accepted. The question's wording does allow for the interpretation described by the utility. The alternative response requested will be allowed. Answer key modified to reflect additional responses.

Question 8.07 NRC Resolution: Utility comment not accepted. That the writing of an MR does not include inherent to it, the requirement for equipment investigation to the level desired, is evident in that SP 12.24, specifically and uniquely, identifies the two tasks. Additionally, the utility Learning Objective indicates that an operator should be able to

" explain" the fuse replacement guidance. " Write an MR to electrical maintenance" does constitute an explanation of partial acceptable quality. When combined with specific reference to the operators not replacing the fuse, the answer key has been modified to show a partial credit breakdown.

Question 8.09 NRC Resolution: Utility comment accepted. The question's wording does allow for the interpretation described by the utility. The alternative responses requested will be allowed. Answer key modified to reflect additional responses.

Question 8.10 NRC Resolution: Utility comment acknowledged. The answer key is adequate to grade the question - it provides sufficient guidance to cover both situations described by the utility. Also, no automat :

functions are discussed in the key. The utility cautions that " care must be taken to accept an answer based upon the question and not word for word phrases ...". Likewise, the utility should not look at the answer key as a " bean count", but as a guide to ensure equitable and consistent evaluation of examinee's demonstrated knowledge. No change to answer key required.

i Question 8.11 NRC Resolution: Utility comment not accepted. 10 CFR 55.22, 10 CFR 55, Appendix A, and NUREG-1021, ES-202 and 404 provide the basis for requiring senior operators to know Technical Specification LCOs.

The requirement for this knowledge has been consistent since, at least, 1982 and is still considered appropriate. No change to exam or answer key. I

Enclosure 1 6 (b) R0 Examination Question 1.04 NRC Resolution: Utility comment not accepted. The question calls for the ability to understand that THRESH 0LD power is based upon PCI failures. Factors effecting PCI are adequately discussed. It is considered appropriate that the examinee be able to correlate these concepts. No change to the exam or answer key.

Question 2.03 NRC Resolution: Utility comment not accepted. If the examinee reaches a final conclusion of normal injection, but addresses the potential for a turbine trip or system isolation, full credit will be given. If he assumes totally normal operation, this displays a lack of knowledge as required by the utilities Learning Objective and 0I-73. No change to answer key required.

Question 2.08 NRC Resolution: Utility comment not accepted. The question is based directly on a Learning Objective (See Exam Reference). Additionally, the relevance of this level of knowledge has been specifically addressed on both of the last two BFNP exams (See Exam Reports 50-259/0L-85-02 and UE!BS-03). No change to exam or answer key.

Question 2.09 NRC Resolution: Utility comment accepted. TCV's #1, 2, and 4 will all open to compensate for #3 being closed. Answer key modified to reflect the changes requested.

Question 3.09 NRC Resolution: Utility comment acknowledged. The operator should know that the ball valve will not close until the in-shield limit switch is closed (i.e., the TIP is fully withdrawn). This is not detailed circuity knowledge, and is considered appropriate for both the R0 and SRO. Answer key, however, was modified to reflect more accurate partial credit.

Question 4.02 NRC Resolution: Utility comment accepted. The response provided is more direct under the basis of C-5, vice RC/L of the BWROG Guidelines.

The reason for ADS inhibition is directly and specifically addressed.

Answer key modified to reflect new correct response.

{

)

L A

5 Enclosure 1 7 Question 4.03 ,

NRC Resolution: Utility comment accepted. 'Due to 'the utilities changes to the E01 Entry Conditions, the new set points will be placed in the answer key. Note that the setpoints are still required for full credit.

Question 4.09 NRC Resolution: Utility comment not accepted. This is General Employee Training (GET) level knowledge. All personnel with access to the plant should know the Emergency Classifications. No change to exam or answer key.

s

4. Exit Meeting At the conclusion of the site visit the examiners met with representatives of the plant staff to discuss the examination.

There was one generic weakness noted during the examination. The Browns Ferry simulator had great difficulty in providing a continuin0 accurate simulation of plant conditions during scenarios where E0I usage was required, particularly low water level conditions. This problem was made aware to the examiners before the exam start (See Enclosure 4). The difficulty in transfering between computer models was noticed on numerous ,

occasions; correction of this problem should receive high priority when the Browns Ferry simulator is moved to the plant site.

The cooperation given to the examiners was also noted and appreciated.

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

O s

e e a ENCLOSURE 2

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_'_S' the source o# water to the Resetor Vessel between 350 and c.

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(0.5) b, STATE the reason #or deirv.in: c. l a c i n : the Ceedwater Pun . m v s in service .intil '50 ostw. 2 (0,5)

( * * * * *. C A'E G 0 5:Y 04 CONTINUED ON NEXT PAGE ****m)

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%. . 4 REFERENCE Genera'. Electric u ent T r a n s a r and 21vid riou, Chapter 9 BCNP: TRAMSI' ION 90ILTNG ! ATLAS TESTING L/o v t.5-68 .

GEV' CORPELATION

C:ITICAL 009E? L/':.P.3; Uter, Chrots- 9 7 .. 0.'s 5.; e 5.~

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instrumentation. A significantly uIGHEC (approMimately 300 times) count rate would be ese^ for the UNVOIDED ereas of the core as opposed to the VOISEO. (1.0) o.cerReNrc

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Geners' Electric ueet 'ransfer and Fivid Clow, Chapter ?

General Electric Reactor Theoryr ChEpter 4

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_ _ _MITOUMENTS _ _ _ _ _ _AND _ _CONTRO_S 26

'3 . :' AGE

a N S W E;: S -- 590WNs CE;:ov 1 ?&3 '

-8 6 /0 6 / _5-E:RO CM AN r ANSvE2 ?.0' (2.00) 3 . Secrease

2) Dec*erse

3) Increase a) Decrease (0.25 es '-i

I' " / 'a :' r e t i ' a e is

b. -

.41 ci t : c e n d r e s ci e r- - e-tsure it

' 5 .

itg* 3 st?"* jn31 is 3 9 :~ ' ", 0 the EUR ? U n p ': (f.23) l O '. 5 c

r!

cpening s:.gual ._ s ie t to the i n c e r t. i c ; ocives (0.125). cut t'iey will not :r e- 'O.125) (due to the need 'or eo:.ncidence *' r o m NR GE"AT' (0.S) 2' recire';12 tic- pump ci s chtige velves r!er= #en reactor

- e - . c e decre as es to 200 ps o_: den s .PCI syste" nitiatic- _-

present (0.25' ".ey will rio t c l e t. e ( C.c e te ,he need fe' cr:neidence

. . n ,. .

; r_ u. .a. r_ ,

, e. n . _ c -

_ (0.e) a n.. :_ ,, :. s, ,m, :

r,' e n e r s '; ".'.. a : t r i c . UT 9 - ' - - 2ec6..icn c_: e p :. . s ur _ ,/ :- (4 a. a ) , u . o . ,., . _ _- e. e f o. (g 4s), . .n. -

4

. 4. ; pec.rm_

'/P (* -- ) ; ~ ansient A n .2 '. ,2 3 i s '/c (t 55).

_ _.0. A

%u ~:2

r e. e

- . n. -_ ( 4. . c n >

a. As -he detector 0;+:vt incre.3ses. .Se S T '.) will a_ive 2 rio out'ui s t

'. C '. er-1; fr.ince the MTU ttill ptovidet i- a co t; uci enclos signal).

0.8) At 'he trip point. the *TU will also oi.e 3 trio outwt . nas 4 4

'0.2)

. (1.0)

%. r.,.>_.. n. -

(0.r1 a

' C_ '~ C_ ;Q '_~ L} f' T_

396c ; A T S '_ / c . 0. A; 9:NP ACN P0126

3. INSTRUMENTS AND CO M OLS

AGE 27 ANSWERS -- 990WNS CERRY 1, 2&? -36/04/'.6-900CKMAN, .

ANSWER 3.03 (2.004

3. Ic ANSWER IS CESE L'IO 'O CHANNEL L3. No trip cf O'9 'O.5) The IFM ING: will deenergine rela. 5:412A. causing rele'. 5A-M13A to t e e n e r s :. n e .

ucuever, since e OES snd 9'_ti t-Ls are in, as:sys 5 A ;(15 A ? voaim enersized 'e .i)

IF ANSWIF IS NOT ?ES :!ES ~C CMANNEL AS. Half Scram of ??S (0.5)

The IR" INCr . !' give the r:: , rough the eutoms .: channel (A1). . 0' O. w alf Scram a# 005 Channel 5 'O.5) The SRM VI-WI denerg:re; aelay SA-413A. ": s epent con + :- SE 136 (SA-M:3A i s. still sho-tedi, deen-ergining ralays 53-vi5; ? C '5?-M159 1 0). to.5) (1.0) e._-

,n _ e p e y r_ e_

9FNP* co? './o 't 28). r ; r; e -: 0 8 8, _.C.'s E, Hr -M, & L ANSWER ?,rc (2.003

4. Sele:t a rew :c Byptss the reference ?PR" oush tSe Null Init: 2te *? in the RBM Cabinet (0.5 each)

b. LPQP ?canscele ( '.5 w e ' ; L / cm-c m ) (0.5)

REFERENCE .

9FNP: RSM _/P (t 25), _.J.'s E & G ANSWED 2.05 (2.00)

2. No Chance. (0.5) The :t'er R707 will speed v? to co n ? er.3 3 t e

'or the e d v e t i c r. In ' low # om ReoT A. (0.5i (1.0)

b. 4!!! Increase and Stabilize at : "igher level. (0 5) As HPCI injects the level will irewetse which will call #or FW Flow to decrease. Stabil;:ation vill occur when the SF/FC error is countan-balancec by the level err et . (0,5) (1.0)

L.e e. --

e R.: N C e EFNo: LPt 2 p 20; TRANSIENT $20; OI-57 p 53; RQ 95/01/02 CWLCS L/0 (f 12)

2. IN37ouMENTS AND CONT;' OLE := c. G I 28 AN 5 WE: 3 .- 3POWNS LERTY 1 ^13

_ -S 6 / 0 6 ' 16

R O C 'f f 4s. b' -

EIu' _-PG 72s crce.

3

',3

y n 9. 6 . '" O *~

s .i ~./7 o..

8 %. . r. . . .'. >

. 7..'.

ANSt.'ER 2.0: (1 00) 1 No (0,5)

T c+.e

5. t's '~ 3 C Ste-t/9."- 9 ite' to the OESET t c s i t i o r- (A:. ;be wey

+Q

- .a u, . p ' :, e a \. c. n. > .:v s 0, _ : : :..s e :

i' T M C

E)G _/D (t

'3 S ) r ' 0.'s 0+ E7 ! C p:g p g o 7

r. ,

(1 ops 3

o._: c. e 5-c-_N r :-

r_ T. g *, ^cyT.

-. '..'r.'.. l.' II . P. h. m. . +. r e. 3,^-."J1. , .7. ;. _ - :%.777 --

r g . t

ocCq i ,i o ($

. s o_ r_ ' . .n. n.

ANSLES 2,08 f.1.00) c.

e.

s c_ c-.c. c. c_ n c e_

T. I '. '. .' "s*N" o

< .' . V I T ,. c'

- .w. :. ,3... e 9. 9 . ,._ a. ..

s r .,...

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o w c, y. .. c..* : n r , .i: c y o) .

-... .n. o.

7 -

A N S '4 E ' 2.09 ti,00)

1) 'he ~It v i l id? v *, o tr2rs"er to the m a n '.t a l

e v e r s e rio ri el (0,5) mwd ca.w

2) The brl'. elve will close (0 35) when the in-shiel: l i'n i t switc- i s closed '.0.15). (0.5) c.;cc:.c_hir_r m_ _, _

BENP: 'I? L/P (* 23)

f

3. IN9 UMENTS AND CONTROL 9 oAGE 29

_ _ C:

ANSWERS -- 9ROWNS FEPPV '

- 213 -96/06/16-9ROCKMAN. ': .

ANSWER ?.~0 (1.00)

The s: Isncid is ener;;;ed (9.li - It will not light o n h i g:-

pressure actuition (0.5: 's. ee the solencic :s still deene Iiredi (: .01 REFERENCE OGNS: OP-E22-2-501, pp 7. 2 - 10 BFNP' M S '_ / F (t 3); ADS L/0 (f c35 .

L.O. C ANSWER 3..; (2 0C

1) Avtc Initiatio; Cir n. w;11 not operrte.

2) 'arbine Trip 2 012 :; c i d will not operate.

3) *a' Logic Isolatio- will not operate.

C' ' rip Govecr.or' .alve (CCU ^1-10) CO (if RCIC operating). (0.5 eachi RE ERENCE 9FNP: PCIC L/c (%40)r L.O. I 2 O

. \

s ..

f

.I . o D n. f.'. T. 3 :- .1 aR t o - A1 n q a.4 4. tr A C. k!. n..D.M.a. . r V T..Q. Fa-.

. . . . C N r V. ANr

'. a,.

- , { '.2. 0, 2 p, r, _ n. _ . ., .r. c_ 4. ' ".,0 N T R. O .

w ewe s - :cewss cERs< .. :?.3 -96/06/*;-3ROCMMAN7

. v.

ANSWE0 0 . 0 :. I: .50'

3. S E 2?E mers ,5 s you are tc .pe an 2c+1on b e t'o r e a cond . y.

s ne- / 's 2 is nc spec:':: ncrcin to ellow before ycvi rot:on) (0.5):

FE: . ecans ' Mat you are ., u3it until ,he described condit.ons exist r d them yee can .- @. e the "equired ection (0,5). '; 0)

3. Yet ae w ; di.rected -

-es e snet action et some otbe" icestion w . 5 ,. . . . .

.. r. , T_ ' c- '., . t g . t.. s REFi:INCE c.: r N, o *.

. enT_.

-u. e. e . . , ,<..r t, n.

AN5WE- C.02 '

00)

(ADS :s d:sab.ed as '.cn3 22 3 Reectoa Sh' .down is not assured, or may be c o r . r.s ent upon S Ci tc prevent the irjection o# ECCS sierge v o '_ v m e s of r e l a t i v e :. / cold wata') w h l i, may result in 2 reacter power excursior. leading to rubrtant:El core damage. (1.0)

REFERENCE 9'4 R O G U s e s Guider EDI RC/'_, p3 DCND* T. _O_ T ' ./.., - F. r.

m

-it;cyr2 . n, .3 ...c03, a

.y

..: .;. s. .=. ,, +c,.;. :n

. .m. <

< <>' . = r r.

. t.o.='.

e,

. , : _ :2. e. e., . , . c.

. . ( n. . u .ee3 n e.a o , (0.o . 3 r, . r; 3

7. .

n..,<w o m,c...

2 c.o..,es. .

_,cea g i n. . e..e. s. ( n. , e.

a .

4) ?" S - a c: required and Power 3%- or indetermine51e (0.5)

5) " S I ') Isciation Requiret (0.5)

R. c r. e e. r_ . :-

9W000 EDI Users Guide D.FNP'. C

. - 0 7. '7..

C_ a_ e. . . .n.

. - ' . *. :. C0.7 i -f o. , e.n.

. m e

+

.v 9

b s,

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e - N O R M A '. , A c. m.. ?

n* '

r. *. C_

c., r_ $ r A N. O_

x* c., r_ " , *_

'50I0 LOGICAL CONTROL c y e. g e_ ; c.

-- o.r.n_ung cepg, v _i , m .m. .

o. ;. r.g ./ 4_ /,- q. o. 0 C M M. A N s t's .

tANSWEF a.04 (~.00' 2 eat emov2' ' rom the reac+,cv sv"#icie-: tc restore and a i n t a i r.

the peak fuel clad t ec:p ?r t tur e (PCT) LTE 2200 deg r. (Hee vp .:

311 owed al lom3 as 2C7 will aw5 era e x : s 9.: 2200 deg ). (1.0)

,3 e

_ e. r_ p .e- w

. r_ e_

SW?CG EDI Lsers Guide

? NP: EDI L/P. p 5t .0 D AMSWER a.05 (1 50)

3. All applicable steps n. v ; - re completed =nd s_sned off in each sectic, pr:cr to proceed:n; ic the next section (0.5)

c n c o +' the e c *. i c 5 cutlir,ed in each c" the proced'.'ra s7etions era equ: red to be pe-+v m9d in sequence. (0.5)

5. Non-applicable portions see M07 SoECEDED by an (R). (0.25)

They must be init elec by the SE. (0.25)

- OR -

oisce 'N/a* in the ca:cedene Step (0.25)

' eve the entry init_cled _y , the SE. -(0.25) o c_ e e_ v e. s; r. e_

e yo. . en_. '00 '_. .-

.LNSWE? 2.06 f.1.50)

1) An automatic initiatier. signel fails te stret all trains.

2) When operating the WPCI turbine.

3) When venting Primary Containment.

4) When purging Primary Containment. (3 9 0.5 each) r

e

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(***** CATEGORY 05 CONTINUED ON NEXT PAGE **.***)

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(***u CATEG00Y 05 CONTINUED ON NEXT PACE *****)

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(***** CATEGORY 05 CONTIN 1JED ON NEXT oACE *****)

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The elent is ooerattu. n '. ~' 0 ". ower- :. '?-elenent contro1r when 6 s t 8

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(***** END Oc CATEG00Y 06 *****)

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GUESTION 7.07 (1.50)

EXC'._CING TESTING, .I3T the three '. 3 ) conditions which require e M A N '.:A '. STARTUD of the Standby Gas Treatment Syste- (SGTS),

as er O!-65, ' Standby Gas Treatment.'

(***** CATEGORY 07 CONTINUED ON NEXT PAGE *****)

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e:ch of the "o'.'.ouing cor ectly describes the 79 definition c" er ' Instrument Check.'

.s . 'he adjustment of in instrument signal output so that it correspondt. within acceptable rense and securacy, to

e.ncun valve o' the parameter uSich the instrument ':onitors.

w,

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c. : ... u '. a t a. r.' s i. g n. .. '. _n. *., s7 '., 5, a i n 'r ', *.o. m e n +., ' e.

rimary serior to veri #y the proper :.n s t r u m e n t channel resnc^se, r clarm, and/or in:tistin action.

c. The qualitat:ve determ: nation of secaptf.'le operibility by observation of instrument behavior durins operztion, including, where possibler comparisor of the i n s *, r u n e r t with other inderendent e :nttruments measva: n .- - the same variable.

d. A test of 311 relays and contacts o# 3 logic circuit to insure all ecmponents and instruments are operable per the design intent,

(***** CATECORY 08 CONTINUED ON NEXT cACE *****)

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CONC"?'d!NG *n e p a s L ',:. a n o a '. o c V. e d ulve.

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y obcerving the sten sos: icn; confirn locking device intes-

:. , y and perper instil'rtion.

(***** CATEGORY 08 CONTINUED ON NEXT PAGE *****)

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A "une b'.aus #or an J<M0wN eason. I+ supplies power to 3 place :"

equipment whic- is NG' REGUIRED for continued *c,lant nporation

'3 ' S '~ I *he actions whira c, s':>;; ': ract te b e- '

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e 21."I t5e ,"cvisions "ar per'crning shott-ter't e ir e a 3 e n c y 7: a i n -

tene.ce i f the werkers are not author:. ed to hold e clearance.

Specifically addaess to ihom the clearance .s iasued and what "Remarus' are required on the clearance.

. :.i r. c r. . n_ N n . n. o. e.. . cac., 3, .

Stancsrd oractice 3.117 '

Second-Person Veri #icaticr', provides guidance

ca ::Y R A 9 91N G the second-oerson ver:Fication r e e.. : r e t bv an instructicn. . <

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c. IST whc u;st be not1 #ied of this, and 9 Y 'P E N this noti # c a t :.o n n n '. be nede. (0.5'

(***** CATEGORY 08 CONTINUED ON MEXT PAGE *****)

g, enwT.urgrosTTyc- : 9.0 C C. ; r-,c , r.g

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the r e l e s :. e o' ni e c ' i s u:steE thecus" the nt:n steck

n. '. .:.. ,_

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ro l l o w i r..; - I o + -mee. ,Se 'C' '!$ :' 2 .1 valve cid not auto c1cse.

The TI: occhine e e t. . - e ': t r e cog 3;r; te close this v e '. v e dee te 3 4*. 9 r _-. 'n-3' 1. l c ' 1;mit so : tc- Se o r11 val,e is subsequently c1Osed. .

'37A?E ubether 0-t'ery .'a ,'. 2 : n n e n t Inte;et y is : :tist'ied EX P'_ A IN the beris for yeu* deci::ent including uhet additional action (s)

i

s/a e require- ntegrity ic ot being met,

y. n_ T r . t e :

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l n.e -- 3.

e J ,- . > r.) n, i

'he Un . t i nes: tor is shutdewn "o.- naintenance and refueling. The head is removed end some irradisted fuel st 11 *emains in the reactor. There is ro u c r k. In sregress uhich 'as , the , n t. e n t i a l to d r a i r: the vesse'i.

c:vpca :yn 3. het been decleaed INO: (1 dayi EM 0 has been declared IN0o 'l day)

You "eceive direct:or to tee- out ALL ' 0UF of the CS Pumo Suction ,

i,' a l v e s (MOV's) ( ::o t h Loo. s . 2nd 2)

A:'PROSR!iTE TS's ARE ENCLOSED FOR REFERENCE + DIA3RM OF CORE SPRAY SYSTEM STATE whether you, as the SE. would allow this action to :cmmence.

Include in you response any sdditions! requirements which wculd have to be met, and de, ermine whether these requirements can or can not be met i r: accordance with the Browns Ferry Tech Specs.

(***** END OF CATEGORY 08 <****)

(************* END Or EXAMINATION ***************)

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5. OF NUCLEA; 00WE0 o' ANT OPE?ATION, TLUIOS. AND OAGE 20

_________________'_______m___________________________

____'uEORY

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ANSWER 5 02 (2.00

3. The assemoly power A;c', would cav se ne onset cf transition bellinj st some point in th= assembly. ( 1. G .)

5. 4 ns e_ e. r_.._ g e--p e r Gener51 Ele:, ;c deat Trans'er and Fivid 210u. C '.ia p t e r c m

a e y. . .. Tpnpe_m.'_ON.

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By observing the neutror le-e. While moving the nuclear inst umentation. A 2:3nt'icantly 4IGHER (apper ic.ately 300 timet) : cunt rete would be seen for the UNUDIDED areas of the cors as opposed to the VOISED. (1 0) cr_ err.eNCe General Electa ic Ueat Transfer and Fluid Flow, Chapter o General Electric Reretoa Theory, Chapter 4 .

EIu: L-RG-540 (d.3) 'MCO)

'?CND: HTFF. Chaptee c' Rs Theory, Chrpte- 4. L.O.'s 3.3 8 3.6 ANSWER 5 05 (1.00$

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'* IO,5)

Co9 = ( C :':. I P ) '

( fi F '_ C P R ) = 271) / '0.317) ,

= 1.536 S.

que

= oc..go E'. + n. /1 . b, ( o, . *.: )

"'. C 7 C '",s'C. N { C-3ereral Electaic, Heat T e e n 's f e " and ClO'.d CloW, C h a .o t e r 9 "CND.

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c' Deseto* Scr ar -tine Trip) 53

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b. G T O 'J ". I IT,C'I'.ich . ( ' O 'W _

D P e C 51'* ? 1 *- RU t "oca) (0.5)

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ANSWEcc -- 9ROWNE 77 .- 2?'3 R6'04/16-9ROCM W - ' ' . -

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e ., : : .: - '.C : +he Botor. Tant. 'ce* the s o, s t e - : '

r , , o..

c~ .c. 4

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s. . vee

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. C, ,v-. C s.e s . ,c n. e. . s

' '-' s - i.'/> res. ;- ?.C to the ?o ' c - ' e n y. (per tS+ r/ stem e/1)

+ n.... i . . c .f . e ,. r- . m v e.

ea n4 :. : . e n. . ,. 3 r-.,,.,,.,a.

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of

b a. . c. 3r . . L. v. c '. ', = 3 2 c e : g e. n. ~ r.

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8. . , , . .

y...

r., ( c.,. --. -c.

2.-o;4 A EC will coeaa.e *ith their Min:.nv' Olow Valves closed . (0.5)

.# g r. i.

r. t-ywe -

r= r (a.oes V aJI C' U ffip ? W13'. Ci'.'itatt (OV"? C m a y r u h 0 V t '- (0.5) g e e. r. g e.y r c.

9 c n =. c3 . jo <g : c '. .

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n t. .,. n. e. ,

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a ,

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. , ea. 95) _ .p. , o . .

2.

coenin.2 sicne' -

.s s e r. t to ^ . : n i e - t t i o r-v e l *. e s (0.125), but t5ev will n G T, 0,". 9 P ' O 12 $ .I (dVe "C . 59 "* e d Or C Q 1 ": 01 d 9 n C e I " O *. SS 9EMSC). (0,5)

C' 5- ecircule.ic- . r- di: herge "alvet e;o:e when reactor

-e

e. e. i.t p c.3 #. p c_ +. o_ r.. c.

. .

e_ . 7_ 7. O. ,S e; e.

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_ _ t .

" r E* s O n t 4- i9.'!' ' b' i U V'.

e C2059 idUO tC tI 9 need for CC;"Oidence E p . % se. 'D [ E' \

. .) I_ M ( . k 9. "_ I. . f. 0 ..

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^

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D..C N D *. T,.1.? O. '_ ./ C /.t 44), I

_ . .J . r a; ('--C; $- ,/ O (t 4. t." ) , _.0. C.1.,* F. e c..4 , .

_/' (t 7); Tran3.eet Analysis '_/o : 4 55)r '_.0. A ANSWER f.04 (1.50)

. . c. 5 +5e .. .s. o. +. 2. n. + . .- o n. + p n. +. . n. e. . o 3 e m_ .:., +5_ e n. i s .+ '. . a.vo_

-4 3 + e. .c

. 4. y . .s u

10% ear ly (sir.cs the MTU stil'. provides it t cent:nual enalog signal).

(0.9) A *. '. 5 e trip .ooi *- the MTU will :150 give a t o :. 4o :vtout. (0.2) (1.0) 4

. 'v-i On (0.5)

e_ e. r..xn e g.vr e 3 C N C' : A*? _/? i (,n. A; 2CNe ACN P0126

. ~

7 e

i. ELAN ~ SYSTEMS OESIGN, C0".~;C , AND INSTCUPENTA ION : AGE 25 ANS.1:5 - :m o w N S c'C' : - ., 210 -96/06/16-3ROCMMAN. K.

r4 ~: n n- ..r- c c ., . r .-

., -c pc.w e. -.

. c e. r. e ,j e n. r. - .ye-_ 4,2 , ye +.,3., g, goS (0.5)

- , "S .r a .a.

IN00 will fee ^e s;:e *-elav SA M12A. e susins rel ey 5 A-M13 A t t- deenergine.

'" o u e v e - s t r e? ths I? s< 1"_UE 1:n>s are in, r el sys 5 A-K15 A ! C remain enerstret t0,5 IT ANSWER IS e40~ RESERVE ~> *C CHANNEL A3. ualf Scram of :oS (0.5)

The I:: ~ INO: wi!! sive the trip through the autometic channel (A1). ( ". 0 ~-

5. valf Scr:m of RPS Chan^el ?; (0.5) The SRM MI-HI derereires relay 5 "~.3L. This opens contec- 53-K138 (54-K134 it still shorted). deen-eas::ing *al3ys 59-M15A 5 C (58-K159 & 0). (0.5) (1.0) w.-= = =. = c. rew :.

?FNP: 909 /* := 29), Tig'. 3: a & 8, L.O.'s E, 4, K, &L ANSWEo 6.06 ( 1. 0 0 :'

RECERENCE EIP: GoNT. Vol._VII, :hipter 7.2.3-1,2; _-99-722 '

BFNP: RSCS / :' (# 25), L.D. D A N S - E :: 6.07 (1.50) .

The solenoic :s enersized (0.5) - It will not light on high pressuae actuation (0.5) (since .5e solenoid is still deenergized) (1.0) m===o:NCc n- m- .

GGNS: 00-E22-2-501, pp 7, ? - 10 BCNP: M5 L/o r, p); A93 L : (t qs), L.D. C

I

+

.. i

l l

.:3 , : . .s v

. s v -e- T c M S n.- e c. *. ~>' N . rn v.qo'<, .e<n. * -: r -q..%. . . e N, T A T n ....

. - :, ,+ r, c. _4 s y c. .; r..ag. e -- c.. q n. .a y e er cv, r ,#.,.

-- 3 o .e n. t. e.. , j, _ e. : . r. o ~. y , v.

A p e w c :;. - 6.^.C. (*.^o'

.) a. . . . . -

.. >.., e. , _. g . .

c,,,,,.

_.. .a , -.._ nn.. ,,.,e m_ .. : . _. ,

2) Turbine ' y Scien:id will no: cp= ::e.

. .i .. a ._g. e.

r

.3, . - c,. m.,.. ,o. p .o , a. ,

c) Tr:p r, c . .y .

.:- %1ve (rct 7:.-10) c0 (i' F C I:. cpercting). (0.5 each)

, c. c = o c e. _ r.,

e 2 p .. c. C I F.

'/@ ' 4 4 ^, ) - '

.. C . '.

.t.49ugo 6.00 (2.00) 3 Acciden; 2.gnal on Un.. ; 2R 1 & 2 'O. 5)- conev'ren* u-- s Loss o' 0+ft:te ;'ouer (0,5) (1.0)

. e o,,y. . . . . r., c. o . w.- ,.,.,c.

_ n. <n.

<- e3

- , 9 . e., )

~

. 2 .tt o .e t i c - Ut. i r. : i c t i n g c o n e'i t : :~ :.e" (0.25)

Manual - to aeconds 0.25) (0,5) gere.nc e r.

sso: eut '_ f o (g ac), '_ 0 , g

~ ~

ANSWER 6 10 (1.00)

'41 1 '. 'm: ease and Str.,i' ire at a ',i3ber level. (0.5' As upc1 1 t .i e c t t. the - el will increase which will :r:' for CW Clow tc dec~et-e. Stabilt:3 *, . r- will occur 'D e r the SC/Fr ?r y ic :ounter-5 .-iced by the leve'. e or. (0,5) (1.0)

ICE 7ENCE

?7NP; '_ P t 12 , p 23: TRANSIINT $20; 01-57, p 53: 90 85/01/02

r. w. C S i / o.

- - (t .o.)

EIM L-70-726

??ED: RTN 026; HD 17-2/3-B. See::co 3.2 d

. ~

~. con _CeDiJe.re

- -- . e ae

- u n p -u, . A i-. . .u. m ' _.

, r- g r : e_ w* v n'ND

- a . ' i"> r

- ^- 7,

?aA .q '_ o_ _ w--

r. " T c A L r 0 N. T R O'-

g y e .; e_ r. g_ - g e_n g :; >. ; c.

ec_o;v _. n_sp. _ o 6./ 0 6 / '. 6 - M.0. "'f.* : N . 's' .

ANSWER 7 . 0 ". .504

3. ?ErC;I tesni t .u + . ee to ta.e v - :ction be r cre : condition i -e. (there :s ne spe: ';: me":in _

to c11ov be' ore your action' (0.5)'

PIs teans

hat e-e *o 'n

. m 11 the described conditions enist and t5 'cu ren tet s 'N+ "equired action (0.5). (1.0)

b. Y o '.- tre :et:e di"+.;,e1 to t a ). e t a - 1ction t. a t some ther location w , +. s. ,

. .. .he _e n- v>< .-s. (e.re s s t e_ 7 C

' o cwy.pse_

- .T E.cND: EDI '- l e t i o ^ c.0 ANSWER r.02 '2."01 95 deE r (0.25)

1) Supp*estion Pool-Tempert*..re (0.25)

2) Orywell 'e-ee ature 0.25) - 160 dec (0.25)

3) Orywell tressurm (0.25) > 2.45 * (0.25)

4) Suppres; ion 000,1 e>el (0.25) -1 *

(0.25)

5) Suoo.vession Pool

. evel (0.25) < -6.25 (0.25) (0.5 each) .

?ICERENCE .

BWROG E0! '_'sers Guide BCNP: ICI-2 Section :.i' EDI L/Pr L.C. ?

ANSWER ?.02 ( .50)

Suppression ecol :> essure (0.5)

REFERENCE BWROG E0! 'Jser s Guide . Caution 4 8 DrNP: EDI RC/L, Sectic~ RC/L-27 EDI L/t, L.D.'s r &G l

i I

l

)

J t

e p 0 ", C. 9 0 R C S. - N 0 0.". A L , 4w.: v.m_ .a r, e : . m. : m*r, r,. '"..

______________________-_N"y________ . .

1010 LOGICAL CC4 . 0L

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c< 4. . ;. n_,.

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. = - - , <perr ,,c ,nct rec : c ,., g ". .' ' ..

,+m7,h

$ [$ ' ~ .$.n.3 3 m, g L.a . . ; ' '

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. . n. 3, 4

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e. , . _

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c.N3uc; - os _.

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: r. r.s .n r_

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^ - -

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e. -_n T _ . . .

c..>c + . n r..:-

. . . . 5 .

. t.4.:

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T_

gyewe. 7.04 '^

3. ' '3 C - Petween the '.' 1/ 2 ard U2 Control Rooms elev. 613') (0.5)

OSC - Intr ument Shop - ~1o'*rical Sho, + Maintenance S 5 r. . ,

(0.5)

b. . *1 '."' . ; ,a. .ei,+

r., * ., c.2-4.+'.. .- 3 4. . .O n

' a . r. )

4 C' [1 [ p p n nwese.1t.4p - r.4I G. 4er

- .. e a. .; ( 4, we

. .g c, 4y D. Y.a .p (g r*l . -,4, .

.e .

nw P #. 4. p.s b e4. w. 1. g

.r

, e .i nw en a a f ,*

w

.* 1" C F 4f .i * ( t)

. , .

h, a %

C' J -)

3 ,s 5 9 9. - . .~a a - .,

C* .C. C T Q. : f. <' D.-T

.e.s .. + .. ...g .4 "

2 '. .%

1

. OoCCE000ES - NCOMAL. t'<0tM4L, EME'5 ENC # ANO : AGE 29

. ' v, _ D. r aT -c A i- r. n. m : n. .

w.,, g e_ : .:

. o. --g .n y y c. .-.--

. . , _ y. _ q t. .f n 6,' '. .5

. t. o. " r. '-f ..* A N r

v. .

pneu=.p. .

.~., t. . . .e-

.)

- q ,- . . . .< 0 3. 3 2. ,.....

..,.m,,.

.g e. ... ., ,3 g. 3. +- , ,,,... ., 3 .2 n ..s ,

2 '- W,' e- cpersting the ve:I - - b; ie .

3) When venting ' ' m .s c y Centai e-..

~ -

4) Wher : ~;ir.s 5-imer, tinment- (? ? 0.5 each)

E ERENCE

.. c. e. e ..

nr te, um e

m n c+,_ioi .

++

-...e_,., G_I e

. .z o , ._ 0 . :. s ANSWER 7.0E (1.00

'With the len3 start T ume aequired c r the system). this enseva; thr; the stendb;. -ertabine? 15 usamet up- thould it be mee:sd expeditiov2_. . (1.0) nn e_ c.- e- R e h,C .e BCNP: CI-66, Section 2 ~.c.21; OI-66 L/;, L.O. E ANSWEF ' 0o (1.00)

The Recirculation *v'? Potor H e a t e r-E will not operate unless the

~ield Breaker : : r. the (INSESTED or) TEST position. . (1.0) o c- . c. q c_ .n r. e.

3FNP GI-sS,Section I!! . A . 7 t 01-68 L'5- _,0. C ANSWEF, 7.10 (1.00)

1) Evacuate the Refuel 2cne

2) Place the other loop o# Shutdown Cooline in tervice .

immediately, (without flushing). '.0.5 each)

e

. ~

G 7 ::m .. r. e_ .,n. .-p e e. - n r_ ; ,a* L r s c: y-1 co ,n p.i .. .

s e e c., r_ u c Y . ann.

' .%r c o0 s

~~~~35656E66555[~56sTkUE~~~~~~~~~~~~~~~~~~~~~~~~

ANSWECT -- 3 0WNS #E2 " .

283 -96/06/16-9ROCMr*AN- K.

. c : : :. : s ~. _

. e ., := -

. ns n. T. .' as e r . ^. . ; c. c. e. . .a r.

. .T xT T_ . e .:

- r_.

-- ' 7 '. 0 0 '.. ' ' ,' O >

-.0. '.

mpm,

- e wee - , _ ._ (,.o.r)

. a.

1) 7 0r w o r k. w Sn 3 7.ctential whole '.'ody radiation enpos re greater the- EO PPen :n any r e s v '_ I ' L"a n i'. day.

? :or work in,cisino s whcle bor/- dose rat,es 1rsater than l')0 .

0 e m'h r .

(High Radit; cr Ares)

3) or u c r '< :n an ares .2ving airborne activity greater than MPC fee e c ' ', c n week. (Ai*bc' : 'ctivity Area) 2: Caa w e r '< :. n any cont ani is . ::: 3rea.

5) Whe - r_ . ;:. ion or conia.1 :.stion hazards tre unknown er for other ressenc- - ;. c 5 MP deen .s::. .s r c.e r i s t e .

a c iog r aphi c o e et:crs conducted on site. (5 ? 0.25 each) c.ss e e. c-.s

c. e_ .e< C -e c r. . ; e .. ;Cv.._o..

. . %..*.on iJI.A,

_, sr. T. ./o, ,

. . n. . n.

ANSWER 7.12 (1.00)

. r. r.

o sh

5. Governar centrcl funct: ens are better :0.5 each)

EFE::E NCE c.: : i.;. c.

. . n.

m _ _ . : , 2_ _ c +. .e. r. . r. n_ _ . n. 4. : O. .v-_- , i << e ,

. .n.

s C ANSWER 7.13 (1.00)

1) Open e.nife blade switches (CS-17 2r ? ?)

2) Tse - each with e SE Hold Ts.a (0.5 each)

. 6

.e e

m

I

,',es w

,"M -S.

g .4 . .. . fp a

[..4 ,,. , q , )i f. Y.

A f-t ,

ap p {

.-4,.. ., .

4

- -Y p

m

,y .

4 p

. . . . y, f.

O eee emenemi.ese e ee. aimse m es. age aus e menum ANSWERS - iR G u '1s C E : : _ 2&3 -'i c 's/*6-SROC'eAN. -'

s

% -c r .e_ t .. , ; . r. -

.. c :. . - ,'.-r 1c 7 e. n_ _,-. .+ . . - *vT.<,,_

,c e

r l

l l

I l

l t

e

2

d. ,4 P,. . "_. '

1_ T, O. t. ' I t) C_.

- C Q '." ' T_ ..S I ? 7_ 0, , P_ Qi N N. A T ---

T T ' ra !. . .i. hj Q i ? j.4 A iT -" .*. T T_ ? ,, C

*, f , c 70 16'yeqc . .s O p n ?,. . ' O_

P e_ t p y -

1. y 7 ,?.. q_

_ Q /.s. /< e A 6,/1.t, T; q.1. t' t.( u .4 y ,

. .e s .

f. Ll C.' '2 C ,"'

C," ( '., . O O. e 2

_ : r_ e, r_ .a4 r. e_ .

_ A q. .. iJ 1 C. 7 %; C-

I_; 1_ *q, _

g- * *

. ,. ,C,

s _ . - qs ,. , r. r

/ C. ,

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m N r6 , , , , -,

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- p _

n_ '., rw - .-

-a. n +v _e ...e. c. e. ,

, o. n. .,. # ,.v..,, _-.. a.., 3 , A o . p .1_ p. . e_ w. _ .

-_ , ; ,2.. :. .... r c_ .%. . qu,.,,g. . . .

c_ _ . - . .c,

. cm C 1) E '-

r. -. n_. c , i C_ . i no.- T r .

c * '

_ n_ e_ '. e_ E. t a_ n',:> a.. r. a h_ _' a_

, . . .._ : o i t r o ,. ; c -s t,a e 'n a inten a n c e

> .3aana_1/

a Inc ,see ad.iacent e to

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namer ourpose- time, and date.(0.5) n,._ :. c ~nc,

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At.5cEr ?.09 ( 1. 5 0

'MECGENCY CT'O: !CNS ARE A35'_MED

t. Shift Ers. eer

5. :1;n, Energency 'c-ttt ons (0.25), or "or Perscr.ne; ?afety (0.25) .

c, Frought to the ette icn o# the PORC. r- e _eter than the next

.: : '<. day. 0.5 each)

I: N O N -E M E R G E N C '- CONDITIONS ARE ASSUMED

a. 5090 (0.25) ,3 n d tre :lant Manager (0.25)

b. 9:e.n ':cen+ Radiation Ex:oc'; s will occur.

c, o0RC anc oM ?.or to ocevrance. (0.5 each)

RE~ERENCE

=. c y ; . c : n. . . .....

,. . ,-.. e: a. , 2- .. , . 4_ .4 ,f e , i. . n. . .

ANSWER c.10 (1.00)

) Establish an app *opriate C .r e Jatch. (0.5)

2) Implement olant proceduret for the renovel of fire protection equipment # rom service. (PM, er designee ?pproval; Posting c#

nanua2 opersting instructions near the menval actuation station - .

or stationing of a properly instructed fire watch at 'he station) (0.5)

RECERENCE

~, r

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2 , ,n ... c- . y . s+s a .-

,,. es r, 4 a

.s. c ,/ .* ,e, r

.0. O.

ANSWEP 8.11 (1.50)

1) 9 eta, Gamma Monitor (Noble Gas)

2) Iodine Sampler

3) 0 3-ticulate Sampler (0.5 each)

. O J

S. ADMINIS'?A"IVE PROCEOUTEE, CONDITIONS. AND LIMITATIONS :' A G E 36 ANSWE?3 -- ? t0WNS CER o 1, 2E3 - S 6 / 0 6 /16 - ? ? C K M A N . M.

RECERENCE

. c u.

. .c .

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o. . e. : 7 . ,.

ANSWER S.12 (1.00' Pri.ary C tainment I^t+;.-' is no 're rj :e t . f0.5- "e .

fall valve must -c :esct seted in _ - : :: 15- t a d o. t t i t : c - ': n c- e the auto closing

lon is n c +, c,r.e sting orope*:y. (0,5) (1,0) a::::=ne:

c y .: -

. o. r. T - o - : 4 ~. 7 )-> . .- - .- rso

. n +. ,. .a n i..^-.C'r 'S.i'O r -' O. :: .

A N 4. W C R 8.'.~. (. ' . 0 0 The 3 *. vi'.y shou'.d ret ce allowe: to commence (0,5)

U1 75 *erc2 c; leest one CE a

cop with one oumo and the associated EDO :: be operable, This re< snent can ,ct se met w i +. h sli CS .

Suc t : c,' t ' u : - _-losed: the*e'c e. the Collowing el*= nTtive cr:ter:e mus. ~e met * (0,5)

N= cue: Gates nust be 0 en -

71 :. E should be (or can be) sceomplished (0.25)

The rue; oce: level must be -

This causer no difficulty above

he ' o Lev el Setpoin*

. (0.25)

Ome '4RSW Pump (D; c" 221 end assoc- _

D1 ' 02 redundancy NOT MET as isted valves a u .t .o l Y ne i -

.e Standby r. e r the de# n: tion of LCO Coolen. uzt be operable - OR -

02 :. s inoperable since LCO definitior (12' is NOT APPLIC-AftE 'ua i n- refuelin:m (0.5)

RcrepENr.e.

9FNP' U1 TSr Sections 1.9 3.5.Ar 3.5.? ! 3.5.C; T S '_ .c' *

L.O. B

r, e

TES.T C90SS REFERENCE LAGE 1 FUES' ION VALUE REFERENCE 05.01 1.50 e'E 9000075 c 05.02 2.00 .E 9 0 0 0 0 7 6 0 05.03 2.00 EB0000761 05.04 1.00 .EB0000762 05.05 1.00 KEB0000766 05.01 1.00 E ? 0 0 ' ^ 7 ~

05.07 1.50 -IB0000770 05.08 1 50 KE900007"a 05.0c 2.00 ME??000776 5.10 3.00 'E90000777

. o . esn.

96.01 1.50 ME90000~~0

?i.02 2.25 EB00007?0

.u n, e og vet.nnnq n-5 b5 5.50 'libhbb-b8 06.05 2.00 MEB000078o 06.06 . 0^ '< E B 00 00791 06.07 1.50 MEB00007os 06.02 2.00 E B 00 00 9 2 9 06.0c 2.00 *:E?0000834 06.10 1.00 KEB0000835 16.75 07.01 1.50 KEB0000797 .

07.02 2.50 KEB0000E00 07.03 . 50 KE90000801 07.04 1.00 ME90000302 07.05 1.00 :E30000803 07.06 2.00 v.E90000812 07.07 '

. 5C KEB0000813 07.00 1.00 KE90000814 07.09 1.00 KE90000815 07.10 1.00 KEB0000816 07.11 1.25 KEB0000826 07.12 1.00 KEB0000832

. 07.13 1.00 KEB0000833 16.25 08.01 1.00 KEB0000001 08.02 1.00 KEB0000805 08.03 1.50 KEB0000806 08.04 1.50 KEB0000810 08.05 1.00 KE90000817 08.06 1.50 KEB0000818 08.07 1.00 KEB000C819 08.08 1.00 KEB0000820 e - - - -- - - ~,--e ,

-~

r 1

- o e.

9 c

TEST ER053 REFERENCE oAGE 2 GUESTION VALUE REFERENCE 08.09 1.50 K 20000821 08.10 1.00 KE90000822 08.1- 1.50 KEE0000824 08.12 1.00 KE90000830 08.13 2.00 KEB0000831 16.50

$6.00 4

E9 e # ENCLOSURE 3 TENNESSEE VALLEY AUTHORITY Browns Ferry Nuclear Plant P.O. Box 2000 Decatur, Alabama 35602 Mr. John Nunro, Chief Operator Licensing Section 3 U.S. Nuclear Regulatory Commissisn, Region II 101 Marietta Street, NW Atlanta, Georgia 30323

Dear Mr. Nunro:

In accordance with the provisions of NUREG-1021, " Operator Licensing Examiner Standards," Standard ES-201, Section H.1, enclosed are comments by the Browns Ferry Operator Training Section staff concerning the written examinations administered at Browns Ferry Nuclear Plant June 16, 1986.

The enclosed comments are offered with the intent of providing assistance to the NRC examiners in establishing the appropriateness of the examination questions; e.g. concerning those questions which require rote memorization without reference material, whether the question was appropriate given the level of technical expertise required, and whether the learning objectives established for the accelerated retraining program were exceeded. Also, the comments serve to clarify and expand the answers on the NRC answer key as supported by TVA reference material.

With respect to any questions deleted, NRC is requested to consider allowing the examinee full credit for these questions in light of the time, effort and concentration required of the examinee.

These comments are respectfully submitted, and it is hoped the enclosed comments and proposed resolutions afford the examinees every opportunity to sucessfully pass the examination based upon the knowledges and skills required j to safely operate the facility.

Very truly yours, TENNESSEE VALLEY AUTHORITY 0E L p A. R. Champion, Acting Supervisor BFN Operator Training Group I

An Equal Opportunity Employer

2 John Munro Enclosures cc (Enclosures):

K. R. Brockman Operator Licensing Branch NRC Region II 101 Marietta St.

Atlanta, GA 30323 Gary Sly ~

Pacific Northwest Laboratory Bate 11e Blvd.

Richland, Wash. 99352 l

l l

RO Requal Section 1 1.04 -

Problem / Comment:

The reactor theory textbook does not even discuss or explain why the threshold value decreases, just states it does. It does discuss the factors which effect Pellet Clad Interaction.

Resolution:

This question should be deleted.

Reference:

NONE 1.10 -

Problem / Comment:

The question requires calculation of the CPR (i.e. critical power / bundle power) for bundle 41-34. The CPR is already given for the

~._

bundle and to get it from the P-1, no calculation is necessary. T-Information is not available to " calculate" the CPR (i.e. critical power / bundle power) for a bundle from a P-1 printout. The computer does this automatically. The CPR may be read directly.

Resolution:

Full credit should be given for the answer 1.156.

1.10b. Problem / Resolution:

The correct answer is 29.42 BTU /lba, NOT *F

-Comment:

The amount of subcooling in 0F is not available from the information provided on the P-1.

Reference:

HT&FF, Chapter 9 Page 1 6-22-86

/

R0 Requal Section 2 2.02 Problem:

The answer key is not correct.

Comment:

(1) This SI requires the common suction valve (63-500) be closed.

(2) A drawing should have been supplied.

Resolution:

Correct answer should be:

a. Take the local control switch to normal or stop the pump.

Re-align the system per the checklist. Take che C/R control switch to the 'A' position.

b. Same as 'a' above except go to the 'B' position with C/R control switch

Reference:

OPL171.039 Fig 1; SI 4.4 Al 2.03 Problem:

The answer key does not include all possible answers.

Comment / Resolution:

Another possible answer for full credit would be: The system will respond normally and inject to the vessel.

OI 73, p3, states that the possibility of a turbine trip or isolation may occur, but this may not happen.

Reference:

OI-73 page 3 Page 2 6-22-86

RO Requal Section 2 l

i 2.08 Problem /Corment: -

l This question is not based on an learning objective and is something that we would not expect a person to know from memory. There is too much of a possibility if he/she relied on memory they would miss something. We would expect them to use the procedure and NRC would expect them to pull the procedure if this were to occur. This question also references 83-84 Requalification lesson plans which were not used for this class.

Resolution:

The question should be deleted.

Reference:

OI-57 2.09 Problem:

The answer key is not correct.

Comment:

The answer to this question assumes partial are admission to the '

turbine. BFN has full are admission.

Resolution:

The answer should be: the #1. 2, and 4 TCY will pick up the load for the #3 TCV. They will open further to allow the appropriate steam flow to maintain steam throttle pressure at proper level. There will be no protective trips within RPS since the TCV scrams is based on hydraulic pressure decrease which does not occur in this instance.

Reference:

OPL171.015 Page 3 6-22-86 l

l l

R0 Requal Section 2 2.10 Problem / Comment: -

The answer key is not correct. The Unit 1 or 2 is incorrect.

Resolution:

part 'a' answer should be:

Loss of offsite power with U1 and U2 in accident mode or Loss of offsite power with an accident signal present on the adjacent unit will trip and lockout the non-preferred pumps.

Reference:

730E920; OPL 171.044, page 22 k

Page 4 6-22-86

R0 Requal Section 3 3.01a. Problem / Comment:

The instrument referred to in part a-4 Jet Pump Total Developed Head is used only for initial startup testing and has no operational signifiance. Also, the drawing does not show any of the taps for this instrument and it is not commonly used. An operator should not be required to know this much detail about it, per NUREG 1021 ES 202.B.3.,

paragraph 2 page 2, of 6.

l Resolution: !

This portion of the question should be deleted.

Reference:

BFN OPL171.045 3.0lb. Problem:

The answer key is not correct.

Part 1- The correct answer is:

If Drywell is greater than 2.45 psig and reactor pressure 4

is less than 450 psig, a start signal is sent ot the RHR pumps. Simultaneously, an opening signal is sent to the injection valves. The circuitry requires two reactor pressure inputs, one from the Standby Liquid Control Line and one from another instrument line.

Part 2- The recirculation pump discharge valves close when reactor pressure decreases to 230 psig when a LPCI system initiation signal is present. The pressure inputs to this circuitry are the same as those referred to in part 1.

Comment:

f (1) This question demands far more detailed knowl. edge of circuit operation than anyone should be required to know. Additionally, l

)

the question gives an incorrect valve for drywell pressure.

Unless the applicant assumed drywell pressure to be greater than 2.45 psig, there would be no effet on the RHR system.

(2) This question is outside the criteria of ES-202, page 2 of 6 section 2 (i.e.. Immediate operation action is not required).

f.esolu tion:

Part b of this question should be deleted or credit should be given for answers based on reasonable assumptions.

Reference:

730E920; SI 4.2.B.7 Page 5 6-22-86

l R0 Regual Section 3 3.03 Problem /Comraent:

The aaswer stated on the key for part 'a' is correct only for that partion of the system shown on the provided figures. It does not reflect actual system operation. When the examiner was asked to clarify this matter, he responded only to the individual asking the question. The clarification should have been given to all of the examinees.

Resolution:

The answer below should also be accepted.

'A' RPS will operate and give a half scram through the automatic scram circuit, due to the inoperable IEM. The applicants know that an IRN INOP gives a scram signal in startup.

Part 'b'

- A half scram in RPS Channel B manual circuit would be received. This opens contact SAK-13B which drops out SAK15B&D, not 5AK15A&C. 'Since the drawing only shows A&C either response should be correct.

Reference:

730E915 3.09 Problem:

When a group 2 PCIS signa.1 is received the TIP receives a withdraw signal, which internally shifts the TIP to the manual reverse mode.

Comment:

An operater needs to verify that withdrawal has begun when a group 2 i

PCIS isolation signal is received. Primary Containment integrity should also be verified by the ' ball valve closure'. The actual internal circuitry is beyond the scope required by of ES 202, NUREG I

1021.

Resolution:

Full credit should be given for a response that includes withdrawal of the TIP and closure of the ball valve.

Reference:

l OPL171.023 Page 6 6-22-86

RO Requal Section 3 3.10 Probigm:

Part 'a' of this question does not apply to BFN.

Comment / Resolution:

(a) The ADS system at BFN requires a manual individual control switch operation to open the valves. To open the ADS-assigned MSRV requires:

(1) electe zal power to the solenoid (2) air . essure available (3) ~ 30 psid motive pressure (steam) to overcome spring pressure & move the valve disc off the seat.

Neither the NRC answer key or the question applies to BFN. This part of question should be deleted.

(b) The NRC response is 'B' solenoid is energized. At BFN, high pressure actuation of an MSRV will not energize solenoid; therefore, the red light on panel 9-3 will not illuminate. Also, there is only one solenoid for each SRV so the 'B' solenoid part of answer should be deleted.

Reference:

730E929 Page 7 6-22-86

l RO Requal Section 4 4.01b. Problem: -

The " Flag System" per PORC E0I's was deleted and the new method of carrying out these actions was implemented per E0I-1 section 4.0, paragraph 4.10.

Comment / Resolution:

The NRC should also accept: " action is required and you will be directed to take that action."

Reference:

EDI-1 Section 4.0, paragraph 4.10 h

l l

l Page 8 6-22-86 l

7 -w--

s RO Requal Section 4 i

I 4.02.

i Problem:

The answer key is incorrect.

Comment:

Defeating ADS in the situation mentioned has nothing to do with the answer. The answer actually describes one of the three reasons the operator enters C-5 and why the actions for control of water level are different in C-5 than in RC/L.

Resolution: -

The answer key should be changed to give full credit for the correct answer which should include the following:

" ADS is disabled as long as Rt shutdown is not assured (or may be contingent upon SLC) to prevent injection of ECCS (large volumes of relatively cold water) which may result in a reactor power excursion leading to substantial core damage.

Reference:

E0I LP155.001 (attached) -

Page 9 6-22-86

RO Requal Section 4 4.03 Problem:

The answer key was developed from old material.

Comment:

The new E0I's were sent to the examiners and the answer key should be changed to reflect these new entry conditions.

Resolution:

The answer key should be modified as follows:

(1) Ex water level below +11 inches (low Er water level scram setpoint) either acceptable (2) Ex pressure above 1043 psig (high Rx pressure scram setpoint) either acceptable (3) Drywell pressure above 2.45 psig (high drywell pressure scram setpoint) either acceptable (4) A condition which requires a ree: tor scram, and Rx power above 3% (APRM dcunscale trip) either acceptable or cannot be determined (5) A condition which requires a MSIV isolation

Reference:

EOI-1 l

i i

I l

i I

Page 10 6-22-86

{

R0 Requal Section 4 I

i 4.05b Problem:

1 The question is unclear as to what exactly is required for full credit. l Comment / Resolution:

The question requires the examinee to state the methods he should use to identify and sign-off steps or portions of the procedure which do not apply. The operator identifies the non-applicable step by putting an N/A in the block and the N/A steps are signed off by the SE. It is not clear whether NRC desired the examinee to state how he knows if a step is required or can be marked N/A.

Full credit should be given for following answer:

1. Place N/A in procedure step.

2. SE initials.

Reference:

GOI 100-1

~

u.,

4.06 Problem:

The answer key requires both purging and venting to receive full credit.

Comment / Resolution:

NRC should accept " purging" or " venting" as an answer by itself since these are different operations.

Reference l

OI 76 III.D.II l

l l

l Page 11 6-22-86 i

R0 Requal Section 4 4.07 )

Problem: ;

The answer key required " Inserted" but the question addressed tagging the syJtem out. Thus breaker would be placed in the " Test" position and not left inserted.

Comment / Resolution:

The question asked why the breaker is left in the ' Test' position.

Full credit should be given for: To ensure the motor heaters operate.

Reference:

OI-68,Section III.A.7.

4.09 Problem: -

This question is not an R. O. level knowledge requirement, and falls outside of the " scope of written examination" for Reactor Operators (NUREG-1021).

Resolution: -

The question should be deleted.

Page 12 6-22-86 1

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

SRO Requal Section 5 5.06 Problem / Comment:

The phrase "several hours" is not clear enough to answer the question.

(Several is defined in the dictionary as more than two and fewer than many.) During the first 2-6 hours, rods would have to be withdrawa.

Subsequently, rods would have to be inserted. Both time periods could be considered "several hours".

Resolution:

Answers a or e should be accepted for full credit.

Referene ,:

GE Reactor Theory, Chapter 6 5.08a. Problem / Comment:

The question requires calculation of the CPR (i.e. critical power ratio) for bundle 41-34. Information is not available to " calculate" the CPR for a bundle from a P-1 printout. The computer does this automatically. However, the CPR may be read directly from the printout.

Resolution:

Full credit should be given for the answer 1.156.

5.08b. Problem / Resolution:

The correct answer is 29.42 BTU /lbm, NOT *F Comment:

The amount of subcooling in CF is not available from the information provided on the P-1.

Reference:

HT&FF, Chapter 9 Page 1 6-22-86

SRO Requal Section 5 5.10.b Problem / Comment:

The question asks for the " response of the plant" as reactor pressure passes through point 9. The question should have asked for the

" response of MSIV's" since that is all the answer requires. Many plant responses can be implied from transient graphs.

The transient graphs do not really "show" indications of MSIV isolation. Total staam flow remains high due to the location of the break, and the graphs cannot be used to conclude a Group I isolation was actually achieved.

Resolucion: -

Delete part b of the question.

Reference:

Transient Analysis LP, Transient #21 l

Page 2 6-22-86 l

SRO Requal Section 6 6.01 Problem:

The answer key is not correct.

Comment:

(1) This SI requires the common suction valve (63-500) be closed.

(2) A drawing should have been supplied.

Resolution:

Correct answer should be:

a.

Take the local control switch to normal or stop the pump.

Re-align the system per the checklist. Take the C/R control switch to the 'A' position,

b. Same as 'a' above except go to the 'B' position with C/R control switch

Reference:

OPL171.039 Fig. 1; SI4.4.Al 6.03a. Problem / Comment:

The instrument referred to in part a-4, Jet Pump Total Developed Head is used only for initial startup testing and has no operstional signifiance.

Also, the drawing does not show any of the taps for this instrument and it is not commonly used. An operator should not be required to know this much detail about it.

Resolution:

This portion of the question should be deleted.

Reference:

! BFN OPL171.045 1

Page 3 6-22-86

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4 SRO Requal Section 6 6.03b. Problem: '

The answer key is not correct.

Part 1- The correct answer is:

If Drywell is greater than 2.45 psig and reactor pressure is less than 450 psig, a start signal is sent ot the RHR pumps.

Simultaneously, an opening signal is sent to the injection valves. The circuitry requires two reactor pressure inputs, one from the Standby Liquid Control Line and one from another instrument line.

Part 2-The recirculation pump discharge valves closes when reactor pressure decreases to 230 psig when a LPCI system initiation signal is present. The pressure inputs to this Comment:

circuitry are the same as those referred to in part 1.

(1) This question demands far more detailed knowledge of circuit operation than anyone should be required to know. Additionally, the question gives an incorrect valve for drywell pressure.

Unless the applicant assumed drywell pressure to be greater than 2.45 psig, there would be no effet on the RHR system.

, (2) This question is outside the criteria of ES-202, page 2 of 6, section 2 (i.e., Immediate operation action is not required).

Resolution:

Part b of this question should be deleted.

Reference:

730E920; SI 4.2.B.7 i

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CR0 Requal Section 6 6.05 Problem / Comment:

The answer stated on the key for part 'a' is correct only for that portion of the system shown on the provided figures. It does not reflect actual system operation. When the examiner was asked to clarify this matter, he responded only to the individual asking the question. The clarification should have been given to all of the examinees.

Resolution:

The answer below should also be accepted.

'A' RPS will operate and give a half scram through the automatic scram circuit, due to the inoperable IRM. The applicants know that an IRM INOP gives a scram signal in startup.

Part 'b'

- A half scram in RPS Channel B manual circuit would be received. This opens contact SAK-13B which drops out SAK15B&D, not SAK15A&c. Since the drawing only shows A&C either response should be correct.

Reference:

730E915 6.07 Problem:

Part 'a' of question does not apply to BFN.

Comment / Resolution:

(a) The ADS system at BFN requires a manual individual control switch operation to open the valves. To open the ADS-assigned MSRV requires:

(1) electrical power to the solenoid (2) air pressure available l

(3) - 50 psid motive pressure (steam) to overcome apring pressure & move the valve disc off the seat.

Neither the NRC answer key or the question applies to BFN. This part of question should be deleted.

(b) The NRC response is 'B' solenoid is energized. At BFN high pressure actuation of an MSRV will not energize solenoid; therefore, the red light on panel 9-3 will not illuminate. Also, there is only one solenoid for each SRV so the 'B' solenoid part of answer should be deleted.

Reference:

l 730E929 l

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SRO Requal Section 6 6.09 Problem / Comment:

The answer key is not correct. The Unit 1 o_r 2 is incorrect.

Resolution:

Part 'a' answer should be:

Loss of offsite power with U1 and U2 in accident mode or Loss of offsite power with an accident signal present on the adjacent unit will trip and Icekout the non-preferred pumps.

S';ference:

730E920; OPL 171.044, page 22 i

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SRO REQUAL Section 7 7.01b. Problem:

The " Flag System" per PORC E0I's was deleted and the new method of carrying out these actions was imp'emented per E0I-1 section 4.0, paragraph 4.10.

Comment / Resolution:

NRC should also accept: " action is required and you will be directed to take that action."

Reference:

E0I-1, Section 4.0, paragraph 4.10 7.03a. Problem:

Different terminology can be used to describe the same item.

Comment / Resolution:

NRC should also accept:

(a) " suppression chamber pressure" or " torus air space pressure."

7.03b. Problem:

The previous curve was in error, the answer is wrong. The curve decreases at 4,000 spm which is rated pump flow. Above it the pump is in run-out. The new figure is attached.

Resolution:

Delete question.

Reference:

E0I L.P.

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SRO REQUAL Section 7 7.06a. Problem:

The answer key is wrong.

Comment / Resolution:

The TSC is located between U2 and U3 control rooms (EL 617')

NRC should accept " Shop or Maintenanca area", since this is the normal terminology used in the plant and the BFN-REP. The answer should not be required to be as specific to receive full credit.

Reference:

BFN REP Appendix A, page 88 6nd 90 (attached) 7.07 Problem:

The answer key requires both purging and venting to receive full credit.

Comment / Resolution:

NRC should accept " purging" or " venting" as an answer by itself since these are different operations.

Reference OI 76 III.D.II i

7.08 Problem:

The answer key is very detailed.

Comment / Resolution:

Per OI 66, pl3.. C.7.22 Caution, "to ensure standby recombiner remains warmed". This should be sufficient for full credit

Reference:

OI 66, P13, C.7.22 l

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SRO REQUAL Section 7 7.09 Problem:

The answer key required " Inserted", but the question addressed tagging the system out. Thus breaker would be placed in " Test" position and not left inserted.

Comment / Resolution:

1 The question asked why the breaker is left in the ' Test' position.

Full credit should be given for: "To ensure motor heaters operate".

Reference:

OI-68,Section III.A.7.

7.11 Problem:

The answer key does not have all possible correct answers.

Comment / Resolution:

Part 2 - NRC should accept "High Radiation Area (RCI 9, p2)

Part 3 - NRC should accept Airborne Area (RCI-1, p23)

Part 4 - NRC shou?.d accept "HP discretion"

Reference:

RCI-1 and RCI-9 i

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SRO Requal Section 8 8.03 Problem / comment:

This question is not related to a learning objective. We consider it to be far beyond the scope of required knowledge. The situation described would be handled by r ' erring to the Technical Specifications and appropriate procedures.

Resolution:

The question should be deleted.

8.04b. Problem:

The question does not clearly state what is required for full credit.

Comment / Resolution:

The question requires the examinee to state the methods he should use to identify and sign-off steps or portions of the procedure which do not apply. The operator identifies the non-applicable step by putting

' an N/A in the block and the N/A steps are signed off by the SE. It is not stepclear whetherorNRC is required desired can be the N/A.

marked examinee to state how he knows if a Full credit should be given for following answer:

1. Place N/A in procedure step.

2. SE initials.

Reference:

GOI 100-1 i

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SRO Requal Section 8 8.06 Problem:

)

The question is unclear regarding what is required for credit.

Comment:

The applicant could have answered from the T.S. LCO requirements or from the Bases and could give two different correct answers for the same question.

Resolution

The answer below should also be accepted.

T.S. 3.3A.1 (p 120) - A sufficient number of control rods shall be operable so that the core could be made suberitical in the most

reactive condition during the operating cycle with the strongest control inserted.rod fully withdrawn and all.other operable control rods fully

Reference:

T.S. 3.3A.1 (page 120)

T.S. 3.3/4.1 Bases (page 127) 8.07 Problem:

The answer key needs to be changed to accept other answers for full credit.

Comment / Resolution:

The number 2 part of the answer key should be sufficient for full credit.

To write an 'MR' the operator must check out the equipment, panel, etc. to get the information necessary to complete the MR. Also, do not replace the fuse and write an MR should be acceptable for full credit.

Reference:

S.P. 12.24 and S.P. 7.6 Page 11 6-22-86

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SRO Requal Section 8 8.09 Problem: -

The answer key makes the assumption the applicant will assume

" Emergency" conditions in answering the question. If applicant assumes "Non-Emergency" conditions, his answer could be different.

i Comment / Resolution:

Part 'a' - The answer stated on the key is correct if it is an emergency situation; if non-emergency, Plant Operations Review Committee must give approval along with the plant manager (student may have assumed non-emergency). (Ref BF 3.11 p. 5)

Part 'b' - For emergency conditions, as defined in BF 1.3, the answer stated on the key is correct. For non-emergency situations, "The only exception for second-person verification will be in situations where there would be significant exposure to radiation.

Part 'c' to this question may have indirectly led the student to think the whole question was based on an emergency situation. If a student assumed a non-emergency situation the answer to part "c" would be very similar to part 'a' comment. Based on the point value full credit should be given if student based his answer on a non-emergency l situation.

i . ',

Reference:

l t BF 3.11, p.5 and BF 1.3, p.9 i

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SRO Regual Section 8 8.10 Problem / Comment:

The question and answer is word-for-word out of SP 14.15. However, an important sentence is missing; " Fire protection systems may be removed from service for a period not to exceed one hour for testing or servicing". The question implies that a test or service will not exceed I hr., then during the test it is discovered that the 1 hr. time limit will be exceeded. The question could also have been read to imply the original intent was to exceed I hr. before the test or service started. In this case the correct answer is:

(1) Have Plant Manager or designee approval.

(2) Initiate form BF-31.(Implement Plant procedures for removal of fire protection equipment)

Also, part of the answer key deals with having automatic functions. Such restrictions were not specified in the question.

Resolution:

Care must be taken to accept an answer based upon the

' question and not word-for-word phrases out of an administrative procedure. The question could be answered I

in accordance with the answer key or as indicated above for full credit.

Reference:

I SP 14.15 i

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SRO REQUAL Section 8 8.11 Problem:

The question is unclear regarding what was required to satisfy the answer key.

Comment / Resolution:

Students have an objective in OPL171.030 (Offgas) to locate specific requirements in Technical Specifications relating to 3.8.B. Students also have an objective in OPL171.033 (Process Radiation Monitoring System) to state the type of detectors used in the Stack Gas Radiation Monitoring System. Even though the question was almost word-for-word out of Tech. Specs, this was not required knowledge from memory. Most people who would be able to answer their objectives would have tried to come up with monitoring systems, such as the Stack Gas Radiation Monitoring System based on the knowledge they are suppose to have to safely operate the plant. Full credit should be given if Stack Gas Radiation Monitoring System was given as an answer to question #8.11, since the stack gas monitor contains the three types of monitors in the answer key.

If the question was re-worded and put in Section 6 that all students .

should have answered it correctly. All students know the basic TYPES

of monitors.

References:

l OPL171.030 and OPL171.033 i

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