ML20215F659
| ML20215F659 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 11/26/1986 |
| From: | Brockman K, Munro J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20215F645 | List: |
| References | |
| 50-325-OL-86-02, 50-325-OL-86-2, NUDOCS 8612240018 | |
| Download: ML20215F659 (17) | |
Text
ENCLOSURE 1 i
EXAMINATION REPORT 325/0L-86-02 Facility Licensee:
Carolina Power and Light Company 411 Fayetteville Street Raleigh, NC 27602 Facility Name:
Brunswick Steam Electric Plant Facility Docket No.:
50-325, 50-324 A written examination was administered at the United States Nuclear Regulatory Commission, Region II Offices, Atlanta, Georgia.
Chief Examiner:
Me
,tds/
8-2$~J6
~
rpo Date Signed Ke eth'
'an
///A 6!A Approved by:
hn F. Munr6ISection Chief Date Signed
~
Summary:
Examination on October 28, 1986, One candidate was administered a written examination of Reactor Operator Section 2, which he passed.
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REPORT DETAILS
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. 1.
Facility Employees Contacted:
- D.
Shaw
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. %ttended Exit Meett.ng N
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1 2.
Examiners:
- K. E. Brockma,n 4
. M '.
- Chief Examiner
+. 3
'3.
Examination Review Meeting n
s 3
At the conclusion of the written examination, the examiner provided Mr. D., Shaw with a copy of the written examination and answer _ key for rev'i ew.
No technical comments were made concerning the exam. The licensee did not identify as propriety.any of the material provided to or reviewed by the examiners.
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NRC RULES AND GUIDELI' 3 FOR *ICENSE EXAMINATIONS
.. s During the.f,rdninistration of this aven na tic:, the fol2 cuing rules apply; s-J li Cheatir@ on?the ev. amination beans an automatic denial of your applitstion-
- i. +
'and could result..in note severe penelties.
2.
Restroom tripscare.te be li nted and oniv one candidate at a time may
- leave.
You d6t b ai.d cli contacts with anyone cuts'.de the examination I
r c a.m to avoid even':she appearance er possibility cf cheating..
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2.
Use black ink or dark. pencil only to facilitate lesible reproductions.
ki 4.
' P r i n t - v. o u r none in-the blank orovided or, the cover sheet of the 1
examination.
'5.
rill in the dateconothe cover sheet of the examination (if necessary).
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- 6.
- Use only the paper provided for answers.
7.
Print'your name in the upper right-hand corner of the +' i r s t page of each j --
s ec ti o 9,, o f - t h e En s we r - s5tte t.
.8.
Coasecutivel/ nt6 3er each answer sheet, write 'End of Category __' as appropriater' start each category on a new page,' write cnly on one side o
-of the nay e and write "Last P a o,, e
- on the Icst answer cheet.
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Sumber e~ch answer as to categor"> and ovmber, for e x a m,o l e r 1.dr 6.3.
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' 10 '. Skip at lecct three lines between each answer.
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- 11. Separate answer sheetsefrom o2d and place finished answer sheets
- ace down m your desk o r 3 d ip.
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- 12. Use. abbreviations only if they are ccmmonly used in #acility literature.
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- i - The point value for eacF vuestion is indicated in p.:renthese: after the i -11 ove<t?.on Jnd cm be used as a cuide for e depth of answer r e q v :. r e d,
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- 14. Show EL.halculctioner metSodcr. or a s s e n.p t i o n s used to Sb*;m rn answer j
to mathemat:cel' problems whether indicated in the quest:.or or not.
- 15. Partici credit me">
be
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Thereferer AN5h'ER A L :. PAPTS NE
'GUESTION'nND 00 NOT.' E AVE A N '?
ANGWEP F_ A W.
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-16. Ir parts of the e nsmir at; c e are not clea: :: t to intent. -
ye:::.ons o'
the e n c a :.n e r only.
l '?. YOU MU5t sian *Se s t.2 t e t e ^ t the cover 3heet ' !)2 t :nd;"
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-10.
When you complete your enanination; y oi.'
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Assenble your enmination as follows:
(1)
Enan avestions on top.
(2)
Enem aids - #ieu-esr-tables, etc.
(3)
Answer
.aa.es includin.n fi2ures unich 3re cart of the answer.
p b.
Turn in your copy of the examination anc t;11 pages used to Enswer the ex2mination questions, c.
Turn i rt all scrap paper and the' balance of the paper that you did not use for answering the questions.
d.
Leeve the examination crear as defined by the u.
c'. n e r.
If a +' t e r leavin3r you are found in this area while *he > < 2 m i n a t i c r.
- . c still in pec3r > s r your licei.se may be denied or reveked.
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. 2, c'L ANT DESIGN INCLUDING S ACET'r AND EMERCENCY SYSTEMS PAGE 2
i
- 0 U ",, ", "v N = "
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06)
- 4..
w DESCRICE how the Core Spray sys t w. piping br e ak detection systen confirms
-the inteerity of the Care 57 rey piping.
Include in yout' answer; i
(a). what piping integrity is.vertried AND.whyr 1
1 (b).'censine ocintst 4
a.
1
. ( c).- nor mal readings-AND Saw systen. operability.chanses when a b r e a !'.
1
. occurs, 4
QUESTI0t4 2.02 (1.50'1 1
I
- a. FILL IN T9E ELANK' M a in,5 t e a r4 Isolation Valve closure time must be between (0.5) 4 4
secondt and cecondt.
4 e
b.
OE3CRIDE the bas:s for these closure times.
(1.0) 4 2
2 4
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OUESTION 2.03 (1.25) i
' LIST 5 si;nals
- hat uculd cause the Main Steam Line Iso:stion valves CMSIV's) 'te isolate.
SETPCINTS ARE NDi REQUIRED yLT.r. m g e n y. e-Tyc
.-p,. r r n R.
",, O n t C '.~T. T r. u.
T b' Pa'
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j-GUESTION 2,04 (2.00)
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LIST. 211 initiation signals / perr_csives that us. be met for the Automatic Depressur'rction System (ADS) to init ete. SETPCINTS ARE REG 01?ED 1
i
'l QUESTION 2.05 (1.00)
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DEECRISE Why thit GCcO"E AND h0W it iC ECCOnOliSh9d+
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0 QUESTION 2. ') 6 f1.00)
STATE TWO (2s reesans for maintaining the 4PCI system fully ' loaded (ie, keep fill system).
QUESTION 2.07 (1.00)
LI P the normal but power supplies of the Unii ;
'<HR pumPL-r.) u r e n. n e 9 no e.s rJ sns
.w vi v if ue w-s e
/
WHICH cf the fol.ow: w describes Sour s losa af
- .ns,' ment air would e f' f e c t J
the operation of Stendby iquid Contro'. <: EkC10 j
(2).
The 0 : ' C.
tan? level ' -d i c a t i o n would 52 inoperabla.
(b).
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,w r w o u l t' be inonerabit.
- c).
The SELC ;wk level indication a t: d air s.o a r c o r would be i r.c p e r r b l e.
(d).
It would have NO..mpact since the cervice 2 :. r sy;wr cupplies all S E L '_ needs.
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Each of
'e events listed below wc"id c2use **w actcr Water Cleanup elet:en or nach event. CTATE uhe w the Inbe r -
system tc I5JLATE, r
valve fr001) AND/09 *he Outboard Isolation /cive tr^00' would auto-r,e t i r r 1 1 y close.
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PLANT DESIGN. INCLUDING SAFETY AND-EhERCENCY SYSTEMS PACE 4-j-
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_The RWCU system' reject #1cw rate is controlled by CCV-F033.-
LIST TWO (2) conditions that Will.autonctically shut the FCV-F033 i
valve rad-DESCRISE what these conditions may indicate.
1 NOTE: SETPDINTS ARE REGUIRED i
r 4;-
GUESTION 2.11 (2.00)
DESCRIEE the methods required to reset the RCIC turbine Trip i
and Throttle valve after:
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o mechanics 1 trip.
(1.0)
(b).
en electrical trio.
'(1.0) i i
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i The Reactor R e c i r c u l a t i o n. o u rx. seal cartridae assemblies consist of two.
^
sets of seclins surfacer cod breckdown bushins assemblies.
Cailere of the t i seal assembly at rated canditions w a r..e l d result in....(CHOOSE ONE).
- i 4
... 2 decrease in i 1 seal cavity pressure f r e c. approutaately (0).
j 1000 ps:s tc s:renimately 300 p t.13 l-(b).
an increase 1.n i 1 seal cavity proosure from approximately 500 osi2 te o Fm r c ;:n e t e l "r 1000 osic, a
c 4'
(c),... an increase :n t : seal c2vity,orosscre # rom appro inately 500.n s i c te w+,a r o n i m a t e ! ')-
10 r,9 m t ;. q,
r
... a decrease in 1 2 ccal 2 7,v i t y pres wro "ren approxic:tel, (d).
500
.e s :. ta vP e r o n i n c t e l '1 o s: c.
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LIST 2 des gn bese-c' the Rod Sequence Cantol systco.
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-PLANT DESIGN.INCLUDINC SAFETY AND EMERGENCY SYSTEMS PAGE' 5
QUESTION 2.14 (2,00)
The ADRM scram _ function. actual-ly consists of two separate setpoints:
a.
FILL IN THE BLANKS:
Flow Biased Scran (1) --
w * --(2) --%
(0.25)
Fixed Scran (3) --%
( M o d r. Switch.' in R IN)
(0.25).
b.
LIST the specific locaticn(s) of the sensor (s) which measure the variable
'w'.
(0.5) c.
Jhile operating at powerr.one MSIV fails shut resulti'n3 in a brief
(~
1.second) flus spike-tc 121% power.
STATE which of the two stran setpoints mentioned above (one of both) should
. initiate a reactor' scram..
JUSTIFY your choice.
(1.0) t DUESTION 2.15 (2.00)
.For each of the following situations (1 and i :!) select the correct Feed-wcter Control Systen / plant responst
- rom the. list. (a through e) which follows. An cnswer may be used. ore t h a n c r.-; e r ' and NO cperater actions are taken.
(a). Reactor water level decreazee and stabilizes at 2 lower 1cvel.
(b). Reactor water level decreaseu and initiates c actor stran.
(c). Reactor water level increases ar.d stabitices at 2 higher 1rivel.
(d). Reactor water level increases and init ates a t u r b i r.e trip.
(e). None of the above.
1.
The pl2nt is operating 2+
70% power >
n Feletent cor: roir whcr one of the Stec-
~1s -, Oetector: FAI'S DOWNSCALE.
1 2..
I~ h e plant is crersting at ' 0 '. 7 0uei, t r, 3-clen.ent c c n t r : ~. r ; hen PPCI InadVerten: 1,- in:::ates 7ne injeet:.
(T*XYY CATEGOFY Q2 : N ' ! l) U E D Ei N E )' T T '.". G E V X :t v V )
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As the Instrument and Service Air header pressures-DECREASE below normal, certain automatic ac.tions.and a l a r :n s occur.
MATCH the a
i piessures listed with'tne applice'n mittmatic act_an cr alarm, i
AI?: MEADER PRESSURE ACTION / ALARM 1
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Standb"r Elde. Air Co w essors START r
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Ir.t er r up t ab l e Instr Air 4dr Isolat,ien
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Scram Air 4dr Isolction 6.
Service ir Hdi Isolatior 4
^7 ACC Ai-System trancfers to Nitrogen t
OUESTION 2 ;7
(
,50) r o u,'n e..yIq. n.
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P o r_'
T. i.m. ', i v...'
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i -r s.
n-With tr e e n c e.o t i c - ;f the PDCI Turbine Enhaust D:a.chter Precture High, j
an autanat:c isolation signa: seals in both A and S logic
~.n e s and must 2
be nanually recet by the operctor b "i denressina the AUTO ISOLATION FIGNAL A aid 9 b "5?30t D U t I C itS On thG NICS.
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siasrv**-rrxewri 4 L 2 i 4 F T 4 J 4 i
) 4 -f G '2. - PL#NI DESIGN INCLUDING SAFETY AND EMERGENCY SYST7MS PAGE 7 ANSWERS -- SRUNSWICV 132 -G6/10/21-E'ROCKMAN, K. 1 ANSWER 2.01 (2.00) a ' The e i n i n c, in e.vastion i s that between the reactor vessel nenetration(SBLC Inlet) and the shroud (0,5), Pressure i t cented above the core plate (0.25) and at the s p r w, c.oarner(0.25). The indication :: normall"/ a necative d.o l w w -(0.25); when c brets occuro, the dp will so positive (0.25), If a break occured in the 'noni t or ec c r e a s full spray flow would NOT be 2vailable for i core coc1:ng(0.5). 1, ps : c. c o..c N. C C BSEP H0d 4-2/3-E p.? i A N S '4 E P 2.02 (1.50) P 1 2. 3 coconds; 5 ceconds (0.25cacn) b. The three (3) seconc m:nimum is to limit the pressure /#1ow t r a n s i e n *, on the reacto?. (0.5) i The i v e (5) second m_ timum is to l i r. i t the loss of cociant iOV9ntOry g n rj sdUCO the 3 m O '. n t c rOdiOSChiYi", relOased tC th6 OnV;rOnnent, (0.5) t b' u.7 II_ C' 7 >4' f C ,s-i u. ~
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I ?. CLANT DESIGN INCLUDIN'; E AFETY AND EME :GENCY SYSTEMS
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a w _i .c. 7 ANSWER 2.04 (^.00)- 1. Reacter Lou water-1cvel, LLt3 ( 2.5') '.0.5) 1 2. Recctor Low ucter level, LLt1 (162.5') (0.5$ 3. Operat:.cn of both pumre of one tPCI loop cr Core Spray pump-ac (0.5) i nd;cated by e pun? 'n s c h e r s e proscure of 100 pois. '4. Time delay of '05 - econds has e '. c p s e d. (0.5) 4 p : c c c,c e.t L :. s_. a a .<.~.. u0 '.c ~.F
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J p.s t i. I L +'_ 2. PLANT DESIGH~ INCLUDING SAFETY AND PAGE 9 3 -___.___.._______________________________' EMERGENCY SYSTEM 9' 4 f fANSWERS -- NRUNSWICK 1&2 -86/10/21-SROCMMANr K. 4, 4 A I ANSWER 2.07 (1.00) 4 Pump Power supply IC 1E (0.25) 1: _33 ~e -(0.o.e) b - 1 A. .3E (0.25) 3 3:. m . a r. t.o.cm) n e r. r_ p Lr, r_ .w l BSEP 40-14-2/3-D p.19 i ANSWER 24 02~ (1.00) 'i {- 4 ~~A (1.0) i 'REFERENCt i SSEP HO-14-2/2-H p.14 i ANSWER 2.09 (1.50) l, (a). C001 stays open, F004 closes (0.5) t (b). F001 stays open, F004 closes (0.5) 4 (c), C001 Itays open, C004 closes (0.5) r REFERENCE BSEP 3 - 1 1 - 2 / 3 - A pp. 9 12,14 I i P L .t l-f l t i. ( t t I i I ( i i l t.-_
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i i v t ANSWER 2.10 (2.00) (a). Lou pressure isolationr 5 psis + a: - 2 psig (0,5) a s This indicetes a broek I r. the cystel. Process line (e cures that the RWCU systen does not go into a vacuum lika the Mein Condenser) - CR - '0y indicate thct no ditcherp path exists (Sotn u;n condenser and radWacta sclation valves clcsed), (Either E4 0.5) (w). q.4.,3i g<p x.. a,.r. m. 4.3 0. w,4. 4 a n F 2 4n, m.,,., s g ,J,1 ., 0.r en es .s g ., c g 5 w av, This
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7 4 t 2.- PLANT DESIGN INC' UDING SAFETY AND EMERGENCY SYSTEMS oAGE 11 k. ANSWERS -- E'RUNSWIC" :. R 2 -P6/10/21-SROCMMAN, K. 3 t - A N e W C o, ,. _ c. . <,. v. 0 3 a - 1 (1). M train ^cd c20 tion such t h a t -- s costulated rod d e cio accident l will not *esult-in a peak f'v e l enthalpies greater than the I desi-an limit of 280 cal / gram for the entire range of plant o.nerations and core e :.m. o c u r : :, 1 (2)- revent the reactor ope"ator from. moving an cut of sequence control rod in the 100% to 50% rod denc;ty rcnge. 4 (3), All.ous from the 50% rod density point to the 30% power level, ONLY 3roup not?5 nede rod withdr w alt o~ insertions, s
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