IR 05000286/1986018
| ML20212Q024 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 08/25/1986 |
| From: | Keller R, Kister H, Norris B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20212Q022 | List: |
| References | |
| 50-286-86-18OL, NUDOCS 8609030374 | |
| Download: ML20212Q024 (40) | |
Text
C U. S. NUCLEAR REGULATORY COMMISSION REGION I OPERATOR LICENSING EXAMINATION REPORT EXAMINATION REPORT NO. 86-18(0L)
FACILITY DOCKET NO. 50-286 FACILITY LICENSE N0. OPR-64 LICENSEE: Power Authority of the Stat.e of New York '
P.O. Box 215 Buchanan, New York 10511 FACILITY: Indian Point Unit 3 EXAMINATION DATES: August 13, 1986 CHIEF EXAMINER: A Ea#y'KTNorris, Af ur d Date 4 Rea 66r E in Examiner)
REVIEWED BY: NI) 8 Robert M. Keller, Chief, h 11/W/
Odie Pr ects Section N .1C APPROVED BY: , h - I [ b Harry B. Kiper, Chibf, /Date / / l Projects Branch N SUMMMARY: One Senior Reactor Operator (Upgrade) candidate was examined during this examination period, the candidate received a license, i
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REPORT DETAILS TYPE OF EXAMS: Replacement EXAM RESULTS:
SR0 Pass / Fail Written Exam 1/0 Overall 1/0 CHIEF EXAMINER: 8. S. Norris, USNRC 1. Summary of generic strengths and deficiencies noted from grading of written exam:
Candidate showed a significant improvement in his understanding of the plant systems and the application of theoretical knowledge to operational problem However, weaknesses were also observed in the area of procedures, particularly administrative procedure . Examination Review:
The facility comments on the written examination were discussed at the examin-atton review held August 1.1, 1986. (See Attachment 2)
Attachments: SRO written exam and answer ke . Facility comments on written exam and NRC resolutio _ -
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U. 5. rJUCLE AR REGULATOE) COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAe1INATION FACILITY: INDIAN POINT 3
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REACTOR TiPE: PWR-WEC4
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~ THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 2
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GUESTION 5.01 (3.00)
There are THREE primary parameters that affect DNB and can 'e o controlled by tne resctor operstor otner tnsn core flow or fluu distributio E;r t e f l y enplain how an INCREASE in each of these parameters affects tne DND A s s u n.e otner F ar ameters r enssir. constan QUESTION 5.02 3.00)
E x rs l a i r. HOL cnd WHi ccntrol rod uottn .arles; With its radial cosition in t, n e cor If tne RC5 coron concentistion is inerease It 6, o e m 1er ster temperature incresse . - , - , .. , . ..
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For the following, s s,s u m e roc control ts in manua Descr ibe tne ressonso sdirection of cnsnye AND reason, of power sno is.ee arter 2 minutes ci Emergency Ecratico at: ISM. 9 owe- (1.50s E-3 Amp t 1.00i Entend scur a n s .a e r to tne r e s t c r s ti cr. of stsole c o n o i t t o n s.- $No numerical salues are re:otre c40TE: If tower sncect T.s se co NOT change. so stata s n c, ea91 tin - ric c n a n y a. -111 occu GUE. TION 5.04 t 2-..>
1 Fct s reacter a:-:rattng at s c c n s +,a n t ;ciar snc temperature, will tne I riE E r. A L rie u t t O f lu: n e i. r EOL De tGEEAIEE IHA: /EnALLER THANJ
.a r IhE 3A.mE AG- the flu nect EOL? EAFLAIN sour answe Iof E' TE6etGr Operatin] . t 4 c Drill E n t power C ri O t e rtip e r O t u r e , W1;l the 7A37 n .? v t, .^ 0 n flux near EOL oc CI1AIET T h s rJ , 3rtALLEB THAN/
ct inE IAnE sii tne fiu. nest E. D ' . M sume the 9 t o r..s, t / d e i s y e c heUtrQn r ', *,1 '3 remsins :Cn5*,snt,. EtFLAIN .our snswer.
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. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 3
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GUESTION 5.05 (1.00)
Assume that yoi.. have estaoltsned a 1 OP rt SUR on t i- reactor while the source range t rici1 c a t e s 1000 cpne on botn c h arin e l s . .fter 30 seconos would you have increased Power by 1'2 decade ( by a f .s e t o r of 5);
EXPLAItJ your answe QUE5 TION 5.Go ( .7 The -L/5 0Fn SUR following a reactor trip is causeo oy wnten ONE of tno following: The decav constant of tnc l o rcg e s t -l i v e c group of celsvea reutton r. T e C U r s o T s . The act11t. cf U-235 to fission witn source neutron *
. The a nio u n t of negative r e a c t i s i t .- s co e c; on s tr1- being greater than tne Shutdown nar31n~ Tne coppler effect adcing positive reactivity ove to the temperature cecrease tc11cwin3 a tri '.U.....ON
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CoSpare LGe CslCulateG EstimatCO CTlt1 Cal Positish ECPf for a s startur 15 houri after a tric to tne Actual Cr;tical Roo Position ACE ' . if toe followLag events. conditions oCCurr?q. Constaer escn ince9encerati t1 mat Vour answer t ACF ..igner than E C F' . ACF lower tnan EC ACP woulc not oc signtitcantiv cifferent taan IC:. One heettor Cooltnt Fump 1: It:4ceo one manute trier to criticzitt :. inc s t e s e, aum; pressure ietscint ts increasec to s saive ,4 u s t oclow tne cooe s a f e t v s. ' 2.etto: :. Tne startue :: celavec ; more nour .Assis C6TEGOEi 05 C0rT NUED 09 r; E X T PAGE *****>
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- THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 4
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00ESTION 5.08 (2.00) What - .he followin3 reactor trips designed to protect against? Overtenperature Delts T 2. Overpuwer Delta T Whv does tne Overtemperature Delta 7 circutt have pressure aL sn input whereas the Overpower Delta T circuit' does nott GC E 5 TIGrl 5.07 s2.00)
D' reactor is operating at 3 0 *. : o w e r snen one ACF trte /ssuming r. c reactor trap or turotne i o . . r; cntnge occurs, ancicate wnetner tne . . . . _ . , .
following persmeters will ANintnot, u t o n, t s .:, E , or e t n .. .4tn ..i r4 :. ., an .
_......._ Flow in coertting reactor coolant 1c.cos Core deltz T
. . . Reactor versci celta P Operating loops s t e s.t generstor pressure
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, THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 5
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GUESTION 5.12 (2.00's Explain why you agree Or cisagree with eacn of the following statement Equilibrium Xenon at 100% power is aoovt twice as mocn as equilior ium Xenon at 50L powe . Equillortum 5amartum .s t 100*. power is about twice as much as e q u i l l o r i u::t 5 a n,a r i u m at 50% power.
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~ PL ANT SYSTEris DESIGN, CONTROL, AND INSTRUhENTATION PAGE 6
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GUESTION 6.01 (2.00i State the purpose of the bypars lines installeo around the No. 1 seals Of the reactor coolant pump (1.0s What unoestrable consequence has occasionallv resulted from Operiirig the No. I seal bypsss valve? (1.0-,
OUESTIOr4 .s.02 (2.75e Concerning tne pressurl:et scr av 11 rie s Whien reactor coolant loopt si providessi the source of NORrinL spray flow (0.5>
0 WH tc presisten m ace for AutILIART sprsv cs: sot 11tv; 60.75) Etste TW: F. E .'s L D r4 5 1 or n a v a r. 3 c smsil a n. o u n t of c o n t i rm o u s, G rF Ass flo_ ar-:uno tne scra. .al.e (1.5)
_GUEETIOt1 6 . :i ? (I.00 Concerntog the Pressor 1:er Relief Tank (FETs4 Etste tne purpose of tne r. i t r o g e r. o l e ci n. r a n t : 1 n rf o o n this r, a n e . (0.5) How is tne F F, T protecteo s3 sin:t overpresp.ne - (0,5) Otste toe TwG cest;n !astures of the FRT wnica may oc utilized to C orioen! E 3 ri G ccol i nc on.i n? E tG 3 m EitEf 1 li t ir.3 &
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. PLANT SYSTEMS DESIGNe CONTROL, AND INSTRUMENTATION PAGE 7
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GUESTION 6.04 (2.50)
How are the following CVCS components affected by a loss of instrument air pressure (<30 psig)? Answer either Fails open, fails closed, goes to me: imum s r.,e e d , goes to min. speed, or no change.) Oper ating ber le acid transfer pump Letdown valves LCV-457 ano -460 E;o r i c acid to blender valve FCV-110A Operating ensrging pump Cnargin3 pumps suction f t o ni VCT valve LCV-112C OUESTION 6.05 (1.00)
In the conoiticn or a Unit Trie .alth Llacxcut and NO Sarttv Injection, all Component Cooling Wster (CCW, ov n.p s are t r i c. p e o , ano sucsequently restsrted a u t on.s t ic s l i ss s function of ener 31:ea 4 30's ousse Whst componentsse recuire CCW cooling out ing this c onos tioni GUESTION 6.06 (0.00i Refer to tne attacned sim-lifico sk e tch of toe Restoval dear, Removal System .F13 4.2-2). tste TWO pur;cses of +hc itn , centsining .sives 743 ano LS7 (1.0) De scr ibe the oteration of t..e cr essur e ar ter loci assoelste, ai tn valves 30eT3 Incivae anv setpcints cr effects.(1.0) Wnen v al s e s ' 3 0 ArdD 7 51 si e o :. e n , esi.es 5854 555E: 7 8584, OR 3 3 5 E. C.;n n 0 T ce cpene What TWO unoe s s r ce.le events ts this inter 1cco cesigneo to orevent: (1.0, a a s a CATEGORr ;., CONTINUED 0.-i . , F X T FAGE e.x m 2
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. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE B
QUESTION 6 07 (2.00)
Concerning the Steam Dump system' In tne Temperature Control mode of operation, wnst TWO conditions will cause the steam dumps to open automatically to control temFerature? What TWO INTERLOCKS must be satisfied in order for the steam dumps to actuate? Setpoints are not require QUESTIGra 6.03 (2.00, Describe TWG automatte control functtens provtoed ov area raalation mor.i tor s . Ir.cluoe i r. voor oi scus slori whlen enannel coritrols whlen functio OUEETION ti.OGe Concerning tne 3afety Injection Svstem accumulators The low level sisim notifies tne operator inst tnere is an insufficient water vclume in tne accumulater tc provice acequate core cooling during an acticen For what iesson is a HIGH LEVEL ALARn installed; GUESTION t.10 (2.25)
Concerning tne Containment 5cra. Eystend Oncer wnat concitions snoutc tne operator want to OVERRIDE the cdostaan si Loosun. Hyotonice (NaDH) to tne c on t ai n n.e n t sprav water: [1.253 How is over r iding tne riaOH aoottion accomplisheo? [1.03 GUESTION 1.!! . .50<
Ouring a Acwer e -s c a l c t i o n from 1 5 '. to 100*. operator error causes a power recuction to E *. . Tne oroer is a g s i .- given to raise losd tc L30%. wito no cre ator action GTHER THAN ratsing turoine loac cr.d placing ioos in suto, s Reactor Trip cecuts. E u n c a r. WHY a Aeactor Tr ;p occureo sn 1 the 3EGUENCE of events tnat lec to tne Tri t .a.* * , r CATEGOR' 06 CONTINUED Gn NEAT P A G E .* * * * * :-
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. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 9
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OUESTION 6.12 (2.00)
Followin3 a reactor trip, tne trace of one of the intermediate range
_9 detectors levels out at 10 amps: Is the detector over compensated or uncercompensated? (0.5) E ;-: p l a i n now the compensstion is accomplished within the detector. ( 1. 5 's 1.a a s EriO 0F C;.TEGOR r Go a .a .m .: a .
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. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 10
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QUESTION 7.01 -(1.50)
The_following pertain to information found in ONOP-RC-1 ' Rod Cluster Control Deviation'.
' With respect to maintaining Tavs, how does the use of roo control systen, differ for a dropped rod and a masaligned tod? (1.04 Whose permissior, must be obtaineo to operate at a power level
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greater tnan 70*J witn a cropped rod? (0.5>
GUESTI0rl .02 (2.00)
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In accordance with 50P-CVCS-3, RC5 Boron Concentration Control, state tne ONE norn.cl arid THREE alter res te floupcths for E nie r g e ne v Boratio GUES TIOrd ~.03 (2.50)
Per 50F-;C-1E. Con.ponent Cooling Systeni Operation; 4 What ts the maximum Component Cooling Water iCCW) return temperature dur ing not mal operation and unct is the basis for this l i n. i t ? ( tate the minimum AND maximum flow rates for the CCW system anc the bst:5 for n e n. s u i n.u n-. flow rat (1.5)
(xae** CATEG06( 07 COrJ TIrJUED ON rJEXT F ACE Ax * 4* )
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- PROCEDURES - NORhAL, ABNORMAL, EMERGENCY AND PAGE- 11
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~ QUESTION 7.04 (2.50)
The following concern information found in POP-1.1 ' Plant Heatup from Cold Shutdown Condition'. State the e::ception to the f ollowing statemen 'The shutdown banks must be at the fully withdrawn position unenever positive reactivity is being inserted by baron and : tenon' changes ,
RC5 temperature change, or motiors of control rods other than the shutdown banks.' (1.0) tate the shutdown margin requirements f or solid plant operation ArJD when they may be r e l a ::ed . (1.0) Above what temper atur e must RC5 chemistr y oe within allowable limits J0.5)
GUEETION .05 (3.00) Procecure ECA-0.1, Loss of All AC Power Recovery Without S Required. advises caut2on when re-establishing RCP seal coolin What are TWO RE A5GrJ5 f or this caution; ii.0) ECA-0.1 gives indications to verify natural circulatio List FOUR of the F I'J E incications tn.st serifv natural circulation enast (2.0L QUESTION 7.0c (1.00)
Frocedure'E-3 s5 team Generator Tube Rupture; oirects tne operator to 'Depressurire the RCE'
List in oraer of decreasing preference the THREE methocs available to the operstor to reduce RC5 pressure per E- QUESTION ,~.07 (2.50)
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Fer GNOP-ACS-; thalfunction of Pressort:er Pressure Control system':
Wnst F O U F, sctions (verificationsi are oirectec to ce taken 11 pressurl:er pressure is CECREA5ING below the control / alarm setpcint ano a reactor trip has not yet occurred?
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L PROCEDURES - NORhAL, ABNORMAL, EMERGENCY'AND FAGE 12 UTR5E------------------------
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-QUESTION 7.08 (2.00)
i In orcer to maintain tne plant at 100% power, work must be performed inside the containment in a radiation field of'100 MREh/HR gamma and 100 MRAD /HR neutron. The maintenance man selected is 27 years old and has a lifetime
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I -exposure through last quarter of 29 REh on'his NRC Form In addition, he has accumulated 1.0 REM so far tais quarter.
, How long may the man work in.this cres witnout exceeoing his 10 CFR limit? Show all assumptions and esiculation C1.53 What is the allowable dose '.o' save a life? (0.5) ,
GUESTION 7.09 (3.00)
The following concern a loss of Instrument Eos 31 oue to a fault,
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while operating st 851 powe Why will a reactor trip NOT occur? Enplain-now. rods are used to control Tavg.
- Explain ahv.a turotne runback will occur 0 Explain how stean. oump actuates to control temperature 11 the temFerature moce is selected ano a turcine run'sck o occur ; QUE57 ION 7.10 (1.50i Frtorttire tne below listeo Critical Safetv Function 5tatus Trees from
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h13 hest ~tc lowest * Containment - Red
- . Core Cooling - Red 3 Heat 5tnk - Yeilow l Integrity - Orsnge
' Inventerv - Green c. . ' superititalltv - Orange
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QUESTI0'N 7.11 'i .80)
Answer the following per GNOP-RP-3 ' Loss of Refueling Cavity Water Level During Refueling':
I If an irradiated fuel assembly were to become exposed.to air, approximately now long would it be before you exceeded the quarterly 10CFR20 limit for whole body dose if you were 30 feet away? (0.55)
(l's one second s2) one minute (3). one hour (4) .one day GUESTION 7.12 t!.70s
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Answer the following in accordance with E-3 '
Steam Generator Tube Rupture tste 4 pct sn.a ter s that should be monitored to sie in toentifying a
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steam generstcr with a tuce ruptur .(1.201 State 5 actions that must ce performed to isolate a steam generator with a tube ruptur ti.50)
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00ESTION 8.01 (2.00)
Answer the following assumans normal at-power operations.
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INCLUDE APPLICABLE TIME LIhITS
- Per TS. what action (s) are required if operating with minimum ' crew composition AND the RO becomes incapacitated? (0.5) Fer TS, is the following action proper by the Shift Supervisor?
JUSTIF ! 15 minutes oefore scheouled arrival of the on-coming shift, John Doe, an on-coming RO calls in sic The on-duty SS decloes, due to his shift's present overtime situation. to call in a replacemen The SS also decides tnat since the replacement's arrtval will be shortly (30 minutes) after shift' change to send nis people home and let the next snift to start one person snort 2 of minimu (0.5) F er AP-21, Conouct of Operations. the 55 must be able to Yeturn to the control rocm within ____ trainute (0.53 Per AP-21* by whom may the SS oe relieved? (0.53
GUE S TIOri 6.02 (2.50) What 12 the manimum Guadrant Fower Tilt natio (GPTR) allowed bv Tecnnical Specif1 stionsi (0.5i
- What protection coes tais limt; provide' s 0.Si The two hout time provision fot continueo power operation wita OPIR above the TS limit sllows time for tne operator
, to perform wnst TWO sctions; (0.5) How t c the OF TR data obtained if one Pcwer Range NI enannel is inopersole at 100*. Power operation? (0.4)
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. QUESTION 8.03 (2.00) What ACTION must be taken if the RCS Specific Activity exceeds 1.0 vCi/cc Dose. Equivalent I-131, and also exceeds the limit of the Technical Specification activity identified in l F19ure 3.1-3? (1.0> What is the TS basis for the LCO Action Statement for RCS specific activity? (1.0)
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GUESTION 8.04 (2.00)
Assume that it is 0310 on 5/19/86 and the plant i s presently i
at 45% power. Considering the AFD penalt'. historv celow, at wnat date and time may power be increased above 50%7 EXPLAI t5how all work.) Assume no deviation cutside the band after ,
0310 on 5/1?/B TIhE WENT GUT TINE BACK DATE OF E;AND IN BAND POWER 5/15/86 0310 0313 35%
5/15/56 1557 1637 65%
5/11/86 0148 0310 45% (2.0)
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'GUE5 TION 6.05 (2.00) What is the basis of the ' Reactor Core safety Limit' What are tne Shift Supervisor's responsibilities if a ' Reactor Core Safetv Limit' is violated?
GUESTION 6.06 (3.00)
Accorcing tc IF 3 Technical Specifications. temporary changes m a :. ce n.a d e to plant procedures if three c;1teria are me State tnese THREE criteria.
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i t .a .m .t * CcTEGORY 06 CONTINUED ON-NEXT PAGE **axA>
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e h ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 16
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'
' QUESTION 8.07 (2.00)
[ State the purpose of the following tag . Stop tags i Do not operate tags (1.0)
I List the three colors of locks required to be put on valves i that must be locked prict to enceeding 200 Include the position each color indicate (0.6)
} List the two colors of locks requireo to be put on electrical i breakers that must be lockec prior to exceeding 200 F. Include the position each color' indicates, t0.4i QUE5TIOr; 8.05 s2.50>
J The following concern AP 21.2 ' Post Trip Review / Restart Frceecure'. Last the three notificBtions tnat must be made by the Sn11t Supervisor tn the e.ent of any reactcr tri (1.0)
, 'Having Icentifled the immeciste snd root causes for a p1snt trip, under what two conditions mav tne 3hift Supervisor
- authorice plant restert? (1.0)
, If s second trip shovic occur while starting up following l- a reactor tr i p. who must be consulted silot to attempting ancthe;
restart? (0.5) s i
j QUEETION B.09 (2.50;
'
The (cilowing concern Informstron founo in the IP-3 Emergency Pla List the-o per sonnel (bv title or position) who nave 'een o destgnstec as Emergency 01 recto'. (1.5; j 'During an emer3ency situation. at wnzt ocint coes Pnsse Two (-. aegin' (0.5) Descrice the adc;;1ons to Fhase Tuo tr oviced av Fhase Thre (0.25)
i W h a t, perscn (bv title or positicn, ass r,he vittmate sotherity
- 'duilng Ph5se Pouri '.0.254
)
s e .u .* * CATEG0Rt 08 C0rlTIduEC CN HEXT PAGE * * .s e .* ) .L
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.. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS' PAGE 17
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QUESTION B.10 (1.00)
Answer'the following in accordance with AP-11, Radioactive Effluents Control Program; Whose permission is required if the instantaneous release dose rate limit is to be authorized for an Airborne Radioactive Waste (0.5)
Release Permit? , The projected release limit requires that the decay tanks be used to reduce gaseous radioactive wastes released if the projected air-dose enceeds ____ mrad gamma or ____ mrad bet (0.5)
GUESTION 3.11 t i.75i Answer tne following in accorcance with SOP-CB-2 ' Containment Entry ano Egress'; Prior to entry, what sur .eys are performed cy Chemistrv and HP?
List THRE (0.75i List two types of dostmetry_ required when entering the containment while the reactor is critical? (0.50' , What TWO action must be taken if your costmeter reads seven-eightns
- 50 50, of iull seslei QUESTION 8.12 (1.75i The Technical Spectitestions state that 'Each surveillance Requirement sns11 ce performeo witnin tne speelfled time interval with; A maninum allowaole entension not to exceed 25% of the surveillance interval; and The total maximum c o m o i r.e d time intervsl for anv three consecutive sur vell; ance I n t E t '. a l s shall not Enceed 3 25 times the specified
'
survetilance :nterval.'
List THREE reasons for tne acove?
- AA2* END OF CATEGORr 03 ***2A)
i (xxtatt u AAs.** END OF EAAnINATION *AtA***********i
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EQUATION SHEET f = .3a v = s/t Cycle efficiency = (?tet work cut)/(Energy in)
2 4
, = mg s = Y,t + 1/2 ac
-
I = mc~ .
A = A e~' ",
A=1 1 KE = 1/2 mv a = (Vf - 13 )/t 3 PE = mgn vf = y, * at d = e/t x = In2/t1/2 = 0.593/t1/2 y,y g -
n0 2 t
1/2 W = UtusM ,
A= 4 ((t1/2) * II }l b e
d = 931 .m ""Y 4 av Ao t,le
. .
Q = mCaat *#
d = (JA A T I=It7 pwr = W,ah ,
I = I,10**/ *
Til. = 1.3/u
P = 7 010 sur(t) HVI. = -0.593/u t
? = Po e /*'
SUR = 26.06/T SCR = 5/(1 - K,ff)
CR x = 5/(1 - K,ffx)
SUR = 25e/t= + (s - o)T CR;(1 - K ,ff)) = CR 2 II ~ *eff2)
T = ( t*/a ) + ((a - o V Io] M = 1/(1 - K,ff) = CR)/CR, T = 1/(o - s) M = (1 - K,ffa)/(1 - K,ff))
T = (a - o)/(To) scM = ( - K,ff)/K,ff tw = 10 seconcs a = (X ,ff-1)/X ,ff = AK,ff/K,ff -I I = 0.1 seconds a = ((t=/(T K,ff)] + (i ff /(1 + IT)]
d Id Ij ) =2 ,2 2 I;d) 7d 22 7 = ( uV)/(3 x 1010) 2
- = :N R/hr = (0.5 CE)/d (metars)
R/hr = 6 CE/d2 (feet) ,
Watar Parameters Miscs11aneous Conversiens I curie = 3.7 x 1010:3, 1 gal. = 8.345 le I kg = 2.21 lem 1gaj.=3.78litars 1 f. = 7.48 ga I no = 2.54 x 10 3 Stu/ar Density = 62.4 lem/ft3 ,
1 a = 3.41 x 100 5tu/hr censity = 1 ;m/c::r3 lin = 2.54 cm Heat of vaporitation = 970 5tu/lem V = 9/5'C + 32 -
Heat of fusion = iaL Stu/lem *C = 5/9 ( ?-32)
1 Atm = 14.7 psi = 29.9 in. H BTU = 778 ft-lbf f
I ft. H O2
= 0.4335 luf/i _ _
- . - - _ - ___ _ .. ._. - - _ .
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RESIDUAL HEAT REMOVAL SYSTEM
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(Ot D t t . . F tooc as @ g - _ ypj
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LOOP 33 toOP 34
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,33 conggen,_... . ,_ . . . _ _ _ _
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FIGURE 4.2-2
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5. : THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 18
'
THERHODYNAMICS
-_-_----_-----
ANSWERS -- INDIANLPOINT 3 -86/06/13-NORRIS, B. S.
i
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, ' ANSWER 5.01 (3.00)
'
i 1) Reactor power C0.53. Increasing reactor power results in increased heat flun and DNBR decrease CO.53 2) Temperature CO.53. If pressure is held constant and Tave is increased, subcooling will decrease. Therefore the hest flux required to reach DNS will decrease and the ONER will decrease. CO.53 3)' Pressutirer pressure LO.5 If Tave is held constant and' pr essur e increased, subcooling increases and DNER increases. CO.53-REFERENCE IPS Therscdynamics, Ch ?. p39 ANSWER 5.02 (3.00)
I a. ' Rod worth will vary witn neutron flux (0,5). tnus rod worth increases
'
f r o n, the outside edge of tne core to tne middle of the coret0.5). As boron concentration increases, rod worth cecreases (0.5)'because of-the higner competition for neutronsCO.5^>.
<- As moderator temperature increases, rod wortn increases (0.5) because the thermal dif f aston lengtn increases. thus n,ot e neutt ons are in the epitnermal range anc svstlable fcr rocs to absoro(0.5).
^
REFERENCE IP3 An Theory. Ch 7, pp3-35.
i 5.03 s2.50i ANSWER s. Fower decreases inittally CO.25] cue to the negative reactivity of
- the boron sod; tion E0.253. The primarv to secondsiv mism&tch [0.253 cause5 IaVe to Cecre3se C0.253 The cecrease in Tave inserts positive
'
r6activ:ty t0.253 and. r estores power to slignly louer than or the same
) as initial power E0.253, i' Tave-1s determined by tne amount.of pump nest and the s t e a immp. pressure setting C0.25] tnus it coes not cnange CO.253. After the initisi transient, power cecreases [0.253 ,st 3 -le l DPn rate) to the
- multipliec source level E0.25 .
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- THEORY OF NUCLEAR POWER. PLANT OPERATION, FLUIDS, AND PAGE 19
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ANSWERS -- INDIAN POINT 3 -86/08/13-NORRIS, B. REFERENCE CP&L Reactor Theory Chap. 12, IP3 Rx Theory, Ch 5, Sect. 5.3; Ch 7, pp33-5 ANSWER 5.04 (2.00) CREATER THAN CO.;53; because as the fuel is depleted (boron decreasing)
the macroscopic cross section of the fuel will decrease, and to maintain the same power level the thermal flux must increase CO.75 AnE'A3 [0.2531 because fast neutron flux is cirectly propertional to power E0.75 REFE6ENCE IF3 R: Theory, Sect. 2 . 5 .i ANSWER 5.0L (1.00)
-No C0.25 SUR is an exponential increase CP=Pc10eap5UR(t)] _C0.75 REFERENCE IP3 R;. Theory. Ch 4, pp;;-3 ANEWER 5.0c i .70s a
REFERENCE 001/000-K5.49 .s2.9J IF3 R: Theory, Ch A. pps-11 Ad3WER 5.07 1.30) e tsames a ,ACF highere 4 o ;ACF loweri ;;.6 e .
. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 20
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ANSWERS -- INDIAN POINT 3 -86/08/13-NORRIS, B. REFERENCE IP3 R:: Theory, Ch 5 & 6 KA001/000,K5.15, At45 W E R 5.08 (2.00)
a.1) DNB E0.53
) E.:cessive fuel power s: K W / f t ; CO.53 DNE is a function of pressure whereas KWJft is not telsteo to pressur E1.03
_
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250.;c pst3 .Will sccept anv value t' r c m 247 psi 3 to 253 psig if w o r aie t a c o s ar e correc .
t c 0 0 p s t _: = 1614.- :s;3 (0.40)
5et. temp. for it;4.~ r418 = 60o.10 F interpolated) (0.40)
= 40c.10 F iO.40; 200 F succcclec Lat press. f or 4::s.10 = 2c4.76 tslo ' 1 rite r pol ateo ) (0.40)
Zo4.fc p sis = 257 20 pst3 (0.40)
REFEEErJCE 4t,eam Ta'les c
.
. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 21
~____ _________-____________________________
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ANSWERS -- INDIAN POINT 3 -86/08/13-NORRIS, B. ANSWER 5.11 (3.00)
N1=1500 rpm Vi=250 gpm Hp1=15psis Pl= 40 KW N2 = 1500 sqr root (10.0/15) = 1224.7 rpm C1 03 V2 = (1224.7/1500)(250 gpm) = 204.1 gem C1.0]
F2 = (1224.7/1500) (40 KW) = 2 KW C1.03 REFERENCE
- P3 Thermocyr.amics-Ch 6, pp29-2 AN5WER 5.12 (2.00)
- D i s a gr ee , C0.25] ienon has a non linear f lu:: dependence. Its ptcouction is ilu:. dependent but ren. oval depencs on flu:
Enc cecay C0.75] sagree, C0.253 3amarium is flu: incependent since its removal ano prodvetion is totally flux dependent. Once it resenes equ tlibr tum, toe este of production matene the rate of remeval CO.75 RCFEFENCE Ip 3 E ,4 Theory, p6-3, -19 -2 t
.
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s PLANT' SYSTEMS DESIGNe CONTROL, AND INSTRUMENTATIO PAGE 22 ______________________________________________________
ANSWERS ---INDIAN POINT 3 -86/08/13-NORRIS, ANSWER 6.01 (2.00) To allow for additional seal injection water ficw through the RCP lower radial bearing for cooling purpose (1.0)
- Lifting and jamming of seal rings (either No. 1 or No. 2 (1.0)
Seel ring).
REFERENCE IP3 SOF -RCS-1, paragraph ANSWER 6.02 (2.75)
- Loop 33 (PCV-4558) CO.25]
Loop 34 (PCV-455A) CO.25] 0.5) To provide spray flow when normal sprays ar e not available ( when RCP's 33 ano 34 are shutcoun>. s0.75) . Reduce tnermal stresses (by keeping spr ay lines and surge line warm). Helps equalice boron concentraticn between pressuricer and.RC . Helps prevent temperature stratification in the pressurine E2 required & O.75 esen] (1.5)
REFEREt4CE i IP3 3D 1.4, PP. 13-14 ArJ5WER 6.03 (2.00) Tc prevent tne formation of explosive hydrogen-on-gen mintures (by displacing onygen from the PRT thr ough the v e n t, neader). 0.5i Two rupture disks are installed, (which dischar ge into tne
.sper containment building at a setting of 100 psis.
,
(0.5s
, . - The r elief s oischarge tnrough sparging no :les located below the normal water leve r A spray header ssupplied by prim;ry makeup water) .is installeo accve the normal water leve C2 G 0.5 e.sen: ,
t i.Os i
REFERENCE F 3 ~ 30 L.4, FP. 15-20 i
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4 PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 23
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- ANSWERS -- INDIAN POINT 3 -86/08/13-NORRIS, B. 5. ANSWER 6.04 (2.50) No change
' Fail closed Fails'open
' Goes to man. speed
- No change CO.5 each] ~(2.5)
I REFERENCE ONOP-IA-1, ,
AN5WER 6.05 (1.00)
The reactor coolant pumps' thermal carrier neat exchanger (Since
charging pumps w211 nave tripped, and seal and bdaring water will oe
'
-cerived from hot RC5 water. CCW water, passing through tnermal carrier HX, will coc1 this hot RCS water.)
FEFERENCE IP3.5D 4.1, P. 24 i
l Ar45 WER 6.06 (3.00>
l . Provice flow patn for test:ng RHR pumps 2.- Frevent cperating RHR pumps at snutoff head (miniflou; Frovices overpressure protection for the RHR' loop Tap off to toe C'J C 5 system sany 2 at 7>.5 each,
'
, Cannot coen 730/731 if RC5 pressure 2450 psig CO.53 If
,
RCS pressure-increases to 550 psts wntle 730/731 are open.
L they w:11 a u t on.at i c a l l y close C0.5 (1.0, i
i :. Orsinino the RCS to the containment sump. C0.53
,- Drain 2n3 tne RCE to tne RW5T (vaa the SI recitculation i
- itne). C0.53 ( t . ;)
REFERENCE-IP3 50 4.c. . 50P-RHR-1, ,4
-
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e: PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 24
ANSWERS.---INDIAN POINT 3 -86/08/13-NORRIS, B. ANSWER 6.07 (2.00)
"
' . Turbine trip CO.53 Loss of load interlock (loso rejection of #10% or ramp rate
- decrease cf 5%/ minute) CO.5J
' . Circ water pump running (pump corresponding to the valve pair dumping to that pump's condenser section). CO 5]
i Sufficient condenser .1cuum (at least 25' HG). CO.5]
REFERENC IP3 3D 18.1; F , 5, and 7
ANSWER -6.08 (2.001 Channel R-1 (Central Centrcl Room) C0,52 ; switches the CCR <entilation to the emergenev.n.coe E0.53.
. ' Channel R-5 (Fuel storage butiding) C0.53 ; sultenes fuel storage building ventilation to emergency mooe CO.253 and seals fuel stor a9e ou11dino '
cocrs C0.253 c;.0)
REFERENCE IF3 50 12.0, P. 31 i
ANSWER 6.09 (1.00i a
l To nottiv the operatcr that there is an tnsufficient gas .c lu ne , tthus
full injection of ac c uniul a tor water n* a v not occu (1,0)
}
'
REFERENCE IF3 SD 10.1, C.
- AdSWER 6.10 t2.25)
' If it is determined that there is s steam (or feed) brear, vice a R C S b r e a t. , inside the c o n t a i n nie n t . (1.25)
. By .vsning the na0H cancel pus.mouttom on superviac anel SB-1 in the control roo (1.0).
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P PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 25
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ANSWERS -- INDIAN POINT 3 -86/08/13-NORRIS, B. REFERENCE IP3 SD 10.2, ANSWER 6.11 (2.50)
Dropping below 10% automatically unblocks P-10 CO.63 (By raising turbine load and placing rods to auto). rods step out to the IR (20%) rod stop C0.6 Tave decreases, raising reactor power C0.63 ; a Reactor Trip occurs from tne (25%) PR, or (25%) IR current equivalent CO.73 REFERENCE IP3 50 28.0, pp 15. 16 a 2 ANEWER 6.12 (2.00) Oncercompenssted (0.5) Two concentt 2 c volun es f orm tne detector, the outer volume is boron Itnec ano is sensitive to both neutrons anc gammas (0.5); the inner volume is. sensitive on1v to gammas (0.5). Tne two currents generated are acdeo together to procuce a current equivalent to neutron current only t0.5).
REFERENCE IP3 SD rJo. 13.0, pgs 31-33
.
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. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 26
~~~~RI656E665CIE~66NTR E~~~~~~~~~~~~~~~~~~~~~~~~
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ANSWERS -- INDIAN POINT 3 -86/08/13-NORRIS, B. ANSWER 7.01 (1.50) Oropped Rod - Rods will insert automaticall hisaligned rod - Rods must be inserted manuall CO.5 es.] Operations Superintenden C0.53 REFERENCE IP3, ONOP-RC-1, p. 2; -RCl-8, p. 1 ANSWER 7.02 (2.60's Normal - Boric Acid Tank thru Emergency Gorate Valve ih0V-33) to charging pump suction (0.5i Alternate - 1. Normal boration path - Boric Acto Tank thru FCV-110A anc FCV-110B(0.4) with charging pump speed maximum (0,1)
_ RWST taru LCV-1L2B(0.4) with charging pump speec man.(0.Li
- E.o r i c Acid Tank thru FCV-110A and nanual stop valve Nc. 2?3(0.4) with cnstging pump speeo manimum(0.11 RErERENCE IF3, 50P-CVCS-3, FF. 5-f ANSWER 7.03 (2.50i ic0 F E0.53 te arctect the crvstal in the racistion monitors E0.53 (1.0i intmum - 500 3pm C0.53 na.<1 mum - 7000 gpm CO.51 to protect tne neat exchanger tube bundle E0.53 (1.5, REFEREr4CE IP3 50P-CC-18, . . .
. - . - . .. . -.
.
. . PROCEDURES - NORMAL, ABNORMAL,. EMERGENCY AND PAGE 27
~ ~~~~~~~~~~~~~~~~~~~~~~~~
~~~~Rd656LU5EddL 5 UTRUL
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ANSWERS -- INDIAN POINT 3 -86/08/13-NORRIS, B. . ANSWER 7.04 (2.50)
a.- The RCS has been borated to at least the nenon free shutdown margin consistent with the temperature being msintaine (1.0)
! daintained subcritical by at least 1% dk/k until normal water level (23%) is established in the pressurt:e (1.0)- F (0,5)
- REFERENCE IP3, POP 1.1, F , 1, 2 ArJSWER 7.05 (3.00 To prevent potential t r.t r ocuc t ion of steam into the CCW system ( CO.53 and thermal snock to the RCP seals CO.5]. (1.0i Fcur of five required C0.5 each]
j- RC5 subcooling soove 25 F 4 1. . . Steam pressure stable or cecreasing 2.
4 RC5 hot leg temp stable or cecressing RCS colc leg temp at sat. temp for steam pressure
> Core exit TC's stable or slowly decreasing (2.0>
REF ER EriCE ECA-0.1, Loss of AC Power Recc-ery Withcut 3I Required, p , 10 t
t
.AN5WEF 7.06 (1.00)
! riormal sorsv. E0.3] '
3 2 Fressuri:er'PORV. CO.33
- Avn. Spray. CO.33 CO.1 for correct croer]
REFERENCE IP3 E-3, Step 23
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.
. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 28
~~~~ - ------------------------
Rd6 bl655ddL E5NTR5L
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ANSWERS -- INDIAN POINT 3 -86/08/13-NORRIS. B. ANSWER 7.07 (2.50)
- Ensure both FORVs are shut. [0.5]
- Ensure both spr ay valves ar e shut. CO.5]
- Ensure backup heaters are ener9 i:ed (if pressure <2185 psisi. [0.53
- Check a v ::i l i a r y spray valve (212) shut E0.53 ano either normal or alternate charging isolaticn valves (204A/B) are open. [0.5] (2.5)
REFERENCE GNOP-RCS-2, p , 2 ANSWER .05 .].00 Sch *5> = 45 fen E0.]]
Tctsi lifetime to cste = 29 + 1 = 30 REM EO.3J Total lifetime avstlaole = 45 - 30 = L5 AEn CO.3J Total this qusiter asallecie = 3- 1 = 2 REn EO.3J Q u a r t e r l '. Limit 12 more restrictive than annual limit 0.1 REn/HR g a ni nis + (.2 RAD /HRi(10 GFi neutr on = 1.1 REn/HR cose rate 2.0 HR.~1.1 REnfHR = 1.32 HR$ = 109 MIN CO.5] REn one time eaocsure CO.5J REFERENCE 10 CFR 20
_
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7.- PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 29
~~~~ ~ ------------------------
R 65ULU556 L C NTR5t
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ANSWERS -- INDIAN POINT 3 -86/08/13-NORRIS, B. ANSWER 7.09 (3.00) The coincidence of power range trips requires more than one i sig'nal to tri Not in automatic (rod stop AVG /TAVG +/- 3 F). Manual control of rods is possibl From loss of power to one power range channel (sensing a' dropped rod). Power mismatch coincident with temperature error will cause steam dun.p to actuate (assuming the otner interlocks.are satisfied;'.
C0.75 sa.]
REFERENCE IP3 ONOP-EL-3 AN5WER .7.10 -(1.50) Ccre, Cooling - Red (0.35 each, proper sequence required)
1 Containeent '
- Red Succritics11tv - Orange 4.- Integti Ortnge Heat sink -
(ellow Inventory - Green REFERENCE F-0, pg 3
_____________________________________________________________________
R&A 000-074-5ystem Generie 10 / IF Ari3 WER 7.11 ( .30) ~ (1) one second REFERENCE GNOF-RF-3 pgs 1 &3
._____________________________________________.______________________
MAA 000-03d.-El1.01 / IF c-5G411 i IF . - _ . _ _ -
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ANSWERS -- INDIAN POINT 3- -86/08/13-NORRIS, B. '
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y 4 Isolate steam,to AFW pump .,
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REFERENCE E-3, pgs 1, 4-5
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s . ADMINISTRATIVE PROCEDURES, CONDITIONS, AND' LIMITATIONS PAGE JW
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ANSWERS -- INDIAN POINT 3 -86/08/13-NORRIS, .
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ANSWER 8.01
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(2.00) $i Obtain relief 10.25) within;2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> (0.25)
- NO (0.25) May not intentionally leave a position vacant ( 0 .' 2 5 ) '
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REFER 2NCE -
I P 3 T e c ,,t.i c a l Specifications; Section o.2 and Table o.2-1 4, 11, 12 IP3 AF-El y ANSWEE R E.02 (2.50)
- (0.5)
s' b'. i D N E: (0.4)- and linear heat generation rate t0.4) Restrict power level (0.4) and reset the nign flux setpoints (0.4) E:V using the movable incore detectors (0.4)
EETERENC IF 3' T/S 3.10.Q 1 p p . J3.164, 3.10-13 '
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, Immediately bring the pisnt to Hot Shutdourg c . .
uith RCS Tavg J500 (1.0)
, Prevents atmospneric, release via S/G 11 's S/G tuce rupture were
.td. occur (because the corresponding S/C Atmospherte Relief s e t, t.h i n t 2s scov'e S/G s.atur a ti on pcessure). (1.0s
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e ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 38
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ANSWERS -- INDIAN POIN /08/13-NORRIS, B. {
ANSWER 8.04 (2.00)
Accumulated penalty over the past 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is 89 minute C1.0]
The penalty will be reduced to 60 m2nutes at 1618 on 5/19/85 and then power may be increase C1.03 I REFERENCE
'
IF 3 Tech Spec 3.1 .10-3 ANSWER 8.05 (2.00) To prevent overheating of the fuel to.3e and possible clad perforation (0.3) snd tnus prevent the release of fission productsiO,4)-
, Shutdown the reactor ano inform tne NRC ivia company personnel) (1.0's j
'- REFERENCE
'IP 3 T/S PP 2+1-1r 5-12
- ANSWER 8.0c (3.00)
i - The intent of the original procedures is not altere + ine change is spproved by two memoers of tne pisnt staff. st least one of whom holds a SRC license on the affecteo unit.
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- ine enanqe is documenteo, reviewed bv tne FORC and appioved oy the
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Resioent Manager within 14 oays of implementatio REFERENCE IP3 Tech. Specs., o-13a i
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- ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 33
__________________________________________________________
ANSWERS -- INDIAN POINT 3 -86/08/13-NORRIS, S.
ANSWER BL . 0 7 (2.00) . Stop tags are used to alert personnel not to make unauthorized changes in the ' status of equipmen CO.53 Do not operate tags are used for the control of jumpers and for tagging equipment, valves, control switches, etc. which are
. operable but may require additional instruction prior to
- operatio CO.53 (1.0)
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'. (0.1 for color, 0.1 for proper position)
'rellow - Throttled
. Reo - Open Green - Closeo (0.1 for color, 0.1 for proper position)
REFERENCE IP3 Ap-1 , 5, e
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ANSWER 5.08 (2.50) . Operations Superintendent The ETA NRC CO.33 each] (1.0) . In the event of a olackout, Providing Tecn. Specs. are e s.s t i s f i e o .
} . A trip that is attrioutsole to operator error and component or systen. oegradation has not occurre [0.5 each] (1.0)
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- REFEREt4CE
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- ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 3f
ANSWERS -- INDIAN POINT 3 -86/08/13-NORRIS, B. ANSWER B.09 (2.50) . Resident Manager Superintendent of Power Technical Services Superintendent Radiological and Env2ronmental Services Superintendent Assistant to the Resident danager Shift Supervisor CO.25 each3 (1.5) When a qualified Emergency Director relieves the Shift Superviso (0.5; ' Addition of the Corporate Response organt:atio (0.25e Recovery Manager (0.25)
REFERENCE IP-3, Emergency Plan, FP. 5-13, 5-c, 5-11 ANSWER 6.10 (1.00) Superintendent of Power (0.5) O.2 mtso.gamn 0.4 mrad beta (0.25 each's REFERENCE AP-11, pg 2 a App. B, pg 3 ANSWER S.11 (1.75: Radiation fields 0 :ygen Combustible gas Airborne contamination i a n .- 3 at 0.25 each; Bets-Gsmma.iTLD)
Neutron (0.25 eachi Lesve contsinment Notifv HP (0.25 each.
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---_.----_---------------_-------_--_---_-----------------
ANSWERS -- INDIAN POINT 3 -86/08/13-NORRIS, B. REFERENCE SOP-CB-2,'P35 1-2
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ANSWER 8.12 (1.75) To allow for operational f l e:< i b i l i t y . CO.63 The surveillance frequency does not preclude the option of more frequent surveillances (as~in co it early). CO.553 The tolerances for intervals is restrictive to ensure the reliability associated with the sur.e111ance is not degrade C REFERENCE T.S. paragraph 1.12
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