ML20210P586

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Safety Evaluation Supporting Amends 52 & 44 to Licenses DPR-77 & DPR-79,respectively
ML20210P586
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 02/03/1987
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20210P570 List:
References
NUDOCS 8702130422
Download: ML20210P586 (5)


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SAFETY EVALUAT10f4 BY ThE OFFICE (F FI' CLEAR REACTOR REGilLAT!Cl RFLATED TC Al,ENbi.Lin h0.5210 FrCILIT CrEP/ TING LICENSE DPP 77

  1. FP /t'Et.T!ThT f40.44TO FACILITY CPERATING LICENSE DPR-79 TEkNESSEE VALLFY AllTPONT) t INTRODUCTION Py letter dated August 8,1986, the Tennessee Wiley Authority (TVA' regeerte c.

changes tc the Technical Specificatiers er c'icscl generators at Sequoyal huciect Plant, Units 1 and 2.

This sobrittal was a supplement to the cript.al 14 sub-mittal datec feltLLry 7, 1905. The preposed chances will delete 6 surveillance requircrtr.t. P('d a footnote to allow a reducticr. in f ast start /f ast ioad sur-uillance testing of Emergency twst! Generators, and correct er editrtial r:is te ke. The remainder of the chorses are Intended to meet the guidclir.t! fe r the Felitt.ility Iraprovement Progran, as proscr.ted ty Generic letter 84-15.

EVALUATION Tre first prcposeo change deletes Sorttillence Requirement 4.P.1.1.C.t.4.c. wLich requires verificaticr: of diesel generator start by in/cction of an Engineered Sa'ety Featurt (FSF) sienal coincident with a sir.ulatec loss of offsite power s i5r,al. The applicant's justincetier for the change explained tFet tti loss cf cffrite power signal is two serits telay contacts in series with 6 ttird certact t.t.ich is associated with the actuation of the ESF signal. These cer-tacts change position in order te operate relay ESIAY which c6Ltt! tte correct alignment of itt er.seciated contacts in the rerr.cte 6Lte-stert circuitry for starting tre ditsti generator. The licensee statt!. tiet due to the electronics of tie circuit it'would be extrerely difficult (if not impossible) tc 16tCitete sir..uitaneous operation of these certacts. Because opening of any cr.c cf the three series contarts deenergizes relay ESIAY Prd etcrts the diesel generator, the staff concludtt titre is no additional safety ber.efit to be gained by insuring thtt sir.;ultaneous operatiori of these contacts durino tho tubject sersc"! tote else starts the diesel. The startir g cf the diesel'through operaticr. c' ttr less rf ef 44te power contacts and the E5F cer tect is essured by existino Scr-veillance Pecuirerients 4 E.1.1.2.a.4.b and d which require that the diesel be started by a sireleted less of offsite power by itself and ar.EFF actuatinn test sigrc' Ly itse.it, respectively.

The ste#f, tLerrfere, considers this cher.ge acceptaLle.

There is a change to Survci11erce Pecuirement 4.R.I.1.F.d.C in the br.it 1 tech-nical specification whic.) is strictly editorial.

As currently present in the techr.ical sterifications this surveillai.ct recuirement refers to a non-c.'t+rrt survrillt.rce requirement. The licensee has i. ace the proper correction. TF 4 is acceptable.

8702130422 870203 PDR ADOCK 05000327 p

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iht lictrsee bes also added a footnote to Surseillance Requirements 4.t.;.:.l.r./

orc 4.6.1.1.2.a.5 whose purpose is to reduce the number of cold test start sur-veillance tests tr. tre diesel generators frer et Ictst cr.cc per 31 days to at least once por IU cly!.

All other engine starts crc' 10eoir.g f or the purpose of surveillance testir.g ::c, be precedec' by an engine ic'le stert, followed by gr adt.cl t.creleration to synchroncus speed, synchrcnization, and gradual it.u' ire.

The steff cchcluded in Generic Letter 64-H the* the frequency of fast start tests from anbient conc'itions cf oiesel generators should tr rer't rec'.

This proposed technical sfocificction change follows that guicar.cc cod is, therefore, acceptd it..

The rettaining changes deel s.ith TrA's Pr11 ability Inprovencrt Prcgren or. the diesel generators.

Il t licersee has revised the presertly D isting Table 4.6-1,

Diesel Gercreter Test Schedule," by replacir.g it with a new Table 4.8-1 entitioc

" Pit scl Co.er ator P,eliability.'- ihe net tcble incorporates into one teFit tit particulars provided by the stiff in Tables 4.8-1 and 4.5-2 whicF are certained in the exarole perferrrrct; specifications provicec in Ger.cric Letter 84-15. The prirary feature ci the new table is that it chargt! tFe tesis for the testing schedule from "a per nuclear urit" tesis tc "a per diesel generatcr Letit, u.d tie frequer.cy of diesel generatcr te:stire tes been reduced fror a r.inirSr.: inter-val of 3 days te e rinir.or., interval of 7 days.

The objective cf testing the diesels on a regulor basis is tr' rrsure the DGs' operebility by tirely fe41.ro c:r;tection ond necessary correctivt action.

Such i

testir.s provices a degree of assuranco c' the exeilablility of the DCs ch rirg the stritc4 between tests. Therefore, the (misting DG testing concept is that the above assurance hos to he dererstrated with more frequert testir,g as the number ct LL f6. lurch increases. Thus, the currert TF re. quires that diesels te tested so thet tic frtervel depends on the derenstrated CG performance, i.e., the irtervei shortens as the nuntes cf fcilures increases. Furthermore, thc test irtervel is established corsersatively on a per nuclear unit bosis, rMFrr tFan on a per dierel basis. Thus, improper diagnosis cf a DG failure could poten-tially result in r.:tre fruuer.t testing of all the DGs. Alsr. test intervals that are ter' stcrt cculd have an adverse impact cn CC re.liebility.

Our past experience has stchn that many licensees heve tcer testino their good DGs nainly to cuickly cet tot c' the frequent test cycles irrposec L3 tFe stardard TS. Tie statt and industry consensus is thet cerrent requirements for testirg of socc lgs cc r.cf iroprove reliability of tFr cred PCs and r.ioy be a factor in poter -

tial degradation o' the gerf rfs erd tray have negative effects cr. their overall expected life anc hence such testing is not warranted. Therefere, we concur with the liter ter 's rreposal to limit DG failurcs on a per LG basis rather than on a cr.r nuclear unit basis anc that the. frequer cy of testing a DG will br tette cr.

it' cvn failures.

This is consistcr.t htth Generic Letter 84-15 (Ger:eric !rtre B-5F) cuic'(lire cr. LG rellebility. We fino thest cherges are not detrirentel to the health ar.d safet) ct the public and, therefore, the TS cherce recuest steuld be granted.

Ir 6c'cition, the staf f has for sur.c tire brer evaluating the frequency of LC testing and the mociated potential for srvert ccgredation of engine parts cLe to frequent fast start tritirr The staff concludes thrit ti t.

tsst frequency can tc teduced to mininiize this poter. tic 1 without affecting the overe11 FC retbGity.

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Thereferc, u ccxur with the licensee's pinuel to reduce the test freoterr; for an individuel dit stl cet erator based on the nun.Ler of f ailures from the present trinircri intervol i>f every three oays to e n.ir.inur cf seven days. This is consistert t.1tl. Lentric Letter 84-15 Weneric !tst'r F-FF) puideline en N re".itbility.

Tat,le 4.6-1 also requires that c#itienal reliability retit ri tv. teku wLer, the nun >ber of diesei serereter frilures in the last Fr er 1r.0 Wlid tests reaches a given nut.ler.

TFrse reliebility actiors ir(1c('e a regrtability requireraer.1 to tFr f rC tre a requalification test rtquf rer ent for a DG which has had ar ryrrtr.he rurtt'er of failures.

30 deys is chtr in lable 4.6-1 to prepbre o reper' frr fPC audit. The sartric tech.ic61 specification provtoed 10 Generic Letter 84-15. hev-ever, crly ellcwtc 14 cays for this report 6Lility rte,t'irerrent.

The Stande.rd Ttcinical Specifications currertly toir,9 used in recently licentec plciis or the cti,er hanc allow 30 days to rescrt rr frilures. The staff concludet tLis is not a safety sigt.1ficcet issue, and the 30-day reportirC ret,uireteent is acceptable.

The detailt of tic rrrrrting reauirerents hevc tecr. prcstceo in a new section rur,tered 6.9.2.2, and the detail:, or th re riutilification test receircrrrit tn e tcrr e Ned as an attachrent to Tebie (.0-1.

K1th the exception of the F day repertire rre,t:ircraent, the staff concluce:, tl.at stede sections and Table a.F 1 are consistent uiti. Ceruic Letter 84-15 guideline cr CC rclirtility. He fird these chances are ret detrir.er.tel to the health and safet) of tic rutlic ard, there'cre, tie Ti r.hange request should be gte.r,ter'.

Cl.'jktlil EliTAL CCNOICERAT!nN Tit er tr'er('trents involve charges tc ttt irstallation or use of the faci"tirs' corperertt Iccettd within the restricteo aree as defined in 10 CFR Part 20 ard chances in surveillance recuirenents. The staff has cetcrrirer' that the amendree.tt irsche no significant increase ir. thc ar.ounts, and no significant ci,aig h Pe ines, of any effluents that ray Lt rrienced offsite and that tbtre is r4 51gri-ficant inuecst ir individual or curnulative eccereticr,61 tediottun exposure.

The Conraissior, has Prvirusly issued a proposed findit.y that these amendrr.ents 1 Aulve no significant t6nrn cons.ideration, and there het terr rr gblic ccrvtrt er such finding. Accordingly, tl'e 6r.er.cnents ineet the el191LW1y criterit.fcrc6tegoricalexclusiensetfcrthin10CFR51.22(c)(9).

Perrerr1 to 10 CFR 51.22(b) no eraircor.tntal in. pact stateinent or envircrrrrtel essess-rnent need tr rrt.prec in tunnection with the issu6r.ce cf the arnendrents.

CONCLIJSiol!

ite Contr.isstun inade a progue' de tctrinttion that the arendrer ta ii.uin no significant h6hr6 u t: sideration which was publittt.d it. the federol Register on June 4,1%$ (CC FF MEF4) and consulted with tht st6tt. t,t lennessee.

No public concer.t> wert rtrefved, and the state of Terrettre did nut have any COUT. el t's.

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b'r beve ccr.cluded, based on the constocraticns discussed above, that: O? tttit is reasonable assurance that the health and safety of the public will ret be endangered by Orret. tion in the proposed manner, ar.d (?) stch ectivities will be conducted in cos.witt. rice with the Comissiosi's regulptfert and the issuance of these amendrnents will net te irirical to the comon defense ano security er to the health ano safety of the public.

Principal Coritributors:

.loe Holonich, PWR*A, PPW.f J. La:evnick, PAEi, OFVP-A Dated: February 3, 1987

F February 3, 1987 J

AMENDMENT NO.52TO FACILITY OPERATING LICENSE N0. OPR Sequoyah Nuclear Plant Unit 1 AMENCMENT NO.44TO FACILITY OPFRATING LICENSE N0 DPR Sequoyah Nuclear Plant Unit 2 DISTRIBUTION w/ enclosures:

<;' Docket No. 50-327/328-3,

"' NRC PCR -

Ji Local POR l

NSIC PRC System PD#4 Reading File C. Stable M. Duncan OGC-Beth R. Diggs, ACM T. Barnhart (8)

E. L. Jordan, DECA:laE L. J. Ilarrron, I&E B. J. Youngblood l

J. Holonich 3

l C. Stable N. Thompson E. Butcher W. Jores

11. Thompson, Jr.

i

11. Denton L. Spessard J. Taylor G. 7ech, RII B. Ilayes T. Novak K. Barr, RI!

M. Reinhart, AR J. Lazevnick

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