ML20083M661

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Forwards Suppl Info on Conformance to SRP,NUREG-0800
ML20083M661
Person / Time
Site: Satsop
Issue date: 01/27/1983
From: Bouchey G
WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To: Knighton G
Office of Nuclear Reactor Regulation
References
RTR-NUREG-0800, RTR-NUREG-800 GO3-83-75, NUDOCS 8302010416
Download: ML20083M661 (7)


Text

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Washington Public Power Supply System Box 1223 Elma, Washington 98541 (206)482-4428 Docket 50-508 January 27, 1983 C03-83-75 Director of Nuclear Reactor Regulation ATTN: Mr. G. W. Knighton, Chief Licensing Branch No. 3 Division of Licensing US Nuclear Regulatory Conrnission Washington, D.C.

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Subject:

NUCLEAR PROJECT 3 SUPPLEENTAL INFORMATION ON CONFORMANCE OF WNP-3 TO STANDARD REVIEW PLAN (January 1983)

Reference:

a) Letter #G03-82-1015, G. D. Bouchey to J. D. Kerrigan, dated October 6, 1982.

Reference a) transmitted amendment #1 to the WNP-3 FSAR. This amendment contained the initial phase of the WNP-3 Review for conformance with the Standard Review Plan (SRP) NUREG-0800, required by 10CFR50.34(g).

In those cases where differences between the WNP-3 design criteria and the SRP acceptance criteria were identified in the initial Supply System review, a schedule was provided detailing when the' bases would be presented for con-cluding that the WNP-3 design criteria are in compliance with the Commission Regulations.

Presented herewith is the material promised for the month of January.

In-cluded are marked up FSAR pages to show the changes which will be incorpo-rated into a subsequent amendment.

In those cases where exception is taken to the SRP acceptance criteria a reference is provided to the FSAR section where further information is provided.

If necessary, additional information will be added to the appropriate FSAR section indicated on the marked up FSAR pages.

In certain instances, following a detailed review, we have been able to con-clude based on information presented in the FSAR that the WNP-3 design cri-teria do, in fact, conform to the SRP acceptance criteria. For these cases, with the exception of a change to the FSAR conformance review table (Table 1.8-3), no further change will be necessary.

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8302010416 830127 PDRADOCK05000g

'Mr. G. W. Knighton Page 2 January 27, 1983 G03-83-75 SUPPLEMENTAL INFORMATION ON CONFORMANCE OF WNP-3 TO STANDARD REVIEW PLAM If you require further information of clarification, the Supply System point of contact for this matter is Mr. K. W. Cook, Licensing Project Manager (206/482-4428 ext. 5436).

Sincerely, G. D. Bouchey, Manager Nuclear Safety and Regulatory Programs AJM/ss cc:

D. J. Chin - Ebasco NY0 N. S. Reyonds - D&L E. F. Beckett - NPI J. A. Adams - NESCO D. Smithpeter - BPA Ebasco - Elma WNP-3 Files - Richland A. A. Tuzes - Comb. Engr.

A. Vietti - NRC l

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4 WW P-3 FSAR TApte 1.5-3 Ne1trC. 09n0 e

Net' 1TAMia9D PTVIW PL AN compt.tMort e? MARKS YT5 MO._ !4/ A JREAsAFyAg rRITrelA 3.0.4 Other setente Category I Structuree Ree.1 - July 1981 (cont'd)

I See Reeerk (1) l) Where dif ferences estet between the mur-estan

_tetertehque3tdentrol, and 4 clel Constructten Technteues ertterte end the seceptance erj entitled in 6.

I thte sar, she bases fe Gdans that the W M.)

For Category I structures outsten the centelnment, the ecceptance criterle desten erteert a cameltence esth the casuelecton's for seterfels, aquellty centrol, and any speclel coastewetten tectiefeues are in accordance ulth the codes and stenderde indicated in essection I.$

reevisitandNil be provided by January Ital.

of SRp Sectlen 3.3.3. es appitceble.

7.

Testine em8 faseretco suro t11ence Requirements At present there em se specte1 testing er faserette servellience regulve-3 see tenerk (3)

(2) '.** 3 hee no streeteres estepertred se spretet seats for Cetegory I structures outside the containment. Ilmever whom m etures.

some reeutrements became pecessary for special structuree se requiremente s

are re nsued en a cese-by-case beste.

S.

Ileseney ifelle e cellerle for L. Vuelle tre centelnad la Wfs 4 se tAls I 8ee Bemerk (3)

(3) concrete mesonry wolle are not destaned to seppert eafety related egelyment er pipes. Their primary funetten I

is ehleiding and se terriere for fire preteetten. linwever.

becevee they are en cleos I butidtpos. thee are destance 3.0.5 Peeneettene Rev. t - ny 1,gp oeseetcelly te withetend ese and Dec (from equivalent elette enetyste),

acctetancecatTing g

stt acceptance criterte ter t's deetea ** Misett totagery I foundettene see g n hs

,te,c 4,, h io p p 3,1,,

bued seesine the reimat regnew of the fetie ine reenietten:

p5di it :

M 36 as 'acd c'N ce'O 'IoO' ""4 Ii se efe port se, sse.sn end carei sulen centerten 1 es they reiste te a

safety-rslated struc*eres being destries, fabelcated, erected, and tested n.

ACI 341 twd AISC #dert s31ec! m b che,cak te quality standards centeneurete utth the leportage of the safety functlen sept.

to be performee.

cled ccMC'O to=*g Cgg MptWd pw comeng cenerel Besten Cetterten 2 (Ref. 3) es it reistee to appropriete a

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less to the most seeere of the noteret phenomene b) 9.

considerations helns fcelly reported for tak site and surrounding eree.

gweb m

-La smeccealcaece u% AMST

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t*.at heee been hteter ca suffectet eergin for it.e Itetted accurwy. quent.y. 4,e perles of 94s s,s 74 mak A,,e,Pb =..icA ies enev la which.the hesterical date have been accumuletas, one to thef w.efat..f n.=ei and =cie=t t idttie= wits the g

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Soleseeh.em 3 s.S c.s.4e c.omei =t.i me the =t.rei, hen e e.

efuss J ve. 8.ve.,3 6s teos us.ca 4 A t#e!J.7 i

r s=rei no.s.n crit.erian 4.(nef. e) = it nieta to stru.ctnes. system.

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af.tv seine enreprietety pr tect.d testa t w ces nu up runs t ed WMP '5 stuharstas fleIes.ciudine m offuss.f missiin, pine uhswin.. dWL ser result free egulpment fedures and fres seente l

e,namic.ffu ss in i

E ead cenetstems outside the aucteer peuer unft.

.E ceneret Deelen triterten s (set. s) es et nietes se structurn erstems.

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and componente temertent to setety met botas shoree amene nuclear peuer entse unin e it een he shoun that en n steelse will not egentftcently tapete their ehllity to perfere thotr eefety functions.

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A tmP.3 fSAR TABLE 1.0-3 IRfatG - 0._09 e

e IIRC f?APDApp Rffffw PLAR m m,,I PWEI.MC e,,,,,,

e serbcCterapC certes 1A 3.3.3 Cenerete one steel Internal Structures of Steet or concrete Centetsumente Bev. I a July 1981 (Cent's)

As e fines in *1tetes* unser first tables in $ deoctfon II.S l

(1) $

=

above.

As settnee in

  • metes
  • unser first tables in 5deactlen 18.5 (2) T e6 eve.

t# sere esperfeental testfag te mees for eeftf tcetten of the sesfes. C shell be the oltleate lees carrying copecity of$lte effects one any eleilltues reistionship (3) C j

'which eey estet between the actual gesponent one the test the oesber.

sesel eben be accountos for la the evaleotten of C.

x see go gt (t) g,,,,

d I

ElleriIllCentelamentSevue11 t.

for concrete pov te ns of the eryuell, the ecceptance cettette e

deser&es ne wve.J5 of it= n.s.e.te,ts) n macrimes fee w si.ime nereter (4) The S>lleoe (t) i t pc>srl.i:

apply.

d es.

for steet meestene of m ery=n that resset penom one m m g.y g;c,gq g -ste io,,c.5

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not neceos my etentmi eencrete, the meptone. criteria s l

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stem n.s.stemt) es macrimes fee the eieser terrier orpis, syi. ACI sit med usc ioere esed as 8

l (esti fee the i e mt portte of the ery en N cgbeable<Msi n e. des. "

outil c=

1YT'i'"*ais ewe,e e if the u s reine m e = nt of the ery.en to c m v.s = =n Tke 1

l not en m.e.at h.ios one the,reinem.e cmrete mise" wwe io,e m ;,e oce,Ja,.e4,4W Mst se reis.e..a f.e otra t m i we,.en, th. etratmi

. 4ed i,,

wuptance criterte is the een n for tie. ti) en..e.

N4s.s.s 14 =>in esenb.ns at.

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.es reinf m ement of the ery.e n to t o inates gi.eeg;.et 3.,,3,s.,4 n

oktei orci heart ws if.w.e the e.nl hein one t ese.i,ist.e it.ine oth C) 80 IdeN.

t faces of the.stl are ettlines fee structural perpees, the ecceptance criterte fee item (11) eteve will apply.

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af.ther str.ctnei erste.e are.e.e in the me resten.

the acceptance criterle ore revie-se e.e e cete*Dy-test beste.

(whereettferencesestetttweenthewwp.3e,eten 1,e in ertterne one the seee,tence er h gestertete. Suente Centrol. ene feectei Con _struction Techataset meta that the wwr.3 See Demort (I) this SRP, the beees,, gn,,,,ggene,s,gth the Ceemiset W e The specif tee meteriale of consteactten ene quality centrol progrene areeccepteble if to accereente with the $ 4 11C cose o F

geogge erone will be prootees by Joneevy 99ss.

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e la e d settlem I.6 ef this 54P settien.

special cometeuctlen techntgees, if est, are treates en e esse-ty-case I see asemet O) in na special eenetrue gen technig es are vece.

j teste.

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IfMP-3 FSAR TAKE 1.e-J ELef t - 0000

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pec 97EARD REV1718 PLA8 EMLLA!51 3881AP88 fts no p/a sar/ACCEPTAnct_CRHrstA

\\\\ cud ] deserb et 4ge (MP 3 Jtsap 3.s.s re.ndettene se,. t July 19st front'd) posdtC** e5 tog *y ' cage g[,e g,3yp 3 ges ys.

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co) ACI M.

The Reguietery Guldes and fadestry stenderds identifled in item 2 of thissesution peevides infer.atten, rece.nendesten end guicen WM M AW peve usM as Oe ohicok cless'ose V-I desertbes a bests ecceptable to the staff that soy be esed to laplement theAlso, speelfic c*ede Th.

e requirement of 10 ElR fort Sn. H0.55e. and CDC I. 2. 4. and 5.

lrm. ls k c.... L

.til co lvd wT'dawee acceptance criterte necessary is meet these relevant reestrements of these b) ne 1

re,uieti.ns f.e the erees.I re.is.. deurib.e in ses.ction : et thee ser em.sleee wW /Uuu o+s awe. in occur sorti.= ore es feite.s:

pumy g;K m ;oc m og g I

1.

Descrietten of the Foundetten SAs,Mies. 5.L 3.6.f..

un oud,d g,w -

g ihe escrt,tive safe,metion in the sAs is considene scentaie it it meets c) p,,,,l&3,( J;c g p p.,3 e

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i the stat== requirements ut forth in sec. tion 3.s.,5.1 et s.ou.ietery f safet anei, sis ts f.r licaweg INgf g,

cuiu u0 u.a.e4 f er.et.nd C.ntent d)g leuclear Power Plants.*

ont, ge.3.tokry Guides.

Deflelent erees of descriptfee infermetten are teentifled by the resteuerneu ee unique aster f

end a r.euest for addittensi information is initiated.

asteadord fermet..."

f. tune that are not seastecess ceared la theherevleuerdetreatnestheedditlene!

require a more detailed rovfew,fnfermetten required for e ameningful review of such now er emique desfyt

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feetweet.

(t) t.shere differences estet between the terr,1 4refse 3

3 gee'asemet (t) zieerts~ldentified in

,Appj.he61e tedee. Standsede. and Spectf tcettens enetedtne thet the Wur.3 eviterte end the seeereence 1

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toetg.,.thebee thee seP i i n's The design, esterf ate, febelcetten, erectlen, inepectlen. testing, and

.ne.iii,re in ee.,t g e.e).Ith the,.ca.m ss o a

d t

ered by e,_ided.,,enuer, i codes, sie<erds and gui.etsetc Category I foundet. ens see cov l

surveiltence, if any, of s s t,et.re.iiher e.iic ie u their.nti ni, e

A flot of each documents is contelnad th sesec-er in pettlers thereof.

!= edditles the documents IIsted in tien 1.2 of the 5er Sectfen 3.3.3.

eubsection II.2 of Ser Sectlen 3.0.1 are ecceptable for the contalsment foundotten.

Nur 3 settef tes Nee eastetnettene Iteted in 11.3 et ser I See Sommet (2)

(2)

Cemeinstlene referenced in subsectlen 31.1 et ser 3.3.3 3.0.4.

3.

Leeds and toed toejs nettent gge, es crete gentagna,nt fenndesten) are not oppsteette.

The specified feeds and. lead combinettene tened i.n the desfon of sefeeft la re.u t i. if feu.d t m. u =ceedence ita l

e Cate.ory i feundati-these continettens referenced in seswtfee II.3 of $ar Sectlen 3.8.1 and with these cochlaettens listed for the contelement foundettenla s esettlen II.3 of SA,SectIen 3.8.4 N ell other selenic Category 1

[, ig foundottene.

la additten to the leed coetastiene referenced ebees, the reelnellene 3

i.

esed to check egetast sildted and seerturning due te eerthquetes, winds.and tornedos, and agelnet fleetetten due to fl i*

L C:*

If in accordance vita the fellentes:

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wup-3 FSAR TABLE l.a.3 IsUerc - 0e00 IMic STAMDARD REV!FW Pl.MI g w t.1Aset er*ARR9 TFs php N/A Str/ ACCtrTANCE CRITTRI A l

Rev. 2 3.11 tavtreoriental Quellf tcetten of hechenicet And stectrieet Equipment July test (Cent'd)

Beguietory Gufde 1.48); Iff t 5td 382 "Golde for Type Test of Class I tiectric peoulatory Velve Operators for nuclear Power Generettng Stettens" (augmented by Guide 1.71); ead lif t 5td 381 *5tandard for Type Test sf Cless 2E Ilectrle Ceties, fleid Spittes end Connectlens for Nucteer Power Generating Stettens*

(sur ented by Degulatory Guide 1.131), ere, specific with regard to tspe test ffe detailed quellficetten of the equipment identified in their titles.

cr4erle contained In these decments as ti.ey reiste to entrennentel queltf t-cellen should be used in conjunctlen with the more comprehensfre crf terle of Intf r.-0M8 for evaluating the respectlee equipment enviremental quellffcellene.

Ifft 5td 317. *tlectric Penetretten Asseshites in Centalment Structures for g

Mutteer Power Generating Stettent* (sugeented by Beguletery Gulde 1.53), Therrfere, contelns generet guldence for quellf tcetten of penetretten esseselles.

this document es et reistes t. wlrennental guellf tcetten should be used in conjunction with InfatG-0588 for eveksting the ensfremental quellffcatten of this equipment.

I See Somerk (1) (t) presently, lett standerde 301. 335, 627. 66e end 650 have I

In edditten. Ifft Standards 301. $39. 427, 649, and $50 con be used for guldence

. net been need for guldence purpeees.

purposes even theech het has not formerly endorsed these standeres through the g

tesvence of a Regelstery Gulde.

The effects of the cheelcels should be addressed for the eeutpoent queltficetten.

3 The concentratten of cheetcals used for qualificetten should be equivetemt te er more severe then that resulting free the most Italting mode of plant opere-If th e (e.g., contef reent spray. ECC5 inttletten, or rectreutetten phase).

the cheelcol compositten of the cheetes) sprey can be effected by egulpment malfunctlens, the most severe cheelcel envfrennent that resvite free e single f attere in the sprey system should be assumed. If only deelnerallred water spe sy to used then the effect of the deelnereltred water sprey should be included in the egulpment quellfftetten.

Bedletten dose and dose rete used to determine the rodfotten enetrenuent e er 3

.e.all be based on utC guelliteetles of electrical and mechenteel egutpeemt l

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steff approved seurre term and methodelegy es dissessed in IIUREG-0500 and The redtatten surf teented by Sectlen 33.8.2 of NuefG-0737 esti NWRfG-9718.envtroement shall be eased on the integrated effects of the normally espected 1

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redtatt a enetromment ever the egulpment's instelled life plus that assocf.

i sted =lth the most severe desten bests event during ne felle= tag whfCh the I

I' ogufpment is regelred to reesta functlenet. Effecss of the Sete redtatten (ffect of recircute-

)

shall else be considered in the quellficotten progree.

tory flute shell be considered for the oestyment located outside the contetseont.

oeE IIILD Ikv1MISEHf a

The ensfressent.et guettfleetten o.f all elect. rice) and machenteel egulament

)( s see sommeh (a) (3)

In.ere etfr,re

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e,lte,ie end t.nces estet between she-usrf'3 deele.

,e e.,e,...een,e e ide.tified..

iecated in the iid.neit.m ont i secept ai if tm feiie

  • e erec = ce thle 997, the bessed eensleding that the upt.3 Is felleued:

deelge e Comteeton's e ore in comptiones with the,e3.

one will be provided by Jewery 3 rese f

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fntC STANDAPD PEV!tU rf A'8 w

COVLTANCE SRP'ACCEPTavCT c? N nI4 YE$ NO N/A RD* As ers 9.1.3 Spenc fuel Pool Cooltr.4 Ami Cleanup System Sev. 1 - July 1981 (Cont'd)

(2) Sultable red W ascy of components 50 that safety functions can x

be perforeed ass aing a single active failure of a component coincider.t with the loss of all offsite power.

(3) The capability to isolate components. systems, or piping, if x

required, so trat the sys*em safety ; unction will not be comprcaised.

(4) In meeting t H s criterion acceptance is based on the reccmmen a-X f' '

a d

-, i em

,E tions of Brasch Technical Position ASB 9-2 for calculatica th beat loads and the assumptions set forth in item 1.h of subsection !!!

m.. ; p i i.

w g of this SAP section. The terperature Ilmitations of the poul

' ll water identified in item 1.d of subsection III of this 54P section i

Is also used as a basis for meeting this criterion.

i e.

General Cesign Celterion 45, as related to the design provisions to x

permit periodic inspection of $4fety-related components and a utpment.

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Cencral Cesign Criterion 46, as related to the design provisions to x

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permit operational functional testing of safety-related systems or components to assure structural integrity and systes leak tightness, operability, and a equate performance of active systes components, and the capability of the integrated system to perform required functions during norsal, shutdown, and accident situations, g.

General Cesign Criterion 61, as related to the system design for fuel x

storage and hand 116g of radioactive materials, including the following elements:

(1) The capability for periodic testing of components important to l

safety.

l (2) Provisions for containment.

(3) Provisions for decay heat femoval.

(4) The capability to prevent reduction in fuel storage coolant inventory under accident conditions in accordance with the g idelines of position C.6 of Regulatory Guide 1.13 (5) The casanility and capacity to remove corrosion products.

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radioastive asterials and impurities from the pool water 49d reducing occ.pational enposures to radiation.

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