ML20037B063
| ML20037B063 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Quad Cities, Zion |
| Issue date: | 08/05/1975 |
| From: | Goller K Office of Nuclear Reactor Regulation |
| To: | Abel J COMMONWEALTH EDISON CO. |
| Shared Package | |
| ML20037B061 | List: |
| References | |
| NUDOCS 8009030766 | |
| Download: ML20037B063 (7) | |
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O AUG 0 51975 N
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corr o:.t.ecit h rdi ren Cem;.cny
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Fr. J.
- 5. Abel, nuclear I.icensing Ad: inist rctor -
Loiline i?cLcr teactors Post Office Fox 767 Cnicero, Illinoir 60 % 0 Re :
i;resden tr.it s 1, 2 cnd 3 Cuad Citics t-nits 3 and 2 Zier Unit s I cnd 7
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Ger.1 le.ren :
IC CFF l'crt 50, Appendix J, Pri:ery Ecoctor Contcin-ent I ce ht.rc Testint fer Kater-cooled Fower Ecactors, t.as published Februcry 14, 197..
Since reny nuclear plants hcd citber received en overct in-
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license or their contain.-ente had rceched advcoced stages of decirr.
or cor.st ruc t ion at that t in, so e plants may not r.ov be i-full' ca.?rliance with the recuircrents of this regulation.
Ycu cre requested to detert-ina if you.are cenduct inr cent s.ir.t.cnt leekare testiny in full compliance *.ith Appendir J.
This deter-instion should include the identificatien of rey design tentures thet do not pe re it conforvance with its rec.uirerients or existine. techr.icc1 speci-fication racuircrients trich are in contlict with /.ppenuix J (i.e.
less restrictive than).
It should be understood thtt chi le a cor.tain.cnt Ic.akace testing progran rey be in cot'pliance with the technict.1 speci-tications for your f acility. the Progre ney not be in confarrar.cc
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l uith Appendix J.
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?! yeu r.re not in full co.plienec, you theuld identity your r:1:nred l
cctiar.s ned oc'wcule to at t a in cor f or-snce to the l eraltt ian.
Ieccible cour8er of act ion it.clede s m.
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00~.emccalth Lc:isen C(epany 2-AUG 0 51975 Please subnit tbc results of your study to us es soon as fossible be:.
later than 30 days fro-receipt of this 1 citer.
ne 1his request ter generic -intoraation was approved i;y Ge0 unavr a blanket cicarance nurber I.-1502:5 (r0072); this elecrar.ce expires July 31, 1977.
r Sincarely,
'Originafsfgned by R. A. Purple
@ P:rl R. Coller, s.ssirtant 'Ji rec t d r U
for Operating teacters Division of Pecctor Licensin;
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Fnclosure:
tippendix J cc e/ enclosure:
fee next pane i
DISTRIBUTION NRC PDR Local PDR Docket ORB #2 Reading ORB #1 Reading KRGoller TJCarter DLZiemann RAPurp1e inliggins' PW0'Connor RDSilver R!!Diggs(c) l OELD OISE (3)
ACRS (bQ/ D MBFairtile DEisenhut
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-Commonwealth-Edison Comptny-August 5, 1975
)
. ce v/ enclosure:
- r. Charles Whitmore Allen'Lavin, Esquire-President and Chairman Chief Attorney j
Iowa-Illinois Gas and Metropolitan Sanitary District Electric Company of Greater Chicago.
206 East Second Avenue 1000 East Erie Street Davenport, Iowa 52801 Chicago, Illinois 60611-John W. Rowe, Esquire Waukegan Public~ Library j
'2' Isham, Lincoln & Beale 128 North County Street-Counselors at Law Waukegan,-Illinois 160095 One First National Plaza Chicago, Illinois-60670
' Anthony 2. Roisman, Esquire Berlin, Roisman and Kessler 1712 N Street, N.
W.~
Washington, D. C.
20036 Moline Public Library
_L 4 504 - 17th Street Moline,, Illinois 61265 Morris Public Library 604 Liberty Street Morris, Illinois 60451 Com=onwealth Edison Company ATTN:
Mr. Byron Lee, Jr.
Vice President ll Post Office Box 767 Chicago, Illinois 60690 Robert J. Vollen, Esquire 109 North Dearborn Street q
i Chicago, Illinois 60602 Mrs. Eileen Jenkins j
7803 - 40th Avenue Renosha, Uisconsin 53140-Mr. David Dinsmore Comey Director of Environmental Research Businessmen for Public Interest 109 North Dearborn Street Suite 1001 j
Chicago, Illinois 60602
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D.3 RULES AND NEGULATIONS sion. The prcro:cd ruk wc.;*d r.et wv required the repertir.g c! such mforr.n t'on unless atttrnp*.S to ref' te the b.-
J mEe rate of poor ICNk-tKh! C tmper.tr..
Iki>d to meet in'n.rnum le&i-CihtnS t.ccrtar.ce critertr.. T1.c. etmporxt:-
U. m tcurcd f at.:. '. d.Jimcn's rGair in erder tc meet s';:.w:X.e !en.s e.s* I!mits sill be scent.*ed and the O-cine reductions in lokage rate va;a resn' ting frem srh ad;mtme
- .s v.C. be repcrted to the Comrnmon. The Ident:-
- cation of suth components M*J premca the AEC with a sounder her.1 fcr judn*.;
whether cr nct containment lea h e rate. could have been exce ded in the unhkely event a design twas accident were to occur, In adc;tscn. such identi-Scation may provide ins 4ht into the ire-
=
Title 10-Atomic Energy cuency and kinds of a<!Justments being made to comMnents to meet the rmn.-
mum acceptable leakace
=.ita and a.
COMMISSION buis for cather estabhshing a more fre-PART 50-UCENSING OF PRODUCTION quent containment leakage test schedu e.
AND UT1UZATION FACluTIES cr rnodifying or replacing components.
Reactor Co'itainment Leakage Test?ng for VAth rers.rd to item W above. the Water Cooled Power Reactors rule act forth below specneg c.tena g, which the licensee mr.y.or certs...
On August 27,1571.the Atomic Energy gs;ety.related syncms temporarily d:s-r% = minaicx1 published in the PED 1aAL pense with drainage and Venhag to Con-Ractsraa (36 FR 17053) a proposed tMr ment atmosphere den =g Type A amendment to its regulations in 10 CFR containment leakare tests. The propomd Part 60 which would specify the mini-rule had spectned that all sysm wh;ch mum conta1= ment leakage test require-would connect d!&ctly with *.he coctain-ments for water-cooled power reactors.
ment atmosphere and would teco:se an Interested par *Jes were invited to sub-extmfon of the containment boundary mit written commenta and suggestions should be vented to contMement. Strict for conside:stion in connection with the compliance with this rule wedd have re-proposed amendment within 60 days quired removing cc-taan matety-rchied after publication in the Panamaa Racts-rystems from scrnee fer the durat:o of Txa.Upon consideration of the enments the tnt and sou d hm t the perfor=atee received, and other factors involved, the c; the overall interrated contn:nment t'ammiadan has adopted the proposed leakage testa to thor,e times when there amandmmmt, with certain mod 1Scations would be no fuel in the resctoc, '?.is 2n the form set forth below, procedure is considered to be unnem -
M gm hnt differences from the sari:7 conservative.
amendment published for em-ent aret The inclusion of all safety-related rys-(1) Modinaa.tian of procedures govern-tems in the overall integrated costu.n-2ng contM-ant inspection and leak de-mest leakage test can be accomphsted taction surveys, as a prerequisite to con. while the reactor is fucled, and in a state ducatar formal leakage testa, and clans-of potential criticality, by mai fM-**g etaien d the basis for reporting pretest the t*.inimum number cf safety-re!ated Isakage values to the Cne--*% (2) erstems in t.n operab:e state until sal establiahment of criteria for deferring erstems are tested. Another option is to cartain safety-related systems from res-periodically teet the contai =ent isola-ularlr achadnied Type A contMnment tion valves in these safety related rys-leakage testa, (3) tucorporation by refer-tems in accordance with the rule set ence of the r~ently-tssued American forth below. ' Itis would raso assure that N=Manal Standard for leakage rate test-the requisite level cf plant estety v'.:] be 2ng of occta:n=ent structures for nuc: ear provided during the costal:=ent leck-reactorr into the regulaUon. (4) inclu-are test procrnm v-tthout ce=promin g sion of nitrosta gas aa.s suitah!e ter'4:s the recurements fcr tr.e:uding all rys.
Enedhm for tes*.ing tho *.caktightness cf tems vt!ch penet r.te the ecuttinreant va2vec. and (6) !=clusion cf 1:T.ter-led-tc*.md ry m the Iec.hcre te-;
age test and acceptance criteria for con-The preposed IVe recured the use cf tainment isolatMn valves which are test methods described in picposed sealed against sentenment atmosphere American Nuclear Society Standard A.NS outleakage during a design basis accident 7.60 by referencmg a portion of the pro-condition by means of a 3eal-ws&er sys-posed standard. On Mrech 16,1977,the tern. In addition, editorial and format Amerteen National Standeads In*titute changes were made.
approved ANS 7.60 and ot5etally issued With regard to item (1) aheve, the it for use as AFSI N45A-2970. k:erican ru:e set fcrth below racuires the licensee Nr. tic =cJ Sts.= dred. "Ixakre hte TcM.
to identify spe:.!Scally those compore=ts in: of Contunnant Sruer. u fcr Nu-whose init:a! poor ler.k-tightschs pat. Ler Feactors." Tne standa :' has been fomusnee p:Tcluded ccmp;etion of s,
redewed !cr ec=ptttn:ty v.th the pic-Type A costfr e=t lerkace tert s.nd tc posed n::: tmd 1* m M:c'uce'i that m-report this informatien to the CGmmi!- Cc p:?: Lc; ci th; TC;u remt:M cf A.'C PtDEtAt bag 45Trt, VOL 3s, NO. 30~WrDNt5 DAY, FrtsuAtY 14,1973
CM RULES AND RECULATCNS
.W! +-;C by referer.ce s cu;a e.ha.-Je minimum recu!rements for periodic teri-
- 3. " Cents:r.rner.t 1sc:sucn valve ^
P. ear tLe t CrJ cf co tai *. ment len test;ng. ficauen by tests of the leak-t:ght integ. any wu em ta rmee upon to per!crm a containment tactatien functica.
Accer".*.g;7 the ru:e set ic*th belcw tow rity of the pr1=ary reactor containment spen".*e t'.At the Type A conter. ment and 6ssociated systems for water-coo!ed E * ** * *** *** ** 4* 7 W^ ~
Iestace testa shC1 be ccnducted in ac-power reacters and the acceptance cri. $ [."a$"a [c(.#**$:b ' bl r.
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i c0*h.*.,*e Mth the prov'J1Cn3 Cf ANSI teria for auch testa.
n O. and im re pecuniy.
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Purruant to the Atomic Energy Act cf D. "14arar. rate" rar teet pur;mee ne that
- ._. t.e ;n;oted rt;e li=;ted the 1eM'E' 1954. as amended, and sections $52 a.nd I'6A'i'* N 0"C'm*tannc!:m M M
- P "*
- i' Cf ' ' 8h t 'f * * * ""
- tC.g =t'.au:n for reactor centrer. ment 553 of utle 5 cf the United States Code.
- * *# ""* L* "* 'E' **
- 3 * * " ". t,.. c e a:.at.:: vn:ves to air. which is s'. del 7 the follow 1;g amendment to Title 10*
teet pransure that escapes to sr.. c-t.wd : the co=tadament lesktie testing apW I.
of ral Regulations, atrncephere during a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> t t pertoc.
pn>rarn. However, the tse c' ::tregen Part 50. is pub!!shed s.s a document sub-E overa.: integrates lutare rate" menu Eks lcr TCre lestage testing is n;so tech-LXY ut!.sfbctcry. Acccid:rg:7. the rule ject to codia. cation to be effective on [h**[,'fr Skth*tt pS ur set Icnn be;ow specia.ee that e;the-Sir March 16.1973.
age path. inc:uett; mnta: cme =t a. es.
or nitregen may be used as the tes*3.g
- 1. A new paragraph (o) 18 added to va.;ves, ett:nga, and componenta ahich pece.
*** L**I^ " ' *-
=e<at:.10 the conduct of the v a:ve lesk* I 50.54 to read sa follows:
F. " Type A Teats" muns testa intended '.o sse tes.4.
O.e :Ce set forth below expands upon 6 50.54 Conditions of heen.co.
meneure the primary resetor centat==ent averan integrated leatage rate (13 arter the the r,equ.irement.a.ontained in t.he pro-c oontainment has been completed and is ready A+e
- n. e for tes valves, sea.ed with (o) Primary reactor containments !cr for cperation, and (2) at periodic interva:s water.rc= a seal-water gynte=, by in' water cooled power reactors aball be sub-there af ter.
c!udir.K m'*"*u:n water tes*. preature ject to the. requirements set forth in G. " Type B Testa ** means testa intended to cet,ct ioca. ient. and to men.ure ienta,.
and test &ccep*.a:Ce criteria.
Appeneixa, acicas each pressure-con:alning or laatap-O.e preposed rule required that the
- 2. A new Appendiz J to added to read um: ting boundary for tne rottoning pr:=a.ry vCves be r.itMted to a seal-water eys-sa follows:
nactor con.4:nment penetra ons:
i tem cpers.t.;;ty test to estar.12 that Arraum J
- 1. contament pu.crauons shoee ca.gn
- ', * *p njginn",*g'g*g'g"[N*
the valves co;//.d be antisfsetcrtly pres-i su ;. zed W.th sed-wster. W.ere was no rauasr atactos currarmetwt taaxact nar- $$#
3 recal".-t to meut.re the rate at which me ros wma-coos.as rowsm aucreas pnam be::ow and extrica: penetrau ss r.tted with tenit;e meta: eaa; manerntises.
wr.ter leaked Ds.st the valve. It h&d been
- 2. Introduction,
- 2. Air lock door sen. soc:uding door operat-saramed that the ses;-water inve=*.ory II. ruplanauez of terms.
- o'r.d be adequate to ses: the va;tes III. tenknee test requirementa.
Ing mechan:sm penetrations shsch an part of the containment pressure boundary.
aC11 Lit outEtak&ge of C00talLOent A. Type A test.
- 3. Doors with real: lent seals cr gaaleta es-
&*.=odphe*e during the desigt b&sts s.cci.
- 3. ' Type 3 tert.
a me c test.
cept fw eendwomed amm dent ec:daticn. However, the itek cf a
- 4. Components other than thee listed in a;eci*.c water 1:VTOtcry CMteric against D. Periodle reteet schedule'ta.
11.0.1. II.G.2 or II.OJ which must meet the IV. Special test requsroman which actual vdre lea.kage rstes would A. Containanent mod:Scations.
acceptance criterta in IIIEL be =es.sured. cculd restit in'an inade-
- n. Multiple testage. barrier containmenta.
E. "rype c mests" means tenta antended to WJate Supply of De&l FEter IC; va2Ve V. Inspect. ton and reporttog of tests.
measure containment too:stion valve tenange rates. The containment laolation valves in-Seth0C w".th attendatt loss Cf tht: Con-A. Conewt inspection.
tal".= t r.1 1%ol&t1CO functiCO. AccC;d.
B. Repet of test res% tits.
cluded are those cat:
- 1. Provide a C1 rect ecnnection beteten the M.& *TCV. alm haa M M "pC;tted I'*
E "**
N*
mary nactor ecntainment vnder normal op-10M the r'L.de set forth below wh1Ch re-One of the conditions or a:3 c perat'ng erstion. sue u purre mLd vent:Jauon.
C'**es tht* the valve leak &ge rtte ahdl Ileenaea for water-cooled postr reactors as vacuum re:let, and instrument vn:ves;
.C. ex:ee 4 the set!-water investery, on spec 1 Sed in I 6044(o) is that primary re.
- 2. Are required to c3cee automatically upon
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the ar.=pt:o that the aca!-water gys-actor containments shan meet the contaan. nC41pt of a containment ladation signE *r.
te=". W be preestriEed for 33 days St ment leakage test requirementa set forth reponse to contro:a intended to acect con-11C percest of the calet.hted peak con-in this appendia. 'Ibene test requirementa t*1". D*Dt 1*oisucmAre required to operste interw.ittent.ly ts.tL= tat 13ternal pressure related to provide for preoperational and period 3c vart-3 the W basis accident. W!th the in.
- r. cation by terts of the leak. tight integrggy under postaccioent conditions; and clur.ics of this reprrwmt, the requ'*.t.
of the primary reactar canw==nt. and sy
- "8 ^88
- 8CPCD*nts which penetrate cca-
- 4. Are tn main steam and feedwater ptp:rg
~.;, ;cy ecce.act::: Csly a r s3-wster "y* Tic = Caer&d:::ty ta.t were e.e.,g,at.d.,,,nroent,o,,f wa,ter. cooled power,,reacto,re, and,other, systems wtle,h penetrate con tat g
,,t, 3,,
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1,,,,.,,,3,
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l Cc ta1L=ent la provided for water
- euch testa. 'Ibe purposes of the tasu are to nactora-I COCled power re&ctors to prevent Un-assure that (a) leakage through the pr!*
I. Pa (psj g.) means the calculated peak
(
CcatrCEed rtlehbe6 Cf r&d!Cf.Ctive =a-mary reactor containment and rystema and containtment internal preerure relatset to 12e ter.als to the en nrot= est if the components penetrating primary contain-daign buts acetdent and spectned eithe in
.snent than not exceed auovable leakage rate the technical speciacation cr amoctated taaes.
12**.271 p*CV.ded by the fut1 Cl&dding values as spectaed in the tectatcal spec 1*
J. Pt (paig ) mea.ns the conta mnt 3,g ;g,g g; coc1gst p;geg;;g DCundar7 ens or easociated bases and (b) periodte vessel reduced test pr=wure selected to snea.a.
- r. a 3.h:*.* d be bitbched. Teg*d:"-C the re&ctor M
- W 6 N h *E' W*
m W integnted leakage nte during pe.
g,;gy+ - t fo;1eatagg he;;g to g,g,gu;,
trattons and toolation valves is pertout riodic Type A tests.
so that p?oper matatenance and repaire are K. La (percent /34 hours) meu.a the ma=1
,,,p e.owable testare rate at pressu.re Pa
'&-,/L% age Cf the pri=&ry rtactor made during the service life ot' the contain.
mum s'a ed for precperatior.M k.:.a in Os CC L* * '* ~ e".I End a&&OCif.ted Eyl*.e=.3 13 ment. and eystams and cocponer.ta p he'd stth:n a;;cwsble :ea.hage rate li=:ta rating pr'. mary cenw nTn-nt. These t'^
technical spect cauer.a or aunctates taas.
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a.s sW*.ed in the tech-ical speciacations requ:r manta tray also be used for g""
and as spec:ced for pertocte testa in the cp.
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cr s_uoc'.a'ad bases of the lice =se:
1eakage test requtrementa in techntes! rpect.'
1"
'***D18'hl'8
- PPF P"***
- L*""
ersting lice nse.
3' D1 (P*#5*"*/2' h*"")
s'gu lemlage rate at pressure,"Pa. as spectied I
sb) Periodic survelllance to pe-for:ned neauces or -ated bases for other typee to a. wart proper Ina20tesa ce End leak af nue; ear power reactas.
In the techntesi spec 12 cations or associated rep &lr dur! S the life Cf the Contain.
IL EzrLaxaTrow or Tsus bases.
g,,ent; g.3 M. Lt (percent /24 hours) means the Inn.xi-A. " Primary reactor containment" mear.s rnum c:owshie Inun rate at pr== Pt l
(:: **he C:sta*-ment vt11 cc tinue to u..tructun or,e e: eat enc:o= ee ec=.
ponesta of the reactor coo;snt prwa m der:ved ficz the prec xrntional taas deu l
e c.;,,*7 *,,
2c 13_.e. ~-...s,,.,,
-+
- ~ "'
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Imundary, na deaned in 3 603(v).and sense as specifed in III.A 4.(a)(111).
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&=c d=est wh th f:00*n p-o-as an eenentianyleal-ttcht benvier scsinat the Xre Ltm (percitt,24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) =can.s v.d y u-Jf 0 = recairtrnetta I:7 c::t&i = uncon*.roned rteeme of racoactivt:7 to the the total measured cents nment 'eatare rues at pmem Pa and P.. retpet:ve:y, c,hwne:
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- .e -1.d; Lee ter*'ng. II &".es the enetrunment.
stI.At LWGrM, Vol. 34, AC. 3WWIhEtDAY, Fit 4 ALT I4, l'73 f
I I
I
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RULES AND REGULATIONS 4.M from testing the cor.tainment with cCrr.po. tems shdi Iso dralned of water or other $uids (b) Accepf o ste crifettN(1) Rdfkrfd nents and systems in the sf. ate sa clone as to the estent necemary to assure exposure of pressare tesis. The 1*skue rate Ltrr. stC1 re praCllCal to that ahtch woLtd estet undar the system containment 1solat1Cn valves to less than 0 7: Lt. If lacM leakafe memre-cesign basis accident concluons (e g.. vented, contalement air test pressure and to a.ssure inet.ts are taken to efect repers in crder to dratned. f. coded Cr pregur12ed).
they will be subjected to the poet.nocident rief t the acce1%tance criteria. tisse r".ea9Hv+
- 0. Acceptance critert'." means the stand. diferential preer.tre. Systems that are re. menta shall be taken at a tatt preature I" ard agalsat which test results are to be quitvd to Innlataan the plant in a safe con.
(2) Pesk pres *ure testa ahn.11 te cer.c.m cc= pared fcr estat:1ahirig the functional me.
41 tion during the test than be operable in IAm shall be less than 135 Le, II ;ocal ;e.a-ceptabtiny of the containment as a ieskage their normal mode, and need not be vented. age inensurements are taken to efeet Ft;s.O 11Td!!ng boundary.
B?otems 1. hat are DCrtnally f.1 ed with Dater" in crCet to rntet the acceptance cf.ter.4 M. IJ.aKact TEaTING E14171aEMsferS tions, such as the containment heat remosal pren.sure Pa.
A prCm7&rn con 41 sting of a Tchedule !Cr cen. system. need not be Vented. Howeter, the
- 6. Additto34! Require?".ests. M) f at*
ducting Type A. E, and C tests shau te de.
containment isolation Talves in the systema peric4tc Type A test fs11s to meet the spf...
teloped for los.k testing the pr:ttery reactor de3ned in IIIA,t.(d) abau be tested in ac. etMe accepunce crite's in II:JE f t). t? e ccnutnment and related systems and enmpo.
cW== with III C. The zr.easured leakage test achedule ap;.ucable to suosequent Tne menta penetra ting primary cor.tainment pres. rate from these testa shC1 be reported to the A tests win be reviewed eld approved by the sure boundary.
Commiation.
Commlaston.
I'pon completion of cons *.ruction of the
- 2. Corwf act of tests. Preoperational leakage (b) If two consecutive period 1C Type A prima.ry reactor containment. including in.
rate testa at either reduced or at post pree. tests fall to meet the appucab;e acceptance stallation of au portions of mechanical.Cu14 sure. aban be ocnducted at the interials criteria in IIIA4(b). notwithstanding the electrical, and Instrumentahn systems pene. specifed in IILD.
periodic re.est schedule of III.D a Type A trating the primary reactor conNnment
- 3. Test methods. (a) A3 Type A teste sha3 test scan be perfortned at each plant abut.
pressure boundary and prior to any reactor be conducted in acccidance wim me pmen. down for refueling ce approx.imately every operaung period, preoperational and periodic alona of the American National standard 18 months. whichever occurs f.rst. until too N44.4 1972. Y anhre Rate "Itsting of Con. consecuuve Type A testa Enett the scaptance lenlage rate tests. as applicable. ehan be nt ctures for Nuclear Reactcm. critens In M.AM. a%er w.%ch um W conducted in ucordance with the following:
March 161972.s De method chosen for the retest schedule specited in IIIE. may t*
A. Type A fest-1. Pretest ecquirements.
(a) Contain=ent inspection in accordance InJtM test than normally be used for the reru med.
p,7 agge g,,,
3, 7pp, 3 g,,g,,
wic V.A. shan be performed as a prerequisit*
(b) The accsracy of any Type A test stan
- 1. Test mef 4ods. Accepable means of pc.
E."e'n%C"Otte il"au^on"O*E"'o*"n*
6" -18 457uupr*=nat. An -pt.
r-ming a pnopemana2 and petedte w a e me od la described in Appendia C d B Wa McIA tainment inspection and the performance of M
N aupplantal test (a) h=e pon W halide kathch the Type A test no repairs or adjustmenta s
aball be made so that the containment can o nduckd W M.
Othed (w y othe equivalent ten NMs rm n es
.s accurs a y e such as Insas spMtmeter) d a W chame be tested in na c1cse to the "ma is" condition During the period between the
- D*"#* I" 3**D*8* **** ****
- ID* TIP*
- D"' ne"88""8'd
*D
- 1' "It"# technicas P
"PP as practical' f one Type A test and tbo tnitia.
cc=pletion o and supplemental test. Resulta from this mat cuid rpectaed in the uen a c. containment inspeeuen for a.
"PP ****'d '"' " ***'P t* *3 ' P""
- P"22**""* *' u. mat,d bases and con.
subesquent Type A test. repaire or adjust. the difennee between the supplemental test structed as part of individual conwment data and the Type A test data is within 025 penetrations.
( r 035 Lt). It resulta m not within 025 (b) Measurement of the rate of pressure 1
I t
spec 12 tb ni
^ (*' '25 W "' "n aan w dau. % a a, u,t annan a ao em.t.%t spumeauon m..oon as pracum aner id.n.
. ed.
rrecuw action taken. and a sec. penetration proerurizal with air. nitrogen, tiacation. If during a Type A test. Including 8WN of pneumaue culd rpn:1ed in tM technxal the supplemental test specif.ed in III.A.S.(b)*
pctantially excesalve leakage paths are iden.
(c) Test leakage rates shan be calculated speccanot.a or amaociated tanea.
uf.ed which wiu interfere with natisfactory using absolute valu e corrected for 1mstru.
(c) Leakage eurveinance by ~~ of a
- #'I "'*#*
compleuon of the test, or which result in the pemanently snataned system with provisons Type A test not sneeting the acceptance ert.
- 4. Preoperstkm.al *eakspe rate fests. (a) for centinuous or intermitte nt preneurisat!on ter'.a III.A.4.(b) er III A A.(b). the Type A test Test pressure-(1) Redkced pressure tests. of individual or groups of contAtrm*"t pene.
ahan be terminated and the leakage through (1) An init14 test shan be performed at a traticna and maesuremer.t of rate of pres.
such pathe shall be measured using local pr'eauro Pt. not less than O.60 Pm to measum sure lou of air. nitroren, or pneumaue fluid ledage ter.:ng methods. Repairs and/or a leakage rate Ltan, specited in the tornw e
w ration or ad;vstmenta to equtpment shan be made and (11) A second test shall be performed as
==-isted bemos through the leak paths.
a Type A test performed. The corrective ac. pressure Pa to measure a leakage rate Zam.
- 2. Test Preseers. All preoperatannal and tion taken and the change in leakage rate
( 111) 'Ibe leakage characteristics ytelded periodic Type B testa shall be perfmned by determined from the testa and.overan inte. by gpaasurements Ltan and Lam shall estab. local pneumatic pressurtzauon of the con.
g-sted leakage determined from the locallest Dah the - mum allowable test leakage tain:nent penetratior.s. e!ther indartdual*y cr and Type A tests shan be included in the rate Lt of not more than La (Ltm/ Lam). In in gToups, at a prwure not less than Pa.
report submitted to the Cormumton as spo. the evoat Ltm/Imm la greeter than 0.7. Lt
- 3. Acceptance eviterna. (See a!.so Type C c1ded in V.B.
shan be spectaed as equal wo La (Ft/Pa)M. testa.) (a) The combined leakage rate of a:1 l
(b) Ciceun of containment teclauon valves (2) Peak precure fests. A test aball be per. penetratloom and valves attbject to Type B for the Type A teet shan be accomplished by formant at pressure Pa to measure the nemlage and C tests shall be les than 0.60 Ia. with normal cperation and witbcut any prenmt. rate lam, the enception of the valves apectfled in i
nary exercia:ng cr adjustmenta (e g no (b) Jereptance cWteWo-(1) Aeduced III.C.3.
l tightening of valve after closure by valve pressure sests. The leakate rate ttm shau be (b) 7 Me measure nents obtatted rnntor). Eepatra cf matoperating er letting less than 0.75 Lt.
through component leakage surveil:ance sys.
i
(
valves shall be rnade sa necessary. ILforma*
(3) feak pressure fests, ne leakage rate tems (eg ocnunuous pres:u-tranon o' in.
tion on any valTo caceure mMfunction or Iam shall be less than 0.741.4 and not greater diendua.1 containment components) that valve leakage that requires corrective actics than Ld.
maintains a pressure rat less than Pa at 10 before the teet, shM1 de includes in the re'
- 8. Pertodic leakspe rate tests-(a) Test pers. dbt:tal tut cehers cf colt &lnment Mne*
pcrt submitted to the Commianlon sa spect. skre. (1) Reduced presure tests shan be trauens during r.crma.1 reacter operstacn.
r.ed in v.B.
conducted at Pt.]
are acceptable in lieu of Type B testa.
l te) The containment test condluona shM1 (2) Pear pressure testa shall be conducted C. rest c tests.
stabiliza for a period of about 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior at Pa.,
- 1. Test method. Type C testa sha 1 be per.
to the start of a leakage rate test.
formed by local pressurtzation, ne pressure (d) Those portions of the fluid systema shM1 te appaed.in the sArne directicn as l
that are part of the reactor coolant pressure ANSI N45.4-1972 Leakage Rate Testing of that mben the TMue would be royatred to l
boundary and are open directly to the con-Containaaent 5tructures for Nuclear Reactora perform its safety function, urJess it can tainment atmosphere under poet. accident (dated Mar. 16, 1972). Copies may be ob.
te determined that the results frc:n the tests ecst:ttens and become an estension of the tained fro:n the American Nuclear Society, for a pnr.sure appned in a dderen* Crec Rn j
b0 tnt's / cf the ccntainment sha:1 be opened $44 East Ogden Avenue. Etr.adale. IL CO*al, asi ;rcW.e equivMent er =cre ecnum stm or vented to the cor.taintnent atmosphere A copy is avanat:e for inspection at the resua ne tot gnetnw.r. m 11h I cay be i
pr'cf to and during the test. Portions of Commiesien's Pub!!c Document Room.1717 autst:tuted where appropriate. Z:.ct vahe to cioord systems inalde containment that pone-E Street NW., Washington. DC. ne incer. be terted strO be clo6ec t* nc!:LM c;cra-tate con *.alcment and rgture sa a result of pwatton by reference wa.s approved by the tacr. an' w ahcut &ny prthmin;.r-ttrrc;8an '
- co c.f occiant sec dent shs'! be vented to 7.reetcr cf the Federa! T.cg. ster on Octo. cr acMir:wnts (e r. Lo % aenin; cfta^t tu m:Mr. ment atmtspere E: tnied sys. ber 30,1$"2.
afu r an: tQc n.
MDERA1 HGilff t 4 CL 3 3, k0. 30.-WEDNE5 DAY. FEttUARY 14, 1973 l
1
GS RULES AND REGULATIONS 1 *ct: p eJr.*t. (a) Valves, us;eas pris. age rate meets th3 requ:remeW cf this sp.
a.r a t sua a gts (e.g. weter, nat.rogen) pendix. Other structatue of mult:>1e barrter
' un a seal systect, aril be prosau-toed w1th or subatmospheric containmente (e.g., eso.
air Cr a:troge. at a pasonre of Pa.
Ondary conf
- manes 2tr boning water teac.
W) Ya:ves. stich are sealed with Suld tors and shiald bundicgs for presourtmed fre:n a anal rystem sha:1 be preer.trised w;th waaer reactart that encloes the entDe prisaar7
'.iat fus to a promrare nct lees than 1.10 Pa.
resetor containment or portions nameeaf) 3 A ' r7:We catte*m. De combined sh&3 be subject to indte! dual testa in accert1 m aif
- a*.* !:- a'l per.etcstscr s and va:Tes ance with the procedures spec 16ed in the
'n.e to Tne z and c tests shan be sees technical specihottuna, or a-.e bassa. -
than CJo : a. Leeaage fmn cectattment A.
a e hapec A genstal in.
E.stL:n valves that are scaled with Suid
- rces a em: res*.em Ins 7 be osciuded when V. brorsc; rose 43rn RrroeTtwo or Turrs 4'te = nt T the cocn'ained lestage rate: spection of the necess:ble inte-1cr and este.
NNed. That-rior surfaces of the containment etructures (a) Such TF.ves tare been demonstrated med componenta ahall be performed prior to
t ha'?.*.uM
.estage rates that do not es.
any Type A test to uncover any evidence cf ceet thase spe::",t-a in the technical spect. atructural deterioration which may afect S c"A t!c nt or ase>ciated beees, and either the occtatament at.ructural integrity (b) to infalled inciatton valve set!.,
or lenk* tightness. If there is evidence of strisetural deterioration Type A testa sha!!
water r-s*.em futt invectmy is suSetect to saanM t.he ses!!ng futsetton for at least 30 not be performed untu corrective action is taken in acocellance with repair procedures, Ca*: et a preum=re cs; 1.10 Pa.
smyndestruettve esaminations, and testa as
- 3. Pr*1 odic ftatts! ac%ufste-1. yppe A spuetSed in the applica.ble code specited tr.
terr (a) A*ter the Troc'perstJanal leakage iMa at the eotr.mesoement of repair rate testa, a set cr' three Type A testa shall be wort. Euch structurni deteriorstion and cor.
per*c9ted, at appror:n.atety equal intervals rective settone takaa shd be reported as Curin, esch 13-year service period.De thtrd part of the test report, subcnitted in accord.
test of each ea* aha:1 be conducted when the ance with V.B.
- 7. lam *s thu!C:wr. IC* th e 10-yes* Plant in, 4ertCe :rJ;ect;;rJ s B. Repo*f of tett resbits.1. The preopera.
(D) Pe t=.is.sible periods !ct testing, he tional and periodic testa shall be the subject perfer. ance'cf Type A testa ahd be ilmited of a summary technical r. port submitted to tne Commiasion approximatejy 3 months ro pr"tA.s Sten the piant fact;1ty is nan. after the conduct of each tert. The report c9erstice.a1 er:d secured in the shutdown ccScitica under the admmistrative control mW be titled "Reecter Contatwnt Duikt.
and in s,acerdante with the safety prtxodures tng Integrated Isak Bate Tast."
cdnv4 in the 11 cense.
3 The report on the preoperational test
- 2. Type F terts. Type B testa except testa shan include a e**matic arrangement of the
's" a*r Icetz, sha3 be performed during each lemlage rate maa.surement system, the in.
reactor shutdown fa refueling, or other con. a:rnmentation used, the supplomantal test vecWat inte.vals, trt in no c.ma at intervals method, and tLe test program selected as sp.
F?wer than 2 years. Att locks than be tested plicable to the preoperational test, and all at d.msnth intervals. However, air locks subsequent periodic tests. De report shan which a.*e opened during sueta in'.etrals.-shall contain an analysis and interpretation of the be tesM after each opening. Por primary leatags rate test data for the Type A test readct con *2 W'=st peneu'ataoss a= ploying rtrgt.e to the ertent necessary to deInon.
strate the acceptability of the containment *s a cceshiness Isahaga umanitarmg systec::,
Twpe B testsc onesyt ser esses of air looks, leakage rste in rneeting the acceptance may, rimsvt.hsinagging me test wNd De spec. critertia.
t 1* *d undra D.1, be perfee: nod esory acher S. Por each periodte teJt, leahse test re.
reacter shersdcwn fcr ref*aeling but tn no came sulta frem Type A, B. and C teeta sha3 be re.
at in:=:vs s greater than s years.
ported. The report shan contaan an analpas
- 3. 71 pe C tests. Type C tests shau be per. and interpretation of the Type A test resulta fe rmed during each remeta shutdown for re. and a suzamary analyets of periodie Type B
=
fueling but in no care at la*.orvals greater sa4 Type C tests that were performed since thaa 3 yeen thq laat Type A test tankage test rossia truma Type A, B, mat O tests that fausd to ry, s,.cza Tsusamma ame-.-ve meet the acceptanes critarts of III.AJ(b),
I A. Cc=CAMme'a# modtj! cation. Asy trajor r'T R e, and III.CJ, respect 1Yely, shau be re.
i Inod::catrn. re;a.ac= ment of a mmponent P*'**d 8" " '*P"'*** ****"P**7 "8 * *"T 8
w:tch ta part of the primary remeter con. seal.. FuPart that includes an analyons and inter.
tain= e nt boundary, or,reaesling a pretation of the test data, the least-equares 3,r:M co:r. performed after the-ptveyers. dt analysts of the test data, the instrumenta-t:Or.a.1 testade rate test shan be fo: lowed by tien error analysis, and the structural cond1 either a Tpe A. Type 2. c-Type C test, sa a;;' test:e fcr the area afected by the meat. t.lona of the containment or components, if 1:stic: The mew 2r.d leakagt frttn this test any, which contritrcted to the !sCure in l
shall te tne:Med in the report to the Otun. =eeting the neceptance criteria. Results and I
~ssion, r*;u::*1 by V.A. ':te acceptance cr!" analyses of the supple:nental vertif. cation l
te.tm -* :1Alf b). ::I.B 3.,
or I:LC3., na
- st e=picyed to demons rate the validity of aW:;.ste, shs.1 be met. Mir.cr mod:Sca. the h% rste test measure =ents ahan s so tar.s. re place =anta. b.7 res.ealing cf acal. be included.
se'.: ed docrs, pe-fc: ad c: ectly prior to the (8ees.103,104,161(1).183, i, t Stat. 936,937 sc.r. duct of a sc.heduled Type A test 60 not 948, Ofre, as amended: 42 UA.C. 2133. 2154 l
require a septf%te test.
2201(1), 2233)
B. #sittp14 leabspe borfter o et.bstmoe-Dsted M Oer mestown, Md, this 5th phe se cwisamests. ne primary reactor l
co=tain=er: bemer of a mu:ttple banter or day of Febienary Wl3.
ruhat=ot;heric cuate w*.* she.11 to sub.
For the A fnm!C Energy Com**"
(-
- e
- te: to Type A tasta to vertfy that ta last.
Part, C. Brnn.,
,5ccretari of the Commina, e such t ae.rv.co inspecticia are required
[Fa Doc.Tb2786 F::ed 3-1b73;8:45 a'al by g f-M m.
l' cpAt gfG1syf2, VN. 38, No. 3C.- WECNESCAY, CUAtY l
9 9
,-