ML19263C061

Proposes Change to Inservice Insp & Test,Incorporating Tech Spec Surveillance Requirements Per NRC 760422 Request. Changes Resolve Conflict Between Present Tech Specs & 1974 Edition of ASME Section XI

ML19263C061
Person / Time
Site:	Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date:	01/30/1979
From:	Vandenburgh D VERMONT YANKEE NUCLEAR POWER CORP.
To:	Reid R Office of Nuclear Reactor Regulation
References
WVY-79-9, NUDOCS 7902020243
Download: ML19263C061 (37)

Text

(, we Proposed Change No. 77 VERMONT Y AN K Elc NUCLEAR POWER COR POR ATION

~

SEVENTY SEVEN GROVE STREET B.3.2.1 RUTL AND, VEltMONT 05701 HEPLY TO:

ENGINEERING OFFICE TURNPIK E RO AD W ESTBORO M ASS ACHUSETTS 01581 TrLEPHONE 617466 90 t t January 30, 1979 WVY 79-9

-~~~~~~~ 7 United States Nuclear Regulatory Commission 1 Washington, DC 20555 '_ ms DOCUMEr;T COSTp1g3 ,

P00R qumTY PAGES -*

k Attention: Office of Nuclear Reactor Regulation t Robert W. Reid , Chief Operating Reactors Branch No. 4 Division of Operating Reactors

References:

(1) License No . DPR-28 (Docke t No . 50-271)

(2) USNRC Letter dated April 22, 1976, R. W . Re id to R.H. Croce (3) VYNPC Letter, dated April 29, 1977, J. L. French to R. A. Purple (4) 10 CFR 50.55.a

Subject:

Inservice Inspection and Testing Requirements Pursuant to Section 50.59 of the Commission's Rules and Regulations, Vermont Yankee Nuclear Power Corporation hereby proposes the following modification to Appendix A of the Operating License.

PROPOSED CHANGE: We propose to amend the Operating License No. DPR-28 as f ollows :

Modify the Technical Specifications as delineated by Enclosure A to comply with 10 CFR Part 50.55.a.

BASIS AND REASON FOR CHANGE: This change is prompted by References (2) and (4) requesting that we propose changes to our Technical Specifications.

These changes incorporate a reference to 10 CFR 50.55.a and resolve the conflicts between our present Technical Specifications and the 1974 edition of ASME Section XI, including the Summer 1975 addenda. All the presently applicable Technical Specification Surveillance Requirements will be incorporated into the Inservice Inspection Program Description, to be submitted by April 30, 1979.

SAFETY CONSIDERATIONS: The adoption and use of ASME Section XI, as defined by 10 CFR 50, represents a substantial increase of the inservice inspection and testing scope and an upgrading of the examination techniques and test 79020 goc 2q33 N

ri a United States Nuclear Regulatory Commission January 30, 1979 Attention: Office of Nucir mt Reactor Regulation Page Two methods. Therefore, this change does not involve any unreviewed safety questions.

This submittal has been reviewed by the Vermont Yankee Nuclear Safety Audit and Review Committee.

FEE DETERMINATION: On February 27, 1976 a revision to 10 CFR 50.55a was published in the Federal Register. By letters dated April 22, 1976 and November 17, 1976, the USNRC requested Vermont Yankee to submit Inservice Inspection Technical Specifications to comply with certain provisions of the revised regulation. We deem that no fee be paid pursuant to 10 CFR 170 because this proposed change is submitted in response to a written Commission request, and incorporates the requirements of 10 CFR 50.55a which the USNRC has previously determined acceptable for use in Inservice Inspection programs.

SCHEDULE OF CHANGE: As requested in Reference (3), this proposed change will be incorporated into the Technical Specification of January 30, 1980.

As noted previously, Vermont Yankee is planning to submit a description of the. planned inservice inspection and testing program, as well as any request for relief from the ASME Section XI requirements determined to be impractical, by April 30, 1979.

We trust you will find this submittal satisfactory; however, should you desire additional information, please feel free to contact us.

Very truly yours, VERMONT YANKEE NUCLEAR POWER CORPORATION At\'

D. E. Vandenburgh Vice President C04MONWEALTH OF MASSACHUSETTS)

)ss.

COUNTY OF WORCESTER )

Then personally appeared before me, D. E. Vandenburgh, who , being duly sworn, did state that he is Vice President of Vermont Yankee Nuclear Power Corporation, that he is duly authorized to execute and file the foregoing request in the name and on the behalf of Vermont Yankee Nuclear Power Corporation, and that the statements therein are true to the best of his knowledge and belief.

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/* - * ..#.p... . .".: ...% NA Robert H. Groce Notary Public

[ [h '.-k .F My Commission Expires September 14, 1984 I 4 i * (e\b.I:i ,

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TABLE OF C0'! TENTS (CO:!TINUED)

• _LIMITI!:G CONDITIC::S OF OPER ATIO"3 Pn~e !o. Surveillance F. Autcratic Deprescurination Syste: 92 F G. Reacter Cere Icolation Ccolin; Syctem (RCIC) 93 G H. l'initur Cere and Centaincent Ccoling Systcc Availability 94 H I. Maintenance of Filled Discharge Pipe 95 I 36  ?.EACTOR C00LA1:T SYSTEM 105 4.6 A. Theran1 Limitations 105 A U. Ccolant Chemistry ICS 5 C. Coolant Leaktge 103 C D. Safety and Relier Valves 103 D E. Structural Integrity and Cperability 1033 E i F. Jet Purps 109 F G. Recirculation Pump Flew Mirmatch 110 G 37 STATIO: CO:iTAI : MENT SYSTEMS 126 4.7 A. Primary Containment 126 A D. Standby Gas Treattent Systen 130 B C. Secondary Containment Sycten 131a C l D. .rimary Containment Isolction Valves 132 D 3.6 RADICACTIVE EFFLUENTS 147 4.8 A. Liquid Effluente 147 A D. Radicnctive Liquid Storage 149 B C. Gaccous Effluents 149 C 39 RADI0f.CTIVE EFFLUE:!T MONITORI!!G SYSTEMS 151 4.9 A. Liquid Effluent Monitoring Systen 161 A B. Gaceous Effluent Monitoring Systen 162 B C. Liquid Procor, Monitors 164 C D. End;ological ::enitcring Frecrnm 165 D ili

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3.4 LIMITI

1 CO::DITIO::F FOR OPERATIO:! 4.4 5U3'IEILLA::CE nZCUIRE:<E!!T3 34 r E'.CTCP STA::D*1Y LICUID CO:ITECL SYSTE: 4.4 EEACTCP. STA?'JDY LICUID CO:: TROL SYSTEM Annlicability: Anolicability:

Appliec to the operating statuc of the reactor Applien to the periodic tecting requirements ctandby liquid centrol sycten. for the reactor ctandby liquid centrol cycten.

Ob ir e ti vo: Objectiva:

To accure the availability of an independent To verify the cperability of the standby liquid reactivity centrol acch 2nica, control cysten.

Sa c c i fi e n.ti o n : Specification:

A. .inrrn 1 Oporation A.  !!crnal Oncration During perioda wher fuel is in the 1. Operability tecting of pumps and l rcactor, the standby liquid control valves ch211 be in acecrdance with cycte. ch211 be operable execpt when the Specificaticn 4.6.E.

reactor is in the cold shutdown conditien, all control rodc are fully 2. During each refueling:

incerted and Specification 3.3.1. 10 net or an noted in Specification 3.4.B below. Recirculate the borated coluticn.

Manually initiate t% cycten, excent explosien valves, and ccnduct flc.! testo using dcnineralized water injected directly to the reactor vcscel.

I Dicaccenble and incpect one explosion valve co that it can be establiched that the valve in rot elecged. Both volvec cball be incpected in the ecurce of two operating cjelen.

I 79

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7.4 LIMITI':G CC::DITIO::S F03 OPER ATION 4.4 T@'lEILLAMC2 RF^UIFF"E:;T3 B. Operation with Inonerable Ccreenente B. Operation with Inonerrble Coroonent; Frcr and after the d2tc that a redundant k~ hen a pc ponent beccres inoperable its cc~.?cr.cnt is mad 3 or fcund to be redundant componen; chall be dcrenctrated ir.c p o ra ble , reactor cperatica 10 to be ccecable ir cdiately and daily permissible darin[; the succeeding neven thercefter.

dayc unlean such conponent ic cooner made operable.

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The liquid poicon tank shall contain a The colution volume and to perature in bcron bearing colution that satisfied the the tank chall be checked at leact dnly.

volume concentration requirements of Fimtro 3.4.1 nr.d the colutica Ucron concentratten ch,11 be deternined tor;' rature, inclu-ling tint in the pump at len.L caer a tooth and a t n .- tire uut, ion piping, s ha ll be r.o t lea; th'n water er beron are ,d&d or if t!N the tetperature precented in l'iz.ure 3 4.2. coluticn tercerature dropa bele,7 the limits specified by Figure 3.4.2.

D. If Spccificaticn 3.4.A cr B crc not r.et, an cederly shutdown chall be initiated and the reactor chall be in the cold shit <'own condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

60

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3.5 LI:4!TI! G CC';DITIC?! FOR OPE 7 ATION 4.5 SURVEILLT TP RFCUI?"3'E::T 3.5 COBE A?:3 CO:;rAI!':E!:T CCOLII;O SYSTE:43 4.5 cc37 f.?:D Cet; TAI:w:F';T CCOLI!:G SYSTFr, Applielbility:

.A.n.nl i cab i l i tv :

n;'plien to the cperational ctatun of the cmcrgency Applied to periodic testing of the emergency ccoling subayrtero, coolin~ rubs /ctcus.

Ch' active: Objcetive:

To accure cdequate cooling capability for heat To verify the operability of tPc core containnent r- ~ 1 in tl.o c'ent of a lor'; of coolant acci<icnt ecclin4 ubr"itcyn.

or inolation frem the norcal reactor heat ci. .

Specification: Snecificaticn:

1. Core Sarnv nnd Lou Prencure Ccclant Injecticn A. Cere Sprav and Lew Precru-e Cooli ~ Injaction

1. Except as apccified in 3pecifications Surveillance of tPn core cpra:, d L"CI 3.5.A.2 through 3 5.A.4 belcw and subnycteca chall be perforreu as follows:

3.5.11 3 : nd 3 5.11.4, bcth Core rpray and the LPCI subnystens chall be 1. Cencral Testir3 op? rabic whenever irradiated faal is in the reactor vercel and irier t.o a I tm Fr aLu _n r_amv re,ctor ctartup from the cold rhutdown conditicn. a. Siculated Automatic Each refueling Actuation Tect cutage

b. Operability testir.; of nrns cnd valvec nh:11 b: accordr.cc i:ith Specificatica 4.6.E.

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3.5 LIMITI::C CO':DITIO:7 FOR OPERATIC?J U.S SURV:'ILL.U!CE EECUIRF"~NT

2. Frcn and af ter the date that one of the Core So, ray 2. 'ihen it 10 determined that ene Core Spray cub-cubrystcmc is nade or fcund to be inoperable fcr cysten is inopernble the operr'cle Core Spmy at-cny reacon, pecotor oper?. tion 10 percinnible only cycten, both LPCI cubsycter.c (Execpt the Pac:r-durir; the t.unceedin; coven days unlecc cuch cub- culaticn Sycter dircharce valver) and t% dierel ny h ~ in cooner made cperable, provided that ceremte-c rc';ui'vl fcr cwrc ticn of rueb 00 70-durir.3 cuch coven da's all active ccnpcnents of n:nts 2r no external ::curcc of perc v:re crail-the cther Cere Opray subnycte:, the LPCI cub- able chill bc eronstrntc:t to bc cocrrble ir e-cyrtcts, and the dict 1 generatorc required fc" diately. The cperable Core fpray cubarater -h711 o;; ration of cuch ccnpercnte if no external cource be de.ncnctrated to be cperabic dail3 thercarter.

c: pc;;cr ':cre nviilable, chall be epcrable.

3 F rc a. ,nd after the dato that one cf tb LPCI pur.no 3 *;han

< it in dater nired ti .t o le c f the LFCI p'.1n-ic . nae cr fcund to be inoperable fer any reecen, in inoperable, the renainin.~, ac t ive corx : : nts of reactor operation is perniccible only durin.- the the LPCI (exccpt the Fairculntien yrt, -- du-cucceeding < cven d yn unless cuch pump in cocnce charge 'talves) nnd the Ccntninrent Coolir cub-m .2 epor:ble, provided that d'Irinc, such sevcn cycccrn, both Ccra Cp c , cubcystcr.c, and ti dic-difc tN rc ninin; active ccapenenta cf the L"CI v1 c:ncrntors reuirei fc: cor at_c7 c' rrh c:.-

Centcirr.cnt Cooling subcycten and all active cen- penents if no cxternal cource of pc..ar are es.il-pcr. cats of both Core Cpray cubrysters and the dic- able c' all be doncnctrated to b2 oper .M e irm-cel ger.erctors required for operaticn of cuch ccm- diately and the operable LPCI pur00 daily there-ponente if no external cource of power were avail- cfter.

able, chill be cperable.

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'4 From and after the date that the LPCI cub- 4 ', T. ' e n it 10 ceternincd that a LPCI rub' 7t.~

ryster is rado cr found to be ir.oparable for it ir.o p e r:ble , both Core Sprr" cubn te .

nny rencon, reactor operation is per":lc- the reminin' LPCI (c:: cept the 'ccirculntien nible only durir' the cucceedinr,ceven dayc dicchn w valvm) and Centainmnt Coalin; unlcr3 it is coor.cr cade operable, provided subsyster~ and the diecul r.cnnrlton "c-that durin,3 cuch cnven days all active com- quired for coeratica of cuch cr pen _ ;to if ponent: cf the other LPCI and the Contain- r.o external courec of power ure availabic

~ cat Coolin; Es. aystc ., the Core Spray cub- rhall te dcr. nctrnted to be c?crable cm-ryctetc and tPe diecel cencrators requircel diately nnd daily tb:rcarter.

for operatica of cuch compcnente if no ex-tornal nource cf pou2r were availabic, chall be operable.

5 All recirculatien puro dicch-'rce valves and 5. a. All rectrealatica purp dicehary 'nd by-bypaco .clvec shall be operable cr cloced pace ulver chall be te tcd fcr cper-price to reactor startup. abilility during cny pericd of r:actcr cold rhutdown exc'edir: 4E beurs, if op-

6. If the requirements of Specification 3 5.It ernbility tecto have not bec. ,erfer:cd carnot l'e rat, en cederly chu cdcwn of the daring the preca dir -- 31 d yo.

r^ector rb;11 be initiated and the rcactor rh ll be in a cold chutdown ccnditien within b. Op.rability tectira of H.o "ecirculation P4 nourc. Pnm diceharr,e Tlven , call be in nc-co' dance with freifiention o.6.i.

B. Containront "prav Cooling Cannbility D. Centnin~ent Scrw Ceolir~ Crmbility

1. Ecth containment cooling cpray loops are re- 1. Survcillar.cc of the dryttell cpray leopo quired to be operable when the reactor water chall te performcd as folleur, durir; each ter.p3rature is creater than 212*F cxcept five ycar period, cn air tect chill be per-thut a Containaent Cooling cubrycter may be forred en the dry.rell cpray hcadora and non-inoperable for thiry dayc. clec.

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r.~7 L'o m" ". " -' . r. L" '.P' ' " ". '1" If thir re wiren'nt cannot be tet, an c"-  ?. '. ne- it in d,torrined that a ccatri- n-t d ' r lv. chutCov' chall be initiated and the ecolir.o subovctcr is inco.erabic, the remain-rcactor chall be in the cold chutdcun ccndi- in~ aubrqctea chall be c':~;stra t 9 to b 2 tien uithin 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. cperable ir cdiately and daily thereaf te: .

C. P.c : dun' F at Pcnocal (FIid Servien '..' ter Sy y C. Renideal Fe't Re oval (T"ll 3 'rvic' 'd'ter 'in' m

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be perfo ..ud ac folleus:

1

1. Except ac specified in Specificationc 1. Crer,bility tcsting of purns and valvar

' G.C.2, 2id 3 5.C.3 helew, both ir ; cervice hail > in acc^r-2.vcc -ilth Cpecifi^7ticn s:,ter . :h: , t n loepa chall Le o,'. :r c Ic 1.6. .

5:L :v u r i r: Hint <d fuel is in the reactcr uncl out prier to reactor ctartun fren a n a svm. u c n2.a ; + > v. C ,., .

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carvice etater purps is made c" fcund to b3 ta te: pun? ic incc 7able, the rcr-inin ; c :n-inop rable for any reason, reactor operation pencats of that radayr'.cr cr.d the o t'c c - T m ir pceni:nible cnly durin; the cucccedin? rervice rater cubaynter nhall be dr.on-t h ir t _y hva unlocq cuch o.uro. 13 rooner cade strated to be c"<crabic ir =Miately a-d daily c ,n .' - N r , provid"" that d".ri r",

cuch thirty therenfter.

!. O all ct.har .-ctive ccr:'enentr o: the "iul nervice tra te r :>u';cy nten are cocrable.

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3 I ren nnd cf ter the date that onc FH!i cervice 3

• man one Iri3 ervice 7ter rv5-vcte- bec c3

.:1te" nubcysten is nde er fcund to be in- i.cperable, the cperable "u'acp te. .'r i tt op;rable for any reason, reacter operation dienel c.cner; tors required fcr cperation of y., c., _r

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4. If ti requircr.ents of Specification 3 5.C ca nr.o t bo e' , nn orderly chutdoun shall be initiatM .mi tee rmetor nhall be in a cold c'a te mn rond itica with' r 2!! Seu .

D. Statir . Service ':'Tter and /.lternate Coelin- Te.:cr D. Station Service Water nnd Altern-te Coolir-- Tccar Svntm; 5.'"te c O..-. . ,.~.

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1. l'.cpt an cpecified in Specifications 3 5.D.2 1. cperability tectir., or purpo and valvca anel 3 5.D.3, both nt,tien oorvier n tor 'ub- -hall be in aceo' dance with cpecificatica aycten icopo rna the alterrato ecolin , tc',r r 4.6.F.

@ nil ba operable wienaver irradiated fuel 10 in the rcacter vecccl and reactor ecolar.',

tenerature is craate." than 212*?.

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2. From and af ter tbe date tint one of the eta- 2. i.r.e., it 10 deterninM that crn atntien e-tien service rater subsysterc ic r.ade or vice 1:ater cubryaten is inoperable, the re-fcund i.noperable for any rencor., rcactor c,- rainint; cprable cceponento of that rub-eration is perciscibic only durir.G the cuc- ty;tcr and the other station cervicc <7tcr c % n; 15 dayr unler: cuch rubsyster in erbcystem and the altern,te ecolir:: tence e..~-i.,

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dayn all other netiva components of the sta- di;tcly enf daily thor arte .

ticn cervico ,,cter and alternate ecoling to,:er cynten are operable.

3 Frer and after the date that the alternate 3 h".m the alternate coolirg tower or both coolini; tc:.ar cuboycten or both ctati.cn cer- .'r. tion corvico 'nter cubsyrter.c accc-' in-vice >:nter subsysters are r.nde er found in- cpercile, the cptrable oahrv.3 tem rn-! dirnal operable for rny reason, reactor Operation gener;tccc required for cpern tien c tach in perticcible only during the cucceeding 7 c pcnentn -hall tm de nnstratM 'ac be cper-day, unlecc such cubsystenc are r.cde opcr- Oble !"~ dintcly and daily ti.creaf ter.

tble, provided that durinc cuch 7 daya all cthtr activa cciponents of the other sub-c;'nter are optrable.

4. If the requiremento of Specification 3 5.D cannot be ret an orderly chutdown shall be initiated nnd the reactor chall be in a cold a'r.u tdo:-:n condition within 2 1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

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'3u: vei'. lance cf dPCI cyntem ch711 be p -fern'd as felici :

1. Execpt as rpecified in Specification 1. Ta c t inr3:

3 5.E.2, n,never irradiated fuel in in the rv.etar vec:. el nnd reactor preccure in Itcn " r e a ': c_r ^"__

rector tF,n 150 aci.~,rnd 7.ricr to conctor ctortup frc:r a cold condition: Simulated Autenatic Each r" fueling Actm tion Tect cuta;u

a. Tt:" i!PCI cynt"n uhall be operable.

0;:er thili t y tentir

• of the pu p an ! al,e

b. 'ir.e condenrate .',orare t.v.k r!r:ll con- '" :a l ' l'<' in ,ccordc.r.ce i.lu h tf:07t vn tair, at leant M .C00 allonc of conden- 4 . 0 . t. .

cate water.

2. Fece end after the dato that the HPCI cub- 2. 't."cen it is datermined that tPc HFCI sub-cy-ter ic ado er found to bc innocra51c for nyctc-' in incperable, the LFCI cub t -tc~',

ny r aron, reactor creratico in permiccible the Cora Spray cu M ys'.o m , t'r' sut1 7tf r e -

enly during the m:ccendinr mven dayr unle-n p rer iu ri-*at ion j " < .:, and tho F C I C c f .t t -

. . h pub :ynten 2: coonce made cperrble, pro- chall be donor.rt ~atcJ to t o oper.t'ne . m a-

/ idc.! th t dirir,~ ch .,even da*.1 all cetive diately. The Anten' tic Deprenr'.rirntics en wo :n' of the fotont ic Dorn - curination r u te;'a and the PCIC ny.:t a nhal' b ' d ' mn-3

• r ., tho Core '

a rri y '/bt g te n",, thc Ara t mi to be oper o'11 c ': ily th ~ .f', .

l.r ;1 na3;;y, , ,: c , and the liCIC ::ynton are operable. NOTE: 1.utenatic Deprencurizaticn Syste~

eperability chall be decor.ctrnted by 3 If the requirenents of specificaticn 3 5.E perfornins a functic.c.a1 test of the connot be .ct, an orderly chutdovn shall be trip cyster legic.

initinted cnd the renctor precoure chall be reduced to 120 poig within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

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4-4 . r; u oia ,1 F. Autcmati c ik:r.rrrr :rination Syster F. Autem 'in Deprercuriratien Strte~

Surveillance of th' r.utcr.atic deprersurititicn

-.s o. . > ,1 1 s o. e

ayw ~. a.. p, o.- cs, c..m. .. ee an

.3 a c ~ L <w

1. Weapt ac Opccified in Specification 3.5.F.2 1. Cperability testin, cf the rel ar val.ec b e lc ,, , the r:ntire automatic depreocurir.atico cinli be in accordnnce with Eracification relief c jatt.m str'.ll be operable at a :y tiro 4.6.E.

th: reactor preccure in above 100 poir, and

> a 4 . cs

~a.~>.m~ c _, 4

~ 4n + L,n r , ,, m. a c r \. c .. .~., .. ,

2. Frc nnd ctcr the date that cr.c of tha four 2. Uhen it is deterrined that cn.' elief valv'.

-es ... . - l4 u. -a n - o r +v5. n. e,m+u .. 5 e 7: o. c, -n .o.m.r y,i.m -

0. , u_ m - c ' *v..o b -

a. u t o . .. s '. i_ v' , re v- c o ur - . L. 'i

.. 'mor .e, t .~~; ."., o - -

i tion nub y~!m' ar<. r/1dc cr found to b' in- in ir.o p c rable , thn UF"I r.ubry.;trm nhall 50 c 'rnble du to nalfunction of the decanntrated to 'ec ri e-able ir cdi.'.cly.

elcatrical partien of the .'alve uher. the p .. ,.c_ .-.n ,, .o y..,,m,.,,.

. a . c. ,.

.w .m _0

<.n.<, 4 s, ,,-c.,

.:.w m...

irradiatcd fuel in the reacter vccac1, contided rctetor operatier ir cr"-in cible c,,,,.

..; g. r.e. 6..,

., , t. u. r.

,, . . ,, . c_ C u.

om .

• 4 r. o7 o. ' ' ,v, a-

, ur.4l o_ a s cuch a valva is recr.cr ade opt. ',

nro.id ; nt duri..~, 'ach nevon dy

- both

. . , . . f g- s t ..r p. ;,. - . pc.,s .-.. *i.c t^1io" c"".

. .. . 2. . y c_a. .' m1 1". m" a-D'Id the ii' f CI Sf Ster. CPC opCrable c -

r, Y 12 u,;oq a r i. I ". . T_

i. T T "<,- rn :97.,. T. on.s e.nm; opt.gto m.mn.y m r q.,o n r c e mm m". . - . m.

-; a --Ion.

m -.. .

a . 5. m . .m...

3 If the requirement of Spccification 3 5.F cannot be ~et, nn orderly shutdo.n shall be inithted and the reactor preocure ch,Il be rr 'O ed to 100 psiC kithin 24 hcura,

u. no mt er Core Trn'1tirn Cnolinq &, r: t c m ( i'C I C ) C. I:e n c te r C r' r e' Irolatien Coolir' &rnter C ' ? i C ';

Surveillr.nce of the !iCIC nyrtem chall bc perfor~,d na follcw .

1. E::ce_ 't a spccified in Specific 7 tion 3.5.G.2 1. Tectinf,

'c 71 c, the RCIC sycten chall 'e cperable

.:1 :ver the reactcr prercure in r ere:ater Itoa T rem: m r m.;.

thi1 150 pa ir. and i r: adial.cd fuci in in the r- ' tor v<  :.c l . Sin:ulo tm! n':te ratic act uation e 1.c h re-tt ~! (test n : /al" ep e r:' b il- O . *

• ity) cu'n~?

Cperability tecting of the pc p and valves ch711 be in accordance uith .Spt.eification 4.6.E.

2. Fron and after the date that the RCIC ryrtcr 2. 'c hr:r it in deterrined that the ECIC 4

/cten is carle cc fcund to be inoperable for any in i no pe:ra ble , the lii'CI nyaten rin17 ha re; aon, reactor operation in per miLaible detonatrated to be og rabic trmeiirite:y and

.cnly du rir.t* the cucceeding 7 days unless 6111y thereaf ter .

cuc!1 ;cte- in scor.er rade operable,

rovvied that durin.c*

n , *:uch 7 d'ya all cctive cotNnente cf the I!PCI nyntem are operable.

ct

VYUPS 4, . -5 CDr.a

r. . .s] t-o .. .a. .a.

. u, C n o.,u. t..d.e,v c e., , em S.Y m A. Core Spray and LFCI During normal.plent operation, anual tects of cperable purps and valves shall be ccnducted renthly to de-r: castrate operability with the exception of the nacirculation Purp Diceharge valves. The Recirculation Sycten diccharge valvcs are not tested during plant cperation since to do co would creetc a covere plant trancient.

Durin3 each refueling chutdewn, tests (as sun arized below) shall be conducted to denct strate proper automtic Cperaticn and Sy3 ten perforr.anCO.

Pcricdic testing at the intervals specified above will dcncactrate that all con 7onants unich cu -'c t. eper-during normal conditions will operate prcperly if required.

The autenstic actuaticn tect will be performed by rimulatien of high dry.rell prescure er 1cw-Icw wator level.

The ctactin:; of the pump and actuation of valves will be choc'ced. The norml re: - cupp'.y .ill N used durir~

the tect. Tcutino, of the cequencing of the purps when the diesel cancrator ic the cource of po:.ar ' ill be chccke i durir~, the testing of the diesel. Fo11cwing the aut.omatic actuation tent, the fle. rate lill be cbc e' -

el by recirculation to the suppren*,icn cPntber. Th ' pur? and valve opr rability chec%c 'nll p<rfcrred by s

canually starting the pump or 'ctivatir; the valve.

B. and C. Centainment Spray Ccoling Capability and PMB Service Uater Syctcm Tna periodic testing intervals specified in Specifications 4.5.3. and C. will demonstrate that all ecrpenents will operate properly if required. Since this is a mnually actuohd systen, no autenatic actuation tc-t in required. The systen will be activated nanually and the flew checked by an indicator in the centrol rcar.

Once every five years air tents will be performed to assure that the centairner opray hander -o 31cc are cper-cble.

D., E. and F. Statien Service Water and Alternate Cooling Tcwer Systers and HiCh Precaure Ccolant Injecticn and automatic Deprcacurization Systen The tacting intervals for the liPCI systen will denenotrate that the ryater will operate if requirci. The cute-tatic deprecaurization synten will dcnonntrate that the rysten will operate if requirea. .ne aute~atia deprec-

ur

atien cynten in tented during refueliny, outar.m to avoid an undenirable bleudm;a of th reactor ecolrnt cyoten.

The :'?CI Aut.cmatic Actunticn Tect will be perferred by citulatier of the accident signal. This tent is nor-v ' l:. perfc" ' in conjunction with th2 Automatic Actuation of all core star.dby ecoling rystc .

103

3l .g

, p e, a

4.6 SUnVEIL LA"CE 'ECUIizir":T3 3.6 LIMITI?:3 Ct'!:DITIONS FOR OPERATION C. Ccolnnt Lea': -e C. Ccolant Lenkn 2 Foneter ecolant systen Icakage chall be checked

1. Any tine irradiated fuel is in the reactor 7ni lecced at least cnce par day.

vencel and renetor coolant temperature in above 21'>*F, reactor coolant leakage into the primary centnirc'ent frcr unidntified courecs ball not exaced 5 r,pn. In addi-tion, the total reacter coole t cyctea leakage into the prinary c # 2inment chall not cxceed 25 cpa.

2. Both th. cu.. ? n:rl air camp' rr- ;7.;ter. ,

shall be coe"able during ; N:cr operat ten.

Frcn and after the d.'.te that cne of there cyctera is vade er found inoperabic for any reas: ., r r ter cpcraticn 10 cermirsible caly dur_rt the nucceeding sevcn daya.

3 If they conditions cannot be not, initiate en ordoc.y chutdcun and the reactor shall be in the cold chutdoun condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

D. Safety and f.elier V'.lves D. S'.fety and S lief Valvec During reactor power operating conditions Operability tecting of Safety and Relier Valves

1. chall be in accordance with Specificatica 4.6.E.

and .:henever the reactor coolant precsure The lift point of the enrety valves and relief ic creater than 120 psig and tcrocrature .alves shall be cet an crecified in Specificatien greater than 350"F, both safety valven shall be operable. The relief valver shall 2.2.B.

be cperable, except that if one relief valve in inoperable, 1ctor pcuer shall be nmediately re'duced to and maintain ^d at or b^10, %% cr ra ted po. cr.

2. If Specificatirn 3.6.D.1 is not 'act, initi-at e an orderly shutdown and the reactor coolr nt pres.iure ch,11 he belcw 120 poic, a".d 300*F t.ithin 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

,fb, .)

V. .n. ..., e e 4.6 SUiF.'EIU,f '!C" 'E'JIRZ' E';T 3.6 LI:'ITP:0 CO"DITIC:: FOR CPERATIO:1 "tructural Integrit'.* nnd Operabilit:.- Tentir~

E. 9tructural Inte'riy* and Op,fr1bility Testin~ E.

The structural intc~rit"3 v and the eperabilit.y of 1. Incervice ins,ccchien of cafety-related cen-a -b,11- p ~. . .. *. ~. ,"w' 1 b o. -..su-e

,o 4 ns~.

^'

'u--.~...

a.- . . ,...,.,._ u ", d, c .w.,, c . o, n +,. o- c.~ . .

e., s .c.3,._

u..- .e v, . .L.u, w .

be rnir.tcired et tho leval requircd by tSn cri- t Lth Ecotica XI c f th A.T'~ % !1 ~ n' '

~.ir.al acceptcnce ctand.rds throu;heut the life of Frercure .~ sel Ce@. rad appin-51a Addenda t.h> plant.

en rnqu i re:d by 10 CIf 50, c' :t i c.

SC.55:' N), ex'ont ' v re nn >ci fic c:'i t ten reiief 1,1; been i;. nted by the IF' puracint to 10 CF? 50, E.:ctica 59.5Sa f ;)(6'(i).

2. Operability tactirc cf rarety-related .u pc and .alvec chall be rerfor~ d in ;cccrd. nce with F. e tica XI of the Af' !hiler ud f:.. nuro Ver*] Co.!< 'nd vplic.ble n t.% nia an op.1 red by 10 CE. 50, .;c e t i t -

S G . 51 - ( ry ) , excopt ' "! T cific L:ritt ,1 reliet hac' been cfanted by t!' : n. pur m.at to 10 CFR 50, Scotion 50.53a(r,)(6)(i).

WD t '.s J?

VYKPS 3.6 LIMITIUO CO::DITIO:I F0il CPEFATIO" 4.6 SUP.VEILLl. FF. FEOUIP~'2::T F. Jet Puron F. Jet Purpr

1. 'Sunever_the reactor is in the startup/ hot

1. Taenever there is recirculation ficw '-ith strtndby or run rodec, all jet purps chall the "acter in the startu? /Pot utnndby er be intact and all operating ,)ct pur.pc chall run caden, jet pump intecrity and oper-be oporabic. If it is determined that a ability chall be chcekad daily by verifyin:,

jet pu:n ic inoperable, en crderly nhutdown tPat the following two conditicac do not ch211 bc initiated rnd th2 reacter cPnil be occur cir1:lt ancourl:, -

in a cold shutdcun conditica aithin 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. a. The rceirculation purp flow differn by tore than 10% from the establi:: md cpced-flo.4 ch :cteristicc.

b. Thr indicated total core floa is rcre than 107 grcnter than th2 core fle s value derived from establiched power-cc e flet reintienchips.

2. Flcw indication fror cach of the tuenty jet 2. Additienally, when crerat!nc . tith cne re-purpo ch711 be verified prior to initiation circulaticn pu, with the caualir - alvcc of reactor startup from a cold chutdoun cloced, the diffuner to Jox -

elen"n s if-condition. fcrential prem :re shall be clock d daily, an1 the diff cre itial prewn'c of any ;. c t 3 The indicated core flow is the num of the pucp in the idle Icop chall not ary by flow infication from each of the twenty jet mcre than 1C3 frcm catabliebed patternr.

purpr. If flow indicatien failure occurs for tuo cr morc jet pumps, ir.rediate cor-rective acticn chall be taken. If flow in-dicatien for all but onc jet purp cannot be obtained within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> an crderly chut-dcun chall be initinted and the reactor ch711 be in a cold chutdown conditien with-in c+, hours.

109

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,., . a .; . r, r <u~~. a. ~,.< ,a, ,, , e cren. tor than th2 limit specified fer unidentified lechn:'c, the probability is cmil that iroerfectien- or crac'--

urcOciated witii cuch lc A2;c eculd grow rapidly. l.ca'"n,e lecc than the linit cpecified can bc ictoctcd ..it in 2 fc  ; curs utilicin the availabic lea'en;c detectier e etcas. If the limit is c:<:cceded and the origir cr~:ct te deter.. ired in a rencenably chort time th2 plant chould be chut do..*n to allcw further invectir;ction rnd cerccetive

' 10: .

Ti'c recval capacity frce the drywell floce drain cunn and the e'iuipt.cnt drain rump in 50 gpm each. "emrzal of 50 gpr frc eitner of thecc sunpc can be accerpliched with conciderable carcin.

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u. ....a o, . n. ,. 5 c o-

,.a, y t~

Pa m m ' *- t a evalmticuc have chcun that only threo of the four re'icf valvec are rc : ired to provid" a prerm re

. o .' :t. - ti, m the r rrmnded 25 y ' holew thu :a fe! ' v: ! , <

r' ution -: t t .n' , a n ' 011 r a ":fd > 1.f3 fer ti" li.itin ou ror ';ure trancient boloa 93/ pawn. Con:1guently, W / pnuer i s , L'+n M t e te<i as a linttir-

3. m 10 : 1 for three valve operation. For tha nurpc.:en of thin liniti v condition a relief nlve that is un.ble

'A ic con-idered to be :' inoncrable ec ^ cchnnically

_.w_ .,.q , c_.e. .ith ',,teicrance of its cet prer ute

t 1 2

. _ _ _ m,- .,

-.,n.

E v. ,. ~ i e n c e in safety valve operatien r.bouc that a tactini of 501, of the ca fety valvec per refuelir; out ~,c ic

- p: T i t. to dctcet failurec or deterioration. The tolerenen value ic rpecified in &ction III of the ,. ' Pciler

. P,s me V.. ml Cod" as + 1% of de::i;*n proncur e. An anal', air, req been rerfor.:cd chich -hews that ,ith nll fity <al<, t 'S ligher tha r'actnr conlant prc rurc rafety linit cf 1375 pair 1. vot xece ' ad.

. '

tr tural Int <a ' ity ,M Operability a p re-scr'ile : i: e cticr. t h' conpon.:ntn lirted in Table 0.<'4 of the FCAH hac been conducted afte: ; i. t e e: "'en to a: Euro fr< -!cm f rm d e re o t ' J.r nter than cede n l ' o' nner, in ndn'i t i en, th b ". n- a re form < < h w Tm furt: 0 ir.~ t e: L ira n . Pricr to 1peration, the reacto" prir ry a/cten :!n frce of crw a d^feetc. It > ~ition, the fr.cility hac be"n decisned cuch that grecs defectc nhould not cccur thrcuchaut plant life. The incer* ice incpcotien progran .till be in tecordance with 10CF*i50, Scotien 50.551(g)(6)(1) execpt were specific written relief H becn 3rcnted by the URC. Thi's inspection provideo furthe- accurcree that grecs defects are nct co' .:rr i ng. This inspection will alco incure cafety-related compecents remain coerable.

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T4 le

.r v. e. .ro 3.7 LI:'ITI" C0!:DITIO"S FOR OPER ATIO!; 4.7 SU?VEILU"CE T'0UI3P'3I3

6. E m ore "annrensicn Chamber - Dry,211 6. P- me ""- ,rc~;icr. C1 mber - Nyt;oll

e. ~, r_.. ... . . .pns . o m.,v .~.-,

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a. .xn prirary contain m t is required, a. Periodic C"cr-5'lity Terta all ruppr:rcion charber - drywell y .. ~u.. e - 1 rJm ,. 'r. o. ~v-s . v- 'rs.

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if:

(1) The valve ic der:enntratc 1 to open fa'ly uith the a, plied force at cil valve pcsition; not exct ? din; th t e lui rnient to 0.5 poi actirc or: th > cappreccion cF-~"" &cce 3

o r, t .ne vaive d1c,r:.

(2) The valve can be closed by r.ravity, when released af ter beirq opened by ram.cte er mr.ual c me , to .ithin not gr'atcr t W the e ;uiv:t1cnt of 0.05 ir.ch at nll poin en ale:, , th. coal ::urface of the dink.

(3)  %. . . .rno ,5+v;c.r

a. _1 ,r... o%g

~nn a1. ,1 c.nr.unciate in the centrol roon if th.' valve opening execeds the equivalent of 0.05 ir.ch at all points clcng the real cur.^ ace or 123 the di %.

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b. Up to t;c (2) of the ten (10) b. F e fu .' ' i - N_t.' _ n Ton'.

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.3 ;

, .4 le- 4 or pccition 11.

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7. Oxvern Crncentr."ticn 7. Cxz en Cc.ccrtratien

a. The primary containment atmosphere The prirary contairnent exyc'n chall be reduced to lecc than 4 cencentratien shall be roa m red and percent cxygen wit'r nitrogen c'c rc:crded en a ':ccxly basic.

darir.; reactor pc,:cr cporation with rcacter ecolant precr.ure abo;c fiO pcig, execp; na crecificd in Specificatica 3 7.A.7.b.

b. ..ithin the 24-hour paried cubcecx nt to pIncin; the rcac',cr in the Run tcde follc;.ing a chutdcva, the contain=ent attccphera cxygen concentratica chall be reduc:J to lera than 4 percent an!

. T i n' a i- u! in thin condition.

D < i r. " L i t . - :y co wcc 2:i inur price lo a c Il'.1 I.,d O'.?n .

8. If Spacification 3 7.A cannet tc net, an orderly shutdexn shall be initiated iracdiately and the rcactor chall be in a cold chu' down condition withir 24 hourn.

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. i m :rnorc rcT.:irce fer epcratica of such circ:M", OM 11 be "r-rable at '.11 tirca n. Prernure drop rereas t!.e ev.5i' ' ~'A L. 1",m. . _ ' . ' =' ' . < ^ - "5 'o '*

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. . .v. . y reqlired. 6 fr.chc* cf tar it I S o f 1'. ; ,' .

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2. a. Th' recultn of the in-place cold DDP 2. a. Th9 tectr ~d m ale m l,ric cf rr. , , ' r. - . ,. 'u n d. v.i.c,.9 *m o t~- s,.'.- .", i.f4 .' '+ ' c . . ~i . ~ . 0 ' ,1. 1

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2 . .

4

. .n fi r.m en li"' A .ind cMrc x l n y fe- 1 2 i t.>1'; r*'at Ir^~t Pro filte- hand r6 11 rho.; 19M,l'? r caratinJ, evele r. t to r . I?

w/al 'nd LOM halo;r nated r en ti ', , aM ro110 ; t -

• s i r '. i r e . Tir

,,Jrec,rbcn removcl. er cW'-ical rele za in ~T., vo ti?atian

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4.

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m.

ch.nrcent riccrbers.

b. The renults of Jaboratcry carbon b. Col <! DJP te,tirc 'n11 be p'rfe - d r , o.. m. o. . o. c, - [r.t..v <. -

.,.,.,m,c. ....1ysa. ,- - c. . .-n. miiA v.. . . y rJ p ,

os .'+t~.

v - s ' . .2 n'dienctive rethyl iodide rcteval, replacc~ent of 'T' T i l t 7r 'nn'< .

s l ,J

., e vc, cJ r)w p h . ll. )

c. Syntar. fana chall be chown to cperate c. Haloyr.ntcd hydrect-bon t e n t ir ~, -h211 L thin _+10 % o f den t".n fl ow, be p rfer~' aftor "cb ec leto or partial re;' Ir c "n t c f L ' ; c. '. r.- 1 3 i'ro  ;,nd tfter the data that- cne cirm it of filt '-br'.

th^ ' ndby can trentc.ent acte- <> r'ie or fon.d ot be ir.cpernble fer r;y reacen, In Oddition, ti" nrn'" ana l,; i of ra,^ to: c p era t i e- - - ^ r: incible only Epo 'I fica t ir.n 3 . "T . b . !' . ' n r d t h <

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- 4.7 S ur ,.". mT r i..ne.,r co .m' c ", I .y-. ~ .._s C. ~3 <' n c- ^ r y Ccnt'inmant Cynten C. Scendnrv Contair~~nt S'-t-

1. Integrity of the accendary contoirrent 1. Surveillance of ccerndary ccatainment e nll cycten ecil be r. intained du.ing all codes be perfce: red as fclls,3.

cf p1rnt operation except 'vihen all of the follo;.irr; conditions are met. c. A preopcratic"cl ceccndary ccntairment cer Lility tect chall b: cr~ uctcJ

n. The reactor in subcritical and after itel., ten? the re ': c t c - b u l b! i n ',

P.",,in7.,.a. .cit her ctan hi >' a a Specification 3 3. A la ::et and and ,

u  : ,,

• I'.,.,,,._Cv m ., , . 5., .x ,. m , , .- t ,, - 4. n.

. .1 v- s% . ..-

operaticn. Cuch tects un'll O ncratr' tc ' tc cc-tility to r'intair n 0.15 inan o ' -

c" vann: ur.d1r en'"

i n6 2 c '

< 5 ~r:h) ccn'iition :ith .

filter tra in flou rate of rot rc: '

ti nn 1500 err.

131a l

Lv , .o e~..o 4, . , ,, , ,

.,v.r.., 7. L L A. ,, u,, T . . , . . . .l p u i .3

..o ,c, a,. 0 v. c. h,i I O,.J

-3., o 7_,,,1

. L..<,

.u C O.,..,.

.vt e I O., ut .t The re .ctor triter tenperature is bele*, b. e.Hitic~11 tents chll ce ;crferr ;d b.

212*E and the reactor ecolant cycter durirr th7 firrt cper st im - cycle u'for c r .' P ; r te rx Scr of di f fe: .:nt in vent.cd.

envir^ c s on tal ',7: nd en" !i t ion: t.o en:1blo vali d ef.t ra pola t i o:. cf % > t*Lt renulta, No cctivi.ty is beirq perforn^d which c. S'ccedary ccntainrent cnpability to c.

enn re?uce the chutdcan marr.in below riintnin a 0.15 inch of . ite r .'c w u- calm ind (2di<5 ph) cendit :na' th'It sp2cified in Specification 3 3.A.

'th a filt"r tra in flo.7 'n te c f r.e t ur< t h .n 1%d .c, < 111 >

d. ri ' E.

ca:' or I rrc' d i n '." ' fv:1 ir qu : H . ty m! nt not b p, trm en in th.. rtactor e r tratod at 1. a nach re fueline, cutt'Cc pric to building.

refunlir.g.

2. Care Ep ly and LFCI pump lcwor compartr.nt 2. The Corc Sprny and LFCI Ice + cor-crtm nt

< n c e er. 11 ; ' ' ch111 be closed at all tires cpenirm ch:.ll be chce>cd cloncJ d-il', .

except d' iring pa:

• 47,c cc t. hen reactor caolnn' te port'ture in lerr th:1n 21?'F.

nt I r oi n t i c.r V:,17 er D. Prf-crv Co,tninment Inolotien Vn1ven r> . Prir,ry con tn i t.,

1. Durin,, re actor po,.cr cperatin,q conditienn 1. Tne pric'ry acninincont _901ntien valveu nurveillance rhn11 be performed .9 followa:

n11 isolatica valves linted in Table 4.7.2 ~

nnd all instrument line floa check valvec The operable isolation valves that rre chall be operable except as specified in a.

Soccificatica 3 7.D.2. po..er cperated nr.c auter.atically initinted ran11 be tected fer autecatic initiatica at lecst cace par operatir7, cycle.

b. Operability testin', of th] P rir.n ry Centair :n t Ir.0).nrion VM von r M 13 he in 'iceerd ne' 'ith "p 7c i fic.1t : n. '4 . f) . E . l c

VYl;FS 3.7 LIMITI :G CC: DITIO::S F03 OPER ATIC I 4.7 SUDVEILLA :CE PECUIRI'2 .:JTS

2. In the event any icolatien valve cpecified in 2. Whenever nn icolation valve licted in Table 4.7.2 Table 4.7.2 beccces inoperable, reactor power in inopernble, the positien or at lenst en other cperatic. ~iy continue pro'.ided at lcact one ' calve in meh line havin:, an inoperable valte zalve in e ch lina hT/in~ nn inoperable talve is c?711 bc ic~;ed dtily.

in thn .cde carrecpending to the isolated conditien.

3 If Soccificction 3 7.D.1 and 3.7.D.2 cannot be at ,  ; n cederly chutdc:m shall be initiated and the recotor shall be in the cold chutdo;:n conditicn v;ithin 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

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. ,I ..>

4.7.D. Priacry Containnent Icolation Valvec Th:"o lar32 oipes comrining a pcrtion of the recctor coolant cyctc~ ,' acre failu o could rerult in c r.c c re r ir <; the receter core are cupplied with wtcratic icolation : uvec (cxcept thore lines r.cedad fer er. cry '.cy core coolin; cycten operation er containncat cooling). The closure timer spceified hercin arc an' ito to prevent loco of tcre coolant from the cireu .ferentici rupture of any of thcx lir'r o;taide the c c r. ' ir ent tion frca a cteam line rupt,ure. There, thic icoletion valve closure tire is cuffici>nt t.o pr m t ur.co . rir'- the core.

In ord r to cura that the dore.a that ray renult from c '.toam line br :% do not exc:ca th > 10 CE3 '.00

ui lir.'c, it is neces.cary that no fuel rod perforation recultinr, fren the cccident occur pricr to cle ure of th e ^in stear. line icolatica 'talves.

Analycec indicate the fcel red cladding perforctienc ,culd be rvoi. : fcr the nin stea~' valve clocure tinec, including inctrument deley, ao long an 10.5 ccerric. The t<- elt ure ti: n lid t of 5 cecer n foe thec: - ;in ct. < 1 :nla tic, valve f rovid' . nu fficient -m ir to m u r- that e.1naiinq perferation~ are avoido ! . ad 10 C?it 100 li 'it s n rc' rot "xec~ ;d. H en ';nt valve in wh l i r:' i r:c u re that '

olat. ion will be ef f: cLed applyin ; t.h" . ire.le failure criteria.

Th- .m!a .tcm lino inolation valves are functionally te3ted ra a more frequent interval to ectablis':

hn ? -  : ce of relinbili ty.

Tip contair :ent in penetrated by a large nur6er of stall dinneter inntrenent linco. The flow check valver in thec< lines are tected for operability in accordance with Specificatica 4.6.g.

146