ML19210B081

Amend 36 to DPR-50,revising Definition of Containment Integrity Re Airlock Maint,Repair or Mod & Adding Surveillance Requirements for Interlock Sys of Airlocks

ML19210B081
Person / Time
Site:	Crane
Issue date:	01/07/1978
From:	Reid R Office of Nuclear Reactor Regulation
To:
Shared Package
ML19210B079	List: ML19210B078 ML19210B081 ML19210B082
References
NUDOCS 7911040028
Download: ML19210B081 (6)

Text

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UNITED STATES yg NUCLEAR REGULATORY COMMISSION

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W ASHING ton, D. C. 20555 e.s, m /

METROPOLITAN EDISON COMPANY JERSEY CENTRIL POWER AND LIGHT COMPANY PENNSYLVANIA ELECTRIC COMPANY DOCKET NO. 50-289 THREE MILE ISLAND NUCLEAR STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.36 License No. DPR-50 1.

The Nuclear Regulatory Coimission (the Commission) has found that:

A.

The application for amendment by Metropolitan Edison Company, Jersey Central Power and Light Company and Pennsylvania Electric Company (the licensees), dated October 28, 1977, complies with the standards and requirenents of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in confomity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the' Commission's regulations; i D.

The-issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

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. l Accordingly, the license is amended by changes to the Technical 2.

Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-50 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and 8, as revised through Amendment No. 36

, are The licensee hereby incorporated in the license.

shall operate the facility in accordance with the Technical Specifications.

This license amendment is effective as of the date of its 3.

issuance.

F0_R THE NUCLEAR REGULATORY COMMISSION d uI kl W

Robert W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors

Attachment:

Changes to the Technical Specifications Date of Issuance: January 7, 1978 f

1507 329

ATTACHMENT TO LICENSE AMENDPENT NO. 36 FACILITY OPEPATING LICENSE NO. DPR-50 DOCKET NO. 50-289 Revise Appendix A as follows:

Remove Paces Insert Pages 1-5 1-5 4-34a & 4-34c 4-34a & 4-34t The changed areas on the revised pages are shown by marginal lines.

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.6 PO.G D,.S 1.6.1 QUA :PA'T" PC'4ER 711,7 Quadrant ;cver tilt is defined by the fol. levi:., equatics and is ex; essed in pereest.

100

. Fever in a-r : re tat 1.t Average ;cver of C1 quad 2::s

.a The quadrant tilt limits are stated in Specifiestic: 3.5.2.k.

1. 6. 2 REA0 TOR FC'4E3 D'A1.A.02 Reacter pcver istc as:e is the ;cver 1: the t:; half of the ---

'-.:s the power in the bet :: half cf the ::re e.r;ressed as

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e : age of rated ;cver.

I: balance is =c:'t: red ::::inuously by the ?.F5 usi:g i:;u-fic: the pcVer rt ge cha::els.

I:te. lance 'ts a.re defined in Specift:stic: 2.1 a:d i=t c ance setpoints are defined in Specifi:stien 2.3 7

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Contal=est 1:tegrity exists vte: the folleving co.*itie:s are satisfied:

a.

The equip e:: h:::h is elesed a:d sealed a:d heth decrs of the ;ers:.rel l

hatch and energe :7 hatch are closed and sea'.ed exce;;.s is "t"or "f"

below.

b.

At least c e decr c each of the persettel hat:h and energency hatch is closed a:d sesled duri:g refueling er perse=e1 passage through these hatches.

c.

All =enautensti: e==tain e isolatic: valves and bli:d fisages are closed as required by the '!;

sin =en: Integity o -->

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" atta: ed to the c;ersting precedure "C:stai==?:: Integrity and A: cess *icits."

d.

All autcratic cc::a'--a - 'solatic: valves are operable er Iceked closed.

e.

The contaf==ect leakage deter =ised at the last testing inte: tal satisfies Specificatic: *.k.1.

f.

Crie door of the personnel hatch or emergee (,

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for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for maintenance, repair or o1;* ;r a t. r frS-tidad the Other dCor of the hatch is maintained Closed and hat been }*3b tested and found to m*et the loral laab "a!-

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1.8 FIRE SUDFSESSI**i *JA"13 SYS' Et A FIRE SUFFEISS ::I ~4ATI3 SYSTE! shsil censist ef: a vater scurce. psvity tank or pu=p a:d distributien pipi::g -ith associated sectic 211:ing ::: rel or isolati:: vCve:. Such talves icel.de yard 'yd.2 cu-t valves, 1:d the first valve upstret: of the '.ater fiev riar: device en each sprinxier, hose standpipe er spray syste: riser.

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centsir. er-vil; te strer.gth tested at lic per:er. Of desig press ee and ; ear.

rate tettei at the desig-pressre.

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.a These tests vill verify that the ;eakage rate frc: rea::cr building pressuri:ati:n satisfies the relationships given in the specificati ns.

Tne perf r=ance of periodie integrated and Ices; len age rate tes*.s dring t'e r

p; art life pr:vides a c= rent assessment of potentia; lenage frc: the certain=e.:t in ca:e cf an acciden-that vcu;d pressurize the interier cf the contain:*ent.

In crder t provide a realistic a;;ra; sal of the integrity of the containment under accident conditions "as found" loca; ledage res.*ts =ust be docu ente:

for correcticn cf the integra*ed ledage rate test resu!* s.

Contain=er.;

Ase;ati:- valves e.re te be c!csed in the nor=al canner prict to local or integrated Ied age rate tests.

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Amendment No. F 36 h-31.e l ~'

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The minimum test pressure cf 27 5 psig for the periodie irtegrated leakage rate test is sufficiently high te pr: vide an a:: urate measurement cf the J eaksge rate and it duplicates the pre-operational leakage rate test at the redueed pressure. 7te spe:ifacatien provides a relationship fer relating the censured leakage of air at the reduced pressure to the potential leakage of 55 p:ig.

The minimu: of 2-hours was specified for the integrated leakage rate test to help stahilize conditions and thus i= prove a: cura:y and to better evaluate data scatter.

The frequency of the periodic integrated leakage rate test is keyed to the refueling schedule for the reacter, because these tests can best be perfer=ed during refueling shutdevns.

The specified frequercy of periodi: integrated leakage rate tests is based en three ma'er considerations.

First is the icv probability of leaks in the liner, because of confer =ance of the complete contain=ent to a 0.11 percent leakage rate at 55 psis during pre-operational testin6 and the abeen'ie'Or any significant stresses in the liner during reactor operation.

Second is the more frequent testing, at design pressure, of those portiens of the contair.nent envelope that are most likely to develop leaks during reactor operation (penetrations and isolation valves which are not continuously pressurized by the penetratien pressurization syste= or are not fluid blocked post-accident by the fluid tiock system) and the lov value (0.06 percent) of leakage that is specified as acceptatie from penetrations and isolation valves.

Third is the tendon stress surveillance progrs= vhich provides assurance that an important part of the structural integrity of the contain=ent is maintained, acre frequent testics cf various penetrations is specified as these Ioeatiens are more susceptible tc leakage that. the reseter building liner due to the acebanical closure involved. Particular attention is given to testing those penetrations and process lines not serviced b; the penetration press':rizatien system or the fluid block syste=. The basis for specifying a tota' leakage rate of 0.06 percent frc: those penetrations and isolation valves is that more than one-half of the allevable integrated leakage rate vill be frc: these sources.

Valve operability tests are specified to a.ssure prcper elesure or opening of the remeter building is01stien valves te provide for iselati:n er functiening of Engineered Safety Teatures syste=s. Valves vill be strak ed to the positic:

required to fulfill their safety function unless it is established that su:h testing is net practical during operation. Valves that cannot be full-streke tested vill be part-stroke tested during operation and full-stroke tested during each nor=al refuelir4 shutdevn.

Periodic surveilla":e C# the airloc. interlock syste-c 13 specir:e: to assure Ccetinued ope"3bility ard erec1Udt irstances where ere e-tg.r g eg r. 3rg irad.er*Antly le#* orer.

W9er ar interlock is inoceratia arc r.p ta:e e;*

integrity is recuired, local surervi*ior cf airloca cre atic

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RE FE G E'C E (1)

FS'R, Sectior 5-O h

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