ML20141K849

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Forwards Category B Rept Re Util Re Adequacy of Primary Containment & Safety Sys Components.No ACRS Action Appears Warranted
ML20141K849
Person / Time
Site: Oyster Creek
Issue date: 09/25/1970
From: Mckinley J
Advisory Committee on Reactor Safeguards
To: Bush S, Stratton W
Advisory Committee on Reactor Safeguards
Shared Package
ML20091A092 List: ... further results
References
FOIA-91-282 NUDOCS 9203250289
Download: ML20141K849 (3)
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September 25, 1970 ky '.4-wy .,

$y' W. R. Stratton, Chairman Oyster Creek Subcoimaittee S. H. Bush, Vice Chaltuan, ACKS A CATEGORY B REPORTS - OTieTER CREEK - JERSEY CDITRAL POWER & LIGirt COMPANY LETTERS DATED SEPITMBER 8, 10, 11, 12, 14 & 17, 1970 AND DEL 1.ETEER l,

DATED SEPTEMBER 21, 1970 Attached is a brief sunuaary of the information presented 1i the subject correspondence. No ACES action appears warranted.

All itsac except the Supplesent to the annual report should be incorporated in your set of project documents to maintain an up-to-date description of the plant, organisation, procedures, etc. The supplement to the annual

) report r.ay be destroyed upon completion of your rarview.

Original Signed by J. C. McKinley J. C. McKinley j 8taff Assistant Attachments:

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2) Jersey Central Power & Light Co 1tre dtd 9/8, 10, 11, 12, 14 &

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3) DRL ler dtd 9/21/70 cc: ACES Members w/sttrts 1 & ltre dtd 9/8, 14, & 17/70 l

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~g OYSTER Cart" Jersey Central N.r & Limht Crent istter dated * ~ --

6.1970 f orwards their answer to DLL's geestion Be. 344 ,, '

regarding an evaluation of the adequacy of the prisery ,4 contaitument and safety systes coe m te to withsteet Me envirotweental conditions that tasy estet in the eventzefj ..

a stese rolesse, such as occurred at Dresden Unit 2.=

Jersey Central concludes that the desise of the Oyster Creek Containment System and the drywell systems required during a loes of coolant seeident is adequate to protect the public, to provide suf ficient indication of the status of the reactor, and to allow for the proper operation of safety systems in the event of a loss of coolant accident in the drywell.

1 No ACRS action appears warranted, i

JLrsey Central _ _ fower_6hht Coep,any letter dated September j 10. 1970 transmite Change Regaest No. 3 to the Technical i Specit ications . The proposed change is to allow one channel in a trip system to be oude inoperable briefly for testing and calibration.

No ACES action appears warranted.

l Jersev Central Power 6 Light Ccamany let ter dated September 11, 1070 answers DRL's request for iniforestion concerning I furnace senaltiued stainless etsel of and within the reactor i

coolant pressure boundary. Most of the inforuation has beet' included in earlier sutuissions.

i Ho ACRS action appeara warranted.

I Jersey C ntral Power 61.ight Corapany le*ter dated September JJ,1970 torwards the Sucuary Technical Report regarding Secondary Centaitument Leak Rate Testing, for the period July 1969-June 1970.

The Standby Cas Treatment Syster as originally desi;.ad, f ailed to meet the miniman operating requirements during the Pre-Op Testing in February and March of 1969. Majac leaks were discovered around tbs Reactor Building roof flashing, personnel doors, electrical penetrations, iuse the railroad airlock doors. Af ter making repairs t4 these areas and increasiug the f an motors f roci 5 to 10 horsepower, the system: still f ailed to yield satisf actory results, .

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5 t-OYSTER CREEK (CONT'D) The General Electric Coumpesy them proceeded with major system modifications. Noe sedificatismeD discussed in detail in Amendment 53 et the Mg j; In order to maintain a negative pressere of 0.35,w .

inches of water in the Reactor Seilding, the p flow rate was increased from 1200 BCFM per fem to W 2600 BCFM per f an. This incrossed flew rate assees-itated changes to the sharcoal filters to insure the filter ef ficioney was mot impaired by the redeced residence time. N alternate Standby Filter Train is now started by a loss of flow signal in theorent

- the selected exhaust fan fails to start. These anodifications, however, did not alter the overall i saf ety requirenents of the systern as originally stated j in Volume 1 of the FDEAR. N Standby Cas Treatament j System Pre-Op Test C-14 was successfully eempleted during the first week of July, 1969.

Because of the inability to reproduce satisf actory leal, rats data af ter the Fre-Op Test, en investigation of the Reactor Building revealed emeessive leakage f arour o the personnel doors. Trunion Room doors, cable trays, and the outer airlock door. N Matutenance Departrent installed closing devices en the outer airlock door and corapleted sealing the leaks in the railroad airlock. Rubber seals were replaced er adjusted on all of the Reactor Building personnel doots.

By tha end of August, mil of the repairs were completed and building leak rate tests on September 3,1969 yielded satisfactory results.

1 No ACRS action appears warranted.

Jersey Central Power _L Lisht Corspany letter dated l'

I s e n t er.ibe r i t. , 1970 forwards supplement No. I to l Annual Report No. 1. N oupplement describes the l _ , ,

repairs made to 23 rod drives in October 1969.

l 1 No ACRS action required.

Jersev Central Power & Linht Company letter' dated September 17, 1970 forwards Amendcent 63. We Armendment is in support of their request for authort-sation to operate at power levels up to 1690 Wt and will be reviewed by the Cessaittee in October 19f0.

V DRL letter dated Septe ~oer 21. 1970 traneutts an erdet extending the Oyster Creek POL to April 9, 1 .

No ACRS action required.

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