ML20141K874

Notification of Oyster Creek 701111 Subcommittee Meeting in Washington,Dc to Further Consideration of Proposed Increase in Power Level from 1.600 Mwt to 1,690 Mwt.Tentative Schedule Listed

ML20141K874
Person / Time
Site:	Oyster Creek
Issue date:	11/02/1970
From:	Mckinley J Advisory Committee on Reactor Safeguards
To:	Stratton W Advisory Committee on Reactor Safeguards
Shared Package
ML20091A092	List: IA-91-282, Forwards Written Statement Submitted by Sp Russo for ECCS Subcommittee Meeting on 770129,for Info.W/O Encl ML20141K026 ML20141K047 ML20141K056 ML20141K063 ML20141K066 ML20141K070 ML20141K076 ML20141K082 ML20141K091 ML20141K095 ML20141K121 ML20141K137 ML20141K141 ML20141K153 ML20141K163 ML20141K175 ML20141K185 ML20141K190 ML20141K359 ML20141K365 ML20141K368 ML20141K372 ML20141K375 ML20141K379 ML20141K382 ML20141K386 ML20141K390 ML20141K395 ML20141K398 ML20141K402 ML20141K406 ML20141K408 ML20141K415 ML20141K418 ML20141K423 ML20141K426 ML20141K432 ML20141K436 ML20141K441 ML20141K618 ML20141K620 ML20141K625 ML20141K626 ML20141K630 ML20141K633 ML20141K635 ML20141K637 ML20141K641 ML20141K643 ... further results
References
FOIA-91-282 NUDOCS 9203260031
Download: ML20141K874 (2)

Text

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Novenber 2, 1970 l

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Dr. W. R. Stratton i OYSTER CREEK StTBCONITTEE HEETING MOVDGER 11, 1970  !

i ne Oyster Creek Subermnittee will meet on November 11, 1970, in Washington, D. C., to Mrther consider the proposed increase in maxitem power level frorr 1600 Wt to 1690 Wt. We adequacy

&f the current core st -dt~ cooling system will also be discussed, h e meeting is present / p.anned to be held in Room 1062 H.

no tentative schedule for Wednesday, Ncnrember 11, 1970 ist 8:30 AM Executive Session 9:00 AM Heeting with the Regulatory Staff 9:30 AM Heeting with RDT Contractor (INC) 10:30 AM Heeting with Jersey Central Power & Light Co.

11:45 AH lunch Lt00 PM Continue Heating 3:00 PM Adjourn Topics to be discussed incNde

1. a. Ivaluation of the adequacy of the current core i

standby cooling system based on current experi-mental information and analysis.

b. Applicant ten of TLECHT Yest results

c. Anolicability of the level eve 11 phenomenon,

d. rn t .+ . .isl usefulness of the fire protection systen ,

tbc t. ore flooding.

. 2. Radvaste releases as cornpared with technical specificatten ,

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3. Bases for not installing a third diksel drivsn generater."

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! Topics s>ay be added to or deleted free the sten list at the '*rafj'l ,

l i discrett e of the Sutconmittee Chairs.an. &* j Attendance by Dr. Stratton, Dr. Rendrie, Dr. Kaufman, Mr. Elil, Dr. O' Kelly, and Dr. Siess is anticipated.  ;

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i J. C. McKinley '

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JCH:bjh 11/9/70 trajectt Oyster Creek ,,

11&Dht: Provisional 7perating License issued Operation at increased power level requested

• k lackgroundt December 12, 1968 - ACR8 operating license report April 9, 1969 - POL issued May 3, 1969 - Initial criticality Doesaber 22, 1969 - Completed 100 hr full pont (1600 l mrt) demonstration May 5,1970 Amendosot No. $$ requesting authorisation to operate at 1690 Hwt i

June 2,1970 - Amendment No. 57 correcting and supplement-ing Amendment No. 55 l July 30, 1979 - Amendment No. 38, startup test results h ptember 17, 1970 - Amenenent No. 63, additional inforn-ation in support of Amendment No. 55 i september 30, 1970 - DRL report on the proposed power

! increase October 14, 1970 - blcommittee meeting October 15, 1970 - ACRS nieetirig Novem5er 10,1970 - Supplemental DEL report November 11, 1970 - Subcoaur.ittee meeting Jersey Central power & Light Company has requested a " mini stretch" power increase from 1600 to 1690 MWt. The initial DRL report on this increase stated that the POL evaluation of the engineered safety features ras based on a stretch power rating of 1860 MWt and therefore, they did not believe operation at 1690 MWt would present a hasard not previously

\ considered.

f The licenses has added two anticipatory scram signals; one from turbine l trip, the other from generator load rejection.

The Cocunittee review has centered on the adequacy of the current core I

standby cooling system. DRL was asked to evaluate that system in light of current experimental information and analysis, j Topics for consideration at the 127th ACR8 meeting include:

1. Adequacy of current ECCS

2. Review of rationale that led to decision to not install the third

, diesel generator. M!i

3. A momparison of actual radvaste releases with the technical spec 1* k ,"

fiention limits. }

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