ML20141L865

Forwards Util Transmitting Amend 69 to Plant Description & Safety Analysis Rept

ML20141L865
Person / Time
Site:	Oyster Creek
Issue date:	06/01/1972
From:	Skovholt D US ATOMIC ENERGY COMMISSION (AEC)
To:	Siess C 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 9203270050
Download: ML20141L865 (3)

Text

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UNITED STATES -

- ATOMIC ENERGY COMMISSION

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%n e June 1, 1972 y 6 t,i il il tecket No. 50 219

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, Dr. Chester P. Siess Chairman, Advisory Cocnittee

. on Reactor Safeguards U. !.. Atomic Energy Comission Washington, D. C. 20545

Dear Dr. Siess:

Sixteen (16) copies of the following are transmitted for the Comittee's infomation:

Letter f rom Jersey Central Power 61.ight Company dated May 26, 1972, transmitting the following:

(1) Amendment No. 69 to the Oyster Creek Station Facility Description and Safety Analysis Report, and (2) Change Request No. 12 to the Ovst;,r Creek Techr.ical Specifications.

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Sincerely, l

25e.m.c- . ( f.Q ? f i t .

1. :e

' ' Donald J, Skovholt I

Assistant Director for Operating Reactors Directorate of Licensing

Enclosures:

As stated above 1

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q; l '1 D SUFPLDalfr No.155 CAfs00RY B Dracer Creet June 30, itM m.;

km uts' containment torov out of Service *. _.

g, F ACES- Jersey Central Power Q 0aht Caseany 3 ,,r dated May 17. 193,'

formally submits the request containd i r ,; heir TWK of the some date (see Supplement No.134, page 10). 4EC letter dated May 18. 1072 approves the roguest.

No ACKS action is recomanended.

The enclosed material should be retained and the TWI dated May 17, 1972 may be discorded, i

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. WRS Core Physics Calculations ACRS Jersey Centrale Power & Liaht Company letter dated May 26, 1972 forwards Amendment No. 69 to the FSAR answering questions l_ contained in AEC letter dated April 25, 1972 (een Supplement l No. 153, page 49). In addition, Proposed Change No. 12 to the i f Tech Specs is subnitted to make plant safety systee operation consistent with the analyses of Assendment No. 69.

A review c,f the previously subenitted transient analysis was done in support of the request for the Cycle 2 core releed. This .

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consisted of a review of the parameter changes for the reload core and a coe.parison of these parameters with those used in

{ previous analysis. The' original conservatissa in tbs earlier l

b transient analyses were suf ficient to cover the einer changes I: i attributed to the reload core. During this review for the Cycle 2 reload at Oyster Creek, it became apparent that a

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significant change in the shape of the scram reactivity insertion-curve is required in order to ensure conservatise throughout core life. However, since the reanalysis of the transients considering this new scram reactivity insertion b curve was not completed, and since operation without

coi 31deration of this change would not result in exceeding Safety Limite even if a transient did occur -the review of the  ;

transients for the reload did not include this change. -As-stated in the- submittal, the comparison between Cycle 2 care dynamic characteristics and' the characteristics of the sore used in the Amendment 65 transient analysis resulted in no -

significant changes. The requested back-up information is l

included in this submission, l1 I

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i SUFFLEMENT *). 155 CATEGORY 4 Oyster Creek Continued The principal changes in the Tech Specs involve the lowering of the pressure setpoint on the electromatic relief valves to 1070 psig and the slightly improved eentrol red serme tLane to 90% in 5 sec. TU s is needed to be consistent with the new assweptions used in the transient reanalyees and is discussed in detail in Amendment 69 to the Oyster Creek F98AR.

The setpoints for the High Reactor Pressure Scree and the High teactor Pressure initiation of the Isolattee Ceedesser na also being changed to 1060 peig.

No ACRS action 12 recoenmecded .

I The enclosed anendment should be incorporated into your copy

! of the TSAR and the eroposed change to the Tech Space retained pending Regulatory Staf f action.

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Form AEC-518 (Rev 943 AfCM C2+0 c. s. mvtpwru racopeu ot rn a me o . m -:4-