ML19347C385

Application for Tech Spec Change Request 34A,amending License DPR-50.Certificate of Svc Encl

ML19347C385
Person / Time
Site:	Three Mile Island
Issue date:	10/03/1980
From:	Arnold R METROPOLITAN EDISON CO.
To:
Shared Package
ML19347C382	List: ML19347C381 ML19347C385 ML19347C386
References
NUDOCS 8010170516
Download: ML19347C385 (4)

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METROPOLITAN EDISON COMPANY JERSEY CENTRAL POWER & LIGHT COMPANY l

AND PENNSYLVANIA ELECTRIC COMPANY THREE MILE ISLAND NUCLEAR STATION, UNIT 1 Operating License No. DPR-50 Docket No. 50-289 Technical ~ Specification Change Request No.34A This Te:hnical Specification Change Request is submitted in support of Lice'.sce's request.to change Appendix A/B to Operating. License No.

DPR-50 for Three Mile Island Nuclear Station, Unit 1. As a pa rt. <> f this request, proposed replacement pages for Appendix A/B are als.)

included.

METROPOLITAN EDISON COMPANY By ._ e Chief Op[ffting Executive-GPU Nuclear Group Swornandsubscribedtomethis3 dayofC A , 1980 l

Notary hc GK ' J. TiiDiFER

? -- ' a ' ' Runng, Derks Co.

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UNITED STATES OF AMERICA NUCLEAR RECULATORY COMMISSION IN Tile MATTER OF DOCKET No. 50-289 LICENSE NO. DPR-50 METROPOLITAN EDISON COMPANY

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This is to certify that a copy of Technical Specification Change Request No.34A to Appendix A/B of the Operating License for Three Mile Island Nuclear Station Unit 1, has, on the date given below, been filed with the U. S. Nuclear Regulatory Cor. mission and been served on the chief executives of Londonderry Township, Dauphin County, Pennsylvania and Dauphin County, Pennsylvania by deposit in the United States mail, addressed as follows:

Mr. Donald lloover, Chairman Mr. John E. Minnich, Chairman

, Board of Supervisors of Board of County Commissioners Londonderry Township of Dauphin County R.D. #1, Geyers Church Roa<1 Dauphin County Courthouse Middletown, PA 17057 Ilarrisburg, PA 17120 METROPOLITAN EDISON COMPANY By Chief dperating Executive GPU Nuclear Group Dated: A tober 3. 1980

Three Mile Island Nuclear Station, Unit 1 Operating License No. DPR-50

- Docket No. 50-289 I. TECHNICAL SPECIFICATION CHANGE RFQUEST NO. 34A The Licensee requests the following:

A. Appendix A Replace pages 1-v with changed pages 1-ix Add pages 1-6, 1-7 and 1-8 Add pages 3/4 3-95 thru 3/4 3-141

• Add pages B3/4 3-142 thru B3/4 3-148 Replace page 5-1 with change page 5-1 Add pages 5-10 and 5-11 Replace pages 6-5, 6-6a, 6-11, 6-16, 6-17 and 6-20 with change pages 6-5, 6-6a, 6-11, 6-16, 6-17, 6-18abc and 6-20, 6-20a and 6-27 B. Appendix B Replace page i with changed page i and 11 Replace pages 1-66 with changed pages 1-24 II. Reason for Change Request This Technical Specification Change Request will modify Sections 3, 4, 5 and 6 of Appendix A and Appendix B of our Technical Specifications to incorporate the requirements of 10CFR20, 10CFR50.34a, 10CFR50.36a, 10CFR50 Appendix I and 40CFR190. These are being submitted as requested by Mr. Brian K. Grimes in his letter of November 15, 1978. This Technical Specification Change has been developed considering the guidance provided by drafts of NUREG-0473 and NUREG-0133 which were provided as enclosures to the letter from Mr. Grimes.

III. Safety Evaluation Justifying Change The Radiological Effluent Technical Specifications (RETS) have been developed at the request of the U. S. Nuclear Regulatory Commission. The requested form represented the addition of new requirements to insure compliance with portions of 10CFR50, 10CFR20 and 40CFR190 as well as reorganizing some of the present technical specifications.

The attached technical specification changes address portions of 10CFR50,

10CFR20 and reorganize current portions of Sections A and B of the Three Mile Island Nuclear Power Station, Unit 1 Technical Specifications. None of there represent an unreviewed safety question such that

a) The probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the safety analysis report may be increased.

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I b) The poosibility fer an accident or malfunction of a different type than any evaluated previously in the safety analysis report may be created.

c) The margin of safety as defined in the basis for any technical specification is reduced.

IV. Amendment Classification Per 10CFR170.22 ,

1 This submittal, provided at the NRC's request, references (a) and (b),

revised entirely an already filed submittal of June 4, 1976 (Technical Specification Change Request No. 34) proposing Technical Specification to fulfill the requirements of Appendix I. We conclude therefore, that this Amendment is exempt from any fees defined in 10 CFR Part .

170.12(c) since fees were not applicable when the requirements put forth by Appendix I to 10 CFR Part 50 became effective, and since review of the previously submitted information has been delayed by the USNRC pending development of revised guidance issued in July, 1978 (reference a).

References:

(a) Letter from B. D. Vassallo, Assistant Director for Light Water Reactors, USNRC, to All Pressurized Water Reactor Licensees, dated July 10, 1978.

(b) Letter f ron B. K. Grimes, Assistant Director for Engineering and Projects, USNRC, to All Pressurized Water Reactor Licensees, dated November 15, 1978.

V. Implementation These changes will be incorporated into the Three Mile Island Nuclear Station Unit 1 Technical Specifications 90 days after approval by the Commission, but in no case before January 1, 1981.

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