ML20149J031

Forwards Tscr 263 Clarification Which Provides Amended Ref Citation in Util 970421 Submittal.W/Certificate of Svc

ML20149J031
Person / Time
Site:	Crane
Issue date:	07/17/1997
From:	Langenbach J GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
6710-97-2312-1, NUDOCS 9707280014
Download: ML20149J031 (4)

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GPU Nuclear,Inc.

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. Route 441 South FA dd 1 057 0480 Tel 717 S44-7621 (717)948-8005

'6710-97-2312-1 July 17,1997

- U. S. Nuclear Regulatory Commission Attention: Document ControlDesk nWashington,DC 20555

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Subject:

Three Mile Island Nuclear Station, Unit 1,(TMI-1)

Operating License No. DPR-50 Docket No. 50-289 Technical Specification Change Request (TSCR) No. 263 Clarification ofCited References In accordance with 10 CFR 50.4(b)(1), enclosed is TSCR No. 263 Clarification. Also enclosed is the Certificate of Service for this request certifying service to the chief executives of the township and county in which the facility is located, as well as the designated officid of the Commonwealth of Pennsylvania, Bureau ofRadiation Protection.

The purpose of this TSCR Clarification is to provide an amended reference citation in GPU Nuclear (GPUN) Inc. submittal of April 21,1997 GPUN Letter No. 6710-97-2133-1. GPUN requests the expedited review and approval of the license amendment authorizing this change become effective

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prior to the restart from the 12R refueling outage scheduled to begin on Sep' ember 5.1997.

1 Sincerely, m

ames. W. Langenbac!

Vice President and Director, TMI Enclosures

. JWUGMG cc;

- AdnatistratorRegionI TMI Senior. Resident Inspector

' TM11 Senior Project Manager lllll l lll]lllllllllllll 9707280014 970717)

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l METROPOLITAN EDISON COMPANY JERSEY CENTRAL POWER & LIGHT COMPANY

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AND PENNSYLVANIA ELECTRIC COMPANY THREE MILE ISLAND NUCLEAR STATION, UNIT 1 Operating License No. DPR-50 Docket No. 50-289 Technical Specification Change Request (TSCR) No. 263-Clarification 4

l This TSCR Clarification is submitted in support ofLicensee's request to change Appendix A to Operating License No. DPR-50 for Three Mile Island Nuclear Station, Unit 1. As a part of this request, proposed replacement pages for Appendix A are also included.

GPU NUCLEAR INC.

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BY.

(, --'4 Vice President and Q ector, TMI Sworn and Subscrib,eq/[u to before me this Q day of.ji-/

,1997.

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, Notary Puke N(tarial Seal '.

Suzanne C, ukkasik, Notary PubHc -

Londonderry Jwp., DaupNn County My Commission apires Nov. 22,1999

- Member, Pennsyle.'al hlation of NotarWs u

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UNITED S7 ATES OF AMERICA NUCLEAR REGULATORY COMMISSION IN THE MATTER OF DOCKET NO. 50-289 GPU NUCLEAR INC.

LICENSE NO. DPR-50 CERTIFICATE OF SERVICE i

This is to certify that a copy of Technical SpeciFcation Change Request No. 263-Clarification to Appendix A of the Operating Licer.se for Three Mile Island Nuclear Station Unit 1, has, on the date given below, been filed with executives of Londonderry Township, Dauphin County, Pennsylvania; Dauphin County, Pennsylvania; and the Pennsylvania Departrnent ofEnvironmental Resources, Bureau of Radiation Protection, by deposit in the United States rnail, addressed as follows:

E Mr. Darryl LeHew, Chairman Ms. Sally Klein, Chainnan Board of Supervisors of Board ofCounty Corranissioners Londonderry Township of Dauphin County R. D. #1, Geyers Church Road Dauphin County Courthouse 4

Middletown, PA 17057 Harrisburg, PA 17120 Director, Bureau of Radiation Protection PA Dept. ofEnvironmental Resources Rachael Carson State Office Building P.O Box 8469 Harrisburg, PA 17105-8469 Att: Mr. Stan Maingi d

GPU NUCLEAR INC.

A BY-e Piesident and Dithr, TMI j

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Three Mile bland Nudecr Planta Unit 1 (TMI-1)

Oncrating License No. DPR-50 Docket No. 50-289 W.

Technical Specification Change Request No. 263 Furthennore, impact upon the margin to safety is limited because the results of the LOCA analyses demonstrate that the 10 CFR 50.46 acceptance criteria are met, specifically: the PCT limit and the core-wide oxidation limit of I percent of the fuel cladding, as identified in the Technical Specification bases. Hence the margin of safety as defined in the bases of any -

technical specification is not significantly reduced orimpacted by the implementation of this change request, or the editorial changes described above.

5.0 IMPLEMENTATION

GPU Nuclear, Inc. requests that the amendment authorizing this change become etTective prior to the restart from the 12R refbeling outage scheduled to begin on September 5,1997 and which willlast

~ approximately 45 days.

6.0 REFERENCES

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GPU Nuclear Inc. will make available on-site the following referenced proprietary documents for NRC inspection, if equired, which were used in the Safety Evaluation above:

6.1 BWNT Document 86-1202153-00,"Mk-B9 LL Spectrum LOCA Study," dated 6/27/91.

6.2 BWNS Document 86-1201110-00," TACO 3 4-FT LOCA LHR Limit Analysis for 177-Fuel Assembly Lowered Loop Plants," dated December 10,1990.

6.3 BWNT Document 51-1239250-00, "PSC 5-94 LOCA Reanalysis," dated June 9,1995.

6.4 BWNT Document 51-1239658-00," Assessment of PSC 5-94 on Core Limits," dated August 9,1995.

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l 6.5 BWFC Document 51-1235309-00,"Op. Limit Eval. for PSC 5-94," dated December 13, j

1994.

i 6.6 FTI Document BAW 10222, "TMI-l 2772 MW1 LOCA Analysis with RELAP5/ MOD 2 B&W," dated March 1997.

i 6.7 FTI Document 74-1152414-05," Emergency Operating Procedures Technical Bases Document," Rev. 5, dated August 8,1991.

l 6.8. FTI Document BAW 10192P,"BWNT Loss ofCoolant Accident Evaluation Model for Once-Titrough Steam Generator Plants," Rev. O, dated February 1994.

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