ML19260A129

Tech Spec Change Request 59 Supporting Licensee Request to Change App a of License DPR-50 to Allow ECCS Component,Decay Heat Removal Pump,To Be Removed from Svc,Resulting in Inoperability Sys for 72-h.Certificate of Svc Encl

ML19260A129
Person / Time
Site:	Three Mile Island
Issue date:	09/06/1977
From:	Arnold R METROPOLITAN EDISON CO.
To:
Shared Package
ML19260A128	List: ML19260A127 ML19260A129
References
NUDOCS 7910290746
Download: ML19260A129 (3)

Text

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UNITED STATES OF AMERICA NUCLEAR REGULATORY C05NISSIO:1 IN THE MATTER OF DOCiGT No. 50-289 LICENSE NO. DPR-50 METROPOLITAN EDISON CCMPANY This is to certify that a copy of Technical Specification Change Request No. 59 to Appendix A 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 Co= mission and been served on the chief executives of Londonderry Townchip, Dauphin County, Pennsylvania and Dauphin County, Pennsylvania by deposit in the United States mail, addressed as follows:

Mr. '4eldon B. Arehart Mr. Harry B. Reese, Jr.

Board of Supervisors of Board of County Commissioners Londonderry Township of Dauphin County R. D. #1, Geyers Church Roa! Dauphin County Court House Middletown, Pennsylvania l's057 Harrisburg, Pennsylvania 17120 METROPCLITAN EDISON COMPANY s / .

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f Vice President

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Dated: SEP - 6 1977 1480 143 39102g9 795

METROPOLITAN EDISCN COMPANY JERSEY CENTRAL POWER & LIGHT CC GA'IY AID PEiNSYLVANIA ELECTRIC COMPANY THREE MILE ISLAND NUCLEAR STATION UNIT 1 Operating License No. DPR-50 Docket No. 50-289 Technical Seecification Chance Recuest No. 59 This Technical Specification Change Request is submitted in support of Licensee'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.

METROPOLITA'I EDISON COMPANY

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/ /L' Vice' President Sworn and subscribed to me this d WI day of / m A A , 1977

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otary Public R.T A !.i. POWERS rirfQJe . #crerg Tap.. Eerks Co.

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• is Three Mile Island Nuclear Station, Unit 1 Operating License No. DPR-50 Docket No. 50-289 E=errency Technical Soecification Change Recuest No. 59 The licensee requests that the attached revised page replace page 3-22 of the Technical Specifications , Appendix A.

Reasons for Pronesed Chance The proposed change vill revise those portions of the TMI-1 Technical Specifications, Section 3.3.2, to allow an ECCS co=ponent (Decay Heat Removal Pump) to be rdhoved from service such that the affected system train may be inoperable for 72 con-secutive hours. -This change is requested in order to perform the necessary Decay Heat Removal Pump inspections and subsequent repairs, if needed, during power operation. This change shall be in effect until October 3,1977 Safety Evaluatien Justifyine Chance This change does not increase the probability of any accident analyzed in the '

FSAR in that the change only involves the method of operation of an accident mitigating system.

This change could not increase the consequences of the only accident of concern namely a Loss of Coolant Accident (LOCA) since at least one LPI system is demonstrated operable prior to taking the back up LPI system out of service.

LPI operability demonstration (and confirmation of integrity of the disassembled The pump shaft) assure that a single failure vill not affect the remaining LPI syste= during the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> exposure period.

This change does not create the possibility of occurrence of any unanalyzed accidents since no new mode of operation is conte = plated or permitted only the exposure period with reduced redundancy is extended.

The bases for TMI-l Technical Specification, Section 3.3, states , "An allovable maintenance period of up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> may be utilized if the operability of equip-ment redundant to that re=oved frem service is demonstrated i= mediately prior to removal."

Because this change is consistent with the existing bases it does not reduce the margin of safety defined in the technical specification bases.

For all of the reasons given above, this change does 1.cc represent any undue risk to the health and safety of the public or an unreviewed safety question.

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