ML20138R915

Application for Amend 127 to License DPR-54,revising Limiting Conditions for Operation Statement for Main Steam Safety Valves.W/O Significant Hazards Evaluation.Fee Paid

ML20138R915
Person / Time
Site:	Rancho Seco
Issue date:	11/14/1985
From:	Reinaldo Rodriguez SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:	Thompson H Office of Nuclear Reactor Regulation
Shared Package
ML20138R916	List: ML20138R915 ML20138R919 ML20138R925
References
RJR-85-538, NUDOCS 8511190248
Download: ML20138R915 (3)

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SACRAMENTO MUNICIPAL UTILITY DISTRICT C 6201 S Street, P.O. Box 15830. Sacramento CA 95852-181o.(916) 452-3211 AN ELECTRIC SYSTEM SERVING THE HEART OF CALIFORNIA RJR 85-538 November 14, 1985 DIRECTOR OF NUCLEAR REACTOR REGULATION ATTENTION HUGH L THOMPSON JR DIRECTOR DIVISION OF LICENSING V S NUCLEAR REGULATORY COMMISSION WASHINGTON DC 20555 DOCKET NO. 50-312 LICENSE NO DPR-54 FROPOSED AMENDMENT NO. 127 In accordance with 10CFR 50.59, the Sacramento Municipal Utility District proposes to amend its Operating License DPR-54 for Rancho Seco Nuclear Generating Station Unit 1. Enclosed is Proposed Amendment No. 127.

Attachment I to this submittal is the No Significant Hazards Evaluation in accordance with 10 CFR 50.92.

This proposal revises the Limiting Conditions for Operation statement for main steam safety valves.

Pursuant to 10 CFR 50.91(a), we have provided a copy of this letter, the proposed change in technical specifications, and our analyses of Significant Hazards Considerations to Joseph Ward, the designated representative of the State of California.

Pursuant to the Schedule of Facility Fees in 10 CFR 170.21, a check in the amount of $150.00 is provided with this Proposed Amendment.

If you have any questions concerning this proposal, please contact Mr. Ron R. J.

W Co}ombo t the Rancho Seco Nuclear Generating Station Unit No. 1 ODRIGUEk ASSISTANT GENERAL MANAGER,

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ATTACHMENT I SAFETY ANALYSIS A dynamic analysis using RELAP5 was performed to demonstrate that adequate overpressure protection of the secondary side of the steam generators can be provided if the three main steam safety valves with the lowest setpoint are out of service on each steam generator (Attachment III). This analysis is consistent with the assumptions used in the B&W Topical Report BAW 10043 on overpressure protection and justifies a revision to Rancho Seco's Tech-nical Specification Section 3.4.2.1.

N0 SIGNIFICANT HAZARDS CONSIDERATION This proposal revises Technical Specification 3.4.2.1 in a manner that meets ASME Section III code limits when applying the conservative assumptions con-tained in BAW 10043. Therefore, operation of Rancho Seco in accordance with this Proposed Amendment:

1. does not involve a significant increase in the probability or conse-quences of an accident previously evaluated,

2. does not create the possibility of a new or different kind of accident from any accident previously evaluated, and

3. does not involve a significant reduction in a margin of safety.

Therefore, significant safety hazards are not associated with this Proposed Amendment.

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ATTACHMENT II DESCRIPTION OF PROPOSED CHANGES

1. Page 3-23, Specification 3.4.2.1; Minimum operating conditions for the main steam safety valves have been revised.

2. Page 3-24, Last Paragraph of the Bases; The minimum relief capacity of the main steam safety valves is discussed.

3. Page 3-24, Reference No. 3: The B&W evaluation that demonstrates that overpressure protection of the secondary side of the steam generator can be provided with three main steam safety valves out of service on each generator is referenced.