ML20133J723

Rev 2 to Proposed Amend 110 to License DPR-54,deleting All Refs to Current Reactor Vessel Matl Surveillance Requirements from Tech Specs

ML20133J723
Person / Time
Site:	Rancho Seco
Issue date:	10/14/1985
From:	Reinaldo Rodriguez SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:	Thompson H Office of Nuclear Reactor Regulation
Shared Package
ML20133J725	List: ML20133J723 ML20133J741
References
RJR-85-478, NUDOCS 8510210059
Download: ML20133J723 (3)

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$SMU=SACRAMENTO MUNICIPAL UTILITY DISTRICT O 6201 S Street. P.o. Box 15830. Sacramento CA 95852 1830,(916) 452-3211 AN ELECTRIC SYSTEM SERVING THE HEART OF CALIFORNIA RJR 85 478 October 14, 1985 DIRECTOR OF NUCLEAR REACTOR REGULATION ATTENTION HUGH L THOMPSON JR DIRECTOR DIVISION OF LICENSING U S NUCLEAR REGULATORY COMMISSION WASHINGTON DC 20555 DOCKET N0. 50-312 LICENSE N0. DPR-54 PROPOSED AMENDMENT NO. 110, REVISION 2 By letter dated March 13, 1985 and May 3, 1985, the NRC found the Babcock and Wilcox Owners Group (B&WOG) Materials Conmittee Report, BAW 1543, Rev. 2, Integrated Reactor Vessel Material Surveillance Program, acceptable for comply-ing with Section II.C of Appendix H of 10 CFR 50. Report applicability listed all B&W 177-FA plants, including Rancho Seco.

NRC's letter dated May 8, 1985 to the Chairman, B&WOG, reiterated Commission acceptance in the following:

Since the licensees of the above listed plants have not yet formally requested consideration of the integrated reactor vessel materials program for their plants, they may provide such a request for approval ..... With such a request, each licensee may also submit a request for a license amendment which would remove the current reactor vessel material surveillance requirements from the Technical Specification.

By letters dated June 27, 1984 and December 24, 1984, the District submitted to the Commission Proposed Amendment 110 and Revision 1 respectively.

The original Proposed Amendment 110 addressed the changes made to the Rancho Seco reactor vessel material surveillance as a result of the Babcock & Wilcox Integrated Reactor Vessel Material Surveillance Program. Revision 1 addressed a revision to the capsule withdrawal schedule.

Pursuant to the above mentioned NRC letter to the Chairman, B&WOG, the District wishes to delete from the technical specifications all references to the current reactor vessel material surveillance requirements. Attachment 1 to this submittal is a description of the changes for Proposed Amendment 110, Revision 2.

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RANCHO SECO NUCLEAR GENERATING STATION L 1444o Twin Cities Road, Herald, CA 95038 9799;(209) 333 2935

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Thi: proposed amendment is one of corrective updating and judged to have no effe~t on safe operation of the plant. Operation of Rancho Seco in accordance with Proposed Amendment 110, Revision 2:

1) does not involve a significant increase in the probability or consequences 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.

Accordingly, significant safety hazards are not associated with this amendment.

It is requested that the amendment authorizing this change become effective immediately after receipt.

The required fees for this proposed amendment were submitted with our original transmittal on June 27, 1984.

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

Colomb at Rancho Seco Nuclear Generating Station Unit No. 1.

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\ ti R. J. DR G Z ASSISTANTGENEh(LMANAGER, NUCLEAR J Attachment b

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ATTACHMENT I DESCRIPTION OF PROPOSED CHANGE

1. Page ix, List of Tables; Deleted Table 4.2-1 title; inserted "THIS TABLE HAS BEEN DELETED."

2. Section 4.2.1, Page 4-10; Deleted.

3. Bases, Page 4-11. Deleted first paragraph.

4. Bases, Page 4-12. Deleted last paragraph.

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