ML20210A448

Rev 1 to Proposed Amend 114 to License DPR-54,revising Tech Specs to Reflect Provisions for Testing Shunt Trip Attachments & Silicon Controlled Rectifier Relays

ML20210A448
Person / Time
Site:	Rancho Seco
Issue date:	11/08/1985
From:	Reinaldo Rodriguez SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:	Thompson H Office of Nuclear Reactor Regulation
Shared Package
ML20210A452	List: ML20210A448 ML20210A473
References
GL-85-10, RJR-85-534, NUDOCS 8511150033
Download: ML20210A448 (3)

Text

o o t

asuunSACRAMENTO MUNICIPAL UTILITY DISTRICT O 6201 S Street, P.o. Box 1583o. Sacramento CA 95852-1830.1916) 452-3211 AN ELECTRIC SYSTEM SERVING THE HEART OF CALIFORNIA RJR 85-534 November 8,1985 DIRECTOR OF NUCLEAR REACTOR REGULATION ATTENTION HUGH L THOMPSON JR DIRECTOR DIVISION OF LICENSING V S NUCLEAR REGULATORY COMMISSION WASHINGTON DC 20555 DOCKET N0. 50-312 LICENSE NO. DPR-54 l PROPOSED AMENDMENT NO. 114, REVISION 1 In accordance with 10 CFR 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. 114, Revi-sion 1. Attachment I to this submittal is the No Significant Hazards Evaluation in accordance with 10 CFR 50.92.

This proposal is in response to Generic Letter 85-10 and supersedes the previous Proposed Amendment No. 114, dated October 19, 1984, in its entirety.

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.

Since this is a revision to Proposed Amendment No. 114, no additional license fees are required.

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

{,o o . at Rancho Seco Nuclear Generating Station.

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R. J. ODRIG Z ASSISTANT GEN RAL MANAGER, NUCLEAR 0511100033 e51100 2 ADOCK 0500 g Enclosures 3 KDR i I l l

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ffotary Public RANCHO SECO NUCLEAR GENERATING STATION () 14440 Twin Cities Road, Herald. CA 95038 9799;(209) 333 2935

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ATTACHMENT I SAFETY ANALYSIS As a result of Generic Letter 83-28, an automatic shunt trip attachment has been installed and technical specifications have been revised to include pro-visions for testing the shunt trip attachment and the SCR relays. Rancho Seco Technical Specifications have been modified according to the guidelines contained in Generic Letter 85-10. Generic Letter 85-10 presents acceptable changes in the form of Model Standard Technical Specifications (STS). Pre-viously, there were no requirements for testing the SCR relays, therefore, the sections on SCR relays from the Model STS have been inserted into Rancho Seco Technical Specifications. However, the Model STS action statement for SCR relays has been modified according to the B&W Owners Group comments con-tained in Attachment III. The sections on the shunt trip attachment have been incorporated into the existing specifications for the reactor trip breakers. Originally, reactor trip breaker LC0 statements only dealt with the undervoltage device, that is if the UV device fails, the breaker will not operate. Now with the addition of the shunt trip which acts in parallel to the UV device, both trip features must fail in order for the breaker not to open. If this unlikely event were to occur, the original LCO statements would apply and are, therefore, retained. With one of the diverse trip features failed, the breaker is still capable of operating and the Model STS guidelines for this situation have been incorporated into the Rancho Seco Technical Specifications.

N0 SIGNIFICANT HAZARDS CONSIDERATIONS These proposed changes provide additional operational requirements to assure redundant and diverse reactor shutdown capability. All of the changes man-dated by Generic Letter 85-10 have been met by incorporating sections of Model Standard Technical Specifications along with the comments of the B&W Owners Group on SCR relays. Therefore, operation of Rancho Seco in accordance with this proposed amendment:

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.

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

o ATTACHMENT II DESCRIPTION OF PROPOSED CHANGES

1. Page 3-25, Specification 3.5.1.6; Action Statement 9 from Table 3.3-1 of Generic Letter 85-10 has been inserted here.

2. Page 3-25a, Specification 3.5.1.7; This was formerly Specification 3.5.1.6.

Minor changes have been made to the first sentence of this specification in order to account for the fact that the reactor trip breakers now have two diverse trip features.

3. Page 3-25a, Specification 3.5.1.8; Based upon the guidance of the B&W Owners Group, this Specification on SCR Limiting Conditions for Operation has been proposed.

4. Page 3-25a, Specification 3.5.1.9; The portions of Action Statement 7b that apply to the reactor trip breakers and the SCRs have been retained in this soecification. Those that pertain to the reactor trip modules have not been included.

5. Page 3-26, 7th paragraph of the Bases; The last sentence describes main-tenance responses to a failure of one of the diverse trip features.

6. Page 4-4, Items 12 and 13; Surveillance requirements for the ARTS inputs have been removed from Item 13 and placed under Item 12. Surveillance requirements for the SCR relays and the shunt trip device have been inser-ted under Item 13.

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