ML20199B334

Application for Proposed Amend 135 to License DPR-54, Changing Wording in Tech Spec 3.3 & Identifying Specific Batteries in Tech Specs 3.7.1E,F,G & 3.7.2F.Safety Analysis & NSHC Also Encl.Fee Paid

ML20199B334
Person / Time
Site:	Rancho Seco
Issue date:	06/13/1986
From:	Julie Ward SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:	Miraglia F Office of Nuclear Reactor Regulation
Shared Package
ML20199B336	List: ML20199B334 ML20199B867
References
JEW-86-003, JEW-86-3, TAC-61870, NUDOCS 8606170115
Download: ML20199B334 (6)

Text

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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 JEW 86-003 June 13,1986 DIRECTOR OF NUCLEAR REACTOR REGULATION ATTENTION FRANK J MIRAGLIA DIRECTOR PWR-B DIVISION U S NUCLEAR REGULAT9RY COMMISSION WASHINGTON DC 20555 DOCKET NO. 50-312 LICENSE N0. OPR-54 PROPOSED AMENDMENT N0. 13S In accordance with 10 CFR 50.59, the Sacramento Municipal Utility District proposes to amend itt Operating License DPR-54 for Rancho Seco Nuclear Generating Station Unit No. 1.

Proposed Amendment No. 135 consists of administrative changes to 1) the Bases for Specification 3.3 to make the wording consistent with Specifica-tion 3.3.3 as revised by Amendment No. 76, and 2) to Specifications 3.7.1E, F and G and Specification 3.7.2F to identify the specific batteries which comprise those required for nuclear service.

Details of the proposed amendment are provided in Attachments I, II and III, which are the Safety Analysis, "No Significant Hazards" Evaluation and Description of Proposed Changes, respectively.

Pursuant to 10 CFR 50.91(b)(1), the Radiological Health Branch of the Cal-ifornia State Department of Health Services has been informed of this pro-posed amendment by mailed copy of this submittal.

Enclosed is a check in the amount of $150.00 as required by 10 CFR 170.71,

" Schedule of fees."

Shnuld you require any further information with respect to this proposed amendment, please contact Mr. Ron W. Colombo at Rancho Seco Nuclear Gen-erating Station Unit No. 1.

v R .W ISTANT GENERAL MANAGER NUCLEAR (ACTING) Subscribed and sworn to before me this /3M day of L o e. 1986.

Attachments (3) J La n Oh XbLLOY>q Totary Public I 4-~.a~c1AL 4 01 ma, g a Og 1 3 3.gj DAWN DARUNG r1 l 8606170115 860613 n . se.: NOTARYiu3UC CAUFCnNtA fI PDR ADOCK 05000312 CACRAWHO COUNTY I(k p PDR - -

My cen a t v,rn Jan. 12,1990

ATTAC K NT I SAFETY ANALYSIS Proposed Amendment No. 135 consists of administrative changes to the Bases of Specification 3.3, and substitution of the generic words " plant batteries" with specifically identified nuclear service 125 VDC batteries (and buses) in Specifications 3.7.1E, F and G, and 3.7.2F. Details of these changes and considerations of their effect on plant safety are discussed below:

1. Amendment No. 76 deleted the requirement in Specification 3.3.3 that a component taken out of service for maintenance must have its redundant component (s) tested immediately thereafter to prove operability. In its place, unexpired surveillance testing of the standby component (s) was substituted.

In approving the change to Specification 3.3.3, the NRC's safety evalua-tion for Amendment No. 76 stated in part: "The proposed change conforms to current NRC policy regarding surveillance as stated in the Bases for Specification 4.0.3 in the Standard Technical Specifications (STS)."

The administrative change to the Bases for Specification 3.3 deletes two sentences which were consistent with the earlier wording of Specification 3.3.3, but which should have been deleted when the District initiated Amendment No. 76. Through oversight, this was not done and therefore, is now being proposed.

2. The second proposed change, also administrative, substitutes the words,

" plant batteries," in Specification 3.7.1E with the specific nuclear service batteries which supply the vital 125 VDC buses. Additionally, the single alphabetic designations of the vital 125 VDC buses are being changed to their actual equipment ID designations. Also, Specification 3.7.2F is being changed to reference Specification 3.7.1E.

The District considers all of the above changes to be purely administrative, and as such are judged to have no effect on plant safety.

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ATTACIMENT II "N0 SIGNIFICANT HAZARDS" EVALUATION Proposed Amendment No. 135 consists of administrative changes to the Bases of Specification 3.3, and of the substitution of specifically identified nuclear service 125 VDC batteries (and buses) in Specifications 3.7.1.E, F and G, and 3.7.2F for the generic words " plant batteries."

The District has reviewed the proposed changes against the criterion of 10 CFR 50.92 and has concluded that plant operation would not:

a. involve a significant increase in the probability or consequences of an accident previously evaluated, or create the possibility of a new or different kind of accident from any previously analyzed. Neither the deletion of two sentences from the Bases for Specification 3.3 making the Bases consistent with Specification 3.3.3, nor the changes to Spec-ifications 3.7.1E, F and G, and 3.7.2F to list nuclear service batteries and the buses they supply affect plant design or operation. The pro-posed changes are purely administrative and thus are judged as having no involvement with any accident previously evaluated or contributing to a new or different accident from any previously analyzed.

b. involve a significant reduction in a margin of safety. As discussed in a.) above, the proposed changes are purely administrative, having no in-volvement with plant design or operation. Accordingly, the proposed changes are considered as having no effect on safety margins.

On the bases of the above, the District concludes that the proposed changes constitute no significant hazards to the public.

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r-e ATTACHMENT III DESCRIPTION OF PROPOSED CHANGES

1. Bases for Specification 3.3, page 3-22: Deleted the following:

"The maintenance period of up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> is acceptable if the operability of equipment redundant to that removed from service is demonstrated immedi-ately subsequent to removal. The basis of acceptability is a low likeli-hood of failure within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> following such demonstration."

2. Specification 3.7.1 E, aage 3-41: Replaced " plant batteries" with " Nuclear Service batteries BA, B3, BC, BA2 and BB2, and added corresponding Vital 125 VDC buses SOA, 508, SOC, 500, 50A2 and S082.

3. Specification 3.7.1 F, page 3-41: Changed 125 VDC bus designations A, B, C and D to 50A, 508, 50C and 50D.

4. Specification 3.7.1 G, page 3-41: Changed 125 VDC bus designations A2 and 82 to 50A2 and 5082.

5. Specification 3.7.2 F, page 3-42: Changed the wording, " Nuclear service batteries are charged -- ", to: " Nuclear service batteries identified in 3.7.1E-- .

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