ML20211J078

Amend 81 to License DPR-54,changing Tech Specs to Revise Periodic Testing Requirements of Diesel Generators

ML20211J078
Person / Time
Site:	Rancho Seco
Issue date:	04/17/1986
From:	Stolz J Office of Nuclear Reactor Regulation
To:
Shared Package
ML20211J073	List: ML20211J068 ML20211J078 ML20211J095
References
TAC-57587, NUDOCS 8606260168
Download: ML20211J078 (4)

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1. ~% UNITED STATES E  % NUCLEAR REGULATORY COMMISSION

p WASHINGTON, D. C. 20555

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SACRAMENTO MUNICIPAL UTILITY DISTRICT DOCKET NO. 50-312 RANCHO SEC0 NUCLEAR GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 81 License No. DPR-54

1. The Nuclear Regulatory Commission (the Commission) has found that:

1 A. The application for amendment by Sacramento Municipal Utility District (the licensee) dated April 15, 1985, as modified September 6.1985, complies with the standards and requirements of the Atomic Energy Act of ~1954, as amended (the 'Act), and tne

, ' Commission's rules and regulations set forth 1.,~10 CFR Chapter I; B. Thefacilitywilloperateinconformitywithlheapplication,the the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted, in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. OPR-54 is herehy amended to read as follows:

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2-Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.81 , are Fereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

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'Jo F. Stolz, Directo Project Directorate #6 Division of PWR Licensing-L

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Changes to -the Technt .

Specifications Date of Issuance: April 17, 1986 G

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ATTACHMENT TO LICENSE AMENDMENT NO. c1 FACILITY OPERATING LICENSE NO. OPR-54 DOCKET N0. 50-312 Replace the following page of the Appendix "A" Technical Specifications with the attached page. The revised page is identified by Amendment number and contains a vertical line indicating the area of change.

Remove Insert 4-34 4-34 s I

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i RANCHO SECD UNIT 1 i TECHNICAL SPEC 2FlCATIONS Surveillance Standards 4.6 EHERGENCY POWER SYSTEM PERIODIC TESTING Applicability Appifes to the periodic testing and surveillance of the emergency power system. ,

Ob.fective To verify that the emergency power sources and equipe>ent are operable 3nd respond properly when required.

Specification 4.6.1 At intervals not to exceed one month, a test of the diesel generators will be performed to verify proper operation of these

, emergency power sources and associated equipment. (his test will

be perfomed to assure that

A. Each diesel generator can be started from the control room.

'B . 'Iach diesel generator can be synchronized with it; associated 4160 volt nuclear service nu..

4.6.2 During each refueling interval, a test of the diesel generators and emergency start circuits shall be perfomed to verify that i these emergency power sources and associated equipment are operable by:

A. Simulating a loss of offsite power in con. function with a ,

safety features actuation signal, and:

i 1) Verifying de-energization of the nuclear services i buses and operation of the load shedding circuitry. ,

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2) Verifying the diesel starts from ambient condition on the auto-start signal and energizes the nuclear

. services buses, and by verifying proper operation of the automatic load sequencing circuitry, including manual closing of the A Train intertie breakers from the Control Room and manual energization of the A Train essential HVAC from the Control Room. The B Train intertie breakers are automatically closed and the B Train Control Room essential HVAC System is ,

automatically energized. The diesel generators will l be operated for at least 5 minutes in this condition.

B. Simulating a loss of offsite power and verifying that on interruption of the emergency power sources the loads are shed from the nuclear services buses in accordance with

, design requirements and that subsequent loading of the emergency power sources is through the automatic load sequencing circuitry. The diesel generator will be operated for at least 5 mi.nutes in this condition.

C. Load testing the diesel generators to SFAS capacity.

Amendment No. JS, JJ, $i!, ' 81 4-M

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