ML20135E867

Amend 74 to License DPR-54,revising Tech Specs to Define Testing Requirements for Pressurizer Heaters Powered from Class 1E Power Sources

ML20135E867
Person / Time
Site:	Rancho Seco
Issue date:	09/09/1985
From:	Stolz J Office of Nuclear Reactor Regulation
To:
Shared Package
ML20135E860	List: ML20135E857 ML20135E867 ML20135E872
References
TAC-63030, NUDOCS 8509170058
Download: ML20135E867 (4)

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UNITE'D STATES og e

NUCLEAR REGULATORY COMMISSION o

WASHINGTON, D. C. 20555

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SACRAMENTO MUNICIPAL UTILITY DISTRICT DOCKET NO. 50-312 RANCHO SECO NUCLEAR GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 74 License No. DPR-54 1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment by Sacramento Municipal Utility District (the licensee) dated October 29, 1984, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the tN provisions of the Act, and the rules and regulations of the Comission; 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 Comission'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. DPR-54 is hereby amended to read as follows:

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Technical Specifications s.

The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 74, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

4 3.

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

FOR THE NUCLEAR REGU TORY COMMIS.110N ohn. Stolz, Chief ating Reactors Branch #4 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance:

September 9,1985 t

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ATTACHMENT TO LICENSE AMENDMENT NO.74 ___

4 FACILITY OPERATING LICENSE NO. DPR-54 DOCKET NO. 50-312 Replace the following page of the Appendix A Technical Specifications with the enclosed page as indicated. The revised page is identified by Amendment number and contains a vertical line indicating the area of change.

Remove Insert 4-35 4-35

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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS.

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Surveillance Standarcs 4.6.5 Diesel generator fuel oil supply shall be tested as follows:

i A.

During the monthly diesel generator test, the diesel fuel oil transfer pumps shall be monitored for operation.

B.

Once a month, quantity of the diesel fuel oil shall be logged and checked ' gainst minimum specifications.

a The tests specified will be considered satisfactory if control i

room indication and/or visual examination demonstrates that all components have operated properly.

4.6.6 The pressurizer shall be tested as follows:

i A.

The pressurizer water level shall be determinec to be witnin its i

limits at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

8.

The power supply for the pressurizer heaters shall be demonstrated OPERABLE at least once per 18 months by using the Nuclear Service bus to energize the heaters.

Bases The tests speciff en are designed' to demonstrate that the diesel generators will provide power for operation of safety features equipment. They also assure that the emergency generator control system and the control systems for the j

safety features equipment will function automatically in the event of a loss of all normal a-c station service power, and upon receipt of a safety features actuation signal. They assure the manual closure of the 3A, 3A2 intertie breakers. The tests also assure tne manual energization of the A Train Control Room essential HVAC System functions in the event of a loss of all normal AC station service power and upon receipt of an SFAS signal. Tney assure tne 38, 382 intertie breakers are automatically closed and the 8 Train Control Room essential HVAC System is automatically energized. The 3A-3A2 and 38-382 interties are not required if the event is only a safety features actuation.

i The testing frequency specified is intended to identify and permit correction of any mecnanical or e14ctrical deficiency before it can result in a system failure. The fuel oil supply, starting circuits and controls are continuously monitored and any faults are alanned and indicated. An abnormal condition in these systems would be signaled without having to place the diesel generators on test.

Precipitous failure of tne plant battery is extremely unlikely. The surveillance specified is that which has been demonstrated over thp years to provide an indication of a cell avcoming unserviceable long befort it fails.

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IEEE 308 Amendment No. U,

, 74 4-35

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