ML20135F762

Amend 75 to License DPR-54,revising Tech Specs to Define Fire Hose Acceptability & Correct Certain Inconsistencies in Reporting Requirements

ML20135F762
Person / Time
Site:	Rancho Seco
Issue date:	09/09/1985
From:	Stolz J Office of Nuclear Reactor Regulation
To:
Shared Package
ML20135F745	List: ML20135F741 ML20135F762 ML20135F776
References
NUDOCS 8509170382
Download: ML20135F762 (5)

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g . =cg#og UNITED STATES NUCLEAR REGULATORY COMMISSION

r. e wAsHWGTON, D. C. 20656 s., *...}

SACRAMENTO MUNICIPAL UTILITY DISTRICT <

DOCKET NO. 50-312 RANCHO SECO NUCLEAR GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 75 License No. DPR-54 i

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

A. The application for amendment by Sacrament'o 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 Commission's rules and regulations set forth in 10 CFR Chapter I; -

B. The facility will operate in conformity with the application, the the provisions of the Act, and the rules and regulations of the Comission; C. There is reasonable assurance (1) 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; i D. The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the p olic; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission'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 The Technical Specifications contained in Appendices A and 8, as revised through Amendment No. 75 , are hereby 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 NUCLEA REG ATORY COMMISSION L -

Jo n . Stolz, Chief rating Reactors Branch #4 Division of Licensing -

Attachment:

Changes to the Technical i

Specifications -

Date of Issuance: September 9, 1985 t

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i ATTACHMENT TO LICENSE AMENDMENT NO.75 j FACILITY OPERATING LICENSE NO. DPR-54 DOCKET NO. 50-312 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages as indicated. The revised pages are identified by i

Amendment number and contain vertical lines indicating the area of change.

j Remove Insert

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PAhCHO 3ECO UNIT 1 TEChi! CAL SPECIFICAT10NS Surveillance Stancards a.

Once per 31 days by visual inspection of the station to assure all equipment is available at the station.

b.

Once per 18 months inspect and replace all gaskets in the couplings that ' art degraded, and remove the hose for inspection and re-racking.

c.

Once per three (3) years, partially open hose station valves to verify valve operability and no valve blockage.

d.

Once per three (3)' years by removing ano replacing all hose with new hose that meets or exceeds NFPA guidelines or recomendations. '

4.18.6 Fire Barrier Penetrations 4.18.6.1 Each of the fire barrier penetrations specified in Section 3.14.6.I' shall be verified to be functional:

a.

At least once per 18 months by a visual inspection, b.

Prior to returning a fire barrier penetration to functional status following repairs or maintenance by perfomance of a visual inspection of the affectea fire barrier penetration (s).

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Amendments Nos. M , M ,75 4-62

RANCHO SECO UNIT 1 IECHNICAL SPECIFICATIONS Administrative Controls Special Reports

• 6.9.5 Special reports shall be submitted to the Regional Administrator Region Y Office within the time period specified for each report.

These reports shall be submitted covering the activities ioentified below pursuant to the requirements of the applicable reference specification:

A. A one-time only, " Narrative Sumary of Operating Experience" will be submitted to cover the transition period (calendar year 1977).

B. A Reactor Building structural integrity report shall be submitted within ninety (90) days of completion of each of the following tests covered by Technical Specification 4.4.2 (the integrated leak rate test is covered in Technical Specification 4.4.1.1).

1. Annual Inspection -

2. Tendon Stress Surveillance

3. End Anchorage Concrete Surveillance .

4. Liner Plate Surveillance C. Inservice Inspection Program D. Reserved for Proposed Amendment No. 43 E. Status of Inoperable Fire Protection Equipment F. Inoperable Emergency Control Room /TSC Yentilation Room Filter System G. Radioactive Liquid Effluent Dose 30 days (3.17.2)

H. Noble Gas Limits 30 days (3.18.2)

Radiciodine and Particulates 30 days (3.18.3)

J. Gaseous Radwaste Treatment 30 days (3.19)

K. Radiological Monitoring Program 30 days (3.22)

L. Honitoring Point Substitutions 30 days (3.22) ti. Deleted N. Fuel Cycle Dose 30 dayst (3.25)

0. Deleted

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Amendmenttio.77,73,D,77,75 6-12f

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