ML20028E433

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Amend 3 to License DPR-76,authorizing Relief from Section 3/4.9.7 of Tech Specs for Period of 120 Days to Verify Certain Mods in Fuel Handling Bldg
ML20028E433
Person / Time
Site: Diablo Canyon Pacific Gas & Electric icon.png
Issue date: 01/06/1983
From: Knighton G
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20028E434 List:
References
NUDOCS 8301260018
Download: ML20028E433 (4)


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l PACIFIC GAS AND ELEClRIC C0!iPANY DIABLO CANYON f:UCLEAR POWER PLANT, UNIT 1 DOCr.ET NO. 50-275 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 3 License No. DPR-76 1.

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

A.

The application for amendnent by Pacific Gas and Electric Conpany (the licensee) dated December 21, 1982, complies with the standards and requirements of the Atonic Energy Act of 1954, as anended (the Act), and the Comission's regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, as anended, the provisions of the Act, and the 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; D.

The issuance of this amendment will not be ininical to the connon defense and security or to the health and safety o'f the pub'ic; 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 anended by changes to the Technical Specifications as indicated in the attachnent to this license anendnent, and paragraph

?.C.(2) of facility Operating License No. DPR-76 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A and the Environ-mental Protection Plan contained in Appendix 8, as revised through Anendment No. 3, are hereby incorporated in this license. The Pacific Gas & Electric Company shall operate the facility in accordance with the Technical Specifications and the Environnental Protection. Plan.

8301260018 830106 PDR ADOCK 05000275 P

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This license aven61ent is effective as of its date of issuance.

FOR THE HUCLEAR REGULATORY C0'411SS10H Georce U. Knighton, Chief Licensing Branch No. 3 Division of Licensing Date of Issuance: #N 6 1983 l

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r ATTACHMENT TO LICENSE AMENDMENT NO. 3 FACILITY OPERATING LICENSE NO. DPR-76 DOCKET NO. 50-275 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.- The revised page is identified by Amendment number and contains a vertical line indicating the area of change. Also to be replaced is the following overleaf page to the amended page.

Amendment Page Overleaf Page 3/4 9-7 3/4 9-8 omer >

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REFUElfNG OPERATIONS 3/4.9.7 CRANE TRAVEL - FUEL HANDLING BUILDING LIMITING CONDITION FOR OPERATION 3.9.7 Loads in excess "of 2500 pounds

  • shall be prohibited from travel over-fuel assemblies in the spent fuel pool.**

.APPLICAB?LITY:

With fuel assemblies in the spent fuel pool.

ACTION:

With the requirements of the above soecification not satisfied, place the crane load in a safe condition.

l SURVEILLANCE REOUIREMENTS d

4.9.7 Loads shall be verified to be less than 2500 pounds prior to movement over fuel assemblies in the spent fuel pool, t

AThe movable fuel handling building walls may travel over fuel assemblies in the spent fuel pool.

    • During the period of -Jaruary 06, 1933 through May 6,1983, relief from this specification is granted to permit the installation and removal of temporary spent fuel pool steel plate covers.

During this period, loads

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in excess of 500 pounds shall be prohibited from travel over the spent fuel steel plate covers.

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O w thee DIABLO CANYON - UNIT 1 3/4 9-7 AMENDMENT N0. 3

f REFUELING OPERATIONS

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3/4.9.8 RESIOUAL HEAT REMOVAL AND COOLANT CIRCULATION

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HIGH WATER LEVEL

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LIMITING CONDITION FOR OPERATION 3.9.8.1 At least one residual heat removal (RHR) train shall be OPERABLE and in operation.**

  • APPLICABILITY:

MODE 6 when the water level above the'. top of the reactor, vessel flange is at least 23 feet.

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ACTION:

With no residual heat removal train OPERABLE and in operation, a.

suspend all operations involving an increase in the reactor decay heat load or a reduction in boron concentration of the Reactor' Coolant System and immediately ini'tiate corrective action to return the required RHR train to OPERABLE and operating status as soon as possible.

Close all containment penetrations providing direct access from the containment atmosphere to the outside atmosphere within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

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SURVEILLANCE REQUIREMENTS 4.9.8.1.1 The required RHR train shall be demonstrated OPERABLE pursuant to Specification 4.0.5.

4.9.8.1.2 At least one residual heat removal train shall be verified to be in operation and circulating reactor coolant at a flow rate of greater than or equal to 3000 gpm at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

"The residual heat removal train may be removed from operation for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period during the performance of CORE ALTERATIONS in the vicinity of the reactor pressure vessel hot legs.

    • The residual heat removal train may be removed from operation and OPERABLE status for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period for the performance of leak testing j

the RHR suction isolation valves.

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DIABLO CANYON - UNIT 1 3/4 9-8

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