ML20198H381

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Amends 7 & 5 to Licenses DPR-80 & DPR-82 Respectively, Revising Tech Spec 5.3.1, Fuel Assemblies to Increase Reload Fuel Max Enrichment from 3.5 to 4.5 Weight % U-235
ML20198H381
Person / Time
Site: Diablo Canyon  Pacific Gas & Electric icon.png
Issue date: 05/13/1986
From: Varga S
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20198H385 List:
References
TAC-60831, TAC-60832, NUDOCS 8605300297
Download: ML20198H381 (6)


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PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON NUCLEAP POWER PLANT, UNIT 1 DOCKET NO. 50-275 AMENDMEhr TO FACILITY OPERATING LICENSE Amendment No.7 License No. DPR-80 1.

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

A.

The application for amendment dated February 14, 1986 (LAR 86-02) by Pacific Gas & Electric Company (the licensee) 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 1; B.

The facility will operate in conformity with the application, as amended, the 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 b'e 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 a change to the combined Technical Specifications for Units 1 and 2 as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-80 is hereby amended to read as follows:

8605300297 860513 DR ADOCK 05000275 PDR l

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(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 7

. and the Environmental Protection Plan contained in Appendix B are hereby incorporated in the license.

PG8E shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment becomes effective at the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION 6.

teven A. Varga, Director PWR Project Directorate #3

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Division of PWR Licensing-A, NRR

Attachment:

Changes to the Technical Specifications Date of Issuance:

May 13, 1986 i

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PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON NUCLEAR POWER PLANT, UNIT 2 DOCKET NO. 50-323 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.5 License No. DPR-82 1.

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

A.

The application for amendment dated February 14, 1986, (LAR 86-02)

,by Pacific Gas & Electric Company (the licensee) complies with the i

. 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 1; i

B.

Tne facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission; C.

There is ceasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and stfety 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 a change to the combined Technical Specifications for Units 1 and 2 as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-82 is hereby amended to read as follows:

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(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 5

, and the Environmental Protection Plan containe.d in Appendix B are hereby incorporated in the license.

PG&E shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment becomes effective at the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION q<a

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Steven A. Varga, Di ector PWR Project Directorate #3 Division of PWR Licensing-A, NRR J

Attachment:

Changes to the Technical Specifications Date of Issuance: May 13, 1986

i ATTACHMENT TO LICENSE AMENDMENT NOS. 7 AND 5 FACILITY OPERATING LICENSE NOS. DPR-80 AND DPR-82 DOCKET NOS. 50-275 AND 50-323 Revise the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by Amendment Number and contain vertical lines indiciating the area of change.

Remove Page Insert Page 5.5 5.5 O

DESIGN FEATURES DESIGN PRESSURE AND TEMPERATURE 5.2.2 Containment is designed and shall be maintained for a maximum internal pressure of 47 psig and a temperature of 271*F, coincident with a Double Design Earthquake.

5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The core shall contai'n 193 fuel assemblies with each fuel assembly con-taining 264 fuel rods clad with Zircaloy-4.

Each fuel rod shall have a nominal active fuel length of 144 inches and contain a maximum total weight of 1766 grams uranium.

The initial core loading shall have a maximum enrichment of 3.15 weight percent U-235.

Reload fuel shall be similar in physical design to the init.ial core loading and shall have a maximum enrichment of 4.5 weight l

percent U-235.

CONTROL R0D ASSEMBLIES 5.3.2 The reactor core shall contain 53 full length and no part length control rod assemblies.

The full length control rod assemblies shall contain a nominal 142 inches of absorber material. The nominal values of absorber material shall be 80% silver, 15% indium, and 5% cadmium.

All control rods shall be clad with stainless steel tubing.

5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4.1 The Reactor Coolant System is designed and shall be maintained:

a.

In accordance with the Code requirements specified in Section 5.2 of the FSAR, with allowance for normal degradation pursuant to the s

applicable Surveillance Requirements, b.

For a pressure of 2485 psig, and c.

For a temperature of 650*F, except for the pressurizer which is 680 F.

VOLUME 5.4.2 The total water and steam volume of the Reactor Coolant System is 12,811 1 100 cubic feet at a nominal T,yg of 576*F for Unit 1 and 12,903 100 cubic feet at a nominal T,yg of 577*F for Unit 2.

DIABLO CANYON - UNITS 1 & 2 5-5 Amendment Nos. 7 and 5

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