ML20072V116

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Amends 27 & 13 to Licenses NPF-87 & NPF-89,respectively, Changing TS to Allow Increase in Max Allowable Fuel Enrichment from 4.3 Weight Percent to 5.0 Weight Percent Enriched Fuel
ML20072V116
Person / Time
Site: Comanche Peak  
Issue date: 09/13/1994
From: Beckner W
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20072V117 List:
References
NUDOCS 9409190199
Download: ML20072V116 (7)


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UNITED STATES ex3 ( I, [ i i

NUCLEAR REGULATORY COMMISSION

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WASHINGTON, D.C. 20666-0001

.....f TEXAS UTILITIES ELECTRIC COMPANY CONANCE PEAK STEAM ELECTRIC STATION. UNIT 1 DOCKET NO. 50-445 ANEIEBIENT TO FACILITY OPERATING LICENSE Amendment No. 27 j

License No. NPF-87 1.

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

1 A.

The application for amendment by Texas Utilities Electric Company j

(TU Electric, the licensee) dated April 22, 1994, complies with the standards and requirements of the Atomic Energy Act of 1954, as i

amended (the Act), and the Commission's rules and regulations set' l

forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, as i

amended, the provisions of the Act, and the rules and regulations of the Commission; j

C.

There is reasonable assurance:

(1) that the activities authorized by this amendment can be conducted without endangering the health i

and safety of the public, and (ii) that such activities will be j

conducted in compliance with the Commission's regulations; D.

The !ssuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the l

public; and E.

l 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.

i 2.

Accordingly, the license is amended by changes to the Technical Specifications as ladicated in the attachment to this license amendment and Paragraph 2.C.(2) of Facility Operating License No. NPF-87 is hereby 4

l amended to read as follows:

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j 9409190199 940913 PDR ADOCK 05000445 i-P PDR b

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~ 2.

Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 27, and the Environmental Protection Plan l

contained in Appendix B, both of which are attached hereto, are l

hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

l 3.

The license amendment is effective as of its date of issuance to be l

implemented prior to initial receipt of fuel enriched to greater than 4.3 l

weight percent.

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FOR THE NUCLEAR REGULATORY COMMISSION i

fev William D. Beckner, Director Project Directorate IV-1 Division of Reactor Projects III/IV l

Office of Nuclear Reactor Regulation l

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Attachment:

Changes to the Technical Specifications l

Date of Issuance: September 13, 1994 l

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UNITED STATES 5.ke,g(// k NUCLEAR REGULATORY COMMISSION E

W 'f 5 WASHINGTON. D.C. 20666-0001 gc f

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TEXAS UTILITIES ELECTRIC COMPANY COMANCHE PEAK STEAM ELECTRIC STATION. UNIT l DOCKET NO. 50-446 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.13 License,.No. NPF-39 1.

The Nuclur Regulatory Commission (the Comission) has found that:

A.

The application for amendment by Texas Utilities Electric Company (TU Electric, the licensee) dated April 22, 1994, 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, as amended, 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 license 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 acrardance with 10 CFR Part 51 of the Commission's regulations and ali 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. NPF-89 is hereby amended to read as follows:

l

. (2) Technical Specifications and Environmental Proteciton Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.13, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license.

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

3.

This license amendment is effective as of its date of issuance to be implemented prior to initial receipt of fuel enriched to greater than 4.3 weight percent.

FOR THE NUCLEAR REGULATORY COMMISSION M

William D. Beckner, Director Project Directorate IV-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: September 13, 1994

ATTACHMENT TO LICENSE AMENDMENT NOS.27 AND 13 FACILITY OPERATING LICENSE NOS. NPF-87 AND NPF-89 DOCKET NOS. 50-445 AND 50-446 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 marginal line indicating the area of change. The corresponding overleaf page is also provided to maintain document completeness.

REMOVE INSERT 5-5 5-5 l

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l DESIGN FEATURES l

DESIGN PRESSURE AND TEMPERATURE l

5.2.2 The containment building is designed and shall be maintained for a maximum internal pressure of 50 psig and a temperature of 280*F.

5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The core shall contain 193 fuel assemblies with each fuel assembly containing 264 fuel rods clad with Zircaley-4 except that limited substitution of fuel rods by filler rods (consisting of Zircaloy-4 or stainless steel) may be made if justified by a cycle specific reload analysis.

Each fuel rod sh:11 have a nominal active fuel length of 144 inches. The initial core loading i

shall have a maximum enrichment not to exceed 3.15 weight percent U-235.

Reload fuel shall be similar in physical design to the initial core loading and shall have a maximum enrichment not to exceed 5.0 weight percent U-235.

l CONTROL R0D ASSEMBLIES l

5.3.2 The core shall contain 53 full-length control rod assemblies. The full-length control rod assemblies shall contain a nominal 142 inches of I

absorber material. The nominal values of absorber material shall be l

80% silver,15% indium, and 5% cadmium. All control rods shall be clad with stainless steel tubing and may include clad surface treatment for wear mitigation.

5.4 REACTOR COOLANT SYSTEM l

DESIGN PRESSURE AND TEMPERATURE 1

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 applicable Surveillance Requirements, b.

For a pressure of 2,485 psig, and l

c.

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

l COMANCHE PEAK - UNITS 1 AND 2 5-5 Unit 1 - Amendment No. 44,27 Unit 2 - Amendment No. 3,13 l

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