ML20117N568
| ML20117N568 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 09/13/1996 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Cleveland Electric Illuminating Co, Duquesne Light Co, Ohio Edison Co, Toledo Edison Co |
| Shared Package | |
| ML20117N571 | List: |
| References | |
| NPF-73-A-082 NUDOCS 9609190279 | |
| Download: ML20117N568 (4) | |
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41 UNITED STATES g
j NUCLEAR REGULATORY COMMISSION o
WASHINGTON, D.C. 20066 4001 s...../
DUOVESNE LIGHT COMPANY 0HIO EDIS0N COMPANY THE CLEVELAND ELECTRIC ILLUMINATING COMPANY THE TOLEDO EDIS0N COMPANY DOCKET NO. 50-412 BEAVER VALLEY POWER STATION. UNIT 2 AMENDHENT TO FACILITY OPERATING LICENSE Amendment No. 82 License No. NPF-73 1.
The Nuclear Regulatory Commission (the Commission) has found that:
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A.
The application for amendment by Duquesne Light Company, et al. (the licensee) dated April 29, 1996, as supplemented September 12, 1996, i
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;
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B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the
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Commission; i
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 amendment will not be inimical to the common i
defense and security or to'the health and safety of the public; and-E.
The issuanceLof this amendment is in accordance with 10 CFR Part i
51 of the Commission's regulations and all applicable requirements have been satisfied.
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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-73 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 82, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated in the license.
DLC0 shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance, to be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION
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y Johr F. Stolz, Director P d ect Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: September 13, 1996
l5 ATTACHMENT TO LICENSE AMENDMENT NO. 82 l
j FACILITY OPERATING LICENSE NO. NPF-73 l
l DOCKET NO. 50-412 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 5-6 5-6 l
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NPF-73 DESIGN FEATURES l
i DESIGN PRESSURE AND TEMPERATURE 5.2.2 The reactor containment building is designed and shall be maintained for maximum internal pressure of 45 psig and a temperature of 280.0'F.
PENETRATIONS 5.2.3 Penetrations through the reactor containment building are designed and shall be maintained in accordance with the original design provisions contained in Section 6.2.4 of the FSAR with allowance for normal degradation pursuant to the applicable Surveillance Requirements.
5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The reactor shall contain 157 fuel assemblies.
Each assembly shall consist of a matrix of Zircaloy or - ZIRLO fuel rods l
with an initial composition of natural or slightly enriched uranium dioxide (UO ) as fuel material.
Limited substitutions of zirconium 2
alloy or stainless steel filler rods for fuel rods, in accordance i
with approved applications of fuel rod configurations, may be used.
Fuel assemblies shall be limited to those fuel designs that have been analyzed with applicable NRC staff approved codes and methods and shown by tests or analyses to comply with all ' fuel safety design bases..
A limited number of lead test assemblies that have not completed representative testing may be placed in nonlimiting core regions.
CONTROL ROD ASSEMBLIES 5.3.2 The reactor core shall contain 48 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 percent silver, 15 percent indium and 5 percent 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 applicable Surveillance Requirements, BEAVER VALLEY - UNIT 2 5-6 Amendment No.82