ML20102A220
| ML20102A220 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 07/20/1992 |
| From: | Quay T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20102A222 | List: |
| References | |
| NUDOCS 9207240126 | |
| Download: ML20102A220 (5) | |
Text
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E' UNITED STATES n
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,i NUCLEAR REGULATORY COMMISSION e
WASHINGTON D.C. 20M6 ARIZONA PUBLIC SERVICE COMPANY. ET AL.
- c DOCKET NO. STN 50-530 PALO VERDE NUCLEAR GENERATING STATION. UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.35 License No. NPF-74 1.
The Nuclear Regulatory Commission (the Commission) has found.that:
A.
The application for amendment by Arizona Public Service Company (APS or the licensee on behalf of itself and the Salt River Project Agricultural) improvement and Power District, El Paso Electric Company, Southern California Edison Company, Public Service Company of New Mexico, Los Angeles Department of Water and Power, and Southern California-Puolic Power Authority dated December 20, 1991, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the
. Commission's regulations set forth in 10 CFR Chapter I; B.
The facility will. operate in conform $ with the appilcation, the provisions of 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 i
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
4 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 isLamended by changes to the Technical Specifications av indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No. NPF-74 is hereby amended to read as follows:
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(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 35, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license. APS sla11 operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan, except where otherwise stated in specific license conditions.
3.
This license amendment is effective as of the date of issuance and must be fully implemented no later than 45 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Af
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n eg Theodore R. Quay, Director Project Directorate V Division of Reactor Projects Ill/IV/V Office of Nuc1 car Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: July 20, 1992 e&
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4 ATTACHMENT TO LICEf1SE AMENDMENT FACILITY OPERATINO._LI ENSE f40. NPF-73 AMENDMENT NO. 35 2
DOCKET NO. STN 50-530 neplace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are ioentified by amendment number and contain vertical lines indicating the areas of change, REMOVE INSERT 5-5 5-5
DESIGN FEATURES 5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The reactor core shall contain 241 fuel assemblies with each fuel assembly normally containing 236 fuel rods or burnable poison rods clad witn Zircaloy-4 except that limited substitution of fuel rods by filler rods con-sisting of Zircaloy-4 or stainless steel or by vacancies may be made if justi-fled by a cycle specific reload analysis.
Substitution of up to a total of 80 fuel rods clad with zirconium-based alloys other than Zircaloy-4 may also be made in two fuel assemblies for in-reactor performance evaluation purposes during Cycles 4, 5 and 6.
Each fuel rod shall have a nominal active fuel length of 150 inches and contain a maximum total weight of approximately 1950 grams uranium.
Each burnable poison rod shall have a nominal active poison length of 136 inches.
The initial core leading shall have a maximum enrichment of 3.35 weight percent U-235.
Reload fuel shall be similar in physical design to the initial core loading and shall have a maximum enrichment of 4.05 weight percent U-235.*
CONTROL ELEMENT ASSEMBLIES 5.3.2 The reactor core shall contain 76 full-length and 13 part-length control element assemblies.
5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4.1 The Reactor Coolant System is desiDned 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 of the applicable surveillance requirements, b.
For a pressure of 2500 psia, and c.
For a temperature of 650*F, except for the pressurizer which is 700*F.
VOLUME 5.4.2 The total water and steam volume of the Reactor Coolant System is 13,900 + 300/-0 cubic feet at a nominal T,yg of 593*F.
- No fuel with an enrichment greater than 4.0 weight percent U-235 shall be stored in a high density mode in the spent fuel storage facility.
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PALO VERDE - UNIT 3 5-5 AMENDMENT NO. 8, 35