ML20082M984
| ML20082M984 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 08/22/1991 |
| From: | Dick G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20082M987 | List: |
| References | |
| NUDOCS 9109060127 | |
| Download: ML20082M984 (4) | |
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UNITED STATES 3 -( 3 y /(f %i NUCLEAR REGULATORY COMMISSION
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WOLF CREEK NUCLEAR OPERATING CORPORATION WOLF CREEK GENERATING STATION DOCKET NO. 50-482 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 48 i-License No, NPi-42 1.
The Nuclear Regulatory Commission (the Commission) has found that:
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A.
The application for amendment to the Wolf Creek Generating Station (the facility) Facility Operating License No. NPF-42 filed by the Wolf Creek Nuclear Operating Corporation (the Corporation),
dated May 14, 1991, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the
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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 c
The issuance or this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
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2.
Accordingly, the license is amended by changes to-the Technical Specifi-cations as indicated in the attachment to this license amendment and Paragraph 2.C.(2) of Facility Operating License No. NPF-42 is hereby amended to read as follows:
2.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 48, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated in the license.
The Corporation shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
The license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 7.
George F. Dick, Jr., Acting Director Project Directorate IV-2 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
August 22, 1991 4
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ATTACHMENT TO LICENSE AMENDMENT NO. 48 FACILITY OPERATING LICENSE NO. NPF-42 DOCKET NO. 50-482 Revise Appendix A Technical Specifications by removing the page identified below and inserting the enclosed page.
The revised page is identified by amendment number and contains marginal lines indicating the area of change, REMOVE INSERT 5-6 5-6 E
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DESIGN FEATURES 5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The core shall contain 193 fuel assemblies with each fuel assembly nor-mally containing 264 fuel rods clad with Zircaloy-4 except that limited sub-stitution of fuel rods by filler rods consisting of Zircaloy-4 or stainless steel or by vacancies may be made if justified by a cycle-specific reload analysis.
Each fuel rod shall have a nominal active fuel length of 144 inches.
The initial core loading shall have a maximum nominal enrichment of 3.10 weight percent U-235.
Reload fuel shall be similar in physical design to the initial core loading and shall have a maximum enrichment of 4.50 weight percent U-235.
CONTROL ROD ASSEMBLIES 5.3.2 The 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.
All control rod assemblies shall be hafnium, silver-indium-cadmium, or a mixture of both types.
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:
In accordance with the Code requirements specified in Section 5.2 a.
of the FSAR, with allowance for normal degradation pursuant to the applicable Surveillance Requirements, b.
For a pressure of 2485 psig, and For a temperature of 650 F, except for the pressurizer which is c.
680'F.
VOLUME 5.4.2 The total volume of the Reactor Coolant System, including pressurizer and surge line, is 12,135 1 100 cubic feet at a nominal T,yg of 557 F.
5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.
WOLF CREEK - UNIT 1 5-6 Amendment No. 3, If, Z9, 48
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