ML20213D523
| ML20213D523 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 10/30/1986 |
| From: | Oconnor P Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20213D526 | List: |
| References | |
| NUDOCS 8611120131 | |
| Download: ML20213D523 (5) | |
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UNITED STATES j
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KANSAS GAS & ELECTRIC COMPANY KANSAS CITY POWER AND LIGHT COMPANY KANSAS ELECTRIC POWER COOPERATIVE, INC.
WOLF CREEK GENERATING STATION DOCKET NO. 50-482 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 3 License No. NPF-42 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment to the Wolf Creek Generating Station (the facility) Facility Operating License No. NPF-42 filed by Kansas Gas and Electric Company acting for itself and Kansas City Power and Light Company and Kansas Electric Power Cooperative, Inc., (licensees) dated August 13, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's regulations as 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 regulations of the Comission; C.
There is reasonable assurance: (1)thattheactivitiesauthorizedby 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 set forth in 10 CFR Chapter I; D.
The issuance of this license amendment will not be inimical tL the comon defense and security or to the health and safety of the public; E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
8611120131 861030 PDR ADOCK 05000482 p
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. 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-42 is hereby amended to read as follows:
(2) Technical Specification The Technical Specifications contained in Appendix A, as revised
-through Amendment No. 3, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into the license. - KG&E 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.
FOR THE NUCLEAR REGULATORY COMMISSION h
Paul W. O'Connor, Project Manager PWR Project Directorate No. 4 Division of PWR Licensing-A
Attachment:
Changes to the Technical Specifications Date of Issuance: October 30, 1986 m
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ATTACHMENT TO LICENSE AMENDMENT NO. 3 OPERATING LICENSE NO. NPF-42 DOCKET N0. 50-482 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised page is identified by the captioned amendment number and contains marginal lines indicating the area of-change. The corresponding overleaf page is also provided to maintain document completeness.
AMENDED PAGE OVERLEAF PAGE 5-6 5-5 O
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DESIGN FEATURES i
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 Zircaloy-4.
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 max-imum enrichment of 3.50 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 rods shall be hafnium, clad with stainless steel tubing.
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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, b.
For a pressure of 2485 psig, and For a temperature of 650 F, except for the pressurizer which is c.
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680 F.
VOLUME 5.4.2 The total. volume of the Reactor Coolant System, including pressurizer and surge line, is. 12,135 + 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
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