ML20205E718
| ML20205E718 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 10/12/1988 |
| From: | Calvo J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20205E721 | List: |
| References | |
| NUDOCS 8810270455 | |
| Download: ML20205E718 (4) | |
Text
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UNITED STATES E'
NUCLEAR REGULATORY COMMISSION e
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.I wAsHwoTON. D. C. 20655 j'
LAt:SAS GAS 8 ELECTRIC COMPANY KANSAS CITY POWER AND LIGHT COPPA,tjY hANSAS ELECTRIC POWER COOPERATIVE, INC.
k'OLF CREEK GENERATING STATION DOCKET NO. 50-482 AMENDMENT TO FACILITY OPERATING LICENSE Arendment No.19 License No. NPF-4?
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1.
The Nuclear FtSulatory Coneission (the Contnission) has found that:
A.
The application for arendrent to the k'olf Creek Generating Station (the facility) Facility Operating License No NPF-40 filed by the L'olf Creek Nuclear Operating Ccrporation, dated July 26, l
19FF cceplits with the star.dards and ree.uirenents of the Atoric l
Energy Act of 19E4, as amended (the Act), and the Comissicn's i
rules and regulatter.s set forth in 10 CFR Chapter it l
1 E.
The facility will operate in confomity with the application, as l
arerded, the provisions of the Act. and the rules and regulations of the Comission; l
C.
There is reascoable assurance:
(i)thattheactivitiesauthorized ty this aner.drent can be conducted without endangering the health and safet,y of the public, and (ii) that such activities vill be i
corducted in corpliance with the Comission's regulations l-D.
The issuance of this license amendment will not te iniinical to the comen defense and security or to the health and safety of the public; l
and i
E.
The issuance of this avendrant is in accordance with 10 CFR Part 51 of the Corrission's regulations and all applicable requirements have i
been satisfied.
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2-o 2.
Accordingly, the license is avended 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 arended to read as follows:
2.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Arendirent No.19. and the Environmental Protection Plan i
contained in Appendix B both of which are attached hereto, are hereby incorporated in the license. KG8E shall operate the facility in accordance with the Technical Specifjcations and the Environrental Protection Plan.
3.
The license ar.endrent is effective as of its date of issuarce.
I FOR THE NUCLEAR REGULATORY COWISSION 1
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1 Jose A. Calvo Director i
Profect Directorate - IV I
Divisico of Reactor Projects - !!!,
IV, Y and Special Projectt Office of Nuclear Reactor Regulation Attachn erit :
1 Charges to the Technical i
Specificaticos Cate of Issisarce: October 12, 1988 l
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ATTACHEhT TO LICENSE AMENDPENT NO.19 FACILITY OPERATlhG LICENSE NO. NPF-42 DOCKET NO. 50-482 i
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Revist Appendix A Technical Specifications by removing the page identified i
below and inserting the enclosed page. The revised page is identified by e
amendreht number and contains a marginal line indicating the area of change.
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l' REMOVE PAGE INSERT PAGE 5-6 5-6 l
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DESIGN FEATUSES i
5.3 REACTOR CORE i
FUEL ASSEMBLIES 5.3.1 The core shall contain 193 fuel assemblies with each fuel usembly i
normally containing 264 fuel rods clad with Zircaloy-4 except that licited i
substitution 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 1
percent U-235.
Reload fuel shall be similar in physical design to the initial coreloadingandspallhaveamaximumenrichmentof4.50weightpercentU-235.
CONTROL ROD ASSEMBLIES
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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.
5.4 REACTOR COOLANT SYSTEM l
DESIGN PRESSURE AND TEMPERATURE l
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 i
applicable Surveillance Requirements, i
b.
For a pressure of 2485 psig, and c.
For a terperature of 650'F, except for the pressurizer which is j
680'F.
t VOLUME f
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.
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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. I6,19