ML20151B491
| ML20151B491 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 04/01/1988 |
| From: | Calvo J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20151B495 | List: |
| References | |
| NUDOCS 8804080258 | |
| Download: ML20151B491 (4) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION o
,E WASHINGTON, D. C. 20555
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NEBRASXA PUBLIC POWER DISTRICT 00CKET NO. 50-298 COOPER NUCLEAR STATION AMENDHENT TO FACILITY OPERATING LICENSE Amendment No.118 License No. OPR-46 1.
The Nuclear Regulatsry Commission (the Commission) has found that:
A.
The application for aaendment by Nebraska Public Power District (the licensee) dated December 14, 1987, 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; 8.
The facility will operate in conformity with the application, 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; 1
0.
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.
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.
i 8004000258 080401 DR ADOCK 050 0
a 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. OPR-46 is hereby amended to read as follows:
(2) Technical Specification The Technical Specifications contained in Appendix A, as revised through Amendment No.118, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of dssuance.
FOR THE NUCLEAR REGULATORY COMMISSION t
d, b< b g
Jose A. Calvo, Director Project Directorate - IV Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation
Attachment:
t Changes to the Technical l
Specifications Date of Issuance: April 1, 1988 i
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ATTACHMENT TO LICENSE AMENDMENT NO.118 FACILITY OPERATING LICENSE NO. DPR-46
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DOCKET NO. 50-298 Replace the following page of the Appendix A Technical Specifications with
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the enclosed page.
The revised area is indicated by marginal line.
Pages 217
5.0. MAJOR DESIGN FEATURES 5.1 Site Features The Cooper Nuclear Station site is located in Nemaha County, Nebraska, on the west bank of the Missouri River, at river mile 532.5.
This part of the river is referred to by the Corps of Engineers as the Lower Brownville Bend.
Site coordinates are approximately 40' 21' north latitude and 95* 38' west longitude.
The site consists of 1351 acres of land owned by Nebraska Public Power District. About 205 acres of this property is located in Atchison County, Missouri, opposite the Nebraska portion of the station site.
The land area upon which the station is constructed is crossed by the Missouri River on the east and is bounded by privately owned property on the north, south, and west. At the west site boundary, a county road and Burlington Northern Railroad spur pass the site.
The reactor (center line) is located approximately 3600 feet from the nearest property boundary. No part of the present property shall be sold or leased by the applicant which would reduce the minimum distance from the reactor to the nearest site boundary to less than 3600 feet without prior NRC approval.
The protected area is formed by a seven foot chain link fence which surrounds the site buildings.
5.2 Reactor A.
The core shall consist of not more than 54f fuel assemblies in any combination of 7x7 (49 fuel rods) and 1x8 (63 fuel rods) and 8x8R/P8x8R/BP8x8R (62 fuel rods).
B.
The core shall contain 137 cruciform-shaped control rods.
The control material shall be boron carbide powder (B C) compacted to approximately 4
70% theoretical density, except for the Hybrid 1 control rods which contain approximately 15% hafnium.
C.
Lead Test Assembly (LTA) control blades and fuel assemblies of different
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design than described above may be installed under the provisions of 10 CFR 50.39 in conjunction with vendor test programs.
The LTAs shall have been analysed using methods previously approved by the NRC.
The licensee will provide the NRC with a report describing the LTAs and analyses not less than 30 days prior to startup.
5.3 Reactor Vessel The reactor vesset shall be as described in Section IV-20 of the SAR.
The applicable design shall be as described in this section of the SAR.
5.4 containment A.
The principal design parameters for the primary containment shall be as given in Table V-2-1 of the SAR.
The applicabic design shall be as des-cribed in Section XII-2.3 of the SAR.
B.
The secondary containment shall be as described in Section V-3.0 of the SAR.
C.
Penetrations to the primary containment and piping passing through such 217 Amendment No.118
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