ML20206G540
| ML20206G540 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 04/02/1987 |
| From: | Rubenstein L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20206G542 | List: |
| References | |
| NUDOCS 8704150039 | |
| Download: ML20206G540 (4) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION r,,
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SOUTH CAROLINA ELECTRIC & GAS COMPANY S0 LITH CAROLINA PURLIC SERVICE AUTHORITY DOCKET NO. 50-395 VIRGIL C. SUMMER NilCLEAR STATION, UNIT NO. 1
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AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 62 License No. NPF-12 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by South Carolina Electric & Gas Company and South Carolina Public Service Authority (the licensees) dated December 9,1986, as supplemented March 7,1987, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
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 Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon 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 reouirements have been satisfied.
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-12 is hereby amended to read as follows:
B704150039 870402 PDR ADOCK 05000395 l
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' (2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 62, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This amendment is effective as of its date of issuance, and shall be implemented within 30 days of issuance, FOR THE NUCLEAR REGifLATORY COMMISSION g
Lester S. Rubenstein, Director p PWR Project Directorate #2 Division of PWR Licensing-A Office of Nuclear Reactor Regulation
Attachment:
Changes to the Techr.ical Specifications Date of Issuance:
April 2, 1987
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.
62 TO FACILITY OPERATING LICENSE NO. NPF-12 DOCKET NO. 50-395 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page. The revised page is identified by amendment number and contains a vertical line indicating the area of change.
Remove Page Insert Page 5-6 5-6
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DESIGN FEATURES 5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The reactor core shall contain 157 fuel assemblies with each fuel assembly normally containing 264 fuel rods clad with Zircaloy-4, except that limited 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 enrichment of 3.2 weight percent U-235.
Reload fuel shall. be similar in physical design to the initial core loading and shall have a maximum enrichment of 4.3 weight percent U-235.
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j' CONTROL ROD ASSEMBLIES l
l 5.3.2 The reactor core shall contain 48 full length control rod assemblies.
The full length control rod assemblies shall contain a nominal 142 inches of absorber material. The nominal values of absorber material shall be 80 percent silver, 15 percent indium and 5 percent cadmium. 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:
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 c.
For a temperature of 650'F, except for the pressurizer which is 680*F.
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VOLUME i
5.4.2 The total water and steam volume of the reactor coolant system is 9407
- 100 cubic feet at a nominal T,yg of 586.8'F.
I 5.5 METEOROLOGICAL TOWER LOCATION j
5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.
i SUMER - UNIT 1 5-6 Amendment No. 27,55, 62 l
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