ML19270E984
| ML19270E984 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 12/29/1978 |
| From: | Stello V Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19270E985 | List: |
| References | |
| NUDOCS 7901100446 | |
| Download: ML19270E984 (3) | |
Text
[
s UNITED STATES NUCLEAR REGULATORY COMMISSION
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,p VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-280 SURRY POWER STATION, UNIT NO. 1 AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No.46 License No. DPR-32 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Virginia Electric and Power Company (the licensee) dated December 12, 1978, as supplemented December 20 and 29, 1978, 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; 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 (1) 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 comoliance with the Commission's regulations; D.
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.
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. 2.
Replace paragraph 3.E in its entirety with the following:
E.
Steam Generator Inscection (1) Unit No. I shall be brought to the cold shutdown condition in order to perform an inspection of the steam generators within six months of equivalent operation from December 29, 1978.
Nuclear Regulatory Commission (NRC) approval shall be obtained before resuming power operation following this inspection.
Equivalentoperationisdefinedasgperationwith the reactor coolant at or above 350 F.
(2) Reactor coolant leakage from the reactor coolant system (RCS) to the secondary system (SS) through the steam generator tubes shall be limited to 0.3 gpm per steam generator, as described in the NRC Safety Evaluation of May 6, 1977. With any steam generator tube leakage greater than this limit the reactor shall be brought to the cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. MRC approval shall be obtained before resuming reactor operation.
(3) Reactor operation shall be terminated if RCS to SS leakage which is attributable to 2 or more steam generator tubes occurs during a 20 day period. NRC aporoval shall be obtained before resuming reactor operation.
(4) The concentration of radiciodine in the reactor coolant shall be limited to I uCi/ gram during normal operation and to 10 uCf/ gram during power transients as defined in Appendix A-1 to the Technical Specifications of the license. Appendix A-1 was issued with the May 5, 1977 Order and shall remain in effect for six equivalent months from December 29, 1978.
. 3.
The license amendment supersedes the Order for Modification of License dated June 23, 1978, and is effective as of the date of its issuance.
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., Director Division of Operating Reactors Date of Issuance: December 29, 1978
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