ML20040E939
| ML20040E939 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 01/17/1982 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20040E940 | List: |
| References | |
| NUDOCS 8202080111 | |
| Download: ML20040E939 (7) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION o
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f VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-280 SURRY POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 73 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 licenseel dated May 15, 1980, as supplemented September 15 and December 4,1980, and March 26 and August 18, 1981, 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 confomity 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 compliance 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.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No. DPR-32 is hereby amended to read as follows:
8202080111 820119 PDR ADOCK 05000280 P
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9 B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 73, are hereby incorporated in the license. The licensee shall operate the facility in accor-dance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEqR jitEGULATORY COMMISSION 3
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Ch e Operating Reactor anch #1 Division of Licens g
Attachment:
Changes to the Technical Specifications Date of Issuance: January 19, 1982 i
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VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-281 SURRY POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 74 License No. DPR-37 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Virginia Electric and Power Company (the 1 tcensee} dated May.15,1980, as supplemented September 15 and Decem6er 4,1980, and March 26 and August 18, 1981, 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 " confonnity with the application, the provisions of the Act, and.the rules and regulations of the Coninission; 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; 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.
2.
Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No. DPR-37 is hereby amended to read as follows:
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. B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised thrc.
hendment No. 74, 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 the date of its issuance.
F0 THE NUCLEAR REGULATORY COMMISSION-f ')
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Operating Reactors E nch #1 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
January 19, 1982 f
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o-ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT N0. 73 TO FACILITY OPERATING LICENSE NO. DPR-32 AMENDMENT NO. 74 TO FACILITY OPERATING LICENSE NO. DPR-37 DOCKET NOS. 50-280 AND 50-281 Revise Appendix A as follows:
Remove Pages Insert Pages 5.3-2 5.3-2 5.4-2 5.4-2 0
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TS 5.3-2 9
3.
Reload. fuel will be similar in design to the initial core. The enrich-ment of reload fuel vill not exce d 4. I veight percent of U-235.
4.
Burnable poison tods are incorporated in the initial core. There are 816 poison rods in the form of 12. rod clusters, which are located in vacant control rod assembly guide thimbles. The burnable poison rods consist of pyrex clad with stainless steel.
5.
There are 48 full-length control rod assemblies in the reactor core. The i
full-length control rod assemblies contain a 144-inch length of silver-indium-cadmium alloy clad with staini'ss steel.
a 6.
Surry Unit 1, Cycle 4, Surry Unit 2, Cycle 3, and subsequent cores will meet the following criteria at all times during the operation lifetime.
a.
Hot channel factor limits as specified in Section 3.12 shall be met.
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l' Amendment Nos. 73 & 74 I
TS 5.4-2 assemblies to assure kaff < 0.95, even if unborated water vare used.
to fill the spent fuel storage pit. The enrichment of the fuel rtored in the spent fuel racks shall not exceed 4 3 % weight percent of U-235.
C.
Whenever there is spent fuel in the spent, fuel pit, the pit shall be filled with borated water at a boron concentration not less, than 2,000 ppm to match that used in the reactor cavity and refueling canal during refueling operations.
D.
The only drain which can be connected to the spent fuel storage area is that in the reactor cavity. The strict step-by-step procedures used during. refueling ensure that the gate valve on the fuel transfer tube which concects the spent fuel storage area with the reactor cavity is closed before draining of the cavity commences. In addition, the procedures require placing the bolted blank flange on the fuel transfer tube as soon as the reactor cavity is drained.
References FSAR Section 9.5 Fuel Pit Cooling System FSAR'Section 9.12 Fuel Handling System Amendment Nos. 73 & 74
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