ML20207S355
| ML20207S355 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 03/10/1987 |
| From: | Rubenstein L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20207S356 | List: |
| References | |
| 60309, 60310, TAC-60309, TAC-60310, NUDOCS 8703190306 | |
| Download: ML20207S355 (6) | |
Text
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NUCLEAR REGULATORY COMMISSION o
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VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-280 SURRY POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.113 License No. DPR-32 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Virginia Electric and Power Company (the licenseel dated December 11, 1985, as supplemented May 13, 1986, complies with the standards and requirements of the Atomic Energy Act af 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter It B.
The facility will operate in confomity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (1) that the activities authorized,
l 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 i
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
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51 of the Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical l
Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License l
No.- DPR-32 is hereby amended to read as follows:
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8703190306 870310 l
PDR ADOCK 05000280 p
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-2 (B) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Arendment No.113, 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.
FOR THE N!! CLEAR REGULATORY COMMISSION h5
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Lester S.
ubenstein, Director PWR Pro.iect Directorate #2 Division of pWR Licensing-A Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 10, 1987 l
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UNITED STATES NUCLEAR REGULATORY COMMISSION o
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VIRGINIA ELECTRIC AND POWER COMDANY DOCKET NO. 50-281 SURRY POWER STATION, UNIT NO. 2 AMENDPENT TO FACILITY OPERATING LICENSE l
Amendment No.113 License No. DPR-37 1.
The Nuclear Reaulatory Comission (the Comission) has found that:
A.
The application for amendment by Virginia Electric and Power Company (the licensee) dated December 11, 1985, as supplemented May 13, 1986, complies with the standards and re Atomic Energy Act of 1954, as amended (the Act) quirements of the and the Comission'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 Comission; 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 (iii that such activities will be conducted in compliance with the Comission's regulations; O.
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 Comission'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-37 is hereby amended to read as follows:
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lI (B) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment Nol'113, are hereby incorporated in the license. The licensee shall operate the facility in accordanie with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NilCLEAR REGtlLATORY COMMISSION Lester S., benstein. Director PWR Pro.iect Directorate #2 Division of PWR Licensing-A Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: March 10, 1987
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ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 113 FACILITY OPERATING LICENSE NO. DPR-32 AMENDMENT NO. 113 FACILITY OPERATING LICENSE NO. DPR-37 DOCKET NOS. 50-780 AND 50-281 Revise Appendix A as follows:
Remove Pages Insert Pages 3.10-4 3.10 4 e
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TS 3.10-4 12.
A spent fuel cask or heavy loads exceeding 110 percent of the weight of a ' fuel assembly (not including fuel handling tool) shall not be i
moved over spent fuel, and only one spent fuel assembly will be handled at one time over the reactor or the spent fuel pit.
This restriction does not apply to the movement of the transfer canal door.
- 13. 'A spent fuel cask shall not be moved into the Fuel Building unless the Cask Impact Pads are in place on the bottom of the spent fuel pool.
- 14. Two trains of the control and relay room amargency ventilation system shall be operable.
With one train inoperable for any reason, demonstrate the other trains is operable by performing the test in Specification 4.20.A.1.
With both trains in-operable, comply with Specification 3.10.B.
- 15. Containment purge shall be filtered through high efficiency particulate air filters and charcoal absorbers.
B.
If any one of the specified limiting conditions for' refueling is not met, refueling of the reactor shall cease, work shall be initiated to correct the conditions so that the specified limit is set, and no operations which increase the reactivity of the core shall be made.
C.
Af ter initial fuel loading and af ter each core refueling operation and prior to reactor operation at greater than 75% of rated power, the movable. incore detector system shall be utilized to verify proper power distribution.
D.
The requirements of 3.0.1 are not applicable.
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Amendment Nos. 113 & 113
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