ML20149D847
| ML20149D847 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 07/15/1997 |
| From: | Edison G NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20149D851 | List: |
| References | |
| NUDOCS 9707180016 | |
| Download: ML20149D847 (8) | |
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UNITED STATES l
NUCLEAR REGULATORY COMMISSION N
WASHINGTON D.C. 3066&4001
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VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-280 lyRRY POWER STATION. UNIT N0. 1 l
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 212 License No. DPR-32 1.
The Nuclear Regulatory Commission (the Commission) has found that:
1 A.
The application for amendment by Virginia Electric and Power Company (the licensee) dated February 3,1997, and March 18, 1997, complies with the standards and requirements of the 1
Atomic Energy Act of 1954, as amended (the Act) and the l
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 (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 10CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
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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:
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l (B) Technical Specifications The Technical Specifications contained in Appendix A, as revised 1
through Amendment No. 214 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 issuance and shall be implemented within 30 days.
)
FOR THE NUCLEAR REGULATORY COMMISSION Gordon E. Edison, Ac".ing Director 1
Project Directorate 11-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation i
Attachment:
Changes to the Technical Specifications Date of Issuance: July 15,1997 i
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p*C8:oq UNITED STATES
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j NUCLEAR REGULATORY COMMISSION 4
g WASHINGTON, D.C. 30666-0001 9...
- 4.,o VIRGINIA ELECTRIC AND POWER COMPANY DOCKET N0. 50-281 SURRY POWER STATION UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 212 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 licensee) dated February 3, 1997, and March 18, 1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulati3ns 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 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 10CFR 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-37 is hereby amended to read as follows:
(B) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 212, 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 issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSI'N O
N0 W
Gordon E. Edison, Acting Director Project Directorate 11-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: July 15,1997
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT N0. 212 TO FACILITY OPERATING LICENSE NO. DPR-32 AMENDMENT NO. 212 TO FACILITY OPERATING LICENSE NO. DPR-37 l
l DOCKET NOS. 50-280 AND 50-281 Revise Appendix A as follows:
Remove Paaes Insert Paagi TS 4.15-1 TS 4.15-1 TS 4.15-3 TS 4.15-3 TS Fig. 4.15 TS Fig. 4.15 1
1 4
TS 4.15-1 l
AUGMENTED INSERVICE INSPECTION PROGRAM FOR HIGH ENERGY LINES OUTSIDE OF CONTAINMENT Acolicability Applies to welds in piping systems or portions of systems located outside of containment where protection from the consequences of postulated ruptures is not provided by a system of pipe whip restraints, jet impingernent barriers, protective l
i enclosures and/or other measures designed specifically to cope with such ruptures.
For Surry Units 1 'and 2, this specification applies to welds in the main steam and main feedwater lines in the main steam valve house of each unit.
Objective To provide assurance of the continued integrity of the piping systems over their service lifetime.
Soecifications A.
For the 20 welds identified in TS Figure 4.15:
1.
At the first refueling outage period a volurnetric examination shall be performed with 100 percent inspection of welds in accordance with the requirement of ASME Section XI Code, inservice inspection of Nuclear Power Plant Components, to Amendment Nos. 212 and 212
L TS 4.15-3 1
4.
In the event repairs of any welds are required following any examination during successive inspection intervals, the inspection schedule for the repaired welds will revert back to the first 10 year inspection program.
- B.
For all welds other than those identified in TS Figure 4.15:
- 1..
Welds in the main steam lines including the safety valve headers and in the feedwater lines in the main steam valve house shall be examined in accordance with the requirements of subsection IWC of the ASME Section XI Code.
t C.
For all welds in the main steam valve house:
1.
A visual inspection of the surface of the insulation at all weld locations shall be performed on a weekly basis for detection of leaks. Any. detected leaks shall be investigate >d and evaluated. If the leakage is caused by a through-wall flaw, either the plant shall be shutdown, or the leaking piping isolated. Repairs shall be performed prior to retum of this line to service.
2.
Repairs, reexamination and piping pressure tests shall be conducted in accordance with the rules of ASME Section XI Code.
Amendments Nos. 212 and 212 l
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