ML20214P277
| ML20214P277 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 11/21/1986 |
| From: | Rubenstein L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20214P281 | List: |
| References | |
| NUDOCS 8612040141 | |
| Download: ML20214P277 (7) | |
Text
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'S' UNITED STATES t
NUCLEAR REGULATORY COMMISSION j
WASHINGTON, D. C. 20555
....+
VIRGINIA ELECTRIC AN9 P0'4ER COMPANY DOCKET NO. 50-280 SURRY POWER STATTM, l! NIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.110 License No. DPR-3?
1.
The Nuclear Regulatory Conrnission (the Comissioni has found that:
A.
The application for amendment by Virginia Electric and Power Company (the licensee) dated February 14, 1979, as supplemented September 21, 1982, and August 30, 1985, complies with the standards and reauirements 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 Consnission; C.
There is reasonable assurance (il 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 Comission's regulations and all applicable reouf rements 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 3.8 of Facility Operating License No. DPR-32 is hereby amended to read as follows:
8612040141 861121 PDR ADOCK 05000281 p
(R) Technical Specifications l
The Technical Specifications contained in Appendix A, as revised through AmendFent No.110, 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 NUCLEAR REGULATORY COMMISSION RE:h..
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\\
les er S.
benstein Director PWR Pro.fect irectorate #2 Division of PWR Licensing-A Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: November 21, 1986 l
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%....+j VIRGINIA ELECTRIC AND F0WER COMPANY DOCKET NO. 50-281 SURRY POWER STATION,IWIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.110 License No. DPR-37 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Virginia Electric and Power Company (the licensee) dated February 14, 1979, as supplemented September 21, 1982, and August 30, 1985, 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 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 (111 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 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:
l
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(R) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.110, 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 NUCLEAR REGULATORY COMMISSION Q
c>.
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: November 21, 1986 i
i
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 110 FACILITY OPERATING LICENSE NO. DPR-32 AMENDMENT NO. 110 FACTLITY OPERATING LICENSE NO. DPR-37 DOCKET NOS. 50-780 AND 50-281 Revise Appendix A as follows:
Remove Pages Insert Pages 4.?-8 4.2-8 4.2-21 4.2-21
TS 4.2-8 Category N - Interior Surfaces and Internal Components of Reactor Vessels It is proposed that examinations in this category be made by remote television or borescopic examination.
A critical examination would be made at the first refueling to detect if any changes have occurred due to initial operation.
The amount of examination to be performed at subsequent refueling outages would depend upon the results of the first examination and those made on comparable pressurized-water systems.
B.
Pressurizer Category B - Pressure Containing Welds in Vessels The primary heads on the pressurizer are of cast material and do not contain meridional welds.
There are circumferential welds joining the heads to the barrel section and circumferential and longitudinal welds in the barrel section that require examination.
The examinations scheduled for the 5-year period and tentatively scheduled for the 10-year period are given in TS Table 4.2-1.
Category D - Pressure Containing Nozzles in Vessels The nozzles are integrally cast into the head, and therefore there are no welds in this category.
Amendment Nos110 and 110
r TABLE 4.2-1 SECTIOlt A.
REACTOR VESSEL AND CLOSITRE HEAD (Continued)
Item Required Extent of Examination Tentative Inspection Examination No.
Category Required Examination Areas Planned During During Methods First 5-Year interval 10-Year Interval Remarks 1.13
( ITEM DELE 7ED )
I.14 I-I Vessel Cladding Visual Mone 6 patches During the 10-year period l
at least 6 patches (each 36 square inches) evenly
)
distributed in the vennel l
head would be visually 1.15 N
inspected.
t Interior surfaces and internals Visual A critical examination tm fnspections made at The examination will in-and integrally welded internal supports will be made of the the 4th refueling cycle clude internal support interior surfaces made will be repeated at the attachments welded to the i
available by normal 7th and 10th refueling vessel whose failure may refueling operations cycle the let refueling cycle.
adversely affect core l
This will be repeated at integrity provided these the 4th refueling cycle are available for visual with the amount of the examination by components inspection being dependent removed during normal upon results of the let refueling operations.
inspection and that made on other pressurized-water systems.
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