ML20079A166
| ML20079A166 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 12/23/1994 |
| From: | Thadani M Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20079A170 | List: |
| References | |
| NUDOCS 9412300186 | |
| Download: ML20079A166 (7) | |
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t UNITED STATES NUCLEAR REGULATORY COMMISSION f
WASHINGTON, D.C. 2066H001 d
,o VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-280 SURRY POWER STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.195 License No. OPR-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 October 11, 1994, 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 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.
9412300186 941223 PDR ADOCK 05000280 p
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l 2.
Accordingly, the license is amended by changes to the Technical i
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:
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(B)
Technical Soecif1 cations The Technical Specifications contained in Appendix A, as revised through Amendment No.195, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
l 3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION I
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Mohan C. Thadani, Acting Director Project Directorate II-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: December 23, 1994
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-g UNITED STATES E
NUCLEAR REGULATORY COMMISSION E
f WASHINGTON, D.C. 2066M001
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VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-281 SURRY POWER STATION. UNIT NO. 2 AMENDNENT TO FACILITY OPERATING LICENSE Amendment No. 195 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 October 11, 1994, 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,
lhe facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Ccmmission; 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.
.2-2.
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 Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 195, 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 d1Glu C' khu Mohan C. Thadani, Acting Director Project Directorate 11-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: December 23, 1994 j
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ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 195 TO FACILITY OPERATING LICENSE NO DPR-32 AMENDMENT N0. 195 TO FACILITY OPERATING LICENSE N0. DPR-37 DOCKET NOS. 50-280 AND 50-211 s
a Revise Appendix A as follows:
Remove Pace Insert Pace TS 4.1-9d TS 4.1-9d l
l-TABLE 4.1-2A (CONTINUED)
MINIMUM FREQUENCY FOR EOulPuFNT TESTS UFSAR SECTION DESCRIPTION TEST FREQUENCY REFERENCE 13.
Primary Coolant System Functional 1.
Periodic leaka0s teshng(a)(b) on each valve Hoted in Specification 3.1.C.7a sher be accor@hshed prior to onterin0 POWER OPERATION after every time the plant is placed in COLD SHUTDOWN for refue8n0 after each time the plant is placed in COLD SHUTDOWN for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> N lestin0 has not been accor@lished in the preceding 9 months, and prior to retumin0 the valve to service after maintenance, repair or replacement wosk is pedormed.
19.
Containment Purge MtN Leaka0e Functional Semi-Annual (Unit at power or shutdown)
N purge valves are operated during interval (c) 20.
Containmort Hydrogen Analyzers
- a. CHANNEL FUNCTIONAL TEST Once per 92 days b.
CHANNEL CALIBRATION Once per 18 months
- 1. Sample gas used:
One volume percent (10.25%) hydrogen, balance nitrogen Four volume percent (10.25%) hydrogen, R
balance rerogen a.
2.
CHANNEL CALIBRATION wNtinclude stastup and g
3 operation of the Heat Tracing System o
21.
RCS Flow Flow 2 273,000 gwn Once per refueling cycle 14 22.
RWST Parameters
- a. Temperature s 45'F Once per shift
- b. Volume 2 387,100 gasons Once per shift 5
a.
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(a) To satisfy ALARA requirements, leaka0e may be measured indirectly (as from the performance of pressure indicators) N accomplis;W in m
accordance with @psowed psocedures and supported by compt.4ations showing that the method is capable of demonstrating valve 7
cor@liance with tno leakage criteria.
g (b) Minimum dNferential test pressure shall not be below 150 psid.
(c)
Refer to Section 4.4 for acceptance criteria.
See Specification 4.1.D.
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