ML20051S449
| ML20051S449 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 05/03/1982 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20051S493 | List: |
| References | |
| NUDOCS 8205170517 | |
| Download: ML20051S449 (5) | |
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4 UNITED STATES N
NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D. C. 20555
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VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-339 NORTH ANNA POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 21 License No. NPF-7 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The applications for amendment by Virginia Electric and Power Company (the licensee) dated February 19, 1982 and March 15, 1982 comply 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 applications, 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 j
conducted in compliance with the Commission's regulations; j
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; j
and I
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.
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2 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amend-ment and paragraphs 2.C.(2) and 2.C.(10) of Facility Operating License No. NPF-7 are hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 21, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
(10) No icter than October 11, 1980, VEPC0 shall submit a design for the backup overcurrent protection system for containment electrical penetration for Commission review and approval.
The backup system shall be installed and operational prior to resuming power operation following the second refueling outage.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMIS'JiON Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
May 3, 1982
l ATTACHMENT TO LICENSE AMENDMENT f
AMENDMENT NO. 21 TO FACILITY OPERATING LICENSE NO. NPF-7 DOCKET NO. 50-339 Add the following pages to the Appendix "A" Technical Specifications as indicated. The new pages are identified by Amendment number and contain i
vertical lines indicating the area of change.
Pages 3/4 8-26
-i 3/4 8-27 l
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ELECTRICAL POWER SYSTEMS NORMALLY DE-ENERGIZED POWER CIRCUITS LIMITING CONDITION FOR OPERATION 3.8.2.7 All circuits shown in Table 3.8-3 shall be de-energized.
APPLICABILITY: MODES 1, 2, 3, 4.
ACTION:
i With one or more of the circuits shown in Table 3.8-3 energized, de-energize the circuit (s) within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY 1
within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within thr following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
1 SURVEILLANCE REQUIREMENTS 4.8.2.7 At least once per 31 days, when operating in Modes 1-4, verify that all of the circuits in Table 3.8-3 are de-energized by noting the position of the appropriate circuit breakers.
F NORTH ANNA - UNIT 2 3/4 8-26 Amendment No. 21
TABLE 3 8-3 NORMALLY DE-ENERGIZED POWER CIRCUITS DEVICE NUMSER Penetration AND LOCATION LOAD l
2C-2 480 V SWGR 2H Refueling and Maintenance
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2D-2 Compart:nent H-16 Circuit 2F1-2 480 V MCC 231-1 Reactor Cavity Manipulator l
Cubicle B4R Crane (2-MH-CR-5) 2F1-2 480 V MCC 2B1-1 Fuel Transfer Control Cubicle B4L Cabinet (2-EI-CB-92) 4 2F1-2 480 V MCC 2B1-1 RCC Fixture Change Cubicle C2R (2-RC-R-18) 11A-2 480 V MCC 2C1-1 RC Annulus Crane i
Cubicle B3 (2-MH-CR-19) 11B-2 480 V MCC 2C2-1 Stud Tensioner, Portable Cubicle A2R Crane Receptacle 12E-2 480 V MCC 2B1-2 RC Stage Basket Cubicle Cll 23C-2 480 V MCC 2B1-2 RC Polar Crane Cubicle A3 (2-MH-CR-01) 4A-2 480 V MCC 2H1-2S Loop 3 Hot Leg Stop Vv Cubicle G2 (MOV-2594)
4B-2 480 V MCC 2H1-25 Loop 2 Hot Leg Stop Vv i
Cubicle H3 (MOV-2592)*
48-2 480 V MCC 2H1-25 Loop 2 Cold Leg Stop Vv Cubicle J1 (MOV-2593)*
11A-2 480 V MCC 2H1-2S Loop 2 Bypass Stop Vv Cubicle F3 (M0V-2586) 11B-2 480 V MCC 2H1-25 Loco 3 Bypass Stop Vv Cubicle G1 (MOV-2587) 21E-2 480 V MCC 2H1-25 Locp 1 Bypass Stop Vv Cubicle F1 (MOV-2585) 22B-2 480 V MCC 2H1-25
_ Loop 1 Hot Leg Stop Vv Cubicle F2 (MOV-2590)*
22B-2 480 V MCC 2H1-25 Loop 1 Cold Leg Stcp Vv Cubicle G3 (MOV-2591)*
- See Special Test Exception 3.10.4 NORTH ANNA - UNIT 2 3/4 8-27 Amendment No. 21
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