ML20084B996
| ML20084B996 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 04/16/1984 |
| From: | John Miller Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20084B998 | List: |
| References | |
| NUDOCS 8404270024 | |
| Download: ML20084B996 (10) | |
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,e VIRGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE DOCKET N0. 50-338 NORTH ANNA POWER STATION, UNIT NO. 1 AftEhDMENT TO FACILITY OPERATING LICENSE Amendment No. 56 License No. NPF-4 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Virginia Electric and Power Company (the licensee) dated December 21, 1983 as supplemented February 21, 1984, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission'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 (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 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.
e404270024 840416 PDR ADOCK 05000338_
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. 2.
Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this license amendment, and paragraph 2.D.(2) of Facility Operating License No. NPF 4 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 56, 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
/,
James R. Miller, Chief Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: April 16, 1984 u__
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 56 TO FACILITY OPERATING LICENSE NO. NPF-4 DOCKET NO. 50-338 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page as indicated. The revised page is identified by amemdment number and contains vertical lines indicating the area of change.
The corresponding overleaf page is also provided to maintain document completeness.
.Page 3/4 7-15 1
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PLANT SYSTEMS TURBINE OVERSPEED LIMITING CONDITION FOR OPERATION 3.7.1.7 At least one turbine overspeed protection system shall be OPERABLE.
APPLICABILITY: MODE 1, 2 and 3 ACTION: With the above required turbine overspeed protection system inoperable, within 6 hdars either restore the system to OPERABLE status or isolate the turbine from the steam supply.
SURVEILLANCE REQUIREME_NT 4.7.1.7.1 The provisions of Specification 4.0.4 are not applicable.
4.7.1.7.2 The above required turbine overspeed protection system shall be demonstrated OPERABLE:
a.
At least once per 31 days by cycling each of the following l
valves through one complete cycle.
1.
4 Turbine Throttle valves 2.
4 Turbine Governor valves 3.
4 Turbine Reh' eat Stop valves 4.
4 Turbine Reheat Intercept valves b.
At least once per 31 days by direct observation of the movement of each of the above valves through one complete cycle.
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c.
At least once per 18 months, by performance of CHANNEL CALIBRA-TION on the turbine overspeed protection instruments, d.
At least once per 40 months, by disassembly of at least one of each of the above valves and performing a. visual and surface inspection of all valve seats, disks and stems and verifying 00 unacceptable flaws or corrosion.
NORTH ANNA - UNIT 1 3/4 7-15 Amendment No. 16, 56
PLANT SYSTEMS 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION LIMITING CONDITION FOR OPERATION 3.7.2.1 The temperatures of both the primary and secondary coolants in the steam generators shall be > 70*F when the pressure of either coolant in the steam generator is > 200 psig.
APPLICABILITY: At all times.
ACTION:
With the requirements of the above specification not satisfied:
a.
Reduce. the steam generator pressure of the applicable side to
< 200 psig within 30 minutes, and b.
Perform an engineering evaluation to determine the effect of the overpressurization on the structural integrity of the steam generator.
Determine that the steam generator remains acceptable for continued operation prior to increasing its temperatures above 200*F.
SURVEILLANCE REQUIREMENTS 4.7.2.1 The pressure in each side of the steam generator shall be determined to be < 200 psig at least once per hour when the temperature of either the primary or secondary coolant is < 70*F.
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VIRGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE DOCKET N0. 50-339 NORTH ANNA POWER STATION, UNIT N0. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 38 License No. NPF-7 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Virginia Electric and Power Company
~
(the licensee) dated December 21, 1983 as supplemented February 21, 1984, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission'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 Comission'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 f
51 of the Comission's regulations and all applicable requirements i
have been satisfied.
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l
2.
Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-7 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 38, 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 l
James R. Miller, Chief Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications i
Date of Issuance: April 16, 1984
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ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 38 TO FACILITY OPERATING LICENSE NO. NPF-7 DOCKET NO. 50-339 Replace the followino page of the Appendix "A" Technical Specifications with the enclosed page as indicated. The revised page is identified by amemdnent number and contains vertical lines indicating the area of change.
The corresponding overleaf page is also provided to maintain document completeness.
Page 3/4 7-12
PLANT SYSTEMS STEAM TURBINE ASSEMBLY LIMITING CONDITION FOR OPERATION 3.7.1.6 The structural integrity of the steam turbine assembly shall be maintained.
APPLICABILITY: MODES 1 and 2 ACTION: With the structural integrity of the steam turbine assembly not con-forming to the above requirement restore the structural integrity of the steam turbine prior to placing it in service.
6 SURVEILLANCE REQUIREMENTS 4.7.1.6 The structural integrity of the steam turbine assembly shall be demonstrated; a.
At least once per 40 months, during shutdown, by a visual and surface inspection of the steam turbine assembly at all accessible locations, and b.
At least once per 10 years, during shutdown, by disassembly of the turbine and performing a visual, surface and volumetric inspection of all normally inaccessible parts.
NORTH ANNA - UNIT 2 3/4 7-11
PLANT SYSTEMS TURBINE OVERSPEED LIMITING CONDITION FOR OPERATION 3.7.1.7 At least one turbine overspeed system shall be OPERABLE.
APPLICABILITY: MODE 1, 2 and 3 ACTION: With the abcee required turbine overspeed protection system inoperable, within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> either restore the system to OPERABLE status or isolate the turbine from the steam supply.
SURVEILLANCE REQUIREMENT 4.7.1.7.1 The provisions of Specification 4.0.4 are nnt applicable.
4.7.1.7.2 The above required turbine overspeed protectiva system shall be demonstrated OPERABLE:
At least once per 31 days by cycling each of the following valves l
a.
through one complete cycle.
1.
4 Turbine Throttle valves 2.
4 Turbine Governor valves 3.
4 Turbine Reheat Stop valves 4.
4 Turbine Reheat Intercept valves b.
At least once per 31~ days by direct observation of the movement of each of the above valves through one complete cycle.
At least? once per 18 months, by performance of CHANNEL CALIBRATION c.
on the turbine overspeed protection instruments.
d.
At 'least once per 40 months, by disassembly of at least one of each of the above valves and performing a visual and surface inspection of all valve seats, disks and stems and verifying no unacceptable flaws or corrosion.
NORTH ANNA - UNIT 2 3/4 7-12 Amendment No. 38 4
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