ML20134L220
| ML20134L220 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 08/21/1985 |
| From: | Butcher E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20134L223 | List: |
| References | |
| NUDOCS 8509030134 | |
| Download: ML20134L220 (10) | |
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UNITED STATES f
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VIRGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE DOCKET NO. 50-338 NORTH ANNA POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 66 License No. NPF-4 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Virginia Electric and Power Company, etal.,(thelicensee)datedApril 15, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, i
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; j
C.
There is reasonable assurance (i) that the activities authorized 1
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 l
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 i
have been satisfied.
P.
. 2.
Accordingly, the license is amended by changes r., the Technical Spect-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 I
The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 66, 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 Edward J. B tcher, Acting Chief Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: August 21, 1985 4
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ATTACHMENT TO LICENSE AMENDMENT NO. 66 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 amendment number and contains vertical lines indicoting the area of change.
The corresponding overleaf page is also provided to maintain document completeness.
Page 3/4 9-3 _
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REFUELING OPERATIONS DECAY TIME LIMITING CONDITION FOR OPERATION 3.9.3 The reacto.r shall be subcritical for at least 150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br />.
I APPLICABILITY: During movement of irradiated fuel in the reactor pressure vessel.
ACTION:
With the reactor subcritical for less than 150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br />, suspend all l
operations involving movement of irradiated fuel in the reactor pressure vessel. The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.9.3 The reactor shall be determined to have been suberitical for at least 150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br /> by verification of the date and time of subcriticality l
prior to movement of irradiated fuel in the reactor pressure vessel.
J l
NORTH ANNA - UNIT 1 3/4 9-3 Amendment No. 66
REFUELING OPERATIONS CONTAINMENT BUILDING PENETRATIONS LIMITING CONDITION FOR OPERATICN 3.9.4 The containment building penetrations shall be in the following status:
The equipment door closed and held in place by a minimum of a.
four bolts, b.
A minimum of one door in each airlock is closed, and Each penetration providing direct access from the containment c.
atmosphere to the outside atmosphere shall be either:
.l.
Closed by an isolation valve, blind flange, or manual valve, or 2.
Be capable of being closed by an OPERABLE automatic Con-tainment Purge and Exhaust isolation valve.
APPLICABILITY: During CORE ALTERATIONS or movement of irradiated fuel within the containment.
ACTION:
With the requirements of the above specification not satisfied, inmedi-ately suspend all operations involving CORE ALTERATIONS cr movement of irradiated fuel in the' containment building. The provisions of Specifi-cation 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.9.4 Each of the above required containment building penetrations shall be determined to be either in its closed / isolated condition or capable of being closed by an OPERABLE automatic Containment Purge and 3
Exhaust isolation valve within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to the start of and at least once per 7 days during CORE ALTERATIONS or movement of irradiated fuel in the containnent building by:
i Verifying the penetrations are in their closed / isolated a.
condition, or b.
Testing the Containment Purge and Exhaust isolation valves and system per the applicable portions'of' Specifications 4.6.3.1.2 and 4.9.9.
NORTH ANNA - UNIT 1 3/4 9-4
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UNITED STATES 6
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g NUCLEAR REGULATORY COMMISSION 5
ej WASHINGTON, D. C. 20555
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VIRGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE DOCKET NO. 50-339 NORTH ANNA POWER STATION, UNIT N0. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 52 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, et al., (the licensee) dated April 15, 1985, 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; 8.
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 (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 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 51 of the Comission's regulations and all applicable requirements have been satisfied.
. 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. 52, 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 COPHISSION Edward J. Butcher, Acting Chief Operating Reactors Branch #3 Division of Licensing
~
Attachment:
Changes to the Technical Specifications Date of Issuance: August 21, 1985 I
.a
ATTACHMENT TO LICENSE AMENDMENT N0. 52 TO FACILITY OPERATING LICENSE NO. NPF-7 DOCKET NO. 50-339 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page as indicated. The revised page is identified by amendment number and contains vertical lines indicating the area of change.
The. corresponding overleaf page is also provided to maintain document completeness.
Page 3/4 9-3 oo
+
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4 k
e l
l REFUELING OPERATIONS DECAY TIME LIMITING CONDITION FOR OPERATION 3.9.3 The reactor shall be subcritical for at least 150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br />.
l APPLICABILITY: During movement of irradiated fuel in the reactor pressure vessel.
ACTION:
With the 7eactor subcritical for less than 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />, suspend all operations l
5 involving movement of irradiated fuel in the reactor pressure vessel.
The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.9.3 The reactor shall be determined to have been subcritical for at least 150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br /> by verification of the date and time of subcriticality prior to l
movement of irradiated fuel in the reactor pressure vessel.
NORTH ANNA - UNIT 2 3/4 9-3 Amendment No.52
REFUELING OPERATIONS CONTAINMENT BUILDING PENETRATIONS LIMITING CONDITION FOR OPERATION 3.9.4 The containment building penetrations shall be in the following status:
a.
The equipment door closed and held in place by a minimum of four
- bolts, b.
A minimum of one door in each airlock is closed, and cc-Each penetration providing direct access from the containment atmos-phere to the outside atmosphere shall be either:
1.
Closed by.an isolation valve, blind flange, or manual valve, or 2.
Be capable of being closed by an OPERABLE automatic Containment Purge and Exhaust isolation valve.
APPLICABILITY: During CORE ALTERATIONS or movement of irradiated fuel within the containment.
ACTION:
With the requirements of the above specification not satisfied, immediately suspend all operations involving CORE ALTERATIONS or movement of irradiated fuel in the containment building.
The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.9.4 Each of the above required containment building penetrations shall be determined to be either in its closed / isolated condition or capable of being closed by an OPERABLE automatic Containment Purge and Exhaust isolation valve within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to the start of and at least once per 7 days during CORE ALTERATIONS or movement of irradiated fuel in the containment building by:
Verifying the penetrations are in their closed / isolated a.
condition, or NORTH ANNA - UNIT 2 3/4 9-4
.