ML20154P238
| ML20154P238 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 05/23/1988 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20154P242 | List: |
| References | |
| NUDOCS 8806030265 | |
| Download: ML20154P238 (10) | |
Text
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Io UNITED STATES q
NUCLEAR REGULATORY COMMISSION o
WASHINGTON, D. C. 20655
%,.....J VIRGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE DOCKET N0. 50-338 NORTH ANNA POWER STATION, UNIT N0. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.102 License No. NPF-4 1.
The ftuclear Regulatory Commission (the Commission) has found that:
A.
The application for amencment by Virginia Electric and Power Company et al.,-(the licensee) dated April 1, 1987, 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; 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 (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 common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in tccordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
8806030265 080523 PDR ADOCK 05000330 P
. 2.
Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this license amendment, and paragraph 2.0.(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 8, as revised through Amendment No.
, 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 issuance and shall be implemented within 14 days.
FOR THE NUCLEAR REGULATORY COMMISSION Of Yf He bert N. Berkow, 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: May 23, 1988 I
. ATTACHMENT TO LICENSE AMENDMENT NO.102 TO FACILITY OPERATING LICENSE NO. NPF-4 DOCKET N0. 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 indicating the area of change.
The corresponding overleaf page is also provided to maintain document completeness.
Page 3/4 9-10 i
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REFUELING OPERATIONS CONTAINMENT PURGE AND EXHAUST ISOLATION SYSTEM LIMITING CONDITION FOR OPERATION 3.9.9 The Containment Purge and Exhaust isolation system shall be OPERABLE.
APPLICABILITY: MODE 6.
ACTION:
With the Containment Purge and Exhaust isolation system inoperable, close each of the Purge and Exhaust penetrations providing direct access from the containment atmosphere to the outside atmosphere.
The provision of Specification 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.9.9 The Containment Purge and Exhaust isolation system shall be demonstrated OPERABLE 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 by verifying that con-tainment Purge and Exhaust isolation occurs on manual initiation and on a high radiation test signal from the containment gaseous and particulate i
radiation monitoring instrumentation channels.
I NORTH ANNA - UNIT 1 3/4 9-9
l REFUELING OPERATIONS WATER LEVEL - REACTOR VESSEL LIMITING CONDITION FOR OPERATION 1
3.9.10 At least 23 feet of water shall be maintained over the top of the
. reactor pressure vessel flange.
APPLICABILITY:
During movement of fuel assemblies or control rods within the reactor pressure vessel while in MODE 6.
ACTION:
With the requirements of the above specification not satisfied. suspend all operations involving movement of fuel assemblies or control rods within the-i pressure vessel.
The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.9.10 The water level shall be determined to be at least its minimum required depth within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> prior to the stcrt of and at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter during movement of fuel assemblies or control rods.
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J NORTH ANNA - UNIT 1 3/4 9-10 Amendment No. 32, 102
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WASHINGTON, D. C. 20555 p
VIRGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE DOCKET N0. 50-339 h0RTH ANNA POWER STATION, UNIT NO. 2 AMENUMENT TO FACILITY OPERATING LICENSE Amendment No. 89 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 1,1987, 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, c~,d 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 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 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.
, 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 issuance and shall be implemented within 14 days.
FOR THE NUCLEAR REGULATORY COMMISSION
)*
erbert N. Berkow, 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: May 23, 1988 i
l
ATTACHMENT TO LICENSE AMENDMENT NO. 89 TO FACILITY OPERATING LICENSE N0. NPF-7 DOCKET N0. 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 9-11 I
[
4 4
i j
REFUELING OPERATIONS WATER LEVEL - REACTOR VESSEL LIMITING CONDITION FOR OPERATION 3.9.10 At least 23 feet of water shall be maintained over the top of the reactor pressure vessel flange.
APPLICABILITY:
During movement of fuel assemblies or control rods within the reactor pressure vessel while in MODE 6.
ACTION:
With the requirements of the above specification not satisfied, suspend all operations involving movement of fuel assemblies or control rods within the pressure vessel.
The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE RE0VIREMENTS 4.9.10 The water level shall be determined to be at least its minimum required depth within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> prior to the start of and at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter during movement of fuel assemblies or control rods.
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i NORTH ANNA - UNIT 2 3/4 9-11 Amendment No. 89
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REFUELING OPERATIONS SPENT FUEL PI) /ATER LEVEL LIMITING CONDITION FOR OPERATION 3.9.11 At least 23 feet of water shall be maintained over, the top of irradiated fuel assemblies seated in the stcrage racks.
APPLICABILITY:
Whenever irradiated fuel assemblivs are in the spen
- fuel pit.
ACTION:
With the requirements of the specification not satisfied, suspend all movement of fuel assemblies and crane operations with loads in the spent fuel pit areas and place the load in a safe condition.
Restore water leni to wtthin its limit within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.9.11 The water level in the spent fuel pit shall be determined to be at least at the minimum required depth at least once per 7 days when irradiated fuel assemblies are in the spent fuel pit.
NORTH ANNA - UNIT 2 3/4 9-12
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