ML20063F202
| ML20063F202 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 02/07/1994 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20063F203 | List: |
| References | |
| NUDOCS 9402140176 | |
| Download: ML20063F202 (10) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. 20555-0001 k..s /
VIRGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE DOCKET NO.50-31Q NABTH ANNA POWER STATION. UNIT NO. 1
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AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. U License No. NPF-4 1.
The Nuclear Regulatory Commission (the Commission) has found that:
I A.
The application for amendment by Virginia Electric and Power Company et al., (the licensee) dated December 10, 993, 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 (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 Commission's regulations and all applicable requirements have been satisfied.
9402140176 940207 PDR ADOCK 05000338 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.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. 177, 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
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Her ert N. Berkow, 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: February 7, 1994 i
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ATTACHMENT TO LICENSE AMENDMENT NO. 177 TO FACILITY OPERATING LICENSE NO. NPF-4 DOCKET NO. 50-338 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages as indicated. The revised pages are identified by amendment nuinber and contain vertical lines indicating the area of change.
Remove Paaes Insert Paaes 3/4 7-5 3/4 7-5 3/4 7-6 3/4 7-6 5
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PLANT SYSTEMS AUXIUARY FREDWATER SYSTEM UMmNG CONDITION FOR OPERATION 3.7.1.2 At least three independent steam generator auxillary feedwater pumps and associated flow paths shall be OPERABLE with:
- a. Two motor driven auxiliary feedwater pumps, each capable of being powered from separate emergency busses, and
- b. One steam turbine driven auxiliary feedwater pump capable of being powered from an OPERABLE steam supply system.
APPUCABILITY: MODES 1,2 and 3.
ACTK)N
- a. With one auxiliary feedwater pump inoperable, restore the required auxiliary fedwater pumps to an OPERABLE status 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 SH' TDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
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- b. With two auxiliary feedwater pumps inoperable be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
- c. With three auxiliary feedwater pumps inoperable, immediately initiate corrective action to restore at least one auxiliary feedwater pump to OPERABLE status as soon as possible.
SURVEILIANCE REOU!REMENTS 4.7.1.2 in addition to the requirements of Specification 4.0.5, each auxiliary feedwater pump shall be demonstrated OPERABLE:
- a. At least once per 31 days by:
- 1. Verifying that each valve (manual, power operated or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.
- b. At least once per 92 days on a STAGGERED TEST BASIS by:
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- 1. Verifying that each pump develops adequate discharge pressure and flow. The acceptance criterion shall be consistent with Specification 4.0.5. _ The provisions of Specification 4.0.4 are not applicable to steam turbine drNen pump testing.
NORTH ANNA - UNIT 1 3/4 75 Amendment No. 10, 32,14;r, 177
i PUWT SYSTEMS SURVEILLANCE REOUIREMENTS (Continued)
- c. At least once per 18 months during shutdown by:
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- 1. Verifying that each automatic valve in the flow path actuates to its correct position on an auxiliary feedwater actuation test signal.
- 2. Verifying that each auxiliary feedwater pump starts automatically upon receipt of an auxiliary feedwater actuation teet signal.
- d. - The auxiliary feedwater system flow paths sh'all be demonstrated OPERABLE prior to l
entry into MODE 3 following each COLD SHUTDOWN by performing a flow test to verify the normal flow path from the emergency condensate storage tank through each auxiliary feedwater pump to its associated steam generator, i
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NORTH ANNA - UNIT 1 3/4 7-6 Amendment No. 10, 32, 147, 177 l
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UNITED STATES
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. j NUCLEAR REGULATORY COMMISSION
- WASHINGTON. D.C. 20556-0001_
,l VIRGINIA ELECTRIC-AND POWER COMPANY j
OLD DOMINION ELECTRIC' COOPERATIVE j
DOCKET NO. 50-339' RQRIP ANNA POWER STATION. UNIT NO. 2~
I AMENDMENT TO FACILITY OPERATING' LICENSE Amendment No.158 License No. NPFL7 u
1.
The Nuclear Regulatory Commission (the Commission) has found.that:
A.
The application for amendment by Virginia Electric and Power Company.
et al., (the licensee) dated December 10,.1993, complies with the i
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 (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 l
of the Commission's regulations and all applicable requirements have-been satisfied.-
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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.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.158
, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
t 3.
This license amendment is effective as of "t, date of issuance and shall be implemented within 30 days.
F03,THENUCLEARREGULATORYCOMMISSION
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Her ert N. Berkow, Airector Project Directorate II-2 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: February 7, 1994
ATTACHMENT TO LICENSE AMENDMENT NO.158 TO FACILITY OPERATING LICENSE NO. NPF-7 DOCKET NO. 50-339 1
Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages as indicated. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
Remove Paaes Insert Paaes 3/4 7-5 3/4 7-5 3/4 7-6 3/4 7-6 r
L r
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PLANT SYSTEMS AUXfuARY FFFDWATER SYSTEM UMITING CONDITION FOR OPERATION 3.7.1.2 At least three independent steam generator auxiliary feedwater pumps and associated 7
flow paths shall be OPERABLE with:
- a. Two motor driven auxiliary feedwater pumps, each capable of being powered from separate emergency busses, and
- b. One steam turbine driven auxiliary feedwater pump capable of being powered from an OPERABLE steam supply system.
4 APPUCABILITY: MODES 1,2 and 3.
f.CTION:
- a. With one auxiliary feedwater pump inoperable, restore the required auxiliary feedwater pumps to an OPERABLE status 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 r
SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
- b. With two auxiliary feedwater pumps inoperable be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
- c. With three auxiliary feedwater pumps inoperable, immediately initiate corrective action to restore at least one auxiliary feedwater pump to OPERABLE status as soon as possible.
SURVEILLANCE REOUIREMEN1'S 4.7.1.2 in addition to the requirements of Specification 4.0.5, each auxiliary feedwater pump shall be demonstrated OPERABLE:
- a. At least once per 31 days by:
- 1. Verifying that each valve (manual, power operated or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its corrdct position.
- b. At least once per 92 days on a STAGGERED TEST BASIS by:
l
- 1. Verifying that each pump develops adequate discharge pressure and flow. The acceptance criterion shall be consistent with Specification 4.0.5. The provisions of Specification 4.0.4 are not applicable to steam turbine drrven pump testing.
NORTH ANNA - UNIT 2 3/4 7-5 Amendment No. -444, 158 F
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PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
- c. At least once per 18 rnonths during shutdown bv:
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- 1. Verifying that each automatic valve in the flow path actuates to its correct position on an auxiliary feedwater actuation test signal.
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- 2. Verifying that each auxiliary feedwater pump starts automatically upon receipt of an auxiliary feedwater actuation test signal,
- d. The auxiliary feedwater system flow paths shall be demonstrated OPERABLE prior to -
l entry into MODE 3 following each COLD SHUTDOWN by performing a flow test to verify' the normal flow path from the emergency condensate storage tank through each auxiliary feedwater pump to its associated steam generator.
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NORTH ANNA - UNIT 2 3/4 7-6 Amendment No.-484,158
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