ML20076C998
| ML20076C998 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 07/15/1991 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20076D000 | List: |
| References | |
| NUDOCS 9107250227 | |
| Download: ML20076C998 (10) | |
Text
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1 UNITED STATES 3-i NUCLEAR REGULATORY COMMISSION
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WASHINGTON D.C. 2C656 o
VIRGINIA _ ELECTRIC _ANDPOWERCgPg OLD DOMINION ELECTRIC COOPERATIVE DOCLET NO. 50-338 NORTH ANNA POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.147 License No. NPF-4 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Virginia Electric and Power Company etal.,(thelicensee)datedDecember 28, 1989, as modified February 14, Energy Act of 1954, as amended (the Act)quirements of the Atomic 1991, complies with the standards and re
, 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 t1e Act, and the rules and regulations of the Connission; 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 compliar.ce with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the connon 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.
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2 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:
(F) Technical Specifications The Technical Specifications contained in A)pendices A and B, as revised through Amendment No. 147, are aereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
T11s license amendment is effective as of the date of issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION 8
t Ferbert N. Berkow, Director Project Directorate 11-2 Division of Reactor Projects - 1/l!
Office of Nuclear Reactor Reguletion
Attachment:
Changes to tha Technical Specifications Date of Issuance: July 15, 1991 L
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ATTACHMENT TO LICENSE AMENDMENT NO. 147 TO FACILITY OPERATING LICENSE NO. NPF-4 i
DOCKETNO.50-32 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 7-5 3/4 7-6 1
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PLANT SYSTEMS AUXILIARY FEEDWATER SYSTEM LIMITING CONDITION FOR OPERATION
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- 3. 7.1. 2 At least three independent steam generator auxiliary 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.
APPLICABILITY:
H0 DES 1, 2 and 3.
l A_CTION:
a.
With one auxiliary feedwater pump inoperable, restore the required auxiliary feedwater pumps to an OPERABLE status within /2 hours or be in at least 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 />, 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 REQUIREMENTS i
- 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 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 driven pump testing.
NORTH ANNA - UNIT 1 3/4 7-5 Amendment No. 18 77,147,
PLANT SYSTEMS SURVEILLANCE REQUIREMENT 5 (Continued)
I 2.
Verifying that each valve (manual, power operated or automatic) in the flow path that is hot locked, sealed, or otherwise secured in position, is in its correct position, b,
At least once per 18 months during shutdown by:
1.
Verifying that each automatic valve in the flow path actuates to its correct position on an auxiliary feedwater actuatior, test I
signal.
2.
Verifying that each auxiliary feedwater pump starts automatically upon receipt of an auxiliary feedvater actuation test signal, c.
The auxiliary feedwater system shall be demonstrated OPERABLE prior to 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 auxillary feedwater pump to its associated steam generator.
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l NORTH ANNA - UNIT 1 3/4 7-6 Amendment No. 19, J/, 147, l
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WASHINGTON. D.C 20666 VIRGINIA ELECTRIC AND POWER COPPANY Oj.0_00ftIN10HELECTRICCOOPERATIVE
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DOCKET NO. 50-339 NORTH ANNA POWER STATION, UNIT NO. 2 AMENDIRNT_TO, FACILITY OPER_A,T,1NG LICENSE Amendment No. 131 License No. NPF-7 1.
The-Nuclear Regulatory Consnission (the Conraission) has found that:
j A.
The' application for amendment by Virginia Electric and Power Company, 1
-etal.,(thelicensee)datedDecember 28, 1989, as modified February 14 1991, complies with the standards and requirements c' the Atomic Energy Act of 1954, as amended-(the Act), and the Camission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will o)erate in conformity with the application, the provisions of tie Act, onc the rules and regulations of i
the Consnission; L
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 Consnission's regulations; D.
The issuance of this amendment will not be inimical to the coninon defense and security or to the health and safety of the public; and E.
.The issuance of this amendment is in occordance with 10 CFR Part 51 of the Commission's rcgulations and-all applicable requirements have been satisfied, I
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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, j
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. 131
, 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 i lin 30 days.
FOR THE NUCLEAR REGULOORY COMMISSION Herbert N. Berko'w, Director Project Directorate 11-2 Division of Rcactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Data of Issuance: July 15, 1991
ATTACHMENT TO LICENSE AMENDMENT NO. 131 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.
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PLANT SYSTEMS AUXILIARY FEE 0 WATER SYSTEM LIMITINO ctwnITION'FOR_ OPERATION 3.7.1.2 At least three independent steam generator auxiliary feedwater pumps and associated flow paths shall be OPERABLE with:-
Two motor driven auxiliary feedwater pumps, each capable of being a.
powered from separate emergency busses, and b.
One steam turbine driven auxiliary feedwater pump capable of being powered from an OPERABLE steam supply system.
APPLICABILITY:
MODES 1, 2 and 3.
ACTION:
With one auxiliary feedwater pump inoperable, restore the required auxiliary a.
feedwater pumps to a 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 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, imediately initiate corrective action to restore at least one auxiliary feedwater pump to OPERABLE status as soon as possible.
SURVEILLANCE REQUIREMENTS L
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 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 driven pump testing.
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NORTH ANNA - UNIT 2 3/4 7-5 Amendnent ?!o.131,
PLANT SYSTEMS SU,RVE!LLANCE REQUIREMENTS (Continued) 2.
Verifying that each valve ' manual, powce operated or automatic)
I in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.
b.
At least once per 18 months during shutdewn by:
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 test signal.
c.
The auxiliary feedwater system shall be demonstrated OPERABLE prior to 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.
NORTH ANNA - UNIT 2 3/4 7-6 Amendment flo.131,
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