ML20058P095
| ML20058P095 | |
| Person / Time | |
|---|---|
| Site: | North Anna |
| Issue date: | 08/10/1990 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20058P099 | List: |
| References | |
| NUDOCS 9008160071 | |
| Download: ML20058P095 (10) | |
Text
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/p uou UNITED STATES.
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.. NUCLEAR REGULATORY COMMISSION i
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! WASHING TON, D, C. 20666 l
VIRGINIA ELECTRIC AND POWER COMPANY-OLD DOMINION ELECTRIC COOPERATIVE 00CKET NO. 50-331 No n ANNA POWER STATION, UNIT NO. 1 KAEN0 MENT TO FAC( M JPERATING LICENSE.
i Amendment Nc.136 License NO. NPF-4 l
1..
The Nuclear Regulatory Commission (the' Commission) has-found that:
A.
The application for amendment by Virginia Electric and Power, Company l
et al.,'(the licensee) dated June 28, 1990, 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;'
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; 1
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 issuanceof this amendment is in accordance'with 10 CFR Part 51 of the Commission's1 regulations and all applicable requirements have been satisfied.
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i 9008160071 900810 PDR ADOCK 05000338 P
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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.136, are hereby incorporated 1
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.30 days.
FOR THE NUCLEAR'REGULATORi: COMMISSION rbert N. Berkow, Director-iroject Directorate <tI-2 i
Division-of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
. Changes to the Technical Specifications Date of Issuance: August' 10, 1990 u
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ATT'ACHMENT TO LICENSE AMEN 0 MENT N0.136
-TdIFACILITY'OPERATINGLICENSEN0.NPF-4 l
1 DOCKET NO. 50-338
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Replace' the following page'of the Appendix "A" Technical Specifications with the enclosed page as indicated..The revised page is. identified by amendment e
number and~contains' vertical lines indicating the area of change.. The i
corresponding _overleafipage is also provided to maintain document completeness.
PaSe 3/4 7-15
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PLANT SYSTEMS TURBINE OVERSPEED LIMITING CONDITION FOR OPERATION' 1
3.7.1.7 'At least one turbine overspeed protection. system shall be
- OPERABLE, i
APPLICABILITY: MODE 1, 2 and 3i ACTION: With the above required turbine overspeed protection system
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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.-
t SURVEILLANCE REQUIREMENT ,4.7.1.7.1 The provisions of Specificationi4.0.4 are.not applicable.
4.7.1.7.2 The above requiredLturbine overspeed protection system-shall be demonstrated 0PERABLE:
At'least once per 31 days by cycling _each of the following
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valves through one complete cycle.'
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4 Turbine Throttle valves 2.
4 Turbine Governor valves *-
3.
4 Turbine Reheat Stop valves' I
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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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 cf all valve seats, disks and stems and. verifying-0o unacceptable flaws or corrosion.
- Testing of the turbTne governor valves may be suspended during end-of-cycle power.coastdown operation between 835 MWe and 386 MWe.
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NORTH ANNA - UNIT 1 3/4 7-15 Amendment Nd. 78,5f',136, I
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UNITED STATES c-
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NUCLEAR REGULATORY COMMISSION-WASHINo ton, D, C. 20666 z
- sees VIRGINIA ELECTRIC'AND POWER COMPANY L
OLD DOMINION ELECTRIC' COOPERATIVE 1
f DOCKET NO.-50-339 1
NORTH ANNA' POWER STATION, UNIT NO. 2.
' I AMENDMENT TO FACILITY OPERATING LICENSE o
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l Amendment No.
119 i
License No. NPF-7 l
l 1.
The Nuclear Regulatory Commission (the Commission) has found that:
n A.
The application-for ' amendment by Virginia Electric and Power Company, et al., (the licensee) dated June 28, 1990, 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 t
and safety of the public, and (ii)/that such activities willibe-l conducted in compliance with-the Commission's regulations;
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D.
The issuance of this amendment will not be inimical to the common j
defense and security or to the health and safety of the public; '
l-and-E.
The issuance of this amendment is in accordance with 10 CFR Part-51 of the Commission's regulations and all applicable requirements
--l have been satisfied.
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2.
Accordingly,fthe license is amended by. changes to'the Technical Speci--
fications as-indicated in the attachment to this license amendment, l
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. '119, 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 the date of issuance;and shall' be implemented by August 15, 1990.
FOR THE NUCLEAR REGULATORY COMMISSION.-
7 0
i-Herbert N.tBerkow, Director' i
Project Directorate II-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance': August 10, 1990 l
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- d ATTACHMENT TO LICENSE AMENDMENT-NO.110-TO FACILITY OPERATING LICENSE-NO. HPF-7 DOCKET NO. 50-339-f Replace the following page of the Appendix "A"' Technical Specifications with-the enclosed page as indicated.- The revised page.is.-identified by amendment-i
. 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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'l PLANT SYSTEMS L
STEAM TURBINE ASSEMBLY i
a LIMITIllG CONDITION FOR OPERATION
'I 3.7.l'.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-;
j forming to the above requirement restore the structural integrity of the steam turbine prior to placing -it in service.
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SURVEILLANCE REQUIREMENTS' 1
l 4.7.1.6 The structural integrity of the steam turbine assembly shall be I
demonstrated; At least once per 40 months, during' shutdown, by.a visual a.-
1
-and surface inspection of the~ steam turbine assembly at -
all accessible locations, and -
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b.
At least once oer 10 years, during shutdown, by disassembly of 41; the turbine and performing a visual, surface and volumetric inspection of all normally inaccessible parts.-
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