ML20114B707
| ML20114B707 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 08/20/1992 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | Georgia Power Co, Oglethorpe Power Corp, Municipal Electric Authority of Georgia, City of Dalton, GA |
| Shared Package | |
| ML20114B709 | List: |
| References | |
| NPF-68-A-053, NPF-81-A-032 NUDOCS 9208310124 | |
| Download: ML20114B707 (7) | |
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3' UNITED STATES 5
D-E NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D C. 20566 o
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GEORGIA POWER COMPANY QGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON. GEORGIA V0GTLE ELECTRIC GEN [fLA.IING PLANT. UNIT 1 AMENDMENT TO FAClllTY OPERATING LICENSE Amendment No. 53 License No. NPF-68 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Vogtle Electric Generating Plant, Unit 1 (the facility) Facility Operating License No. NPF-68 filed by the Georgia Power Company, acting for itself, Oglethorpe Power Corporation, Munici,al Electric Authority of Georgia, and City of Dalton, Georgia (the licensees), dated May 3,1991, as supplemented August 19 and October 11, 1991, and July 20, 1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, tne 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 conductcj in compliance with the Commission's regulations set forth in 10 CFR Chapter I; 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.
9200310124 920820 ADOCK0500g4 PDR P
_ _ _ _ _ 2.
Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-68 is hereby amended to read as follows:
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.
, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license.
GPC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION l
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Dav d B.
,atthews, Director Project Directorate 11-3 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance:
August 20, 1992 e
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UNITED STATES 3 ' Th i NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D.C. 20666 s
f GEORGIA POWER COMPAM OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CllY OF DALTON. GEORGIA YQGTLE ELECTRIC GENERATING PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 32 License No. NPF-81 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Vogtle Electric Generating Plant, Unit 2 (the facility) Facility Operating License No. NPF-81 filed by the Georgia Power Company, acting for itself, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia (the licensees), dated May 3, 1991, as supplemented August 19 and October 11, 1991, and July 20, 1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as 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 set forth in 10 CFR Chapter I; 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.
_ 2.
Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and paracraph 2.C.(2) of Facility Operating License No. NPF-8! is hereby amended to read as follows:
Teci nical Specifications and Environmental Protection Plan i
The Technical Specifications contained in Appendix A, as revised through Amendment No.
, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license.
GPC shall operate the facility in accordance with the Technical -Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION DavDd B.
atthews, Director Project Directorate 11-3 1
Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Change; Date of Issuance: August 20, 1992 l
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ATTACHMEPT T0 llCENSE AMENDMENT NO.53 FACILITY OPERATING LICENSE NO. NPF-68 QD.CKET NO. 50-424 AND TO LICENSE AMENDMENT NO. 32 FACILITY OPERATING LICENSE NO. NPF-81 DOCKET NO. 50-425 Replace the following pages of the Apperidix "A" Technical Specifications with the enclosed pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.
Remove Paces Insert Paaes 3/4 6-15*
3/4 6-15*
3/4 6-16 3/4 6-16 8 3/4 6-3*
B 3/4 6-3*
B 3/4 6-4 8 3/4 6-4
- overleaf page, no change
CONTAINMENT SYSTEMS 3/4.6.3 CONTAINMENT ISOLATION VALVES LIMITINGCONDITIONFOROPERATION 3.6.3 The containment isolation valves shall be OPERABLE.*
I APPLICABILITY:
MODES 1, 2, 3, and 4.
ACTION:
With one or more of the containment isolation valve (s) inoperable, maintain at least one isolation valve OPERABLE in each affected penetration that is open and:
Restore the inoperable valve (s) to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, a.
or b.
Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one deactivated automatic valve secured in me isolation position, or Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least c.
one closed manual valve or blind flange, or d.
Be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
The provisions of Specification 3.0.4 are not applicable provided e.
that the affected penetration is isolated in accordance with ACTION b or c above, aad provided that the associated system, if applicable, is declared inoperable and the appropriate ACTION statements for that system are performed.
l SURVEILLANCE REQUIREMENTS 4.6.3.1 The containment isolation valves shall be demonstrated OPERABLE prior i.o returning the valve to service after maintenance, repair or replacement work l
is performed on the valve or its associated actuator, control or power circuit by performance of a cycling test, and verification of isolation time, l
i
- Isolation valves associated with the containment hydrogen monitors may be opened on an intermittent basis under administrative control.
V0GTLE UNITS - 1 & 2 3/4 6-16 Amendment No.53 (Unit 1)
Amendment No.32 (Unit 2) l-L
CONTAINMENT SYSTEMS l
BASES i
i 3/4.6.2.3 CONTAINMENT COOLING SYSTEM l
l The OPERABILITY of the Containment Cooling System ensures that: (1) the l
containment air temperature will be maintained within limits during normal l
operation, and (2) adequate heat removal capacity is available when operated in conjunction with the Containment Spray Systems durini post-LOCA conditions.
3/4.6.3 CONTAINMENT ISOLATION VALVES The OPERABILITY of the containment isolation valves ensures that the con-tainment atmosphere will be isolated from the outside environment in the event of a release of radioactive material to the containment atmosphere or pressuri-zation of the containment and is consistent with the requirements of General Design Criteria 54 through 57 of Appendix A to 10 CFR Part 50.
Containment isolation within the time limits specified for those isolation valves designed to close automatically ensures tMt the release of radioactive material to the environment will be consistent with the assumptions used in the analyses for a LOCA.
The containment isolation valves associated with the containment hydrogen monitors may be opened on an intermittent basis under administrative control.
Since the controls for these valves are located in the main control room, which is continuously manned, an operator will be available to ensure rapid isolation if necessary.
A list of coatainment isolation valves is provided in Table 16.3-4 of the VEGP FSAR.
3/4.6.4 COMBUSTIBLE GAS CONTROL l
The OPERABILITY of the equipment and systems required for the detection and control of hydrogen gas ensures that this equipment will be available to maintain the hydrogen concentration within containment below its flammable limit during post-LOCA conditions.
Either recombiner unit is capable of con-trolling the expected hydrogen generation associated with: (1) zirconium-water reactions, (2) radiolytic decomposition of water, anci (3) corrosion of metals within containment.
These Hydrogen Control Systems are consistent with the recommendations of Regulatory Guide 1.7, " Control of Combustible Gas Concen-trations in Containment Following a LOCA," Revision 2, November 1978.
The Hydrogen Mixing Systems are provided to ensure adequate mixing of the containment atmosphere following a LOCA.
This mixing action will prevent localized accumulations of hydrogen from exceeding the flammable limit.
1 1
V0GTLE UNITS - 1 & 2 B 3/4 6-4 Amendment No.53 (Unit 1)
Amendment No.32 (Unit 2)
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