ML20086G912
| ML20086G912 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 07/07/1995 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | Southern Nuclear Operating Co, Georgia Power Co, Oglethorpe Power Corp, Municipal Electric Authority of Georgia, City of Dalton, GA |
| Shared Package | |
| ML20086G916 | List: |
| References | |
| NPF-67-A-081, NPF-68-A-089 NUDOCS 9507170283 | |
| Download: ML20086G912 (8) | |
Text
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UNITED STATES
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-j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20066 0001
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GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON. GEORGIA i
V0GTLE ELECTRIC GENERATING PLANT. UNIT 1 AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No. 89 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, Municipal Electric Authority of. Georgia, and City of Dalton, Georgia (the licensees), dated December-27,1994, 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.
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. 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. 89
, 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 and shall be implemented within 30 days from the date of issuance.
FOR tVCLEAR REGULATORY COMMISSION fj.
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Her rt N. Berkow, Director Project Directorate 11-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance:
July 7, 1995 l
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j NUCLEAR REGULATORY COMMISSION 2
WASHINGTON. D.C. 20666-0001
\\.....j GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON. GEORGIA V0GTLE ELECTRIC GENERATING PLANT. UNIT l AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 67 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 December 27, 1994, 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 i
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.
I
1 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-81 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. 67
, 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 and shall be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION us-H bert N. Berkow Director Project Directorate 11-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance:
July 7, 1995
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ATTACHMENT TO LICENSE AMENDMENT NO. 89 FACILITY OPERATING LICENSE NO. NPF-68 DOCKET NO. 50-424 AND TO LICENSE AMENDMENT NO. 67 FACILITY OPERATING LICENSE NO. NPF-81 DOCKET NO. 50-425 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change. This action affects TS Bases page B 3/4 6-3.
There are different versions of this page in effect for Units 1 and 2 until the spray additive system is removed from Unit I during the Unit 1 Cycle 6 refueling outage in the spring of 1996.
These two pages are to be replaced with the enclosed two versions of page B 3/4 6-3.
The page with 3/4.6.2.2 (Spray Additive System) is for Unit 1 and the page with 3/4.6.2.2 deleted is for Unit 2.
Remove Paaes Insert Paan 3/4 6-12 3/4 6-12 B 3/4 6-3 (w/TS 3/4.6.2.2)
B 3/4 6-3 (w/TS 3/4.6.2.2)
B 3/4 6-3 (w/TS 3/4.6.2.2 deleted)
B 3/4 6-3 (w/TS 3/4.6.2.2 deleted) l l
1
CONTAINMENT SYSTEMS SURVEILLANCE RE0VIREMENTS (Continued) 4.6.1.7.2 At least once during each refueling outage the containment purge l
valves with resilient material seals in each sealed closed containment purge supply and exhaust penetration shall be demonstrated OPERABLE by verifying that the measured penetration leakage rate is less than 0.06 L, when pressurized to P,.
4.6.1.7.3 Each 14-inch containment purge supply and exhaust isolation valve (HV-2626B, HV-26278, HV-26288, HV-26298) shall be. verified to be closed or open in accordance with Specification 3.6.1.7b at least once per 31 days.
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V0GTLE UNITS - 1 & 2 3/4 6-12 Amendment No. 89 (Unit 1)
Amendment No. 67 (Unit 2)
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CONTAINMENT SYSTEMS BASES CONTAINMENT VENTILATION SYSTEM (Continued)
The use of the containment purge lines is restricted to the 14-inch purge supply and exhaust isolation valves since, unlike the 24-inch valves, the 14-inch valves are capable of closing during a LOCA or steam line break accident.
Therefore, the SITE BOUNDARY dose guideline of 10 CFR Part 100 would not be exceeded in the event of an accident during containment PURGING operation. Only safety-related reasons; e.g., containment pressure control or the reduction of airborne radioactivity to facilitate personnel access for surveillance and maintenance activities, should be used to justify the opening of these isolation valves.
Leakage integrity tests with a maximum allowable leakage rate for containment purge' supply and exhaust supply valves will allow opportunity for l
repair before gross leakage failures could develop. The 0.60 L leakage limit of Specification 3.6.1.2b. shall not be exceeded when the leaka,ge rates determined by the leakage integrity tests of these valves are added to the previously determined total for all valves and penetrations subject to Type B and C tests.
3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS 3/4.6.2.1 CONTAINMENT SPRAY SYSTEM The OPERABILITY of the Containment Spray System ensures that containment depressurization and cooling capability will be available in the event of a LOCA or steam line break.
The pressure reduction and resultant lower containment leakage rate are consistent with the assumptions used in the safety analyses.
The Containment Spray System and the Containment Cooling System both provide post-accident cooling of the containment atmosphere.
However, the Containment Spray System also provides a mechanism for removing iodine from the containment atmosphere and therefore the time requirements for restoring an inoperable Spray System to OPERABLE status have been maintained consistent with that assigned other inoperable ESF equipment.
3/4.6.2.2 SPRAY ADDITIVE SYSTEM The OPERABILITY of the Spray Additive System ensures that sufficient Na0H is added to the containment spray in the event of a LOCA.
The limits on Na0H volume and concentration ensure a pH value of between 8.0 and 10.5 for the solution recirculated within containment after a LOCA.
This pH band minimizes the evolution of iodine and minimizes the effect of chloride and caustic stress corrosion on mechanical systems and components.
The solution volume limits (3700-4000 gallons) represent the required solution to be delivered (i.e., the delivered solution volume is that volume above ' e tank discharge).
These assumptions are consistent with the iodine rer al efficiency assumed in the safety analyses.
V0GTLE UNITS - 1 & 2 B 3/4 J-3 Amendment No. 89 (Unit 1)
Amendment No. 67 (Unit 2)
CONTAINMENT SYSTEMS BASES CONT.AINMEN! VENTILATION SYET W (Continued)
The use of the containment purge lines is restricted to the 14-inch purge supply and exhaust isolation valves since, unlike the 24-inch valves, the 14-inch valves are capable of closing during a LOCA or steam line break accident.
Therefore, the SITE B0UNDARY dose guideline of 10 CFR Part 100 would not be exceeded in the event of an accident during containment PURGING operation. Only safety-related reasons; e.g., containment pressure control or the reduction of airborne radioactivity to facilitate personnel access for surveillance and maintenance activities, should be used to justify the opening of these isolation valves.
Leakage integrity tests with a maximum allowable leakage rate for containment purge supply and exhaust supply valves will allow opportunity for l
repair before gross leakage failures could develop.
The 0.60 L leakage limit of Specification 3.6.1.2b. shall not be exceeded when the leakag,e rates determined by the leakage integrity tests of these valves are added to the previously determined total for all valves and penetrations subject to Type B and C tests.
3/4.6.2 DEPRESSURIZATION AND C00LiiiG SYSTEMS 2/4.6.2.1 CONTAINMENT SPRAY SYSTEM The OPERABILITY of the Containment Spray System ensures that containment depressurization and cooling capability will be available in the event of a LOCA or steam line break.
The pressure reduction and resultant lower containment leakage rate are consistent with the assumptions used in the safety analyses.
The Containment Spray System and the Containment Cooling System both provide post-accident cooling of the containment atmospbere.
However, the Containment Spray System also provides a mechanism for removing iodine from the containment atmosphere and therefore the time requirements for restoring an inopercble Spray System to OPERABLE status have been maintained consistent with that assigned other inoperable M equipment.
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.2 SPRAY ADDITIVE SYSTEM Specsfication 3/4.6.2.2 DELETED V0GTLE UNITS - 1 & 2 B 3/4 6-3 Amendment No. 89 (Unit 1)
Amendment No. 67 (Unit 2)
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