ML20078C903
| ML20078C903 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 01/23/1995 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | City of Dalton, GA, Georgia Power Co, Municipal Electric Authority of Georgia, Oglethorpe Power Corp |
| Shared Package | |
| ML20078C904 | List: |
| References | |
| NPF-68-A-083, NPF-81-A-061 NUDOCS 9501270150 | |
| Download: ML20078C903 (10) | |
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8 ft UNITED STATES l
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NUCLEAR REGULATORY COMMISSION
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GEORGIA POWER COMPANY t
OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON. GEORGIA V0GTLE ELECTRIC GENERATING PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 83 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 February 3,1994, 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; 8.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (i) that the activities authorized by this &mendment 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.
9501270150 950103 PDR ADOCK 05000424 P
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1 2.
Accordingly, the license is hereby amended by page changes to the l
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.
83, 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 INDm f
Herbert N. Berkow, Dire tor Project Directorate II-3 i
Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Technical Specification Changes l
Date of Issuance:
January 23, 1995 I
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ft UNITED STATES g
j NUCLEAR REGULATORY COMMISSION l
WASHINGTON. D.C. 20555-0001 3
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GEORGIA POWER COMPANY l
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OGLETHORPE POWER CORPORATION l
l MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON. GEORGIA l
V0GTLE ELECTRIC GENERATING PLANT. UNIT 2 i
i AMENDMENT TO FACILITY OPERATING LICENSE i
Amendment No. 61 License No. NPF-81 1.
The Nuclear Regulatory Comission (the Comission) 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 February 3,1994, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations as set forth in 10 CFR Chapter I; i
l B.
The facility will operate in conformity with the application, the l
provisions of the Act, and the rules and regulations of the l
Comission; 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 Comission's regulations set forth in 10 CFR Chapter I; 1
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 Comission's regulations and all applicable requirements have been satisfied, t
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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 l
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 i
The Technical Specifications contained in Appendix A, as revised through i
Amendment No.
61, 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 i
be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY C0PetISSION
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Herbert N. Berkow, Director Project Directorate II-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Attachmert:
Technical Specification Changes Date of Issuance:
January 23, 1995 l
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l ATTACHMENT TO LICENSE AMENDMENT NO. 83 FACILITY OPERATING LICENSE NO. NPF-68 DOCKET NO. 50-424 0
TO LICENSE AMENDMENT NO. 61 l
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.
Remove Paaes Insert Paaes IX*
IX*
X X
3/4 7-27 3/4 7-27 3/4 7-28 3/4 7-28 8 3/4 7-6 B 3/4 7-6 Overleaf page containing no change l
l
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE0VIREMENTS SECTION EAEE 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT Containment Integrity....................................
3/4 6-1 Containment Leakage......................................
3/4 6-2 l
Containment Air Locks....................................
3/4 6-4 i
I nte rn al Pre s s u re........................................
3/4 6-6 Air Temperature..........................................
3/4 6-7 Containment Structural Integrity.........................
3/4 6-8 Containment Ventilation System...........................
3/4 6-11 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS Containment Spray System.................................
3/4 6-13 Spray Additive System....................................
3/4 6-14 Containment Cooling System...............................
3/4 6-15 3/4.6.3 CONTAINMENT ISOLATION VALVES.............................
3/4 6-16 l
3/4.6.4 COMBUSTIBLE GAS CONTROL l
Hydrogen Monitors........................................
3/4 6-18 El ectric Hydrogen Recombiners............................
3/4 6-19 I
l V0GTLE UNITS - 1 & 2 IX Amendment No. 83 (Unit 1)
Amendment No.
61 (Unit 2)
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE0VIREMENTS SECTION EA_GE 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE Safety Va1ves............................................
3/4 7-1 TABLE 3.71 MAXIMUM ALLOWABLE POWER RANGE NEUTRON FLUX HIGH SETPOINT WITH INOPERABLE STEAM LINE SAFETY VALVES........
3/4 7-2 TABLE 3.72 STEAM LINE SAFETY VALVES PER L00P.....................
3/4 7-3 Auxiliary Feedwater System...............................
3/4 7-4 Condensate Storage Tank..................................
3/4 7-6 Speci fi c Act i vi ty........................................
3/4 7-7 TABLE 4.71 SECONDARY COOLANT SYSTEM SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PR0 GRAM.....................................
3/4 7-8 Main Steam Line Isolation Va1ves.........................
3/4 7-9 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION..........
3/4 7-10 3/4.7.3 COMPONENT COOLING WATER SYSTEM...........................
3/4 7-11 3/4.7.4 NUCLEAR SERVICE COOLING WATER (NSCW) SYSTEM..............
3/4 7-12 3/4.7.5 ULTIMATE HEAT SINK.......................................
3/4 7-13 3/4.7.6 CONTROL ROOM EMERGENCY FILTRATION SYSTEM (Common System).
3/4 7-14 3/4.7.7 PIPING PENETRATION AREA FILTRATION AND EXHAUST SYSTEM....
3/4 7-17 3/4.7.8 SNUBBERS.................................................
3/4 7-19 FIGURE 4.71 SAMPLE PLAN 2 FOR SNUBBER FUNCTIONAL TEST............
3/4 7-24 TABLE 4.7-2 SNUBBER VISUAL INSPECTION INTERVAL.....................
3/4 7-24a 3/4.7.9 SEALED SOURCE CONTAMINATION..............................
3/4 7-25 3/4.7.10 AREA TEMPERATURE MONITORING..(DELETED)...................
3/4 7-27 l
TABLE 3.73 AREA TEMPERATURE MONITORING..(DELETED)................
3/4 7-28 3/4.7.11 ENGINEERED SAFETY FEATURES (ESF) ROOM COOLER AND SAFETY-RELATED CHILLER SYSTEM...................................
3/4 7-29 3/4.7.12 REACTOR COOLANT PUMP THERMAL BARRIER COOLING WATER IS0LATION................................................
3/4 7-30 l
3/4.7.13 DIESEL GENERATOR BUILDING AND AUXILIARY FEEDWATER PUMPH0VSE ESF HVAC SYSTEMS..............................
3/4 7-31 V0GTLE UNITS - 1 & 2 X
Amendment No. 83 (Unit 1)
Amendment No. 61 (Unit 2) l
l PLANT SYSTEMS 3/4.7.10 AREA TEMPERATURE MONITORING I
i SPECIFICATION 3/4.7.10 DELETED i
l l
V0GTLE UNITS - 1 & 2 3/4 7-27 Amendment No. 83 (Unit 1)
Amendment No. 61 (Unit 2)
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TABLE 3.7-3 TABLE 3.7-3 DELETED i
1 i
i V0GTLE UNITS - 1 & 2 3/4 7-28 Amendment No. 83 (Unit 1) i Amendment No. 61 (Unit 2)
4 l
ELANT SYSTEMS l
l BASES SNUBBERS (Continued) 4 l
l The service life of a snubber is established via manufacturer input and information through consideration of the snubber service conditions and j
associated installation and maintenance records (newly installed snubbers, seal-1 replaced, spring replaced, in high radiation area, in high temperature area, 1
etc.). The requirement to monitor the snubber service life is included to ensure that the snubbers periodically undergo a performance evtluation in view j
of their age and operating conditions. These records will-provide statistical bases for future consideration of snubber service life.
1 i
i 3/4.7.9 SEALED SOURCE CONTAMINATION 1'
The limitations-on removable contamination for sources requiring leak i
i testing, including alpha emitters, is based on 10 CFR 70.39(a)(3) limits for
)
plutonium. This limitation will ensure that leakage from Byproduct, Source, and Special Nuclear Material sourcu will not exceed allowable intake values.
Sealed sources are classified into three groups according to their use, l
with Surveillance Requirements commensurate with the probability of damage to a source in that group. Those sources which are frequently handled are required l
Lo be tested more often than tW m which are not. Sealed sources which are continuously enclosed within t u,elded mechanism (i.e., sealed sources within radiation monitoring or boron measuring devices) are considered to be stored and need not be tested unless they are removed from the shielded mechanism.
i 3/4.7.10 AREA TEMPERATURE MONITORING l
(DELETED) 3/4.7.11 ENGINEERED SAFETY FEATURES (ESF) ROOM COOLER AND SAFETY-RELATED CHILLER SYSTEM The operation of the ESF Room Cooler and Safety-Related Chiller System ensures that the ambient air temperature does not exceed the allowable temperature for continuous duty rating for the equipment cooled by the system.
3/4.7.12 REACTOR COOLANT PUMP THERMAL BARRIER COOLING WATER ISOLATION This isolation function is designed to prevent a spill of the reactor coolant from a postulated breached thermal barrier should a break occur in the nonsafety-related ACCW piping downstream of the isolation valvo.
Amendment No. 83 (Unit 1)
V0GTLE UNITS - 1 & 2 B 3/4 7-6 Amendment No. 61 (Unit 2)
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