ML20059L326
| ML20059L326 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 09/18/1990 |
| 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 | |
| ML20059L331 | List: |
| References | |
| NPF-68-A-035, NPF-81-A-015 NUDOCS 9009260247 | |
| Download: ML20059L326 (7) | |
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UNITED STATES g
NUCLEAR REGULATORY COMMIE 310N f
WASHING TON, D. C. 20b66
%....+l GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON. GEORGIA V0GTLEElECTRICGENERATINGPLANT. UNI,TJ AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
35 License No. NPF-68 i
1.
The Nuclear Regulatory Commission (the Comission) has found that:
4 A.
The application for amendment to the Vogtle Electric Generating l
Plant, Unit 1 (the facility) Facility Operating License No. NPT 18 filed by the Georgia Power Company acting for itself Oglethe rs Power Corpontion, Municipal Electric Authority of Georgia, i of Dalton, Georgia, (the licensees) dated March 1, 1990, cos;
-m with the standards and requirements of the Atomic Energy Act
- 'W as amended (the Act), and the Comission's rules aM regulatior..
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.
Thereisreasonableassurance(1)thattheactivitiesauthorizedby this amendmant can i;e 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 license amendment will not be inimical to the' connon defense and security or to the health and safety of the 4
public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission'3 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 attachsent 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 j
1 The Technical Specifications contained in Appendix A, as revised through
]
Amendment No. 35, and the Environmental ProtMtion Plan contained in Appendix B both of which are attached hereto, are hereby incorporated intothislicense. GPC shall operate the facility in accordance with the j
Technical tpecifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issnance and shall be implemented within 30 days of issuance.
FOR THE NUCLEAh REGULATORY COMMISSION
., //
(M4 David 3. F1sthews, Director Project s'irectorate 11-3 Divisiois of Reactor.Proj M s-I/II i
l Office of Nuclear Reactor tteplath.
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Attachment:
j Technical Specifications Changes l
Date of Issuance:
September 18, 1990 i
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UNITED STATES
.I NUCLEAR REGULATORY COMMISS ON e
- k' WASHINGTON,0. C. 20666 49 *.. *,o GEORGIAPOWERCOMPAN1 OGLETHORPE POWER CORP 0AATION J
MUNICIPAL ELECTRIC AUTHORIiY OF GEORGIA CITY OF DALTON. GE0k Q V0GTLE ELECTRIC GENERATING PLANT. UNIT 2 l
AMENDMENT TO FACILITY OPERATING LICENSE L
Amendsent No.
15 License No. NPF-81 1.
The Nuclear Regulatory Commission (the Coenission) h4s found that:
f A.
The application for asendsent 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 March 1, 1990, complies with the standards and requiresents of the Atomic Energy Act of 1954, as asended (the Act), and the Cosnission's rules and regulations 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 Commission' i
C.
Thereisreasonebleassurance(i)thattheactivitiesauthorizedby this asendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted l-in compliance with the Connission's regulations set forth in 10 CFR l
Chapter I; D.
The issuance of this license amendment will not be inimical to the L
common defense and security or to the health and safety of the l
public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Connission's regulations and all applicable requirements have been satisfied..
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2 2.
Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachsent tn 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 Appt.ndix A, as revised through Amendment No.15, and the Environmental Protection Plan contained in Appendix D, both of which are attached hereto, are hcreby 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 of issuance.
FOR THE NUCLEAR REGULATORY COMISSION 4
David B. Matthews, Director Project Directorate II.3 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation Attachsent:
Technical Specification Changes Date of 'ssuance:
September 18, 1990 e
ATTACHMENT TO LICENSE AMENDMENT NO. 35 FACILITY OPERATING LICENSE NO. NPF-68 1
i AND LICENSE AMENDMENT NO. 15 FACILITY OPERATING LICENSE NO. NPF-81 DOCKET NOS: 50-424 AND 50-425 Replace the followir page of the '.gpendix "A" Technical Specifications with the enclosed page, he revised page is identified by Amendment number and contains a vertical line indicating the area of change. The corresponding overleaf page is also provided to maintain document completeness.
Amended Pace Overleaf Page 6-15 6-16 I
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ADMINISTRATIVE CONTROLS
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PROCEDURES AND % 0GRAA5 (Continued) c.
The change is documented, reviewed in accordanca with Specification 6.7.2 and approved by.the General Manager-Nuclear Plant or department head of the responsible department within 14 days of implementation.
6.7.4 The following programs shall be 6stablished, implemented, and maintained:
l a.
Primary Coolant Sources Outside Containment A progra.a to reduce leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to as low as practical levels.
The systems include the following:
1)
Residual Heat Removal System t
Containment Spray (System (excluding NaOH Subsystem) 2)
SafetyInjection excluding Boron In 3)
Chemical and Volume Control System (jection & Accumulators) Letdow l
4) 5)
Post Accident Processing System 6)
Gaseous Waste Processing (System 7)
Nuclear Sampling System Pretsurizer steam and liquid sample lines, Reactor Coolant sample lines, RHR sample lines, CVCS Dominera11rer and letdown Heat Exchanger sample lines only)
The program shall include the following:
1)
Preventive maintenance and periodic visual inspection requirements, and 2)
Leak test requirements for each system at refueling l
cycle intervals or less.
b.
In-Plant Radiation Monitorina A program which will ensure the capa'ility to accurately detemine o
the airborne iodine concentration in vital areas under accident conditions. This program shall include the following:
1)
Training of personnel, L
2)
Procedures for monitoring, and 3)
Provisions for maintenance of sampling and analysis equipment.
I c.
Secondary Water Chemistry A program for monitoring of secondary water chemistry to inhibit steam generator tube degradation.
This program shall include:
V0GTLE UNITS - 1 & 2 6-15 Amendment No. 35 (Unit 1)
Amendment No.15 (Unit 2)
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i ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) j 4
1)
Identification of a sampling schedule for the critical variables j
and control points for these variables, i
2)
Identification of the procedures used to measure the values of the critical variables, 3)
Identification of process sampling points, 4)
Procedures for the recording and management of data, 5)
Procedures defining corrective actions for all off-control point chemistry conditions, and 6)
A procedure identifying:
(a) the authority responsible for the interpretation of the data, and (b) the sequence and timing of administrative events required to initiate corrective action, l
d.
Post-Accident Sampling 7
A program which will ensure the capability to obtain and analyze reactor coolant, radioactive iodines and particulates in plant t
gaseous effluents, and containment atmosphere samples under accident L
conditions.
The program shall include the following:
1)
Training cf personnel, 2)
Procedures for sampling and analysis, and 3)
Provisions for maintenance c' sampling and analysis equipment.
l e.
A program which will ensure the capability to monitor plant variables and systems operating status during and following an accident.
This program shall include those instruments provided to indicate system operating st-cus and furnish information regardir.g the release of radioactive materials (Category 2 and 3 instrumentation as defined in Regulatory Guide 1.97 Revision 2) snd provide the following:
1) preventive maintenance and periodic surveillance of irstrumentation.
l 2) pre planned operating procedures and back-up instrumentation to be used if one or more monitoring instruments become inoperable.
3) administrative procedures for returning inoperable instruments to OPERABLE status as soon as practicable.
V0GTLE UNITS - 1 & 2 6-16
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