ML20035C630
| ML20035C630 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 03/31/1993 |
| 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 | |
| ML20035C631 | List: |
| References | |
| NPF-68-A-061, NPF-81-A-040 NUDOCS 9304080217 | |
| Download: ML20035C630 (9) | |
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UNITED STATES j
NUCLEAR REGULATORY COMMISSION WASHINGTON. D C. 20555 0001 gv /
GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON. GEORGIA DOCKET NO. 50-424 V0GTLE ELECTRIC GENERATING PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE i
Amendment No. 61 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 7, 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 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 1
forth in 10 CFR Chapter I; D.
The issuance of this license 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.
9304000217 930331 PDR ADDCK 05000424 P
i 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. 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 be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION David B. Matthews, Director Project Directorate 11-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance:
March 31, 1993 i
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' UNITED STATES
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' NUCLEAR REGULATORY COMMISSION
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WASWNGTON D C. 20555 0001 ga j
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i GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA i
CITY OF DALTON. GEORGIA DOCKET NO. 50-425 V0GTLE ELECTRIC GENERATING PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE 1
Amendment No. 40 i
License No. NPF-81 1
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Vogtle Electric Generating I
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 ( % licensees), dated 1
December 7, 1992, complies with the st,odards:and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the L
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 i
Commission; j
q C.
There is reasonable assurance (i) that the activities suthorized.
by this amendment can be conducted without endangering the health-t and safety of the' public, and (ii) that such activities will be
'e conducted in compliance with the Commission's regulations set -
I forth in 10 CFR Chapter I; D.
The issuance of this license amendment will not be inimical-to the common defense and security or to the health and safety of the public; and 1
1 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-8I is hereby amended to read as follows:
Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.
40, 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 of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION s
David B. Matthews, Director Project Directorate II-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance:
March 31, 1993 t
l ATTACHMENT TO LICENSE AMENDMENT NO.61 FACILITY OPERATING LICENSE NO. NPF-68 AND LICENSE AMENDMENT N0.40 FACILITY OPERATINC LICENSE NO. NPF-81 DOCKETS NOS. 50-424 AND 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 XXIII XXIII l-4 1-4 6-19 6-19 6-25 6-25 t
1 t
INDEX j
ADMINISTRATIVE CONTROLS SECTION 6.4.2 SAFETY REVIEW BOARD (SRB)
Function..................................................
6-9 Composition...............................................
6-10 Alternates................................................
6-10 Consultants...............................................
6-10 Meeting Frequency.........................................
6-10 l
Quorum....................................................
6-10 Review....................................................
6 Audits....................................................
6-11 Records..................................................
6 6.5 REPORTABLE EVENT ACTI0N.................................
6-13 P
6.6 SAFETY LIMIT VIOLATION......................................
6-13
. 6.7 PROCEDURES AND PR0 GRAMS.....................................
6-13 t
i 6.8 REPORTING RE0VIREMENTS r
5 6.8,1 ROUTINE REP 0RTS...........................................
6-17 Startup Report............................................
6-17 l
Annual Reports............................................
6-17 Annual Radiological Environmental Surveillance Report.....
6-18 Annual Radioactive Effluent Release Report................
6-19 l
i Monthly Operating Reports.................................
6-21 j
Core Operating Limits Report.............................
6-21 i
6.8.2 SPECIAL REP 0RTS...........................................
6-21a-6.9 RECORD RETENTION.............................................
6-22 V0GTLE UNITS - 1 & 2 XXIII Amendment No. 61 (Unit 1)-
Amendment No. 40 (Unit 2) w
DEFINITIONS t
MEMBER (S) 0F THE PUBLIC 1.18 MEMBER (S) 0F THE PUBLIC shall include all persons who are not occupa-tionally associated with the plant. This category does not include employees of the licensee *, its contractors, or vendors. Also excluded from this category are persons who enter the site to service equipment or.to make deliveries. This category does include persons who use portions of the site for recreational, occupational, or other purposes not associated with the plant.
OFFSITE DOSE CALCULATION FANUAL 1.19 The OFFSITE DOSE CALCULATION MANUAL (0DCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioac-tive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm / Trip Setpoints, and in the conduct of the Environ-mental Radiological Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Pro-grams required by Section 6.7.4 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Surveillance and Annual Radioactive Effluent Release Reports required by Specifications 6.8.1.3 l
and 6.8.1.4.
OPERABLE - OPERABILITY 1.20 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s),
and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its function (s) are also capable of performing their related support function (s).
OPERATIONAL MODE - MODE l.21 An OPERATIONAL MODE (i.e., MODE) shall correspond to any one inclusive combination of core reactivity condition, power level, and average reactor coolant temperature specified in Table 1.2.
PHYSICS TESTS 1.22 PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation:
(1) described in Chapter 14.0 of the FSAR, (2) authorized under the provisions of 10 CFR 50.59, or (3) otherwise approved by the Commission.
PRESSURE B0UNDARY LEAKAGE 1.23 PRESSURE BOUNDARY LEAKAGE shall be leakage (except steam generator tube leakage) through a nonisolable fault in a Reactor Coolant System component body, pipe wall, or vessel wall.
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1.24 The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, sampling, analyses, tests, and determinrtions to be made to ensure that i
processing and packaging of solid radioa;.ive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in cuch V0GTLE UNITS - 1 & 2 1-4 Amendment No. 61 (Unit 1)
Amendment No. 40 -
(Unit 2)
ADMINISTRATIVE CONTROLS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT ****
l 6.8.1.4 The Annual Radioactive Effluent Release Report covering the operation of the unit during the previous caler.dar year shall be submitted before May 1 of each year. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be (1) consistent with the objectives outlined in the ODCM and PCP and (2) in conformance with 10 CFR 50.36a and Section IV.B.1 of Appendix I to 10 CFR Part 50.
i l
l i
ngle submittal may be made for Units 1 and 2.
The submittal should j
.,+u.ne those sections that are common to both units at.the plant; i
however, the submittal shall specify the releases of gaseous and liquid i
radioactive niaterial from each unit and of solid radioactive material i
from the site.
l i
V0GTLE UNITS - 1 & 2 6-19 Amendment No. 61 (Unit 1)
Amendment No. 40 (Unit 2)
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ADMINISTRATIVE CONTROLS 6.12 PROCESS CONTROL PROGRAM (PCP) (Continued) b.
Shall become effective after review and acceptance by the PRB and the approval of the General Manager-Nuclear Plant.
6.13 0FFSITE DOSE CALCULATION MANUAL (0DCM) 6.13.1 The ODCM shall be approved by the Commission prior to implementation.
6.13.2 Licensee-initiated changes to the ODCH:
a.
Shall be documented and records of reviews performed shall be retained as required by Specification 6.9.30.
This documentation shall contain:
1)
Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s) and 2)
A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.
j b.
Shall become effective after review and acceptance by the PRB and the approval of the General Manager-Nuclear Plant.
i c.
Shall be submitted to the Commission in the form of a complete.
l legible copy of the entire ODCM as a part of or concurrent with the
-r Annual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made.
Each change shall be identified by markings in the margin of the affected pages, i
clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month / year) the change was implemented.
6.14 MAJOR CHANGES TO L10VID. GASE0US. AND SOLIO RADWASTE TREATMENT SYSTEMS Not used.
-1 V0GTLE UNITS - 1 & 2 6-25 Amendment No. 61 (Unit 1).
Amendment No. 40 (Unit 2) l