ML20076E444
| ML20076E444 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 08/09/1991 |
| 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 | |
| ML20076E449 | List: |
| References | |
| NPF-68-A-040, NPF-81-A-020 NUDOCS 9108200127 | |
| Download: ML20076E444 (7) | |
Text
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J'T UNITED STATES 5'3d E
NUCLEAR REGULATORY COMMISSION
,8 WASHINGTON, D C. 20%6 o%* N,[
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 Amendment No. 40 License No. NPF-68 1.
The Nuclear Regulatory Commission (the Commission) has found that:
The app (lication for amendment to the Vogtle Electric Generating Plant, A.
Unit 1 the facility) Facility Operating License No. NPF-68 filed by the Georgia Power Company, acting for itself, Oglethorpe Power Corpo-ration, Municipal Electric Authority of Georgia, and City of Dalton, Georgia (the licensees) dated January 25, 1991, 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 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; I
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.
9108200127 910009 DR ADOCK 0500 4
2-l 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. 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 Ydv LS
/,SavidB.Matthews, Director
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Project Directorate 11-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance:
August 9,1991 i
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UhllTED STATES jf. Q ci NdCLEAR REGULATORY COMMISSION y
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-g0RGIAPOWERCOMPANY OGLETHORPE POWER-CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA t
DOCKET NO.-50-425 V0GTLE ELECTRIC GENERATING PLANT, UNIT 2 AMENDMENT TO {ACILITY OPERATING LICENSE Amendment No. 20 License No. NPF-81 1.
The Nuclear Regulatory Commission (the Commission) has found that:
.The app (lication for amendment to the Vogtle Electric Generating Plant, A.
Unit 2 the facility) Facility Operating License No. NPF-81 filed by
'the_ Georgia Power Company, acting for itself Oglethorpe Power Corpo-ration, Municipal Electric Authority of Georgia, and City of Dalton, Georgia (the licensees) dated-January 25, 1991, 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 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.
, 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 ant; Environmental Prot'ection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 20, 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
[
/7) M fd 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
- 9. 1991 i
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ATTACHMENT T,0 LICENSE AMENDMENT NO. 40 FACILITY.0PERATING LICENSE NO. HPF-6_8 AND LICENSE AMENDMENT NO. 20 FACILITY OPERATING LICENSE NO. NPF-81 DOCKET NOS. 50-424 AND 50-425 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page. The revised page is identified by Amendment number and contains vertical lines indicating the areas of change. The corresponding overleaf page is also provided to maintain document completeness.
Remove Page Insert Page 6-7 6-7 6-8*
6-8*
- overleaf page 1
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f, ADMINISTRATIVE CONTROLS 6.3 TRAINING 6.3.1 A retraining and replacement training program for the plant staff shall be maintained under the direction of the Plant Training and Emergency Prepared-ness Manager.
Personnel will meet the minimum education and experience recom-mendations of Regulatory Guide 1.8, Revision 2 arid, for licensed staf f, 10 CFR 55.59 before they are considered qualified to perform all duties inde-pendently.
Prior to meeting the recommendations of Regulatory Guide 1.8, Revi-sion 2, personnel may be trained to perform specific tasks and will be qualified to perform those tasks independently.
Personnel who complete an accreaited program which has been endorsed by the NRC shall meet the requirements of the accredited program in lieu of the above.
6.4 REVIEW AND AUDIT 6.4.1 PLANT REVIEW BOARD (PRB)
FUNCTION 6.4.1.1 The PRB shall function to advise the General Manager-Nuclear Plant on all matters related to nuclear safety.
COMPOSITION G. 4.1. 2 The PRB shall be composed of Department Superintendents or Managers, or supervisory personnel reporting directly to Department Superintendents or Managers from the departments listed below:
Operations Maintenance I
Health Physics Engineering Support I
Technical Support l
A senior health physicist is acceptable for the Health Physics Department PRB representative.
The chairman, his alternate and other members and their alternates of the PRB shall be designated by the General Manager-Nuclear Plant.
ALTERNATES 6.4.1.3 No more than two alternates shall participate as voting members in PRB activities at any one time.
MEETING FREQUENCY 6.4.1.4 The PRB shall meet at least once per calendar month and as convened by the PRB Chairman or his designated alternate, i
l V0GTLE UNITS - 1 & 2 6-7 Amendment No.40 (Unit 1)
Amendment No.20 (Unit 2)
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-ADMINISTRATIVE CONTROLS RESPONSIBILITIES (Continued)
-QUORUM 6.4.1.5 The quorum of the PRB necessary for the performance of the PRB responsibility and authority provisions of these Technical _ Specifications shall consist of the Chairman or his designated alternate and four members including alternates.
RESPONSIBILITIES 6.4.1.6 The PRB shall be responsible for:
a.
Review of 1) procedures which establish plant-wide administrative controls to implement-the QA program or Technical Specifications surveillance program, 2) procedures for changing plant operating-modes.-3) emergency and abnormal operating procedures, 4) procedures for effluent releases of radiological consequences, and 5) fuel handling procedures, b.
Review of 1) programs required by Specification 6.7.4 and changes thereto, and 2) proposed procedures and changes to procedures which involve an unreviewed safety question as per 10 CFR 50.59.
c.
Review of all proposed tests and experiments that affect nuclear safety; d.
Review of all proposed changes to the Technical Specifications; e.
Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety, including proposed changes to Chapter 16.3 of the Vogtle Final Safety Analysis Report (FSAR);
f.
Investigation of all violations of the Technical Specifications, including the preparation and forwarding of reports covering evalua-tion and recommendations--to prevent recurrence, to the Vice President-Nuclear and to=the Safety Review Board; g.
Review of all REPORTABLE EVENTS; h.
Review of plant operations to detect potential hazards to nuclear safety; i,
Performance of special reviews, investigations, or analyses and reports thereon as requested by the General Manager-Nuclear Plant or the Safety Review Board; J.
Review of the Security Plan and implementing procedures and submittal of recommended-changes to the General Manager-Nuclear' Plant and the Safety Review Board; V0GTLE UNITS - 1 & 2 6-8
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