ML20036C206
| ML20036C206 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 06/07/1993 |
| 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 | |
| ML20036C207 | List: |
| References | |
| NPF-68-A-064, NPF-81-A-043 NUDOCS 9306150246 | |
| Download: ML20036C206 (7) | |
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eDm%q UNITED STATES
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j MUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. 20S55-0001
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GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION tLUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON. GEORGIA V0GTLE ELECTRIC GENERATING PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 64 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 22, 1992, cor. plies 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.
9306150246 930607 PDR ADDCK 05000424 P-PDR
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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. 64, 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 M
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:
June 7, 1993
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4 UNITED STATES
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j NUCLEAR REGULATORY COMMISSION j
WASHINGTON, D.C. 205EiH001 s
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GEORGIA POWER COMPANY
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OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA l
CITY OF DALTON. GEORGIA V0GTLE ELECTRIC GENERATING PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 43.
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 i
filed by the Georgia Power Company, acting for itself,'0glethorpe t
Power Corporation, Municipal Electric. Authority of Georgia, and City of Dalton, Georgia (the licensees), dated December 22, 1992, complies with the standards and requirements of the Atomic Energy
+
Act of 1954, as amended (the Act), and the Commission'sLrules 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
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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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i O 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. 43, 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 II-3 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance: June 7, 1993
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ATTACHMENT TO LICENSE AMENDMENT NO. 64 FACILITY OPERATING LICENSE NO. NPF-68 DOCKET NO. 50-424 AND TO LICENSE AMENDMENT No. 43 FACILITY OPERATING LICENSE NO. NPF-81 DOCKET NO. 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 a vertical line indicating the area of change.
Remove Pace Insert Pace 6-6 6-6 6-5*
6-5*
- overleaf page, no change
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3 ADMINISTRATIVE CONTROLS 6.2.3 INDEPENDENT SAFELY ENGINEERING GROUP (ISEG1 FUNCTION 6.2.3.1 The ISEG shall function to examine plant operating characteristics, NRC issuances, industry advisories, Licensee Event Reports, and other sources of plant design and operating experience information, which may indicate areas for improving plant safety.
The ISEG shall make detailed recommendations for revised procedures, equipment modifications, maintenance activities, operations activities, or other means of improving plant safety to the Vice President-Nuclear.
COMPOSITION 6.2.3.2 The ISEG shall be composed of at least five, dedicated, full-time positions.
Each shall have either:
(1) A bachelor's degree in engineering or related science and at least 2 years professional level experience in his field, at least 1 year of which experience shall be in the nuclear field, or (2)
At least 5 years of nuclear experience and hold or have held a Senior Reactor Operator's license, or (3) At least 10 years of professional level experience in his field, at least 5 years of which experience shall be in the nuclear field.
At least three of these positions shall meet (1).
RESPONSIBILITIES 6.2.3.3 The ISEG shall be responsible for maintaining surveillance of plant activities to provide independent verification
- that these activities are performed correctly and that human errors are reduced as much as practical.
RECORDS 6.2.3.4 Records of activities performed by the ISEG shall be prepared, main-tained, and forwarded each calendar month to the Vice President - Nuclear.
6.2.4 SHIFT TECHNICAL ADVISOR 6.2.4.1 The Shift Technical Advisor shall provide advisory technical support to the Shift Supervisor in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the plant.
The Shift Technical Advisor shall have a bachelor's degree or equivalent in a scientific or engineering discipline and shall have received specific training in the response and analysis of the plant for transients and accidents, and in plant design and layout, including the capabilities of instrumentation and controls in the control room.
- Not responsible for sign-off function.
V0GTLE UNITS - 1 & 2 6-6 Amendment No. 64 (Unit 1)
Amendment No. 43 (Unit 2)
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TABLE 6.2-1 MINIMUM SHIFT CREW COMPOSITION TWO UNITS WITH A COPMON CONTROL ROOM
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POSITION NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION f
BOTH UNITS IN BOTH UNITS IN ONE UNIT IN MODE 1, 2, MODE 1, 2, 3, MODE 5 or 6 3, or 4 AND ONE UNIT IN or 4 OR DEFUELED MODE 5 or 6 or DEFUELED OS 1
1 1
SRO 1
none**
1 RO 3*
2*
3*
NLO 3*
3*
3*
STA 1***
none 1***
i OS - Operations Supervisor with a Senior Operator license SRO - Individual with a Senior Operator license RO - Individual with an Operator license NLO - Non-Licensed Operator STA - Shift Technical Advisor l
The shift crew composition may be one less than the minimum requirements of.
Table 6.2-1 for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements of Table 6.2-1.
This provision does not permit any shift crew position to be unmanned upon shift change due to an oncoming shift crewman being late or absent.
During any absence of the Operations Supervisor from the control room while either unit is in MODE 1, 2, 3, or 4, an individual with a valid Senior Operator license shall be ded gnated to assume the control room command function.
During any absem e of the Operations Supervisor from the control room while either unit is in MODE 5 or 6, an individual with a valid Senior Operator license or Operator license shall be designated-to assume the control room command function.
- At least one of the required individuals must be assigned to the designated
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position for each unit.
- At least one licensed Senior Operator or Licensed Senior Operator Limited' to fuel Handling who has no other concurrent responsibilities must be present during CORE ALTERATIONS on either unit.
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- The STA position shall be manned in MODES 1, 2, 3, and 4 unless the 1
Operations Supervisor or the individual with a Senior Operator license meets the qualifications for the STA as stated in the Policy Statement on Engineering Expertise on Shift, dated October 28, 1985.
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