ML20141M510

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Amends 54 & 33 to Licenses NPF-68 & NPF-81,respectively, Revising TS & Surveillance Interval for Periodic Assembly & Insp of Steam Admission Valves Associated W/Turbine Overspeed Protection Sys
ML20141M510
Person / Time
Site: Vogtle  Southern Nuclear icon.png
Issue date: 08/20/1992
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
ML20141M511 List:
References
NPF-68-A-054, NPF-81-A-033 NUDOCS 9208310368
Download: ML20141M510 (6)


Text

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UNITED STATES g

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GE9RGIA POWER COMPA4y 0GLETHORPE POWER CORPORATION L1UNICIPAL ELECTRIC AUTHORITY OF GEORG_lA CITY OF DALTON. GEORGIA 10GTLE ELECTRIC GENERATING PLANT. UNIT 1 AMENDMENT TO FAClllTY OPERATING LICENSE

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Amendment No. 54 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 Compa iy, acting for itself, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia (the licensees), dated April 28, 1992, as supplemented July 20, 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 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.

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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 l

is hereby amended to read as follows:

Technical Specifications and Environmental Pro'tection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 54

, 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.

FOR THE NUCLEAR REGULATORY COMMISSION s

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f David B. Ma' thews, Director Project Directorate 11-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Technical Specification Changes Date of Issuance: August 20, 1992

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o WASHINGTON, D.C 20066 GEORGIA POWER COMPANY QGL Q iORPE POWER CORPORATION MUNKlfel ELECTRIC AUTHORITY _QF GEORGIA

, CITY OF DALTON. GEORGIA V0GTLE ELECTRIC G MTO TING PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 33 License No. NPF-81 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for ame. ament 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 At.thority of Georgia, and City of Dalton, Georgia (the licensees), dated April 28, 1992, as supplemented July 20, 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 as set forth in 10 frR 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.

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4 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. 33, 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.

FOR THE NVCLEAR REGULATORY COMMISSION d

David B. Matthews, Director Project Directorate 11-3 Division of Reactor Projects - 1/II Office of Nuclear Reactor Regulation

Attachment:

Technical Specification Changes Date of lssuance: August' 20, 1992 l-

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c ATTACHMENT TO LICENSE AMENDMENT NO. 54 FACILITY'0PERATING LICENSE NO-NPF-68 1

DOCKET NO. 50-424 MD

. T0 LICENSE AMENDMENT NO. 33 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 identiflei_by Amendment number and contains _ vertical lines indicating the areas of change.

Remove Pace Insert Pace 3/4 3-81 3/4 3-81 4

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INSTRUMENTATION

- 3/4.3.4 TURBINE OVERSPEED PROTECTION LIMITING CONDITION FOR OPERATION 3.3.4 At least one Turbine 7verspeed Protection System shall be OPERABLE.

APPLICABILITY:

MODES ], 2*, and 3*.

ACTION:

a.

With one stop valve or one control vaive per high pressure turbine steam line inoperable and/or with one reheat stop valve or one reheat intercept valve per low pressure turbine steam line inoperable, restore the inoperable valve (s) to OPERABLE status within 72 hou s, or c1r a at least one valve in the affected steam lines, or isolate the. turbine from the steam supply within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, b..

-With the above r quired Turbine Overspeed Protection System otnerwise inoperable, within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> isolate the turbine from the steam supply.

SURVEILLANCE REQUIREMENTS 4.3.4.1 The provisions of Specification 4.0.4 are not applicable.

4.3.4.2 TheLabove required Turbine Overspeed Protection System shall be demonstrated OPERABLE:

a.

At least once per 7 days while in MODE-1 and while in MODE 2 with the

. turbine operating, by cycling each-of the following valves through at least one complete cycle from the running position:

1)

Four'high pressure turbine stop valves, 2)

Six low pressure turbine intermediate stop valves, and 3)

Six low pressure turbine intercept valves.

b.

At:least once per 31 days while-in MODE 1 and while in MODE 2 with-the turbine operating, by direct observation of the movement of each of the above valves and the four high pressure turbine control valves, through one complete cycle from the running position,

c. -At least once per 18 months by performance of a CHANNEL CALIBRATION on the Turbine Overspeed Protection Systems, and
d. -At least once per 60 months'by disassembling each of the above valves l

-(including the four high pressure turbine control valves) and perfo ming a visual and surface inspection of valve seats, disks and stems and verifying no unacceptable flaws or corrosion.

  • Not applicable in MODE 2 or 3 with all main steam line isolation valves and associated bypass valves in the closed position and all other steam flow paths to the turbine isolated.

V0GTLE UNITS -'l & 2 2/4 3-81 Amendment No. 54 (Unit 1)

Amendment No. 33 (Unit 2)

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