ML20236S244

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Amends 103 & 81 to Licenses NPF-68 & NPF-81,respectively, Revising TS 5.5.7, Reactor Coolant Pump Flywheel Insp Program, to Provide Exception to Exam Requirements of Regulatory Position C.4.b of RG 1.14,rev 1
ML20236S244
Person / Time
Site: Vogtle  Southern Nuclear icon.png
Issue date: 07/21/1998
From: Berkow H
Office of Nuclear Reactor Regulation
To:
Southern Nuclear Operating Co, Georgia Power Co, Oglethorpe Power Corp, Municipal Electric Authority of Georgia, City of Dalton, GA
Shared Package
ML20236S246 List:
References
NPF-68-A-103, NPF-81-A-081, RTR-REGGD-01.014, RTR-REGGD-1.014 NUDOCS 9807240222
Download: ML20236S244 (8)


Text

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MLI8 y

1 UNITED STATES s

P; NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 30eeH001 I

SOUTHERN NUCLEAR OPERATING COMPANY. INC.

GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORG_IA CITY OF DALTON. GEORGIA I

VOGTLE ELECTRIC GENERATING PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE l

Amendment No. 103 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 Southem Nuclear Operating Company, Inc. (Southem Nuclear), acting for itself, Georgia Power Company, Ogletherpe Power Coporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia Ghe licensees), dated May 8,1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's mies 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 tne 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 appicable requirements have been satisfied.

1 9807240222 900721 Y

PDR ADDCK 05000424 P

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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 licen!e 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.103, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. Southern Nuclear 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 from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION 0()

l hI' e

rt N. Berkow, Director roject Directorate ll-2 Division of Reactor Projects - (Il Office of Nuclear Reactor Regulation

Attachment:

Technical Specification Changes Date ofissuance:

July 21,1998 t

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y UNITED STATES u

j NUCLEAR REGUI.ATORY COMMISSION WASHINGTON, D.C. 3000H001 s,/

SOUTHERN NUCLEAR OPERATING COMPANY. INC.

GEORGIA POWER COMPANY t

l OGLETHORPE POWER CORPORATION i

MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA i

CITY OF DALTON. GEORGIA l

VOGTLE ELECTRIC GENERATING PLANT. UNIT 2 l

AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 81 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 filed by the Southern Nuclear Operating Company, Inc. (Southern Nuclear), acting for irself, Georgia Power Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia (the licensees), dated May 8,1998, 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 i

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 er 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.

I i

l

e-1 l

. 1 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-81 is hereby amended to read as follows:

1 Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.

81, and the Environmental Protection Plan containec n Appendix B, both of which are attached hereto, are hereby incorporated into this license. Southern Nuclear shall operate the facility in accordance with the l

Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of its date of issuance and shall be implemented l

within 30 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION i

\\

He rt N. Berkow, Director l

Project Directorate Il-2 Division of Reactor Projects - 1/ll Office of Nuclear Reactor Regulation l

Attachment:

I Technical Specification l

Changes l

Date of issuance: July 21,1998

l ATTACHMENT TO LICENSE AMENDMENT NO. 103 FACILITY OPERATING LICENSE NO. NPF-68 DOCKET NO. 50-424 i

AND TO LICENSE AMENDMENT NO. 81 FACILITY OPERATING LICENSE NO. NPF-81 DOCKET NO. 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 verticallines indicating the areas of change.

Remove Insert 5.0-12 5.0-12 5.0-12a*

5.0-12b

  • overflow - no change

i Prograns and Manuals 5.5 i

5.5 Programs and Manuals (continued) 5.5.6 Prestressed Concrete Containment Tendon Surveillance Prooram This program provides controls for monitoring any tendon i

degradation in prestressed concrete containments, including effectiveness of its corrosion protection medium, to ensure containment structural integrity. The program shall include baseline measurements prior to initial operations. The Tendon Surveillance Program, inspection frequencies, and acceptance criteria shall be in accordance with Regulatory Guide 1.35, Revision 2, 1976.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Tendon Surveillance Program inspection frequencies.

5.5.7 Reactor Coolant Pumo Flywheel Insoection Proaram This program shall provide for the inspection of each reactor coolant pump flywheel at least once per 10 years by conducting either:

a.

An in-place ultrasonic examination over the volume from the inner bore of the flywheel to the circle of one-half the outer radius; or b.

A surface examination (magnetic particle and/or liquid penetrant) of exposed surfaces of the disassembled flywheel.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Reactor Coolant Pump Flywheel Inspection Program.

5.5.8 Inservice Testina Proaram l

This program provides controls for inservice testing of ASME Code Class 1, 2, and 3 components. The program shall include the following:

a.

Testing frequencies specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as follows:

(continued) l Vogtle Units 1 and 2 5.0-12 Amendment No.103 (Unit 1)

Amendment No. 81 (Unit 2)

Programs and Manuals 505 i

1 5.5 Programs and Manuals (con'tinued)

ASME Boiler and Pressure Vessel Code and applicable Required Frequencies for Adaenda terminology for performing inservice inservice testina activities testina activities Weekly At least once per 7 days Monthly At least once per 31 days Quarterly or every 3 months At least once per 92 days Semiannually or every At least once per 184 days 6 months Every 9 months At least once per 276 days Yearly or annually At least once per 366 days Biennially or every 2 years At least once per 731 days (continued)

Vogtle Units 1 and 2 5.0-12a Amendment No.103 (Unit 1) l Amendment No. 81 (Unit 2) l

Prograns and Manuals 4

s.s 5.5 Programs and Manuals i

)

I l

i j

(THIS PAGE INTENTIONALLY LEFT BLANK) 4 l

(continued)

Vogtle Units 1 and 2 5.0-12b Amendment No.103 (Unit 1) l Amendment No. 81 (Unit 2)

L.