ML20069H100

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Amends 73 & 52 to Licenses NPF-68 & NPF-81,respectively, Revising TS Table 3.3-2,ESFAS Instrumentation & Modifying Mode for Which Functional Unit 6.e, Trip of All Mfp,Start Motor-Driven Pumps, Required to Be Operable
ML20069H100
Person / Time
Site: Vogtle  
Issue date: 06/01/1994
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
ML20069H103 List:
References
NPF-68-A-073, NPF-81-A-052 NUDOCS 9406100314
Download: ML20069H100 (6)


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WASHINGTON, D.C. 20555-0001 GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON. GEORGIA V0GTLE ELECTRIC GENERATING PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE l

Amendment No. 73 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 November 19,~1993, 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 t

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;

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and E.

The issuance of this amendment is in accordance with 10 CFR Part

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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 4

amendment, and paragraph 2.C.(2) of Facility Operating License No.

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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. 73

, 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 i

W David B. Matthews,' Director i

Project Directorate 11-3

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Division of Reactor Projects - I/II l

Office of Nuclear Reactor Regulation

Attachment:

Technical Specification Changes Date of Issuance:

June 1, 1994 l

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S UNITED STATES i.

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NUCLEAR REGULATORY COMMISSION

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wAssinovow, o.c. 20ssm, GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON. GEORGIA V0GTLE ELECTRIC GENERATING PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 52

' 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 Georgia Power Company, acting for itself, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia (the. licensees), dated November 19, 1993, complies with the standards and requirements of the1 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 h'ealth 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 renuirements 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-81 is hereby amended to read as follows:

Technical Specifications and Environmental Protection Plan i

The Technical Specifications contained in Appendix A, as revised through Amendment No. 52

, and the Environmental Protection Plan contained in Anpendix 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 Z

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:

June 1, 1994

o ATTACHMENT TO LICENSE AMENDMENT N0. 73 FACILITY OPERATING LICENSE NO. NPF-68 DOCKET NO 50-424

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bND TO LICENSE AMENDMENT NO. 52 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 vertical lines indicating the areas of change.

Remove Paae Insert Paae 3/4 3-23 3/4 3-23 P

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TABLE 3.3-2 (Continued)

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION E

,3 MINIMUM TOTAL NO.

CHANNELS CHANNELS APPLICABLE FUNCTIONAL-UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION e.

Trip of All Main Feedwater Pumps, Start Motor-Driven Pumps 2

2 2

1, 2**

23 h

f.

Manual Initiation 3

1/ pump 1/ pump 1, 2, 3 23 7.

Semi-Automatic Switchover to Containment Emergency Sump

a.. Automatic Actuation Logic 2

1 2

1, 2, 3, 4 14 and' Actuation Relays

b. 'RWST Level--Low-tow Coincident 4

2 3

1, 2, 3, 4

- 15 with Safety' Injection

  • See Functional Unit 1. above for all Safety Injection initiating R

(LI-0990A&B, L1-0991A&B, functions and requirements.

LI-0992A,LI-0993A)

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8.

Loss of Power.to.4.16 kV ESF Bus

-a.

4.16 kV ESF Bus 4/ bus 2/ bus 3/ bus 1, 2, 3, 4 29 undervoltage-Loss of Voltage b.

4.16 kV ESF Bus Undervoltage-Degraded Voltage 4/ bus 2/ bus 3/ bus 1, 2, 3, 4 29 ea 9.

Engineered-Safety Features gg

' Actuation System Interlocks J0

a... Pressurizer Pressure, P 11 3

2 2

1, 2, 3 21 (PI-0455A,B&C, PI-0456 &

PI-0456A, PI-0457 & PI-0457A)

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- pp-b.

Reactor Trip, P-4 2

1 2

1, 2, 3 23

  • See Specification 3.3.3.6-

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