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Amend 2 to License NPF-68,modifying Tech Specs to Delete Refs to Phase a Containment Isolation on Containment Area high-range Radiation Signal & to Correct Refs Which Are No Longer Applicable
	ML20236D925
Person / Time
Site:	Vogtle
Issue date:	07/24/1987
From:	Youngblood B; Office of Nuclear Reactor Regulation
To:	; City of Dalton, GA, Georgia Power Co, Municipal Electric Authority of Georgia, Oglethorpe Power Corp
Shared Package
ML20236D928	List: ML20236D925; ML20236D944;
References
	NPF-68-A-002 NUDOCS 8707310132
	Download: ML20236D925 (16)
	v • d • e

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UNITED STATES NUCLEAR REGULATORY COMMISSION o

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GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA DOCKET NO. 50-424 l

l V0GTLE ELECTRIC GENERATING PLANT, UNIT 1 I

l AMENDMENT TO FACILITY OPERATING LICENSE l

Amendment No. 2 License No. NPF-68

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The Nuclear Regulatory Comission (the Comission) has found thet:

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, (thelicensees)datedJuly 22, 1987, complies with the standards and

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requirements of the Atomic Energy Act of 1954, as amended (the Act) l anc the Comission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Comission; C.

There is reasonable assurance: (1) that the activities authorized by this amendment can be conducted without endangering the health and i

safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations set forth in 10 CFR Chapter I; D.

The issuance of this license amendment will not be inimical to the comon 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 attachments to this license amendment and Paragraph 2.C.(2) of Facility Operating License No. NPF-68 is hereby amended to read as follows:

87073i0132 070724

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I (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised j

through Amendment No. 2, 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 July 23, 1987.

FOR THE NUCLEAR REGULATORY COMMISSION B. J. Youngblood. Director Project Directorate II-3 Division of Reactor Projects

Attachment:

Technical Specification Changes l

Date of Issuance:

July 24, 1987 l

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(2) Technical Specif[ications and Environmental ProtS' ction Plan 4

The Technisel Specifications contained in Appendix A as revised through AverOent No. 2

, and the.2 Environmental Protection Plan 3

contained 1n Appendix 3, both of which are' attached hereto, are hereby incorporated into this license. GPC shall operate the facility in accordaned with'the Technical Specifications and the Environraental Protection Plan.

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This license amendment.is effective as of Vuly ?3,1987.

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r ATTACHMENT TO LICENSE AMENDMENT NO. 2

. i FACILITY OPERATING LICENSE NO. NPF-68 l

t DOCKET NO. 50-424 s

Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change. The corresponding overleaf pages are also provided to maintain document completeness.

Amended Overleaf Page Page 3/4 3-18 3/4 3-17 3/4 3-27 3/4 3-28 3/4 3-29 3/4 3-30 3/4 3-38 3/4 3-37 3/4 3-46 3/4 3-45

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ACTION STATEMENTS (Continued) j ACTION 24 - With the number of OPERABLE channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE j

status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or declare the associated valve inoperable and take.the ACTION required by Specification 3.7.1.5.

ACTION 25 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.2.1 provided the i

other channel is OPERABLE.

ACTION 26 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 7 days or within the next 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months s:

(1) For the Control Room Emergency Ventilation, initiate and av maintain operation of the Control Room Emergency Ventila-tion System in the Emergency mode. With two channels inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months initiate and maintain operation of the Control Room Emergency Ventilation System in the Emergency mode.

(2) For the Fuel Handling Building Post-Accident Ventilation System take the ACTION required by Specification 3.9.12.

t ACTION 27 - Not Used.

ACTION 28 - Not Used.

I V0GTLE - UNIT 1 3/4 3-27 Amendment No. 2

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INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION RADIATION MONITORING FOR PLANT OPERATIONS LIMITING CONDITION FOR OPERATION 3.3.3.1 The radiation monitoring instrumentation channels for plant operations shown in Table 3.3-4 shall be OPERABLE with their Alarm / Trip Setpoints within l

the specified limits.

APPLICABILITY:

As shown in Table 3.3-4.

ACTION:

With a radiation monitoring channel Alarm / Trip Setpoint for plant a.

operations exceeding the value shown in Table 3.3-4, adjust the Setpoint to within the limit within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or declare the channel inopeiable.

~

b.

With one or more radiation monitoring channels for plant operations inoperable, 'ake the ACTION shown in Table 3.3-4.

J' c.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

- 17. j d2 o

l l

SURVEILLANCE REQUIREMENTS 4.3.3.1 Each radiation monitoring instrumentation channel for plant operations shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and ANALOG CHANNEL OPERATIONAL TEST for the MODES and at the l

frequencies shown in Table 4.3-3.

l l

l V0GTLE - UNIT 1 3/4 3-45 1

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TABLE 3.'3-4 (Continued) 1 TABLE NOTATIONS a During movement of irradiated fuel or movement of loads over irradiated fuel within containment.

b During movement of irradiated fuel.or movement of loads over irradiated fuel.

RE-2565 is ennsidered OPERABLE if the' Particulate (RE-2565A) and Iodine c

(RE-25658) Monitors are OPERABLE, or the noble gas monitor (RE-2565C) is OPERABLE.

ACTION STATEMENTS ACTION 29 -

With the number of OPERABLE Channels less than the Minimum 1

Channels OPERABLE requirement, satisfy the ACTION requirements 4

of Specification 3.4.6.1.

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