ML20237G823

Amend 84 to License NPF-5,revising Tech Specs to Delete Section 3.7.8 Re Settlement of Class I Structures

ML20237G823
Person / Time
Site:	Hatch
Issue date:	08/31/1987
From:	Hood D Office of Nuclear Reactor Regulation
To:
Shared Package
ML20237G824	List: ML20237G823 ML20237G833
References
TAC-11158, NUDOCS 8709020426
Download: ML20237G823 (4)

Text

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UNITED STATES l'

NUCLEAR REGULATORY COMMISSION h.

c WASHINGTON D, C. 20555 o

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GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORCIA 1

DOCKET NC. 50-366 i

EDWIN I. HATCH NUCLEAR PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE 4

Amendment No. 84 License No. NPF-5 1.

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

A.

The application for amendment to the Edwin I. Hatch Nuclear Plant, i

Unit 2 (the facility) Facility Operating License No. NPF-5 filed by G9oroia Power Company, acting for itself, Ogletht,rpe Fower Corporation, 1

Municipal Electric Authority of Georgia, and City of Dalton, Georgia, (theliceru

' dated September 27,1c92, as supplemented December 7, 1983, May 4, 49P. December 18,1985, April 4,1986, and January 5, 1987, complies >

h the standards and re Energy Act of 1984, as amended (the Act) quire,nents of the Atomic

, and the Comission's rules and regulations set forth in 10 CFR Chapter I; i

B.

The facility will operate in confonnity with the application, the provisions of the Act, and the rules and regulations of the t

Comission; i

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 l

Chapter I; D.

The issuance of this 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 Comission's regulations and all applicable requirements have been satisfied.

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! 2.

Accordingly, the license is aanded by changes to the Technical Specif1-cations as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-5 is hereby amended to read as follows:

(2)

Technical Specifications-The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 84, are hereby incorporated in the -

license. The licensee shall operate the facility in accordance with the Technical Specifications.

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3. = This license amendment is effective as of its date of issuance and shall I~

~ be implemented within 60 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION h\\

Darl S. Hood, Acting Director Project Directorate II-3 Divisien of Reactor Projects-I/II'

Attachment:

Changes to the Technical Specifications

-Date of Issuance: August 31, 1987

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MDunh<3}DRP-I/II PDII-P0ff-3/DRP-I/II OGC-Bethesda PDII-3/DRP-I/II n/ rad LCrocker f ek DHood, Acting Director 07//(,/87 07//p/87 01/g/87 07/ g /87 Or

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7j ATTACHMENT TO LICENSE AMENDMENT NO. 8!.

FACILITY OPERATING LICENSE NO. NPF-5 DOCKET NO. 50-366 Remove the following pages of the Appendix. A Technical Specifications.

The. overleaf page is provided for convenience.

Remove Insert Page g

3/4 7-31 3/4 7-32 B 3/4 7-3 8 3/4 7-3..

8 3/4 7-4 l

' PLANT SYSTEMS i

BASES i,

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3/4.7.4 SNUBBERS (Continued)

The seEv' ice life of a :nubber is evaluated via manufacturer input and information through consideration of the snubber service conditions and associated installation and maintenance records (newly installed snubber, seal ' replaced, spring replaced, in h'igh radiation area, in high temperature area,etc.'..).

The requirement to monitor the snubber service life is included to ensure that the snubbers periodically undergo _ a performance.

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evaluation in view of their age and operating conditions. These_ records will provide statistical bases for future consideration of snubber-service life. The requirements for the maintenance of records and the snubber service life review are not intended to affect plant operation.

3/4.7.5 SEALED SOURCE CONTAW.INAT10N 4

The limitations on sealed source removable contamination ensure that the total body er individual organ irradiation does not exceed allowable limits in the event of ingestion or inhalation of the source material. The limitations on removable contamination for soteces requiring leak testing, including alpha emitters, is based on 10 CFR 70.39(c) limits for plutonium.

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Ouantities ct-interest to this specification which are exempt from the leekage testing are consistent with the criteria of 10 CFR Part 30.11-20 and 70.19. Leakage-from searces excluded from the requirements of this specification is not likely to represent more than one maximum permissible body burden for total body irradiation if the source material is _ inhaled or ingested.

3/4.7.6 (Deleted)

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'T HATCH - UNIT 2 P 3/4 7-3 Amendment.No. 84 Amendmen; No. J!, 70 4.

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