ML20140C183

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Notice of Consideration of Issuance of Amend to License DPR-57 & Proposed NSHC Determination.Amend Provides one-time Extension of Surveillance Interval Applicable to Testing of Drywell & Torus Headers & Nozzles to 840901
ML20140C183
Person / Time
Site: Hatch Southern Nuclear icon.png
Issue date: 05/31/1984
From: Rivenbark G
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20140C182 List:
References
TAC-55087, NUDOCS 8406190070
Download: ML20140C183 (4)


Text

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7590-01 i

UNITED STATES NUCLEAR REGULATORY COMMISSION GEORGIA POWER COMPANY i DOCKET NO. 50-321 ,

NOTICE OF CONSIDERATION OF' ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE AND PROPOSED N0 SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION The U.S. Nuclear Regulatory Commission (the . Commission) is considering issuance of an amendment to Facility Operating License No. f?R-57 issued to Georgia Power Company, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, City of Dalton, Georgia (the licensees) for operation of the Edwin I. Hatch Nuclear Plant, Unit 1, located in Appling County, Georgia.

The proposed amendment would provide a one time extension of the surveillance interval applicable to the testing of the drywell and torus headers and nozzles as described in Section 4.5.8.1.a of the Technical Specifications. The proposed extension would increase the grace period from 25% to 30% of the nominal surveillance interval, and also would allow the licensee to perform the required testing at the end of an operating cycle (Cycle 8) scheduled for September 1, 1984 In the absence of this extension, the licensee would be required to shutdown the unit on or before June 19, 1984 e4 6 [o$

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. 7590-01 These revisions to the Technical Specifications would be made in response to the licensee's application for amendment dated May 29, 1984 Before issuance of the proposed license amendment, the Comission will have made. findings required by the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations. ,

The Ccmission has made a proposed determination that the amendment request involves no significant hazards ' consideration. Under the Commission's regulations in 10 CFR 50.92, this means that operation of the facility in accordance with the proposed amendment would not (1) involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) involve a significant reduction in a margin'of safety.

A significant increase in the probability or consequences of an accident previously evaluated is not involved in this amendment because:

(a) Chapter 14.4 of the Hatch 1 FSAR showed that operation of the

- containment spray system is not necessary to maintain the peak pres-sures under accident conditions in the drywell below the design value.

(b) For the enveloping event, operation of the containment spray changes the temporal behavior of pressure in the primary contain-ment such that the second pressure peak is lower (11.8 psig versus <

14.3 psig), with no change in the first pressure peak (approximately  !

45 psig). The design value of the containment pressure capability is 56 psig. Thus, the primary margin against containment over- '

pressure remains unchanged whether or not the spray system operates.

7590-01 The possibility of a new or different kind of accident from any accident previously evaluated is not created by approving this amendment because the extension of the surveillance interval does not involve new modes of operation.

The amendment would not involve a significant reduction in a margin of safety for the following reasons:

(a) The period of uncertainty for availability of the spray system is increased from 5 years plus 25% to 5 years plus 30%. The increased probability of unavailability is smafl.

(b) The increased pressure in the second peak under the design basis accident conditions could inc.rease the leakage out of the drywell.

Since the analysis provided in the FSAR envelopes this accident, the decrease in the margin is small.

Therefore, based on these considerations and the three criteria given above, the Commission has made a proposed determination that the amendment request involves no significant hazards consideration.

The Commission has determined that failure to act in a timely way would result in an earlier than scheduled shutdown. Therefore, the Commission has insufficient time to issue its usual 30-day notice of the proposed action for public coment.

If the proposed determination becomes final, an opportunity for a hearing will be published in the Federal Register at a later date and any hearing request will not delay the effective date of the amendment.

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. 7590-01 If the Commission decides in its final determination that tne amendment does involve a significant hazards consideration, a notice of opportunity for a prior hearing will be published in the Federal Register and, if a hearing is granted, it will be held before any amendment is issued.

The Commission is seeking public comments'on this proposed determination of no significant hazards consideration., Comments on the proposed detennination may be telephoned to George Rivenbark, Acting Chief of Operating Reactors Branch No. 4, by collect cal 1 to 301-492-7136 or submitted in writing to the Secretary of the Commission, N.S. Nuclear Regulatory Commission, Washington, D.C. 20555, Attn: Docketing and Service Branch.

All comments received by June 18, 1984 will be considered in reaching a final determination. A copy of tihe application may be examined at the Commission's Public Document Room,1717 H Street, N.W., Washington, D.C. and at the Appling County Public Library, 301 City Hall Drive, Baxley, Georgia.

Dated at Bethesda, Maryland, this 31st day of May 1984.

FOR THE NUCLEAR REGULATORY COMMISSICN I z o c z'b / G)c-c o / n 6 G orge . Rivenbark, Acting Chief Operating Reactors Branch d4 Division of Licensing

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