ML20071P933

Revises Estimated Completion Date for Implementation of NUREG-0737,Item II.B.3 to 830401,in Response to Generic Ltr 82-05.Interim Sampling Capabilities Per NUREG-0578 Provided in

ML20071P933
Person / Time
Site:	Hatch
Issue date:	12/20/1982
From:	Gucwa L GEORGIA POWER CO.
To:	Office of Nuclear Reactor Regulation
References
RTR-NUREG-0578, RTR-NUREG-0737, RTR-NUREG-578, RTR-NUREG-737, TASK-2.B.3, TASK-TM GL-82-05, GL-82-5, TAC-48451, TAC-48452, TAC-48505, TAC-48506, NUDOCS 8212290151
Download: ML20071P933 (1)

Text

oma row cowy 333 Piedvd A <enue A!!a"ta G.;, ma 30308 TehSnore 404 526 6S26 MOng AJJws, Per Offse Box 4545 A Ama c~o amo2 December 20, 1982 Georgia Power Power Generation Department Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Connission Washington, D. C. 20555 NRC 00CKETS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 EDWIN I. HATCH NUCLEAR PLANT UNITS 1, 2 POST TMI REQUIREMENT II.B.3 IMPLEMENTATION SCHEDULE Gentlemen:

Georgia Power Company's letter of June 7,1982, proposed a schedule for implementation of a number of NUREG-0737 requirements in response to the NRC's Generic Letter 82-05. Among these requirements was Item II.B.3

" Post-Accident Sampling Capability". It was estimated that this modification would be implemented in Plant Hatch Unit 1 by the end of the outage following cycle SB, which is currently in progress.

Georgia Power Company hereby revises our estimate of the completion date for the implementation of Item II.B.3 in Unit 1 to April 1, 1983. As discussed with Mr. Morton Fairtile on December 16, 1982, this redefinition of completion date is necessary due to the shortening of the Unit 1 outage by approximately seven weeks from the estimates in effect at the time of our June 7, 1982 letter. Although work on this system is being expedited to the extent possible, it is not expected that full implementation can be accomplished by the revised expected startup date of early February 1983.

As discussed in our June 7, 1982 letter, interim measures for obtaining reactor coolant and d.ywell atmosphere samples under post-accident conditions were provided in response to NUREG-0578. Because of this interim sampling capability, and because the calendar date estimated for the completion of the Unit 1 outage at the time of our June 7, 1982 letter corresponded approximately to the present April I estimate (albeit not defined as such in that letter), we consider the health and safety of the public to be unaffected by this redefinition of the completion date.

Please contact this office if you have any questions concerning this matter.

Yours very truly,

[I 4%

L. T. Gucwa JH/wb xc: J. T. Beckham, Jr.

H. C. Nix, Jr.

J. P. O'Reilly Senior Resident Inspector 8212290151 821220 b PDR ADOCK 05000321 P PDR