ML20212G883
| ML20212G883 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 02/27/1987 |
| From: | Gucwa L GEORGIA POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 1171C, SL-2077, NUDOCS 8703050427 | |
| Download: ML20212G883 (2) | |
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Georgl3 Power Company 333 Piedmont Avenus Attnta, Georgia 30308 T;lephons 404 526-6526 e
Mading Address:
Post Office Box 4545 Atlanta, Georgia 30302 GeorgiaPower L T. Gucwa the southem v!cctrc system Manager Nuclear Safety and Licensing SL-2077 1171C February 27, 1987 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C.
20555 NRC DOCKET 50-366 OPERATING LICENSE NPF-5 EDWIN I. HATCH NUCLEAR PLANT UNIT 2 LEAD TEST FUEL ASSEMBLY MEETING Gentlemen:
At Georgia Power Company's (GPC) request, the NRC Hatch Licensing Project Manager has scheduled a meeting with appropriate NRC personnel to discuss licensing of fuel assemblies manufactured by Advanced Nuclear Fuels, Inc. under a lead test assembly program.
This meeting has been set for 9:00 A.H. on March 5,1987.
Enclosed is a proposed agenda which should facilitate discussion of the issues of interest relative to GPC's proposed program.
We appreciate your prompt response in arranging this meeting.
Please contact this office if you have any questions.
Sincerely, 8 @"
L. T. Gucwa l
JDH/lc Enclosure c:
Georgia Power Company U. S. Nuclear Regulatory Commission Mr. t. P. O'Reilly Dr. J. N. Grace, Regional Administrator Mr. J. T. Beckham, Jr.
Mr. P. Holmes-Ray, Senior Resident Mr. H. C. Nix, Jr.
Inspector - Hatch GO-NORMS Mr. G. Rivenbark, Licensing Project Manager 8703050427 870227 PDR ADOCK 05000366 P
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GeorgiaPowerb MEETING AGENDA GEORGIA ~ POWER C0t@ANY 9x9 DEMONSTRATION LEAD ASSEMBLIES AT HATCH UNIT 2 I.
Meeting
Purpose:
Obtain NRC Feedback on Licensing Approach II.
Demo Program Description o
Purpose.
o Design Considerations / Reload' License o
In-Reactor Considerations III.
Licensing of 9x9 LTAs under 10 CFR 50.59 o
ANF Standard Bundles o
Core-Wide Effects of LTAs for Accidents and Transients o
'Neutronics Compatibility o
Nuclear Instrumentation-Process Computer Compatibility -
o Existing Technical Specifications Limits Applicability IV.
GPC 10 CFR 50.59 Review Scope V.
Discussion and NRC Feedback l-.
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