ML20065B236
| ML20065B236 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 03/24/1994 |
| From: | Tosch K NEW JERSEY, STATE OF |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GL-92-01, GL-92-1, NUDOCS 9404010210 | |
| Download: ML20065B236 (2) | |
Text
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f State of New lersey l
Department of Environmental Protection and Energy l-Division of Environmental Safety, Health, Robert C. Shinn. )r.
Commissioner and, Analytical Programs Radiation Protection Programs Bureau of Nuclear Engineering CN 415 Trenton, New Jersey 08540-0415 Tel (609) 987-2032 Fax (609) 987-6354 March 24, 1994 U.S.
Nuclear Regulatory Commission Document Control Room Washington, D.C.
20555 Ladies and Gentlemen:
Subject:
Oyster Creek Nuclear Generating Station (OCNGS)
Docket No. 50-219 Light Water Nuclear Reactor (LWR) Structural Integrity.
Fracture Mechanics Analysis for Upper Shelf Energy (USE) per Requirements of Generic Letter GL 92-01, Revision 2
~
Generic Letter 92-01, Revision 2
(" Reactor Vessel Integrity")
requested specific information from the utilities, for NRC to access their compliance with 10 CFR 50, Appendices G and H.
GPU Nuclear (GPU), the licensee, reported that since 1977 there have been several information exchanges between the NRC and GPU regarding the plant's USE issues.
On September 22, 1992, GPU submitted its initial response to GL 92-01, Rev.
1 to the NRC.
GPU's initial evaluation had concluded that (for the assumptions used) three beltline plates currently have less than 50 ft-lb USE (lower screening criterion).
Later, since initial USE data for the beltline welds and other miscellaneous site-specific data were not available, to satisfy concerns raised by the NRC regarding the adequacy of the available data, GPU decided to supplement their analysis and rely instead on the Boiling Water Reactor Owners' Group's ef forts for resolution of GL 92-01 issues.
In its supplementary submittal (9/7/93), GPU indicated that their earlier analysis, based on the incomplete plant-specific data presented in earlier submittals, is to be superseded by the approach of the report "BWR Owners' Group Topical Report on Upper Shelf Energy Equivalent Margin Analysis" {NEDO-32205, prepared for the BWROG by GE Nuclear).
GPU asked the NRC to review the OCNGS O
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. P USE case in the light of this latter approach.
The BWR report (which also contains pertinent data from OCNGS), was _ developed following methods provided in ASME Boiler and Pressure Vessel Code Case N-512.
It is understood that the approach and conclusions of this report are acceptable to the NRC.
The plants that can confirm the applicability of this report to their individual cases, may demonstrate that at 32 " effective full years of operation" their USEs will remain higher than the allowable limits derived from the equivalent safety margin analysis.
The New Jersey Department of Environmental Protection and Energy's Bureau of Nuclear Engineering staff has reviewed documentation on this issue (starting with the 9/22/92 GPU's submittal) and has no comments.
If you have any questions, please contact suren Singh at (609) 987-2039, or Ariadni Kapsalopoulou at (609) 987-2052.
Sincerely,
[ f<~ [ V - !CG C#
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Kent Tosch, Manager Bureau of Nuclear Engineering c:
J.
Lipoti, Assistant Director RPP -- NJ DEPE D.
Chawaga, State Liaison, Region I -- US NRC A. Dromerick, Senior Project Manager -- US NRC L. Briggs, Senior Resident Inspector OCNGS -- US NRC M.
Laggart, Licensing Manager -- GPU
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