ML18101A220
| ML18101A220 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 08/30/1994 |
| From: | Shinn R NEW JERSEY, STATE OF |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GL-92-01, GL-92-1, NUDOCS 9409150119 | |
| Download: ML18101A220 (2) | |
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State of New Jersey Department of Environmental Protection and Energy Robert C. Shinn, Jr.
Commissioner Division of Environmental Safety, Health, and Analytical Programs Radiation Protection Programs Bureau of Nuclear Engineering CN 415 Trenton, New Jersey 08625-0415 Tel (609) 987-2032 Fax (609} 987-6354 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Ladies & Gentlemen:
August 30, 1994
Subject:
Salem Nuclear Generating Station, Unit 1 & Unit 2 Docket No's 50-272 and 50-311 Public Service Electric & Gas Company (PSE&G)
Response to Generic Letter (GL) 92-01, Revision 1, "Reactor Structural Integrity,"
By letters dated June 30, 1992, December 30, 1992, August 4, 1993,.Sept.ember 29,.1993;* D.ecember 1, 19;93'; June 20, 'f994, arid Juiy 20, '1994, PSE&G responded.to NRC' s request for -information' relative to *Generic* Letter (GL)
.92-01; *Revision ** 1,* **and to subsequent requests for additional data.
Via GL 92-01, Rev. 1, the NRC is seeking to obtain information needed to assess compliance with requirements *and commitments regarding reactor vessel integrity per (a) 10 CFR 50.60 (acceptance criteria for fracture prevention), and (b) 10 CFR 50.61 (fracture toughness requirements for protection against pressurized thermal shock),
as set forth in Appendices G and H.
Said appendices specify fracture toughness* requirements for reactor system components to provide an adequ.ate margin of safety under any normal and anticipated operational occurrences.
NRC licensees are also using NRC Regulatory Guide 1.99, Revision 2 (March 1988).
Among these requirements, is the prediction of the effects of neutron irradiation on the reference temperature (RTNDT) and upper shelf energy * (USE) of reactor vessel 15elt'line zone materials (including welds).
Appendix G specifies that at least a 50 ft-lb USE be maintained for all beltline materials.of the vessel throughout its operating life... It.fur_ther r,eq~ires~: if 50 ft-lb *usE* cannot be demonstrate*d *for-a bel tllne.material, that methods be' offer.ed to
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confirm the existence of eguivalent margin, as defined in 10 CFR 50. 61.
PSE&G's more recent submittal (dated July 20,1994) presented revised data based on assumptions and generic initial conditions data per NRC's instructions.
Resulting values for the screening parameters met the requirements of Appendice G & H.
The New Jersey Department of Environmental Protection (NJ DEP)
Bureau of Nuclear Engineering (BNE) staff reviewed the information submitted by PSE&G, 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, Kent W. Tosch, Manager Bureau of Nuclear Engineering c:
Jill Lipoti, Ph.D., Assistant Director Radiation Protection Programs, NJ DEP David Chawaga, State Liaison Officer - Region I U.S. NRC J. c. Stone, Licensing Project Manager, NRR U.S. NRC
- c. Marschall, Artificial Island Senior Resident Inspector U.S. NRC F. Thomson, Manager Licensing and Regulation, PSE&G D. Zannoni, Bureau of Nuclear Engineering Radiation Protection Programs, NJ DEP