ML20081A200
| ML20081A200 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 02/10/1984 |
| From: | Gucwa L GEORGIA POWER CO. |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.D.1, TASK-TM NED-84-040, NED-84-40, TAC-44586, TAC-44587, NUDOCS 8403050085 | |
| Download: ML20081A200 (2) | |
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Georgia Power Cornpany 333 Pedmont Avenue Attanta. Georg;a 30308 Tetephone 404 526f;526 Maing Address.
Post othee Box 4545 Atlanta, Georg a 3C302 h
Georgia Power L T. Guewa Pr wo't.m ee.c system Manager Nuclear Eng:neanng and Chief Nuclear Engineer NED-84-040 February 10, 1984 Director of Nuclear Reactor Regulation Attention: Mr. John F. Stolz, Chief Operating Reactors Brcnch No. 4 U.S. Nuclear Regulatory Camission Washington, D.C. 20555 NRC DOCKETTS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 EDWIN I. HA'ICH NUCLEAR PLANT UNITS 1 AND 2 NURK;-0737 ITEM II.D.1 SAFETY RELIEF VALVE (SRV) TESTING Gentlemen:
Your letter of Decenber 29, 1982, rquested Georgia Power Cmpany to address questicus related to the BWR Owners Group Safety Relief Valve (SRV)
Test Progran. Our response of April 4, 1983, stated that a supplenental reponse to a certain question (i.e., question #2) would be sutrnitted to provide the conclusions of a dead weight analysis of the Hatch SRV discharge lines. We indicated in our letter of July 29, 1983, that no one single line could be identified as bounding, and therefore, unique analyses would be performed on each of the 22 SRV discharge lines.
'Ihe analyses included the weight and dynamic effects of water during an earttquake occurrence with the plant in the Alternate Shutdown Cooling Mode (Asm) of operation. In this analysis, we have assmed a low probability for occurrence of an earttquake during the ASCM initiation transient since this initiation is done manually. Further, we have considered the dynanic effect of the initiation transient under service level B, while the eartlquake event during the ASm was considered under service level C.
Hence, there is no need to cmbine the initiation transient loads with the earttquake loads.
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Georgia Power Director of Nuclear Reactor Regulation Attention: Mr. John F. Stolz, 011ef Operating Reactors Branch No. 4 February 10, 1984 Page 2 Although the results of the analyses show that the type and orientation of supports and the piping geometry are adequate, we are still evaluating the strength of the piping supports. It is expected that modifications required to enhance the strength of supports, if any, will be minor in nature. Such modifications will be accanplished at a future outage when design and materials are available.
If you have any questions, please contact this office.
Very truly yours,
[ f OM L. T. Gucwa CT/lb xc: H. C. Nix J. P. O'Reilly - NRC Region II Senior Resident Inspector