ML19331E319
| ML19331E319 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 08/26/1980 |
| From: | Tedesco R Office of Nuclear Reactor Regulation |
| To: | Nichols T SOUTH CAROLINA ELECTRIC & GAS CO. |
| References | |
| NUDOCS 8009090895 | |
| Download: ML19331E319 (3) | |
Text
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'o UNITED STATES
! }.,, j NUCLEAR REGULATORY COMMISSION
,j WASHINGTON, D. C. 20555 August 26, 1980 Docket No. 50-395 Mr.-T. C. Nichols, Jr.
Vice President & Group Executive Nuclear Operations South Carolina Electric & Gas Company P. O. Box 764 Columbia, South Carolina 29281
Dear Mr. Nichols:
SUBJECT:
STAFF POSITION ON CLADDING SWELLING AND RUPTURE MODELS FOR LOCA ANALYSES Enclosed is the staff position concerning tt.e application of the cladding swelling and rupture models for loss of coolant accident analysis. We request that you provide the supplemental calculations described in the second paragraph of the enclosure.
Please advise us of the schedule for your response.
If you require any clarification, contact the staff's assigned licensing project manager.
Sincerely,
-Oh"LO Robert L. Tedesco Assistant Director for Licensing Division of Licensing
Enclosure:
As stated cc w/ enclosure:
See next page 4
4 80 09090fd7
August 26, 1980 Mr. T. C. Nichols, Jr.
Vice President & Group. Executive Nuclear Operations South Carolina Electric & Gas Company P. O. Box 764 Columbia, South Carolina 29281 cc: Mr. William A. Williams, Jr.
Vice President South Carolina Public Service Authority 223 North Live Oak Drive Moncks Corner, South Carolina. 29461 Troy B. Conner, Jr., Esq.
Conner, Moore & Corber 1747 Pennsylvania Avenue, N. W.
Washington, D. C.
20006 Mr. Mark B. Whitaker, Jr.
Group Manager - Nuclear Engineering & Licensing
^
South Carolina Electric & Gas Company P. O. Box 764 Columbia, South Carolina 29218 Mr. Brett Allen Bursey Route 1, Box 93C Little Mountain, South Carolina 29076 Resident Inspector / Summer NPS c/o U. S. NRC P. O. Box 1047 Irmo, South Carolina
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l ENCLOSURE The NRC staff has been generically evaluating three materials models that, are used in ECCS evaluations. Those models predict cladding rupture temperature, cladding burst strain, and fuel assembly flow blockage. We have (a) discussed our evaluation with vendors and other industry repre-sentatives-(Reference 1), (b) published NUREG-0630, " Cladding Swelling and Rupture Models for LOCA Analysis" (Reference 2), and (c) required licensees to confinn that their operating reactors would continue to be in conformance with 10 CFR 50.46 ff the NUREG-0630 models were substituted for the present materials models in their ECCS evaluations and certain other compensatory j
model changes were allowed (References 3 and 4).
Until we have completed our generic review and implemented new acceptance criteria for c_ladding models, we will require that the-ECCS analyses in your FSAR be accompanied by supplemental calculations to be performed with the materials models of NUREG-0630. For these supplemental calculations only, we will accept other compensatory model changes that may not yet be approved by the NRC, but are consistent with the changes allowed for the confirmatory operating reactor calculations mentioned above.
REFERENCES 1.
Memorandum from R. P. Denise, NRC, to R. J. Mattson, "Suninary Minutes of Meeting on Cladding Rupture Temperature, Cladding Strain, and Assembly Flow Blockage," November 20, 1979.
2.
D. A. Powers and R. O. Meyer, " Cladding Swelling and Rupture Models for LOCA Analysis," NRC Report NUREG-0630, April 1980.
3.
Letter from D. G. Eisenhut, NRC, to all Operating Light Water Reactors, dated November 9,1979.
4.
Memorandum from H. R. Denton, NRC, to Coninissioners, " Potential Deficiencies in ECCS Evaluation Models," November 26, 1979.