ML19336A671

Forwards NRC Position Re Application of Cladding Swelling & Rupture Models for LOCA Analysis.Requests Util Provide Supplemental Calculations

ML19336A671
Person / Time
Site:	Limerick
Issue date:	10/09/1980
From:	Tedesco R Office of Nuclear Reactor Regulation
To:	Bauer E PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
References
NUDOCS 8010300443
Download: ML19336A671 (3)

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UNITED STATES y j ) c. c ( _ g NUCLEAR REGULATORY COMMISSION

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'f WASHINGTON. D. C. 20555 o k. a jC OCT 9 1980 Docket Nos. 50-352 and 50-3S3 Mr. Edward G. Bauer, Jr.

Vice President and General Counsel Philadelphia Electric Company 2301 Market Street Philadelphia, Pennsylvania 19101

SUBJECT:

STAFF POSITION ON CLADDING SWELLING AND RUPTURE MODELS FOR LOCA ANALYSES Enclosed is the staff position concerning the 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 para-

. graph of the Enclosure.

Please advise us of the schedule for your response.

If you require any clari-fication, contact the staff's assigned project manager, D. Sells at (301) 492-7792.

Sincerely, set-m Robert L. Tedesco Assistant Director for Licensing Division of Licensing

Enclosure:

As Stated-cc w/ enclosure:

See next page 8 010300 g

l OCT 9 1980 Mr. Edward G. Bauer, Jr.

Mr. Vincent Boyer Vice President & General Counsel Senior Vice President Philadelphia Electric Company Philadelphia Electric Company 2301 Market Street 2301 Market Street Philadelphia, Pennsylvania 19101 Philadelphia, Pennsylvania 19101 cc: Troy B. Corner, Jr., Esq.

Conner, Moore & Corber 1747 Pennsylvania Avenue, N. W.

Washington, D. C.

20006

.eputy Attorney General Room 512, Main Capitol Building Harrisburg, Pennsylvania 17120 Mr. Robert W. Adler Assistant Attorney General Bureau of Regulatory Counsel 505 Executive House P. O. Box 2357 Harrisburg, Pennsylvania 17120 Honorable Lawrence Coughlin House of Representatives Congress of the United States Washington, D. C.

20515 Roger B. Reynolds, Jr., Esq.

324 Swede Street Norristown, Pennsylvania 19401-Lawrence Sager, Esq.

Sager & Sager Associates 45 High Street Pottstown, Pennsylvania 19464 Joseph A. Smyth Assistant County Solicitor County of Montgomery Courthouse Norristown, Pennsylvania 19404 Eugene J. Bradley Philadelphia Electric Company Associate General Counsel 2301 Market Street Philadelphia, Pennsylvania 19101 Mr. Jacque Durr Resident Reactor Inspector U. S. Nuclear Regulatory Commission

-P. O. Box 47-Sanatoga, Pennsylvania 19464 l

I s s

ENCLOSURE The NRC staff has been generically evaluating three materials mo. is that l

are used in.ECCS evaluations. - Those models predict cladding rup : e l

temperatur'e," cladding burst strain, and fuel assembly ficw 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 confirm that their operating reactors would continue to be in conformance with 10 CFR 50.46 if the NUREG-0630 models were substituted for the present i

materials models in their ECCS evaluations and certain other compensatory model changes were allowed (References 3 and 4).

Until we have completed our generic review and implemented new acceptance criteria for cladding 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, " Summary Minutes of l

Meeting on Cladding Rupture Temperature, Cladding Strain, and Assembly Ficw Blockage," November 20, 1979.

2.

O. A. Powers and R. O. Meyer, " Cladding Swelling and Rupture Models for LOCA j

Analysis," NRC Report NUREG-0630, April 1980.

3.

Letter frcm D. G. Eisenhut, NRC, to all Operating Light Water Reactors, dated November 9, 1979.

4.

Memorandum from H. R. Denton, NRC, to Commissioners, " Potential Deficiencies l

in ECCS Evaluation Models," November 26, 1979.

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