ML20062A601

Requests Schedule Be Provided for Submittal of Supplemental ECCS Calculations,Which May Be Generic to Other B&W Plants & Which May Employ Offsetting Margins

ML20062A601
Person / Time
Site:	Crystal River
Issue date:	07/13/1982
From:	Novak T Office of Nuclear Reactor Regulation
To:	Hancock J FLORIDA POWER CORP.
References
NUDOCS 8208040052
Download: ML20062A601 (4)

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t DISTRIB4T-I Ringram OELD docket 711e - ORB #4 PM AE00 NRC POR Gray File IE L PDR DEisenhut ACRS-10 Docket No. 50-302 ORB #4 Rdg H0rnstein EBlackwood bgatner Mr. John A. Hancock Vice President, Nuclear Operations Florida Power Corporation ATTH: Manager, Nuclear Licensing P. O. Box 14042, M.A.C. H-2 St. Petersburg, Florida 33733

Dear Mr. Hancock:

On Hovember 1,1979, the hRC staff net with fuel vendors and industry representatives to discuss 10 CFR 50 Appendix K cladding swelling and rupture rodels. The staff presented new models (Ref.1) that we believed ret the requirements of 10 CFR SO Appendix K and 10 CFR 50.46.

Each fuel vendor was then asked to show how, in light of the new models, the plants analyzed with their ems continued to meet the perfornance limits of 10 CFR 50.46. The Babceck & Wilcox (Bau) response (Ref. 2) cuncluded that the inpact of the hRC curves was small and did not result in cladding tenperatures in excess of 2200 F.

Based on this and the licensee's response (Ref. 3) and the fact that the use of the data did not produce a large effect when the overall conservatisn in an ECCS evaluation nodel calculation was considered, we concluded that there was no sinnificant safety concern for your facility.

Since the Hoventer 1st nceting, we have received revised Eris from all LWR fuel vendors except B&W (Refs. 4 and 5). Recently, Consumer's Power Company subnitted (Ref. 6) a B8W supplemental ECCS calculation that used the cladding nodels of NUREC-0630 Our evaluation of this submittal is given in Reference 7. The results of the 111dland calculation showed a need to reduce linear heat generation rates by 1 kW/ft at the 2-foot, 4-foot and 6-foot core elevations even though partially offsetting nargins were applied in other parts of their ECCS nodel. The supplemental ECCS calculation for Midland is applicable to all B&W plants (OR and CL);

therefore, it nay be that the swelling and rupture data described in NitREG-0630 nay have more effect on the peak cladding tenperatures cal-culated by the B&W D1 than previously considered in 1979 and 1980.

Accordingly, you are requested to provide within the next 30 days, a schedule for subnittinq supplerental ECCS calculations sinilar to those provided for flidland in Reference 6. These calculations reay be generic to other B&W plants and they may enploy offsetting rargins derived fron conpensating models. Justification will be required for the use of unapproved compensating nodels.

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Mr. John A. liancock In addition, permanent nodifications to your ECCS evaluation rodels should be developed and irpleaented, and an imple"entation schedule should be provided to us as soon as possible, but not later than 60 days af ter this 30-day period.

tre will be pleased to neet with you or any of your representatives to l discuss this matter further. Please contact your f.RC Project fianager if you wish such a neeting or if you have questions.

The reportinc and/or recordkeeping requirements centained in this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P. L. 96-S11.

Sincerely, get grei V Thomas M. t,'ovah, Assistant Director for Operating Reactors Division of Licensing

Enclosure:

List of P.eferences cc v/ enclosure:

"r. J. H. Taylor, Manager Licensing Fabcock A Wilcox P. O. Box 1260 Lynchburg, Virginia 245054 Mr. H. G. Parris, Manager of Power Tennessee Valley Authority 500A Chestnut Street, Tower 11 Cha ttanooga, Tennessee 37401 See next page m m A A ( - fw s omce> ('.yNBd.410h. ..C, . . B#4:D -

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Crystal River Unit No. 3 50-302 l Florida Power Corporation l

cc w/ enclosure (s):

fir. S. A. Brandimore Florida Power Corporation Mr. Robert B. Borsum Vice President and General Counsel Babcock & Wilcox P. O. Box 14042 Nuclear Power Generation Division St. Petersburg, Florida 33733 Suite 220, 7910 Woodmont Avenue Bethesda, Maryland 20314 Mr. Wilbur Langely, Chairman Board of County Commissioners Mr. Tom'Stetka. Resident Inspector Citrus County U.S. Nuclear Regulatory Commission Iverness, Florida 36250 Route #3, Box 717 Crystal River, Florida 32629 Regional Radiation Representative Mr. T. C. Lutkehaus EPA Region IV Nuclear Plant Manager 345 Courtland Street, N.E. Florida Power Corporation Atlanta, Georgia 30308 P. O. Box 219 Crystal River, Florida 32629 Bureau of Intergovernmental Relations 660 Apalachee Parkway Crystal River Public Library Tallahassee, Florida 32304 h

668 N. H. First Avenue Crystal River, Florida 32629

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Administrator Department of Environmental Regulation Power Plant Siting Section State of Florida 2600 Blair Stone Road Tallahassee, Florida 32301 Attorney General Department of Legal Affairs The Capitol Tallahassee, Florida 32304 Mr. James P. O'Reilly, Regional Administrator U. S. Nuclear Regulatory Commission, Rt.gion II 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 Mr. L. G. Lanese GPU Nuclear Corporation 100 Interpace Parkway Parsippany, New Jersey 07054

REFERENCES

1. D. A. Powers and R. O. Meyer, " Cladding Swelling and Rupture Models for LOCA Analysis", NRC Report NUREG-0630, April 1980.

2. J. H. Taylor (B&W) letter to D. G. Eisenhut (NRC), November 2,1979.

3. J. A. Hancock (FPCo) letter to D. G. Eisenhut (NRC), Docket No. 50-302, December 20, 1979.

4 R. J. Mattson (NRC) letter to L. Lanese (GPU) and R. G. Snipes (DPCo),

September 8, 1981.

5. L. C. Lanese (GPU) letter to R. J. Mattson (NPC), November 3,1981.

6. J. W. Cook (CPCo) letter to H. R. Denton (NRC), Docket No. 50-329/330, April 2,1982.

Enclosure:

B&W Report No. 12-1132424, Rev. O, " Bounding Analysis Impact Study of NUREG-0630".

7. " Safety Evaluation Report Related to the Operation of Midland Plant, Units 1 and 2", NRC Report NUREG-0793, iby 1982