ML20062A423
| ML20062A423 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 07/13/1982 |
| From: | Novak T Office of Nuclear Reactor Regulation |
| To: | Mattimoe J SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| References | |
| NUDOCS 8208030741 | |
| Download: ML20062A423 (5) | |
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mocKet'TD ORB #4 PM AE00 MC PDR Gray File IE L PDR DEisenhut ACRS-10 ORB #4 Rdg H0rnstein wood ha Docket No. 50-312 Mr. J. J. Hattimoe Assistant General ibnager and Chief Engineer Sacramento Municipal Utility District 6201 S Street P. O. Cox 15830 Sacramento, California 95813
Dear Hr. Matticoe:
On November 1,1979, the NRC staff net with fuel vendors and industry representatives te discuss 10 CFR 50 Appendix K cladding swelling and rupture models. The staff presented new models (Ref.1) that we believed vet the requirenents of 10 CFR 50 Appendix K and 10 CFR 50.46.
Each fuel vendor was then asked to show how, in light of the new nodels, the plants analyzed with their EHs continued to meet the performance limits of 10 CFR 50.46. The Babcock & Wilcox (B&W) response (Ref. 2) concluded that the impact of the NRC curves was small and did not result in cladding temperatures 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 conservatism in an ECCS evaluation model calculatfore was considered, we concluded that there was no significant safety concern for your facility.
Si's:.e the November 1st meeting, we have received revised Elis frua all LWR fuel vendors except B&W (Refs. 4 and 5). Recently, Consumer's Power Company submitted (Ref. 6) a B&W supplemental ECCS calculation that used the cladding models of NUREG-0630. Our evaluation of this submittal is given in Reference 7.
The results of the Midlar.d 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 margins were applied in other parts of their ECCS nodel. The supplemental ECCS calculation for Midland is applicable to all B&W plants (OR and OL);
therefore, it nay be that the swelling and rupture data described in NUREG-0630 may have more effect on the peak cladding temperatures cal-culated by the B&W EM than previously considered in 1979 and 1980.
Accordingly, you are requested to provide within the next 30 days, a schedule for subnitting supplemental ECCS calculations similar to those provided for Midland in Reference 6.
These calculations may be generic to other D&W plants and they nay employ offsetting cargins derived from compensating nodels. Justification will be required for the use of unapproved compensating models.
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!!r. J. J. Ma ttimoe In addition, permanent modifications to your ECCS evaluation models should be developed and implemented, and an implementation schedule should be provided to us as soon as possible, but' not later than 60 days after this 30-day period.
We will be pleased to meet with you or any of your representatives to discuss this natter further. Please contact your i1RC Project Manager if you wish such a riceting or if you have questions.
The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore, OHB clearance is not required under P. L.96-511.
Sincerely, Oridnal signed W Thomas M. Novak, Assistant Director for Operating Reactors Division of Licensing
Enclosure:
List of References cc w/ enclosure:
fir. J. H. Taylor, flanager Licensing Babcock & Wilcox P. O. Box 1260 Lynchburg, Virginia 245054 fir. H. G. Parris, Manager of Power
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Tennessee Valley Authority 500A Chestnut Street, Tower II Chattanooga, Tennessee 37401 See next page J
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Sacramento Municiaal Utility Rancho Seco. Docket No. 50-312 District cc w/ enclosure (s):
' David S. Kaplan, Secretary and Christopher Ellison, Esq.
General Counsel Dian Grueuich, Esq.
Sacramento Municipal Utility California Energy Comission District lill Howe Avenue 6201 S Street Sacramento, California 95825 P. O. Box 15830 Sacramento, California 95813 Ms. Eleanor Schwartz California State Office 600 Pennsylvania Avenue, S.E., Rm 201 Sacramento County Board of Supervisors Washington, D. C.
20003 827 7th Street, Room 424 Sacramento, California 95814 Docketing and Service Section Office of the Secretary U.S. Nuclear Regulatory Comission Business and Municipal Department Sacramento City-County Library Washington, D. C.
20555 828 I Street Resident Inspector / Rancho Seco Sacramento, California 95814 c/o U. S. N. R. C.
14410 Twin Cities Road Herald, CA 95638 Dr. Rir.hard F. Cole Atomic Safety & Licensing Board Panel U.S. Nuclear Regulatory Commission Washington, D. C.
20555
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Regional Radiation f.epresentative EPA Reofon IX Mr. Frederick J. Shon 215 Fremont Street Atomic Safety and Licensing Board San Francisco, California 94111 Panel U.S. Nuclear Regulatory Comission Mr. Robert B. Borsum Washington, D. C.
20555 Babcock & Wilcox Nuclear Power Generation Division Elizabeth S. Bowers, Esq.
Suite 220, 7910 Woodmont Avenue Chairman, Atomic Safety and Bethesda, Maryland 20814 Licensing Board Panel U.S. Nuclear Regulatory Comission Thomas Baxter, Esq.
Washington, D. C.
20555 Shaw, Pittman, Potts & Trowbridge 1800 M Street, N.W.
Washington, D. C.
20036 Herbert H. Brown, Esq.
Lawrence Coe Lanpher, Esq.
Hill, Christopher and Phillips, P.C.
1900 M Street, N.W.
Atomic Safety and Licensing Board Washington, D. C.
20036 Panel U.S. Nuclear Regulatory Comission Helen Hubbard Washington, D. C.
20555 P. O. Box 63 Sunol, California 94586 Mr. L. G. Lanese GPU Nuclear Corporation 100 Interpace Parkway Parsippany, New Jersey 07054 1
Sacrament @ Municipal Utility District Atomic Safety and Licensing Appeal Mr. Robert H. Engelken, Regional Administrator U. S. Nuclear Regulatory Commission, Region V Board Panel 1990 N. California Boulevard, Suite 202 U.S. Nuclear Regulatory Commission Washington, D. C.
20555 Wainut Creek, California 94596 Alan S. Rosenthal, Chairman Atomic Safety and Licensing Appeal Board U. S. Nuclear Regulatory Connission Washington, D. C.
20555 Dr. John H. Buck Atonic Safety and Licensing Appeal Board U. S. Nuclear Regulatory Conmission Washington, D. C.
20555 Christine H. Kohl Atomic Safety and Licensing Appeal Board U. S. Nuclear Regulatory Commission Washington, D. C.
20555 California Department of Health ATTN: Chief. Environmental Radiation Control Unit Radiological Health Section 714 P Street, Room 498 l
Sacramento, California 95814 l
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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. J. Mattimoe (SMUD) letter to D. G. Eisenhut (NRC), Docket No. 50-312,
~ i January 2,1980.
4.
R. J. Mattson (NRC) letter to L. Lanese (GPU) and R. G. Snipes (DPCo),
September 8, 1981.
t 5.
L. C. Lanese (GPU) letter to R. J. Mattson (NRC), November 3,1981.
6.
J. W. Cook (CPCo) letter to H. R. Denton (NRC), Doc' ct No. 50-329/330, r
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, May 1982.
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