ML20055A909
| ML20055A909 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 07/13/1982 |
| From: | Novak T Office of Nuclear Reactor Regulation |
| To: | Crouse R TOLEDO EDISON CO. |
| References | |
| RTR-NUREG-0630, RTR-NUREG-630 NUDOCS 8207200115 | |
| Download: ML20055A909 (4) | |
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( uocke ; ri le3 ORB #4 PM AE00 WRC FLR Gray File IE' L PDR DEisenhut ACRS-10 Docket No. 50-345 ORB #4 Rdg H0rnstein EBlackwood Dgsraer Mr. Richard P. Crouse Vice President, Nuclear Toledo Edison Company Edison Plaza - Stop 712 300 fladison Avenue Toledo, Ohio 43652
Dear Mr. Crouse:
On Novenber 1,1979, the NRC staff met with fuel vendors and industry representatives to discuss 10 CFR 50 Appendix K cladding swelling and rupture models. The staff presented new models (Ref.1) that we believed net the requirements 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 models, the plants analyzed with their EHs continued to meet the performance limits of 10 CFR 50.46. The Dabcock & 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 calculation was considered, we concluded that there was no significant safety concern for your facility.
Since the November 1st meeting, we have received revised ems from all LWR fuel vendors except D&W (Refs. 4 and 5). Recently, Consumer's Power Company subnitted (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 Midland calculation showed a need to reduce linear heat generation rates by I 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 model. The supplenental ECCS calculation for Mid'.and is applicable to all B&W plants (OR and OL);
therefore, it may Le that the swelling and rupture data described in
!!UREG-0630 may have more effect on the peak cladding temperatures cal-culated by the Ba'l Ett than previously considered in 1979 and 1980.
Accordingly, you are requested tc provide within the next 30 days, a schedule for submitting supplenental ECCS calculations similar to those provided for Midland in Reference 6.
These calculations may be generic to other BAW plants and they may employ offsetting margins derived fron compensating models. Justification will be required for the use of l
unapproved compensating models.
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.s fir. Richard P. Crouse In addition, pemanent modifications to your ECCS evaluation codels should be developed and implemented, and an implementation schedule should be provided to us as soon as possible, but not later than 60 days af ter this 30-day period.
N We will be pleased to meet with you or any of your representatives, to discuss this matter further. Please contact your NPC Project P.anager if you wish such a neeting or if you have questions.
The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P. L.96-511.
Sincerely, priginal ;1gned D1 Thomas it. Novak, Assistant Director for Operating Reactors Division of Licensing
Enclosure:
List of References cc w/ enclosure:
fir. J. H. Taylor, Itanager Licensing Babcock A Wilcox P. O. Box 1260 Lynchburg, Virginia 245054 tir.11. G. Parris, flanager of Power Tennessee Valley Authority 500A Chestnut Street, Tower 11 Chattanooga, Tennesrae 37401 See next page
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NRC FORM 31S (10-80) NRCM 024o OFFICIAL RECORD COPY usom asi.-ass.seo
Toledo Edison Company ccw/ enclosure (s):
Mr. Donald H. Hauser, Esq.
U.S. Nuclear Regulatory Corsnission The Cleveland Electric Resident Inspector's Office Illuminating Company 5503 N. State Route 2 Cleveland, Ohio 44101
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Oak Harbor Ohio 43449 P. O. Box 5000 Mrs. Julia Baldwin, Libr'arian Gerald Charnoff, Esq.
Government Documents Collection Shaw, Pittman, Potts William Carlson Library and Trowbridge University of Toledo 1800 M Street, N.W.
2801 W. Bancroft Avenue Washington, D. C.
20036 Toledo, Ohio 43606 Paul M. Smart, Esq.
Fuller & Henry 30011adison Avenue P. O. Box 2083 Regional Radiation Representative Toledo, Ohio 43603 EPA Reaton V 230 South Dearborn Street Mr. Robert B. Borsum Chicago, Illinois 60604 Babcock & Wilcox Nucit:or Power Generation Division 7910 Woodmont Avenue, Suite 220 Bethesda, !!aryland 20814 Ohio Department of Health ATTN:
Radiological Health Program Director P. O. Box 118 President, Board of County Columbus, Ohio 43216 Commissioners of Ottawa County Port Clinton, Ohio 43452 Mr. L. G. Lanese Attorney General GPU Nuclear Co Department of Attorney General 100 Interpace Pa k"##
30 East Broad Street Parsippany, New Jersey 07054 Columbus, Ohio 43215 Harold Kahn, Staff Scientist Power Siting Commission 361 East Broad Street Columbus, Ohio 43216 Mr. James G. Keppler, Regional Administrator U. S. Nuclear Regulatory Commission, Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137 Mr. Ted Myers Manager, Nuclear Licensing Toledo Edison Company Edison Plaza 300 Madison Avenue Toledo, Ohio 43652
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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.
R. P. Crouse (TECo) letter to D. G. Eisenhut (NRC), Docket No. 50-346, January 28, 1980.
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 (NRC), 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, May 1982 I