ML19340B346
| ML19340B346 | |
| Person / Time | |
|---|---|
| Site: | Zimmer |
| Issue date: | 10/08/1980 |
| From: | Tedesco R Office of Nuclear Reactor Regulation |
| To: | Borgmann E CINCINNATI GAS & ELECTRIC CO. |
| References | |
| NUDOCS 8010220107 | |
| Download: ML19340B346 (4) | |
Text
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g UNITED STATES y-y g
NUCLEAR REGULATORY COMMISSION E
WASHINGTON, D. C. 20555 4
Docket No. 50-358 I
Mr. Earl A. Borgmann Vice President - Engineering Cincinnati Gas & Electric Company P. O. Box 960
.4 Cincinnati, Ohio 45201 i
Dear Mr. Borgmann:
SUBJECT:
STAFF POSITION ON CLADDING SWELLING AND RUPTURE MODELS FOR LOCA ANALYSES s
Enclosed is the staff position concerning the application of the.claddng 4
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, Ro ert L. T desco s
1 Assistant Director for Licensing V
l Division of Licensing 7
Enclosure:
As stated
,o cc w/ enclosure:
See next page bl iL 0
8010220l4_].
T.7 s
r Mr. Earl A. Borgmann Vice President - Engineering Cincinnati Gas & Electric Company P. O. Box 960 Cincinnati, Ohio 45201
-n cc: Troy B. Conner, Jr., Esq.
Dr. Frank F. Hooper Conner, Moore & Corber School of Natural Resources 1747 Pennsylvania Avenue, N. W.
University of Michigan Washington, D. C.
20006 Ann Arbor, Michigan 48109 Mr. William J. Moran Charles Bechhoefer, Esq., Chaiman General Counsel Atomic Safety & Licensing Board Panel Cincinnati. Gas & Electric Company U. S. Nuclear Regulatory Commission P. O. Box 960 Washington, D. C.
20555 l
Cincinnati, Ohio 45201 Mr. Glenn 0. Bright Mr. William G. Porter, Jr.
Atomic Safi:ty & Licensing Board Panel Porter, Stanley, Arthur U. S. Nuclear Regulatory Commission and Platt Washington, D. C.
20555 37 West Broad Street Columbus, Ohio 43215 Leah S. Kosik, Esq.
3454 Cornell Place Mr. Steven G. Smith, Manager Cincinnati, Ohio 45220 Engineering & Project Control Dayton Power & '.ght Company W. Peter Heile, Esq.
i P. O. Box 1247 Assistant City Solicitor Dayton, Ohio 45401 Room 214, City Hall Cincinnati, Ohio 45220 J. Robert Newlin, Counsel Dayton Power & Light Company Timothy S. Hogan, Jr., Chaiman j
P. O. Box 1247 Board of Commissioners i
Dayton, Ohio 45401 50 Market Street
~
Clemont County Mr. James D. Flynn, Manager Batavia, Ohio 45103 Licensh g Environmental Affrirs
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Cincinnati Gas & Electric Company John D. Woliver, Esq.
6 P. O. Box 960 Clement County Community Council i
Cincinnati, Ohio 45201 Box 181 l
Batavia, Ohio 45103 Mr. J. P. Fenstemaker l
Senior Vice President-0perations Mrs. Mary Reder
[
Columbus & Southern Ohio Box 270, Rt. 2 Electric Company California, Kentucky 41007 i
215 North Front Street..
Columbus, Ohio 43215 Dale D. Brodkey Assistant Attorney General David Martin, Esq.
Division of Environmental Law Office of the Attorney General Office of Attorney General
[
209 St. Clair Street 209 St. Clair Street First Floor Frankfort, Kentucky 40601 Frankfort, Kentucky 40601 i
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Mr. IEarl. A. Borgmann i
- cc: Andrew B. Dennison, Esq.
200 Main Street Batavia,n0hio-45103-Robert A. Jones', Esq.
Prosecuting Attorney.of Clermont County, Ohio 154 Main Street-Batavia, Ohio 45103 Resident Inspector /Zimer U. S. Nuclear Regulatory Comission i
P. O. Box 58 New Richmond Ohio 45157 4
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N, o
k ENCLOSURE 4
The NRC staff has been generically evaluating three materials models that are used in ECCS evaluations.
Those models predict clacding rupture temperature,' cladding burst strain, and fuel assembly ficw bicckage 7.
have (a) discussed our evaluation with vendors and other industry repre-We sentatives (Reference 1), (b) published NUREG-0530, "Claccing Swelling and Rupture Mcdels for LOCA Analysis" (Reference 2), and with 10 CFR 50.46 if the NUREG-0630 models were substituted for the present materials models in their ECCS evaluations and certain other compensatory model changes were allcwed (References 3 and 4).
Until we have completed our generic review and implemented new acceptance criteria for cladding mocels, we will require that the ECCS analyses in your FSAR be acccmpanied by supplemental calculations to be performed with the materials acdels of MUREG-0630.
j For these supplemental calculations only, we will accect other compensatory model changes tnat may not yet be approved by the NRC, but are consistent with the changes alicwed for the confirmatory I
operating reactor calculations mentioned above.
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. :1-T.X REFERENCES w.,!
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Memorandum from R. P. Denise, NRC, to R. J. Mattson, "Sc=ary Minutes ofq
.g,k..'Meetingon.CladdingRuptureTemperature,CladdingStrain,andAssemb it t
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w..?.
- Blockage,":. November 20,"1979..-.
i '.
v
- v.,q. -
3 4.0, 2.
D. A. Pcwers and R. O. Meyer, " Cladding Swelling and Rupture Mccels for LO
- . ir 6
74
. Analysd," NRC, Report NUREG-0630, April 1980.
' f, j Sf,f 3.. Letter frcm D. G. Eisenhut, NRC
- s l
.' dated Nov.em::e.4.9,;1979.M..:.l). to a l Operating Light Water Reactors, r
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,1l'[. 4. (Memorandum from'H.
R.' Cente.n,' NRC, to Ccamissioners, " Potential Deficiencies
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..a t
jd;,,g.,.n.in..ECCS Evaluation Models t Novemoer.25,'1979..
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