ML20056H081
| ML20056H081 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 08/30/1993 |
| From: | Rehn D DUKE POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9309080198 | |
| Download: ML20056H081 (2) | |
Text
ll l
Duke hmer Compa?
D L Ron Catawba kdear Generanon [xportment nce 14estdent 4DJ ConcordRoad (Sc3gyj.3395 orf,ce brL SC2K45 (Say,gyj.34 5ya, l
DUKEPOWER August 30, 1993 l
i U. S. Nuclear Regulatory Commission ATTN: Document Control Desk i
Washington, DC 20555
Subject:
Catawba Nuclear Station Docke. 'los. 50-413/50-414 l
i 10 CT R i ~ 46 Reporting for ECCS Evaluation Model Changes I
10 CFR 50.46(a)(3)(ii) requires reporting of changes to or errors in ECCS evaluation model (EM), or in the application of the EM, which affect the LOCA peak clad temperature (PCT). The attachment contains the information for small break LOCA (SBLOCA), large break LOCA (LBLOCA) for Westinghouse OFA fuel, and LBLOCA for Mark-BW fuel.
Any questions concerning this submittal may be directed to Kay Nicholson at (803) 831-3237.
Very truly yours, 1
D. L. Rehn KEN /5046.93 Attachment xc:
S. D. Ebneter Regional Administrator, Region Il R. E. Martin, ONRR R. J. Freudenberger Senior Resident Inspector I
Q 9309080198 930830 Sk PDR ADDCK 05000413 0[
p'{
H PDR IV4tkT (f. 4)C)* )$ /WWF v
,s
-l Attachment j
SBLOCA Am1vses The 1985 Westinghouse CCCS EM analyses apply to all fuel types in the Catawba cores. The analyses shown in the Catawba FSAR are for a case in which a 1304 F PCT is calculated. As l
shown in Table 15-39, EM changes previously reported to the NRC could result in an increase in
)
this value by up to 136'F. Per Reference 1, there are no additiont.1 changes to report. Therefore.
-l the resulting Catawba PCF remains 1440 F.
j l
1 LBLOCA Annivses for Wectinohnuse OFA Fuel The 1981 Westinghouse ECCS EM with B ASH analyses apply to the Westinghouse OFA fuel m
~
the Catawba cores. The analyses shown in the Catawba FSAR are for a case in which a 1704 F i
PCT is calculated. As shown in Table 15-35, EM changes previously reported to the NRC could result in an increase in this value by up to 238'F for Unit I and 250*F for Unit 2. Per Reference 1, there are two additional changes to report. First, conection of the metal type (stainless steel vs.
I carbon steel clad with stainless steel) in the structural heat transfer model in the WREFLOOD-INTERIM computer code is estimated to result in a 25*F credit. Second, correction of a 65 psi 3
underestimation of the fuel md intemal pressure is estimated to result in a 2 F penalty. Therefore.
l the resulting Catawba LBLOCA PCT for Westinghouse OFA is 1704 + 238 - 25 + 2 = 1919 F for Unit I and 1704 + 250 - 25 + 2 = 1931*F for Unit 2.
l I
1 LBLOCA Analyses for BWFC Mark-BW Fuel The BWFC analyses described in topical report BAW-10174 apply to the BWFC Mark-BW fuel in the Catawba cores. The analyses shown in the Catawba FS AR are for a case in which a 1945*F PCT is calculated, as shown in Table 15-52. Per Reference 2, there is one additional change to report. Consideration of seismically induced steam generator tube crushing occuning coincident with a LBLOCA is conservatively deemed to result in additional plugging of no more than 5% of the tubes. BWFC estimates a penalty of no more than 40 F for this effect. Therefore, the resulting Catawba LBLOCA PCT for BWFC Mark-BW fuel is 1945 + 40 = 1985"F.
l l
l h
. --.