ML20024C604
| ML20024C604 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 01/08/1976 |
| From: | NRC |
| To: | Suhrke K BABCOCK & WILCOX CO. |
| Shared Package | |
| ML20024C601 | List: |
| References | |
| TASK-07, TASK-7, TASK-GB GPU-2018, NUDOCS 8307120864 | |
| Download: ML20024C604 (4) | |
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UNITED s7A7ts' j
NUCLEAR REGULATORY COMMl333CN
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8 WASHINcToN o. c. 20358
%****4'j JAN. O a 1975 4
Mr. Xenneth E. Suhrke Hanager, Licensing Babcock & Wilcox cenpany
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Nuclear Pcwer Genera. ion P. O. Box 1260 Lynchburg, Virginia 24505
Dear Mr. Suhrke:
We have completed our review of the non-proprietary 35W topical reports BAW-10062. Rev. 1, ":fultimede A=alysis of Sna11 Breaks for 35W's 145-Tuel Assenbly Nuclear Pla=ts with Internals Vent Valves," and BAW-10074, ?.ev.1, i.
"Hultinode Analysis of Small Breaks for 35W's 205-Tuel Assachly Ziuclear Plants with Internals Vent Valves," and BAW-10075, Rev.1 '".kitinede
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Analysis of Sna11 Besaks for S&W's 177-Tuel Assembif Nuclear Plants with Raised Lcop Arrange =ent and Internals Vent Valves." A copy of our evaluation is enciesed.
From our review, we cc.clude that the analytical nothods and =edels used in these three tcpical reports meet the rete. ire =ents of 10 CTR 50 Appendix K.
The results presented are acceptable f== referense in licensing acticas, wi.h one exception f== 3AW-10075 en tha 177-TA plant.
This repr.rt does not contain resul.s f=r the c=re ficed tank lisa break, as do the other reports, but indicates that these results are furnished in the plants' safety analysis reports.
We do not intend to repeat our review of BAW-10062, 3AW-10074, or BAW-10075 when these are referenced in individual licensing actions.
We request that 38W issue a revised version of these repcres within three months of receipt of this letter to include the NRC acceptance letter.
L.
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JAN. 0 81978 Mr. Xenneth I. Suhrke.
es w/enci (c=nt'd):
Detroit Edison C...spasy A2TE: Mr. Arthur 3. Harris N ect Manager 2000 Second Avenue Detroit, Michigan 44226 Virginia Electric & Power Company AM: Mr. Stanley Ragone Senior Vice President P. O. Box 26666 Richmond, Virgisia 23261 Portland General Electric Company AM: Mr. Joseph L. W""==
Vice President Engineering-C=r.struction 621 Southwest Alder Street Portland, Cregon 97205 Washington Publi: Power Supply Syste ATTN: Mr. J. J. Stein Managing Director
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P. O. Box 968 3000 George Washington Way RieMmi, Washington 9935,2 m
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M.08:G7d detail reduction is made by lumping the two primary loops siculated in the large break model inco a single Icop, and by lumping the reactor inner vessel regions of core, core bypass, upper plenum, and upper head into
..a single volume. In addition to the nodal reduction, some large break analysis assumptions imposed for conservatism can be relixed because of
.the slower blowdown of the small break. These changes are:
- 1. normal system low pressure reactor n 'm is included.
2.
All injected ECCS water is assumed to enter the downcomer and is retained in the CRAFT calculations. No conservative removal of this water at the end of bicwdown is used as l
in the lane break analyses.
3.
A heterogeneous inner vessel volume is modeled for t$a small break in CRAr*T coa: pared to the homoganecus volu=es modeled for the large break analyses.
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Results obtained from the topical reports for t$e small breaks cor.sidered for e,ach plant are su=arized in Table 1, and show that peak clad hot spot tar:heratures in any of the three plant types analy:ed do not approach 2200*F.
TOPICAL REPORTS EYt.!.L'ATIO.*!
The small break model programs used in the anaiyses in the three reports reviewed here were evaluated in previous assessments for large break studies in the cases of CRAFT ar.d THETAl-8, and the FON1 program was evaluated in the review of SAW-10064(5)
Appitcations 89 e
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TABLE.1
- OtM PLN!TS: 57'JLL ! P.EAK $?ECTEL"1 PEAR, CLAD HOT SPOT TE'PENTURE "F
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177 FA 2
RAISED Break Site - ft -
145 FA LOOP 205 FA (Pump Otscnarge)
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0.5 1196 1533 1178 0.3 1030 1090 710(2)
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0.1 I.C. (I) 700(2) 710(2)
I.,C. II )
710(2) 0.05 II) 0.04
- 700
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(PumpSuction)
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0.3 824 I.C. II) 710(2)
O.1 (CFTLine) 0.35 760 0.44-I-
1636 NOTES:
(1) - Initial condition - not specified (2) 'Same as initial condition (3)-FromReferenes8 CFT - Core Flooding Tank e
i D23385
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