ML20024C753
| ML20024C753 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 01/08/1976 |
| From: | NRC |
| To: | Suhrke K BABCOCK & WILCOX CO. |
| Shared Package | |
| ML20024C754 | List: |
| References | |
| TASK-06, TASK-07, TASK-11, TASK-6, TASK-7, TASK-GB GPU-0473, GPU-473, NUDOCS 8307130223 | |
| Download: ML20024C753 (4) | |
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- ,,5 UwtTsn STATss NUCLEAR recut.ATORY COMMIS310N
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m.oeqn Mr. Kenneth E. Suhrke Manager, Licensing Babcock & Wilcox Conpany Nuclear Power Generation P. O. Box 1260 Lynchburg, Virginia 24505
Dear Mr. Suhrks:
We have ce=pleted our rev!.ew of the non-proprietary B&W topical reports 4
BAW-10062e Rev.1, "Multinode Analysis of Snall Breaks for BEU's 145-Tuel Assembly Nuclear Plants with Internals Vent Valves," and BAW-10074, ?.sv.1, "Multinode Analysis of Small Breaks for B&W's 205-Tual Assenbly Nuclear u
Plants with Internals Vent Valves," and BAW-10075, Rev. 1, "Multinode-I Analysis of Small Breaks for B&W's 177-Tuel Assembly Nuclear Plants w'ith Raised Loop Arrangment and Internals Vent Valves." A copy of cur evaluation is enciesed.
Trem our review, we conclude that the analytical nethods and==dels used in these three topical reports meet the requir eents of 13 CTR 50 Appendix K.
The results presented are acceptable fer reference in licensing actions, with cne exception for BAW-10075 cn the 177-TA plant.
This report does not contain results for the core ficed tank line break, an 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, BAW-10074, or BAW-10075 when these are referenced in individual licensing actions.
L We reques 'that B&W issue a revised version of these reports within three months of receipt of this letter to include the NRC acceptance letter.
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JAN. O 81973 Mr. xenneth E. Suhrke 3-i oc w/enci (cont'd):
Detroit Edison Company ATTN: Mr. Arthur 3. Harris Project Manager 2000 Second Avenue Detroit, Michigan 46226 i
Virginia Electric & Power Company ATTN: Mr. Stanley Ragone l
Senior Vice President l
P. C. Box 26666 Richmond, Virginia 23261 Portland General Electric Company ATTN: Mr. Joseph L. Williams Vice President
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Engineering-construction 621 Southwest Alder Street Pertland, Oregon 97205 Washington Public Power Supply System i
ATTN: Mr. J. J. Stein Managing Director P. O. Box 968 3000 George Washington Way RieMmM, Washingten 9935,2 I.
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detail reduction is made ~by lumping the two primary loops simulated in th.e 'large break model into a single loop, 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 rela'xed because of L
.the slower blowdown of the small break. These changes are:
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- 1. flormal system low pressure reactor scram is included.
L 2.
All injected ECCS water is assumed to enter the downcomer
't and is retained in the CWJT calculations. No conservative removal of this water at the end of bicwdown is used as
.tn the large break analyses.
3.
A heterogeneous inner vessel volume is =adeled for the small g.
break in CPAFT compared'to the homogeneous volumes modeled for the large break analyses.
Results obtained from the topical reports for the small breaks i:
considered for e,ach plant are s:m=arized in Table 1, and show that i..
peak clad hot spot teccaratures in any of the three plant types analyzed r.
do not approach 2200'F.
L TOPICAL P.EPORTS EV/.LL'ATION y
The small break model programs used in the analyses in the three reports reviewed here were evaluated in previous assessments for large break studies in the cases of CRAFT and THETA 1-0, and the F0.VI program was evaluated in'the review of BAW-10064(5)
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TABi.::,1 I
~ B&W PLA!!TS: SPALL l*P.EAK SPECT?.U'4 PEAK CLAD !!07 SPOT TEPPEP.ATURE 0F 177 FA
' RAISED -
2 Break Size - ft.
T45FA
. LOOP 205 FA (Pump 01 set:arge)
I3)
1196 1533 L
0.5 1178 0.3
. 1030 1090 710(2)
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I.C. II) 700(2) 710(2) 0.1 t
l 0.05 I.C.II) 710(2) 9 52) l
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700 0.04
- p.
(PompSuction) 824 O.3 I.C.III 710(2)
O.1 (CFTLine) 0.35 760 t
0.44
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1636 NOTES:
I (1) - Initial condition - not specified (2) 'Same as initial condition
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(3)-FromReference8 CFT - Core Flooding Tank s
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