ML20040A111
| ML20040A111 | |
| Person / Time | |
|---|---|
| Site: | 05000561 |
| Issue date: | 09/29/1976 |
| From: | Cox T Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML111090060 | List:
|
| References | |
| FOIA-80-515, FOIA-80-555 NUDOCS 8201200358 | |
| Download: ML20040A111 (7) | |
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4, UNITED STATES j
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-4 NUCLEAR REGULATORY COMMISSION
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SEP 2 91976 Docket No. STN 50-561 VENDOR: Babcock & Wilcox Company (G&W)
SUMMARY
OF MEETING WITH NRC STAFF ON BSAR-205, REACTOR FUELS QUESTIONS AND POSITIONS 21, 1976, members of the Nuclear Regulatory Comission On September (NRC) staff met with representatives of B&W to discuss several of the staff requests and positions sent to B&W by letter dated September 10, 1976.
B&W requested the meeting to develop a more complete understanding of the staff's intent regarding request numbers 231.30, 35, 38, 40 and 42. An attendance list is enclosed.
The discussion on request no. 231.30 centered on the meaning of
" design loads", " load limits" and " design bases" as used in request no. 231.1 and B&W's response thereto.
B&W agreed to further expand and clarify the response to 231.1 to provide better definition of, and justification for, their selected " load limit".
Staff pointed out that the justification should demonstrate that the selected load limit will preclude damage to fuel assemblies during shipping and handling.
Concerning request no. 231.35, the staff stated that the " design curve based on the above references" mentioned in B&W's response to 231.7 should be described. Justification of the design values represented by the curve must be presented, with specific, qua~ntitative reference both to the source data reports and to the B&W sponsored irradiation growth data referenced in 231.7. B&W agreed to expand their response in accordance with the staff clarification of the request.
Request no. 231.38 was described by the staff as requiring a quantitative response which was lacking in the B&W response to 231.12.
B&W agreed i
to expand the resoonse, and indicated their plan to cross-reference material alreaay available to the staff on this subject.
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Regarding r? quest no. 231.42, B&W indicated that they were at present unable to submit rate equations for the hydrolysis nf 8 C and rate 4
of loss from perforated rods.
It was agreed that they would evaluate the consequences of reactivity anomalies resulting from conservatively postulated losses of B10 from the burnable poison rods.
f Discussion of request no. 231.42 centered on the submittal date and content of the required topical report concerning seismic and LOCA response of the Mark C (17 x 17) fuel assembly. B&W pointed out that their current planned submittal date for the report is March 1977, which should be about one year prior to the submittal of the first FSAR incorporating the fuel assembly.
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The staff stated that in order to complete the BSAR-205 preliminary design review, appropriate preliminary infonnation describing the planned test objectives, procedures and acceptance criteria would need to be reviewed and approved. The current BSAR-205 review schedule calls for completion of staff review by early December 1976.
B&W agreed to consider this matter and attempt to make an appropriate submittal at some as yet unspecified time earlier than March 1977.
A4Ca 4homasH.Cox,ProjectManager Light Water Reactors Branch No. 3 Division of Project Management
Enclosure:
Attendance List cc: Babcock & Wilcox Company B. G. Shultz ATTN: Mr. Kenneth E. Suhrke Project Engineer Manager, Licensing Stone.& Webster Engineering Corp.
Nuclear Power Generation P. O. Box 2325 P. O. Box 1260 Boston, Massachusetts 02107 Lynchburg, Virginia 24505 Mr. A. H. Monteith Washington Public Power Supply System Ohio Edison Company ATTN: Mr. J. J. Stein 47 North Main Street Managing Director Akron, Ohio 44308 P. O. Box 968 3000 George Washington Way Mr. W. E. Kessler Richland, Washington 99352 Comonwealth Associates, Inc.
209 East Washington Mr. Robert Borsum Jackson, Michigan 49201 Bethesda Representative l
Babcock & Wilcox Robert J. Kafin, Esq.
Nuclear Power Generation Division 115 Maple Street
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Suite 5515, 7735 Old Georgetown Road Glen Falls, New York 12801
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1 Bethesda, Maryland 20014
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9/21/76 MEETING - NRC & B&W ATTENDANCE LIST l
NRC l
l R. Meyer j
S. Burwell M. Houston M. Tokar B. Siegel T. Cox l
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B&W C. Dideon K. Stein J. Hamilton J. Happell 4
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MEETING
SUMMARY
DISTRIBUTION Docket File NRC PDR 6
D. Ross Local PDR R. Tedesco TIC J. Knight ACRS (16)
S. Pawlicki IE(3)
I. Sihweil 0 ELD P. Check NRR Reading T. Novak l
l LWR-3 File Z. Rosztoczy B. Rusche V. Benaroya E. Case G. Lainas R. Boyd T. Ippolito R. DeYoung V. Moore V. Stello R. Vollmer D. Skovholt M. Ernst J. Stolz W. Gammill K. Kniel G. Knighton
- 0. Parr B. Youngblood D. Vassallo W. Regan R. Clark D. Bunch T. Speis J. Collins P. Collins W. Kreger l
C. Heltemes R. Ballard R. Houston M. Spangler l
S. Varga J. Stepp J. Miller L. Hulman F. Williams H. Smith R. Heineman M. Rushbrook (3)
H. Denton
'); Project Manager - T. Cox D. Muller NRC Participants W. Butler R. Meyer S. Burwell M. Houston M. Tokar B. Siegel J
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