ML20039E136
| ML20039E136 | |
| Person / Time | |
|---|---|
| Site: | 05000561 |
| Issue date: | 06/08/1976 |
| From: | Parr O Office of Nuclear Reactor Regulation |
| To: | Shurke K BABCOCK & WILCOX CO. |
| Shared Package | |
| ML111090060 | List:
|
| References | |
| FOIA-80-515, FOIA-80-555 NUDOCS 8201060570 | |
| Download: ML20039E136 (3) | |
Text
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s JUN c 1976 Distribution:
W Gammill, DSE Docket File W Mcdonald, MIPC
!!RC/PDR R Maccary, SS i
L/PDR R Tedesco, SS LWR-3 File D Ross, SS R DeYoung OELD i
Docket lio. STN 50-561 F Williams.
IE (7) 0 Parr ~~' %
ACRS (16).
Cabcock & tiilcox Company T Cox N T.Novak ATTl: lir. Kenneth E. Suhrke 11 Rushbrook E Chakoff flanager, Licensing R Denton, DSE R Martin Nuclear Power Generation R Heineman, SS P. O. Box 1260 V Moore, DSE bec:
i Lynchbrrg, Virginia 24505 R Vollmer, DSE J Buchanan, NSIC M Ernst, DSE T Abernathy, TIC I
Gentlemen:
As a result of our continuing review of the Babcock & lillcox Standard i
Safety Analysis Report. BSAR-205, we find that we need additional in-fornation to complete our evaluation. The specific infonaation required j
is listed in Enclosure 1.
To maintain our licensing review schedule for your SSAR, we need your responses to the Enclosure 1 items by July 23, 1976.
If you cannot meet these requirements, please infonn us within seven days after receipt of this letter of the dates you plan to meet so that we uay revise our schedule accordingly.
Please contact us if you have any questions about the information requested.
Sincerely.
Original Signed by*
O. D. Parr Olan D. Parr, Chief Light Water Reactors Branch flo. 3 Division of Project Management
Enclosure:
Request for Additional Information cc:
See next page s
LWR-3 LWR-1 otr TCox 4 OParr 76
$/_p R ]75070g%4o3 t
i Babcock '& Wilcox Company JUN 8 1976 I
cc: Washington Public Power Supply System ATTN:
Mr. J. J. Stein Managing Director P. O. Box 968 3000 George Washington Way l
Richland, Washington 99352 i
Mr. Robert Borsum l
Bethesda Representative i
Babcock & Wilcox Company Nuclear Power Generation Division i
l Suite 5515, 7735 Old Georgetown Road Bethesda, Maryland 20014
)
j B. G. Shultz Project Engineer Stone & Webster Engineering Corp.
l P. O. Box 2325 Boston, Massachusetts 02107
)
f Mr. A. H. Monteith Ohio Edison Company 47 North Main Street
-Akron, Ohio 44308 Mr. W. E. Kessler Commoriwealth Associates, Inc.
209 East Washington Jackson, Michigan 49201 t
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JUN 8 1976 ENCLOSURE 1 REQUEST FOR ADDITIONAL INFORMATION BSAR-205 DOCKET NO:
STN 50-561
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i 110.0 HECHANICAL ENGINEERING i
11 0. 34 In Section 3.9.1.5 the statement is made that in the analysis l
(3.9.1.5) of the reactor coolant system, the RC loop piping and major components are idealized by lumped masses connected by massless elements and that these massless elements and the associated degrees of freedom are appropriately selected so that the responses of all the internal components can be properly represented.
Provide the criteria and procedures that will be used for. determin-*
ing the adequacy of a given structural model.
110.35 In Section 3.9.1.5, the statement is mace that if the linearity
,i (3.9.1.5) stipulation in a computer program is not satisfied, the dynamic l
response of the major components will be calculated using i
nonlinear discrete macs models. Provide the criteria and/or limits for determining that the linearity stipulation is not satisfied.
Indicate if nonlinearity includes both material l
[
and geometric nonlinearity.
110.36 The information on computer programs which is presented in (3.9.1)
Sections 3.9.1.5, 3.9.1.6, 3.9.1.7 and Tables 4.1-3 and 5.2-9 3
(4.1) is not completely acceptable.
Identify those programs which, I
(5.2) in your opinion, satisfy Paragraph II.2.a of NRC Standard Review Plan, Section 3.9.1.
For the remainder of the programs, provide a summary comparison of the results as outlined in paragraph II.2 of NRC Standard Review Plan, Section 3.9.1.
The mere fact that a program is in the public domain does not necessarily mean that the program has been properly verified and does not satisfy Paragraph II.2.a of Standard Review Plan 3.9.1.
l 110.37 In instances where non-linear analysis techniques are used to (3.9.1) demonstrate acceptabic dynamic response characteristics or (5.2) structurel integrity, provide your commitment to demonstrate that the nonlinear analysis technique gives results consistent with the material characteristics (stress-strain *, load-deficction).
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