ML20039F143
| ML20039F143 | |
| Person / Time | |
|---|---|
| Site: | 05000561 |
| Issue date: | 05/09/1977 |
| From: | Taylor J BABCOCK & WILCOX CO. |
| To: | Boyd R Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML111090060 | List:
|
| References | |
| FOIA-80-515, FOIA-80-555 NUDOCS 8201120062 | |
| Download: ML20039F143 (5) | |
Text
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Babcock &Wilcox
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Po.e, cene, anon c,ou, P.O. Box 1260, Lynchburg, Va. 24505 Telephone: (PO4) 384-5111 May 9, 1977
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'dM Office of Nuclear Reactor Regulation
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Mr. Roger S. Boyd, Director r-A(hY,"3yh'j?j,{,,
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d Division of Project Management U. S. Nuclear Regulatory Commission 4
Washington, D.C.
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Subject:
B-SAR-205 g
s Transmittal of Amendment 14 lj..
Reference (1)
Letter, J. H. Taylor to Olan D. Parr, " Requests for Withholding Information from Public Disclosure -
Portions of Amendments 2 and 6 - B-SAR-205,"
Ma y 2, 1977.
(2)
Letter, J. H. MacMillan to R. S. Boyd, " Transmittal of Amendment 2 - Proprietary Portion", July 19, 1976.
Dear Mr. Boyd:
The Babcock 4 Wilcox Company herewith submits sixty copies of B-SAR-205 Amendment 14 for review.
The amendment includes the following specific items:
(1)
In accordance with reference (1), all proprietary figures submitted with reference (2) in response to NRC request 231.9 have been made non-proprietary and are being included in the B-SAR with this amend-ment as figures 231.9-1 through 231.9-13.
In addition, the non-proprietary responses to NRC requests 231.9 and 231.21 have been revised in accordance with our review of the proprietary portions of Amendments 2 and 6, as discussed in i
reference (1).
(2)
In compliance with an informal reques t by the Staf f, Section 9.3.6.6.18 has been revised to include the basis for establishing the minimum BNST inventory required by the NSSS.
t 0201120062 810403 PDR FOIA MADDEN 00-515 PDR The Babcock & Waccx Cornpany / Estabbshed 1867
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. (3)
In accordance with a request by the Staff, systems operating sequence diagrams 15.13-1 through 15C.13-4 have been revised to include steam line isolation and secondary safety valve operation, as applicable.
(4)
Section 3.7.2.1 has been revised to clarify that the s
analytical model described in figures 3.7-8 and 3.7-23 is typical only (since pressurizer arrangment may vary between plants), and to reference the location of arrangement interfaces.
(5)
In accordance with an informal request by the Staff, the resoonse to NRC request 212.216 has been revised to arovide justification for the maximum expected leai rate from postulated sudden failure of a pump shaf t seal.
In addition, Section 6.3.2.11 has been revised to state a very conservative maximum expected leakage rate of 30 gpm.
(6)
At the request of the Staff, Table 6.3-7 has been updated to include all valves whose position is administrative 1y controlled i.e., that have breakers locked out or manual valves locked closed.
The table has been revised to identify such valves with a ster isks (*).
(7)
In accordance with a request by the Staff, Table 5.2-11 has been amended to include a footnote to provide information similar to that in Table 3.9-5 for check valves which are not in the B-SAR scope of design responsbility.
(8)
At the request of the Staff, the response to NRC request 212.157 has been revised to provide a more complete justification for the B-SAR statement in Section 6.3 that one makeup pump is sufficient to prevent core damage for postulated LOCA break sizes 2
in the range of up to approximately 0.1 f t in the core flood tank line.
(9)
Section 3.2.2 has been corrected to reference Appen-dix B to 10CFR50 instead of Appendix A.
(10)
Table 1.1-1 has been corrected to indicate that B6W has design responsibility for remotely operated valves in the makeup and purification system.
Table 3.2-4 has also been corrected to eliminate the list-ing of the boric acid addition tank.
It should be noted that this tank was eliminated from the B-SAR in Amendment 8.
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(11)
Section 9.2-2, item 4 has been corrected to state that component cooling water shall be provided at no greater than 120F during normal j
operation.
I Very truly you g q,
9th
- /(4 A
, James H. Taylor Manager, Licensing 2
JHT/fw Enclosures 3
cc:
R. B. Borsum (B6W - Bethesda) (2)
U. S. Nuclear Regulatory Commission (1)
Office of Inspection and Enforcement - Region IV 611 Ryan Plaza Drive - Suite 1000 Arlington, Texas 76012 i
Mr. Neil Thomasson (3)
Attn:
Loretta Long Office of Radiation Programs Environmental Protection Agency Room 647A East Tower Waterside Mall 401 M Street, S.W.
Washington, D.C.
20460 Mr. A. J. Oswa ld (1)
EG6G Idaho, Inc.
P. O. Box Box 1625 Idaho Falls, Idaho S3401 1
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- Babcock &Wilcox STATE OF VIRGINIA)
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SS. Lynchburg CITY OF LYNCHBURG)
James H. Taylor, being first duly sworn, deposes, and says:
That he is the Manager of Licensing of the Nuclear Power Generation Division, THE BABC0CK 6 WILCOX COMPANY, the applicant herein; that he is authorized to submit the fore-going on behalf of said applicant; that he has read the foregoing and knows the contents hereof; and believes the same to be true to the best of his knowledge.
Dated:
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JAMESH.TA[0R Subscrib d and sworn to before me, this 9 day of May, 1977.
% /]7 Nd Notary Public in and for the State of" Virginia, City of Lynchburg My Commission expires
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NRC DISTRIBUTION poa PART 50 DOCKET MATERIA'L
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J. H. Taylor 05-02-77 ENCLOSuRh sish,ng of " B6-205 n't. M ltr. ar.d J. ii. MacMillan 07-19-77 ltr-...Trans sions.and $hons to b rewd....
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Notorized 05-09-77....
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