ML20039F166
| ML20039F166 | |
| Person / Time | |
|---|---|
| Site: | 05000561 |
| Issue date: | 02/01/1977 |
| From: | Suhrke K BABCOCK & WILCOX CO. |
| To: | Boyd R Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML111090060 | List:
|
| References | |
| FOIA-80-515, FOIA-80-555 NUDOCS 8201120107 | |
| Download: ML20039F166 (5) | |
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Babcock &Wilcox eo e,cenerationoroun P.O. Box 1260, Lynchburg, Va. 24505 Telephone: (804) 384-5111 February 1, 1977
...a Docket STN 50-561
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Office of Nuclear Reactor Regulation
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ATTN:
Mr. Roger S. Boyd, Director
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Division of Ploject Management U.S. Nuclear Regulatory Commission "f,,
US Washington, D.C.
20555 4.
Subject:
B-SAR-205 Transmittal of Amendment 9
References:
(1)
Olan D.
Parr to Kenneth E. Suhrke, "Round 2 Positions and Request for Information," October 1, 1976, with attachment (2)
Olan D.
Parr to Kenneth E. Suhrke, "Round 2 Positions and Request for Information," October 18, 1976, with attachment (3)
Olan D. Parr to Kenneth E. Suhrke, "Round 2 Positions and Request for Information," October 22, 1976, with attachment (4)
Olan D. Parr to Kenneth E. Suhrke, "Round 2 Positions and Request for Information," November 5, 1976, with attachment (5)
Olan D. Parr to Kenneth E. Suhrke,
" Request for Information," December 17, 1976, with attachment
Dear Mr. Boyd:
The Babcock and Wilcox Company herewith submits sixty copies of B-SAR-205 Amendment 9 for review.
This amendment completes B6W responses to NRC requests for information con-tained in References (1) through (5) above.
Specifically, this amendnent includes responses to NRC requests 212.234, 221.55, 222.18, 222.19, 222.20 and 222.21, which were noted as l
still outstanding in the transmittal letter for Amendment.8.
l 8201120107 810403
$L1.9 PDR FOIA MADDEN 80-515 PDR The Babcock & Wilcox Company / Established IE67 i
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Babcock & Wilcox Mr. Roger S. Boyd Page 2 February 1, 1977 The following comments apply to Amendment 9:
1)
In response to a request by the Staff to clarify Table 1.7-1, B6W has deleted the column " Interface Table" and provided additional footnotes.
Those referencing the B-SAR-205 should refer to the column titled " Interface Figure" for drawings showing point interfaces and related references, and to the column titled " Interface Section" for functional interface information or references thereto.
2)
The statement which referenced NUREG 0103 as the basis for B-SAR-205 technical specifications was inadvertently deleted in Amendment 8 and is being re-included in the B-SAR-205 with this amendment.
3)
Table 1.6-1 (B6W Topical Reports) has been updated in this amendment.
Changes are identified by amendment markings in the margin of the table.
4)
Tables 15.1.8-3 and 15.1.14-2, which list mass and energy release data for postulated feedwater and steam line breaks, have been revised to provide shorter time increments over the period 0-2 seconds so that the data may be used for subcompartment differential pressure analysis by applicants.
The data in Table 15.1.14-2 have also been revised to remove liquid entrainment.
This satisfies the commitment noted in Section 6.2.1.2.2 of the B-SAR-205.
5)
Section 15.1.19.2.2 has been revised to reflect current analysis.
The response to request 212.212 has been revised accordingly.
6)
At the request of the Staff, Table 3.9-8 has been revised to include the length of an orifice rod.
7)
Section 5.4.1.6 has been revised to correctly reference the FSAR as the schedule time when the detailed material surveillance program will be submitted for Staff review.
8)
Section 5.7.5 has been revised to include more definitive interface requirements with regard to postulated pipe l
ruptures.
9)
The commitment in Section 7.1.2.2 regarding the submittal of qualification test results for system isolation devices has been modified from the second quarter of 1977 to six months prior to submittal of the FSAR by the first applicant utilizing the described isolation methods.
' Babcock & Wikox Mr. Roger S. Boyd Page 3 February ~1, 1977 10)
Chapter 11 has been generally updated and clarified.
In particular, appropriate reference has been made to NUREG-0017 and Tables 11.1-1, 11.1-10 and 11.1-11 have been updated.
11)
To support the selection of the maximum power level in Section 15.1.14 as the basis for the steam line break accident analysis performed for the B-SAR-205, Section 15.1.14.2.2 has been amended to note that steam generator water inventory for OTSG units is greatest at high power level and decreases at lower power levels.
12)
Figure 6.3-1 has been revised to include a table of notes inadvertently deleted in Amendment 8.
All other changes in this amendment are identified by amendment markings in the margin or are noted in this letter of transmittal.
Very truly yours, Kenneth E. Suhrke Manager, Licensing KES:dsf Enclosures cc:
R. B. Borsum (2)
U.S. Nuclear Regulatory Commission (1)
Office of Inspection and Enforcement - Region IV 611 Ryan Plaza Drive - Suite 1000 Arlington, Texas 76012 Mr. Neil Thomasson (3)
Attn: Loretta Long Office of Radiation Programs Environmental Protection Agency Room 647A East Tower Waterside Mall i
401 M Street, S.W.
Washington, D.C.
20460 l
Mr. A. J. Oswald (1) l EG6G Idaho, Inc.
P.O. Box 1625 Idaho Falls, Idaho 83401 I
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mhbcock & Wilcox s
._o STATE OF VIRGINIA)
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Lynchburg CITY OF LYNCHBURG)
Kenneth E. Suhrke, being first duly sworn, deposes, and says:
That he is the Manager of Licensing of the Nuclear Power i
Generation Division, THE BABCOCK 6 WILCOX COMPANY, the i
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.
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Dated:
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l' Kenneth E. Suhrke s
Subscribed and sworn to before me, this M day of February, 1977.
O,sidJ Ma Not[ry Public in and for the State of Virginia, City of Lynchburg My Commission expires:
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NRC DISTRIBUTION roR PART 50 DOCKET MATERIAL TO: Mr R S Boyd.
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Amdt #9 to the PSAR:. _ Consisting Of revised
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