ML20039F172
| ML20039F172 | |
| Person / Time | |
|---|---|
| Site: | 05000561 |
| Issue date: | 01/15/1977 |
| 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 8201120113 | |
| Download: ML20039F172 (10) | |
Text
bleNDMW h Babcock &Wilcox
%r cenerma creo P.O. Box 1260, Lynchburg, Va. 24505 Telephone:(804) 384 5111 January 15, 1977 Docket STN 50-561 Office of Nuclear Reactor Regulation ATTN:
Mr. Roger S. Boyd, Director Division of Project Management U.S. Nuclear Regislatory Commission Washington, D.C.
20555
Subject:
B-SAR-205 Transmittal of Amendment 8 References (1)
Olan D. Parr to Kenneth E. Suhrke, "Round 2 Positions and Request for Info rmation,"
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 27, 1976, with attach-ment
Dear Mr. Boyd:
The Babcock 6 Nilcox Company herewith submi.ts sixty copies of l
B-SAR-205 Amendment 8 for review.
This amendment contains additional responses to the Staff positions and requests included in References (1) thcough (4).
This amendment completes B6W responses to all NRC requests for i
information in References (1) through (4) above, with the exception o f 212. 234 a nd 2 21. 5 5.
It is our intent to reply to these items, as well as the four additional requests in Reference (5), in an amendment
,sgheduled for submittal on January 31, 1977.
3 o
e 8201120113 810403 FDR FOIA MADDEN 80-515 PDR -
The Babcock & W;lecx Company / Establisned 1867
5 Babcock &Wilcox (2)
The following comments apply to Amendment 8:
(1)
B6W has recently updated its standard quality classification system to more closely identify non-safety and non-seismic equipment in accordance with Regulatory Guide 1.26.
The results are being included in Section 3.2 of B-SAR in this amendment.
All changes are of a clarifying or editorial nature.
It will be helpful to note here that B6W has substituted " Quality Class" for the previously used term
" Safety Class," and "non-seismic" has been substituted for the previously used term " Seismic Category II."
Certain i
classification changes have also been made in Table 3.2-4 which are discussed in following item 2.
(2)
Section 9.3.4.2 and Tables 3.2-4 and 9.3-5 have been revised to reflect that the chemical addition and boron r ecovery system is now considered to be non-safety related.
Previously, certain portions of this system related to the supply of borated water for plant shutdown had been classified as sa fety related.
The B-SAR-205 now requires that the BWST be qualified as the safety related source of borated water for plant shutdown and appropriate interfaces have been added in Sections 1.7.1.2, 6.3.6 and 9.3.6.6.18.
Section 9.3.4.2 and Tables 3.2-4 and 9.3-5 have also been updated to revise the classification of the degassifier and i
deborating demineralizer from C to D in accordance with the design change made in Amendment 2 to the B-SAR.
(3)
With regard to the CASBR system, the boric acid addition tank (T6 on Figure 9.3-4) has been celeted as not required, since there is adequate storage capacity in the concentrated boric acid storage tank.
(4 )
In compliance with an informal request by the Staf f, the results of the reactor head drop analysis for the WPPSS units NNP-1 and 4 which we re referenced in the cover letter to B-SAR-205 Amendmen t 7 have been summarized and included as Section 15.1.40 in the B-SAR-205.
Additional interfaces concerning this subject have also been added in Section 5.7.15.
(5)
As a result of a telephone conversation with the Staf f on January 5, 1977, the response to regnest 221.54 has been expanded to summarize the statistical methods and bases for the 0.99 flow distribution factor used in analyses.
As agreed with the Staff, additional details will be submitted during February, 1977.
r
9abcocka,Wilcox (3)
(6)
Section 5.5.1 concerning the design bases for reactor coolant pump auxiliaries has been revised for clarification.
(7)
In compliance with a request by the Staf f, Section 6.2.5 and the response to request 022.13 has been clarified to specify the standard conditions used in deriving hydrogen volumes.
(8)
In accordance with our understanding that the proposed analytical model and assumptions described in Appendix 6A are generally acceptable to the Staff, Section 6.2.1.3 and the introduction to Appendix 6A have been revised to reference Appendix 6A as the basis for calculating mass and energy release rates during postulated LOCAs for the B-SAR-205.
(9)
In compliance with an informal request by the Staff, Section 9.5.1 has been revised to include additional infor-mation concerning potentially combustible materials in the NSS scope.
(10)
In response to a request by the Staff, the definition of the factor "k" in Section 3.6.4 has been clarified.
P (11)
The reference in the response to NRC request 232.26 to a rod ejection analysis performed for the Muelheim Kaerlich Project has been found to be inaccurate.
The analysis p'er-formed on that project was actually for a rod drop accident.
The response to 232.26 has been revised to reference the analysis for a 145-FA unit with a comparable power density.
(12)
Additional typographical errors have been corrected in this amendment.
l (13)
This amendment includes additional information and clarifi-cations requested by the Staff during informal meetings and telephone conversations.
In addition, as stated in our response to NRC request 000.2, alterations by BSW to B-SAR tables and figures which are not referenced in responses to NRC questions or specifically identified by special markings l
on the revised page, are listed in Attachment 1 to this letter.
I l
l l
5
Babcock & Wilcox (4)
~
(14)
All recipients of the B-SAR-205 should note that the instruction sheet for filing Amendment 7 should be corrected to revise the reference to Figures 15B.1-1 and 15B.1-2 to 15B-11 and 12B-12, respectively.
These figures should be removed from the B-SAR.
i Very truly yours, l
lb Kenneth E. Suhrke Manager, Licensing KES/fw Enclosures cc:
R. B. Borsum (2)
U. S. Nuclear Regulatory Commission (1)
Office of Inspection and Enforcement - Region IV 611 Ryan Pla za Drive - Suite 1000 Arlington, Texas 76012 Mr. Neil Thomasson (3) 4 Attn: Loretta Long Office of Radiation Programs Environmental Protection Agency Room 647A East Tower Waterside Mall 401 M Street, S.N.
Washington, D.C. 20460 Mr. A. J. Oswald (1)
EGSG Idaho, Inc.
P. O.
Box 1625 Idaho Falls, Idaho 93401 4
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f' babcock &WilCOX 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 Generation Division, THE BABCOCK 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 i
same to be true to the best of his knowledge.
Dated:
/-dU-7 7
.2/x l
Kenneth E. Suhrke 1
Subscribe)dayof-January,1977 and sworn to before me, this 2/> L y
m.
l l3(Q,'/}j A am %wk J Notary Public in and for the State of Virginia, City of Lyn hburg My Commission expires: [d/29/977 9 '
Babcock &Wilcox Amendment 8 January 17, 1977 STN 50-561 This attachment lists revisions made by B6W to tables and figures in the B-SAR-205 which are not referenced in the B6W responses to NRC requests or identified by special markings on the revised page.
Chapter 1 3
Table 1.1-1 "Startup test program for NSS items" and related footnotes a, b, c,dment d added (inadvertently deleted in Amen 7).
" Technical Operating Specifications" and footnote e added.
Chapter 3 Table 3.7-1 CRDM damping values changed and explana-tory footnote added.
Corrected to add appropriate categorization symbols (A, B, etc.) Category G added to table.
Table 3.7 CRDM categorization changed to "G" and footnote expanded to include this category.
Chanter 5 Table 5.1-10 Revised for clarification.
l Figure 5.1-2 Sheet 2 The following corrections have been made:
TI 12-1 corrected to TE 12-1; balancing pressure line for RV1 relocated.
HIS 17-1 corrected to HIS 10-1.
- symbol deleted from HS-4A1, HS-4A2, HS-14, HS-15, HS-3, HS-4B1, HS-4B2, HS-3A, HS-3B symbol R added to TT 4B4 note 4 typo corrected Figure 5.1-2 Sheet 2 Interface flags added at RC pump.
Figure 5.5-8 Table of Interface Requirements deleted.
Classification symbols added at connections.
I Babcock &Wilcox Amendment 8 January 17, 1977 STN 50-561 cont'd.
Chapter 6 deleted to be consistent with revision Tables 6.2-1 to 6.2-26 of Section 6.2 to reference Appendix 6A.
Table number changed to 6.2-1 Table 6.2-27 Table number changed to 6.2-2 Table 6.2-28 Figure 6.2-3 deleted to be consistent with revision of Section 6.2 to reference Appendiv 6A.
The following corrections have been made:
Figure 6.3-1 Sheet 2
- symbols added to vent relief valves RVIA and RVIB.
Ir$8u 6. 3 -h?
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Chapter 9 The following corrections have been made:
Figure 9.3-1 Sheet 2 corrected valve V62 to normally open and deleted interlock to this valve.
mark number MV116 added to diaphragm valve in 1/2" line takeoff from letdown line to boron analyzer AE-13.
- symbol added to HIS-55 HIS-ISA HIS-5b HIS-33B1 "IPT 24" corrected to dPT 24.
c symbol added to HIS-ISA HIS-33B1 design condition flag 23 corrected from 160 psig to 150 psig.
(2)
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Babcock &Wilcox Anendment 8 January 17, 1977 STM 50-561 cont'd e
Chapter 9 (cont'd)
Figure 9.3-2 Changed classification of all components Sheet 2 related to boric acid addition from C to D consistent with reclassification of CA6BR system to non-safety.
Figure 9.3-3 Sheet 3 Changed classification of all components related to boric acid addition from C to D consistent with reclassification of l
CA6BR system to non-safety.
Figure 9.3-4 Degassifier and deborating demineralizer i
classif.ications corrected from C to D con-sistent vi th change made in Amendment 2.
Changed classification of all components related to boric acid addition from C to i
D consistent with reclassification of CASBR system to non-safety.
f Deleted boric acid addition tank (T6);
adequate storage capacity is available in the concentrated boric acid storage tank.
Figure 9. 3-5 Valves V6A and V6B and associated instru-mentation changed to V17A and V17B, respectively and asterisks added to HIS's.
HIS-16A and ZS-16A and HIS-168 and ZS-16B instrumentation added to valves V16A and V16B.
- symbols added to relief valves RV8A and RV8B.
Typo corrected in note 10.
Chapter 10 Figure 10.1-1 The following corrections have been made:
Sheet 2 OTSG vacuum heatup recirculation inlet connections added downstream of valves V8A and V8B ; recirculation return lines and valves added to each OTSG drain header.
- symbol added to LAL 10B.
(3)
O Babcock &Wilcox Amendment 8 January 17, 1977 STN 50-561 cont'd Chapter 15 Peak clad temperature for cases IV and Table 15.1.14-Sb V added in accordance with Amendment 7 commitment.
Footnote (a) added.
Figure 15.1.14-3a Figure number changed to 15.1.14-3 Sheet 1.
Figu re 15.1.14-3b Figure number changed to 15.1.14-3 Sheet 2.
Figure 15.1.14-3c Figure number changed to 15.1.14-3 Sheet 3.
Figure 15.1.14-3d Figure number changed to 15.1.14-3 Sheet 4 Figure 15.1.14-e Data added in accordance with commitment made in Amendment 7.
Figure number changed to 15.1.14 Sheet 5.
Figure 15.1.14-4 Figure number changed to 15.1.14-4a.
Figure 15.1.14-4 Figure number changed to 15.1.14-4b and (cont'd) title clarified.
Figure 15.1.14-5 Figure number changed to 15.1.14-4c and title clarified.
Figure 15.1.14-6a, -
deleted as redundant with 15.1.14-3.
6b Figure 15.1.24-1
" Relief valve" corrected to " Safety valve'.'
j (4)
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-NRC DISTRIBUTION roR PART 50 DOCKET MATERIAL
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24505 1-15-77
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