ML20039F232
| ML20039F232 | |
| Person / Time | |
|---|---|
| Site: | 05000561 |
| Issue date: | 07/19/1976 |
| From: | Macmillan J BABCOCK & WILCOX CO. |
| To: | Boyd R Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML111090060 | List:
|
| References | |
| FOIA-80-515, FOIA-80-555 NUDOCS 8201120235 | |
| Download: ML20039F232 (11) | |
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P.O. Box 1260. Lythbu g, Va. 24505 Telephor.e: (504) 384 5111 l
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V July 19,1976 y
DOCKET SIN 50-561 4/
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48 Director of Nuclear R actor Peguh.tica Atta:
Mr. Roger S. Boyd, Direct.or
%g Divisica of Project Manag2 nent U.S. Nuclear Regulatory Commission x
Washington, D. C.
20555
\\ _1 Subj ect : B-SAR Advance Transmittal of h.endment 2
References:
(1) Letter, Kenneth E. Suhrke to J. F. Stols, }by 28, 1976,
" Schedule for Rasponding to Requeste for Information -
B-San-2J5".
t (2) Letter, Kenneth E. Suhrke to Olan D. Parr, June 25, 1976,
" Schedule for Ecsponding to Requests for Additional Infora.ation".
(3) Let te r, Jchn F. Stolz to Kenneth E. Suhrhe, May 14, 1976, uith encicsura " Request for Additional Information".
(4) Lctter, John F. Stols to Kenneth E. Suhrke, May 21, 1976, with enclosure " Request for Additional Information".
(5)
Letter, John F. Stolz to Kenneth E. Suhrke, May 27, 1976, with c.nclosure " Request for Additional Information".
(6) Letter, John F. Stolz to Kenneth E. Suhrke, June 2,1976, F
with enclosure " Request for Additional Information".
(7) Letter, Olan D. Parr to Kenneth E. Suhrke, June 8,1976, with enclosure " Request for Additional Information".
(8) Letter, J. H. MacML11an to Roger S. Boyd, June 15, 1976,
" Schedule for Transmittal of System Operating Sequence Diagrams".
(9) Letter, J. H. MacMillan to Roger S. Boyd, July 19, 1976, "B-SAR-205 - Advance Transmittal of Amendmant 2 Proprietary Responses".
Dear Mr. Boyd:
t The Bcbcock & Wilcox Company herewith submits sixteen copics of B-SAR-205 Amendnent 2 for revhw in accordance with the schedules stated in References (1) and (2).
This amendment includes responses to IIRC Round One questions included in References O) through (7 ).
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The folleeing comments apply to Amendment 2:
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..abcock & \\Vi!co.
Ifr. Roger S. Boyd July 19,1975 (1)
Responses to questions 212.71, 212.73 and part 5 of question 212.80 have been included in this amendmant in accordance with the commitment stated in the B&W 1etter of trancmittal for B-SAR Amendment 1.
(2)
Responses to questions 212.10, 212.74 and 212.75 are being formally integrated into the B-SAR with this amendment in accordance uith the commitment stated in the B&W 1etter of transmittal for B-SAR Amendment 1.
(Tnese responses were included with A=endment 1 as Attachment C).
(3) Responses to portions of questions 231.3, 231.9 and 231.21 consist of information which is proprietary to the Babcock & Wilcox Company. We are therefore including nonproprietary versions in the attached copies of nonproprietary Amendment 2.
The proprietary versions are being submitted as a separate proprietary part of Amendment 2 under separate cover (Reference 9).
(4) As stated in our response to question 000.2, we are including as Attach-ment 1 to this letter a listing of revisions to tables and drawings made by E&W and which are not referenced in the question respenses. A summary of the technical changes of significance made to B-S AR, which required changes to tables and figures, in this amendment are:
(a) revisions to the reactor coolant pump seal injection arrangement in the makeup and purification system to improve the reliability of reactor coolant pump seal iajection; (b) addition of a reactor coolant pump motor trip in the event of high motor bearing temperature to improve the reliability of pump coast-down in the event of loss of component cooling water; (c) changes to the decay heat removal system to facilitate post-LOCA long term cooling; (d) use of the incore monitoring system to provide the reactor coolant flow signal to the reactor protection system and the integrated control system in lieu of Gentile flow tubes in the reactor coolant system piping; and (e) a reduction in spent fuel storage rack spacing from 15b to 13 inches.
(5)
In accordance with an agreement reached with the NRC Staf f, B&W is in-cluding with this amendment a description of a proposed revision to the methods used for calculating mass and energy releases during LOCA. Th is description is included as Appendix 6A.
b.,o::k & Wilco::
Mr. Roger S. Boyd July 19, 1976 (6) Uith regard to item 1 in Reference (3), a meeting was held at your of fices with Messrs. T. II. Cox and G. R. Mazetis on June 9,1970, to define f.>rmat, methods, terminology and goals of the remaining B&W failure modes and effects analyses and to define an acceptable subnittal schedule for f uture analyses results. An understanding was achieved as a result of this meeting and B-SAR-205 figures depicting these analyses have been revised in this amendment to reflect. the requested changes. The submittal schedule for future analyses has been confirmed in Reference (8).
In addition, to simplify the organization of this material, all systems operating sequence diagrams and tables have been combined in a new Appendix 15C.
(7) With regard to item 8 in Reference (3), the ESU topical report describing the analysis code TRAP will be submitted to the NRC for review on August 15, 1976.
Responses to URC questions in References (3) thrcugh (7) which are not incleded in the attached are listed in Attachment 2 and will be addressed in the formal submittal to be made on July 30, 1976.
Upon receipt of the forty formal copies of Amendmeat 2, which will be submitted on July 30, 1976, the attached material may be discarded.
Very truly yours, h M.\\ \\>M.:,.. -
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John H. MacMillan Vice President Nuclear Power Generation Division J101/db Enclosures cc:
R. B. Borsum (B&W)
da!;coc!: & Wilcox STATE OF VIRGINIA)
) SS Lynchburg CITY OF LY!;CIIBURG)
John H. MacMillan, being first duly sworn, deposes, and says :
That he is the Vice President of the Nuclear Power Generation Division, THE BABCCCK & WILCOX COMPANY, the applicant herein; that he is authorized to submit the forey,oing 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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' John H. MacMillan N
Subscribed and sworn to before me, this /f day of July,19 76.
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lf w u' Lhv Notary Public in and for the St e of Virginia, City of Lynchburg.
L,u, 2#,j 9 F0 My Commission expires :
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d B-S AR-205 Amendment 2 N
July 19, 19 76 jabcocic & Wilcox STN 50-561 ATTACHMENT 1 i
Thin attachment lists revisions made to tables and figures in the B-SAR-205 by B&W and provides a summary statement concerning the reason for each change.
l CHAPTER I Figure 1.1-2 Point interface flag symbol definition revised.
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Figure 1.2-1 Equipment identifications added.
i Table 1.6-1 This table and various B-SAR sections which list topical reports and document references updated to June 15 1976.
Table 1. 7-1 Revised to add footnote concerning B-SAR sections where items are incorporated by reference.
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4 CHAPTER 3 Figure 3. 7-7 Title revised for clarification and ordinate scale corrected..
Figure 3.7-12 & 13 Detail C revised to delete box weldnent assembly which is not in B-SAR scope.
CHAPTER 4 Table 4.2-1 CR guide tube dimension corrected from " wall" to I.D.
i Table 4.2-5 BPR 0.D. and cladding thickness dimensions corrected.
Figure 4.2-6 Reactor internals vent assembly revised to be. consistent with Figure 4.2-4.
Figure 4.3-16 Units for abscissa added.
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B-SAR-205 Amendment 2 July 19, 1976 STN 50-561
_bcGCI Cs 'Nilcox ATTACil"CNT 1 (Cont'd)
CllAPIER 5 Figure 5.1-2
- 1) Revised to utilize in-core monitoring system in lieu of f
Gentile tabes to previde reactor coolant flow signal to RPS and ICS.
- 2) To be consistent with other documentation, the following mark number changes and location changes that have been made:
From To a) Pressurizer pressure recorder PR-16 PR-16-1 b) Pressurizer level recorder LR-14-2 LR-14-5 c) Inlet temperature recorder Tn-4 TR-4A2 d) An additional pressurizer pressure recorder (PR-16) has been added.
c) Pressurizer level recorder LR-14-5 noved to SRCI-X.
f)
Inlet temperature recorder TR-4A2 moved from loop B to loop A.
- 3) An additional pressurizer pressure recorder (PR-16),
which was inadvertently omitted in a previous revision, has also been added.
Figure 5.1-3 Revised to indicate pressurizer location as typical and to identify additional components and corrections. Design changed to reflect individual bottom mounted heaters.
Table 5.1-4 Pressurizer heater data revised to reflect design change to individual bottom mounted heaters.
Figure 5.1-4 Revised to identify additional components and connections.
Table 5.1-8 Table updated and clarified.
Table 5.2-4 Hydrazine specification clarified.
Table 5.2-5 Heater cover plate data deleted. Design changed to individual bottom mounted heaters.
Table 5.3-1 Table updated to reflect latest pressure distribution analysis.
Figure 5.3-2 Curves restricted to 3 pump power limitation.
Figure 5.3-3 Curves restricted to 2 pump power limitation.
Table 5.4-1 Revised to clininate various tests not required by Code.
Figure 5.4-1 Dimensions and identifications clarified.
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,ATTACllMENT 1 (Ccnt'd) l O! APTER 5 (Cont'd) i I
l Figure 5.5-7 Revised to reflect design change to individual bottom mounted i
heaters.
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Figure 5.5-8 Flow arrou in controlled bleedoff line to 'MU system corrected.
Q1 APTER 6 i
Table 6.3-4 Error in HPI fler at 200 psi corrected from 760 gpm to 700 gpm.
5 CHAPTER 7 j
Table 7.1-1 lEEE dates transferred fron References section to IEEE t
Standards section in this table.
Regulatory Guide revision i
levels added.
Table 7.2-1)
Revised in accordance with decisica to utill:e incore dp
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Table 7.2-2) type detectors for RCS flow measurement.
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i Table 7.4-1 Revised to be consistent with te::t.
Information also relocated-l to Table 7.5-1.
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i Table 7.4-2 Revised to be consistent with text.
I Figures 7.4-5, Drawings covering non-safety related heater banks deleted and 6,7,8,9 & 10 replaced with revised Figure 7.4-5 covering safety related i
heater banks.
Table 7.5-1 Revised to identify B-SAR scope and to comply with redundancy requirements of Branch Position ElCSB 23.
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Table 7.5-2 Revised BiW recommended B0P safety related display instrumen-tation to the basis of providine minimum display required for operator information.
Table 7.5-3 Revised non-safety related indicator listing to agree with B-SAR scope and revised in accordance with decision to utilire j
incore dp. type detectors for RCS flow measurement.
1 Table 7.5-4 Revised manual safety actions table to delete non-safety j
related nanual actions.
t Tabic 7. 7-2 CRDM delay time corrected from 0.80 second to 0.08 segond.
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- abcock & Yv'ilecx STN 50-561 i
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CH APTER 7 (Cont'd) i i
Figure 7.8-3 Revised to show change in detector a:Imuthal location.
Figure 7.9-4 Revised so show location of incore dp type detector assemblies.
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CHAPTER 9 i
j Figure 9.1-4 This figure depicted an option and has been replaced with a drawing of the Reactor Containment Fuel Storage Rack.
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Figure 9.1-5 Revised to 13-inch spacing.
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j Figure 9. 3-1 This figure revised to (1) delete non-safety related point j
interfaces, (2) modify piping and valve arrangement to improve the reliability of reactor coolant pump seal injection, and (3) add an additional feed point to the MU pump suction from the t
chemical addition and boron recovery system which bypasses i
the makeup tank (to reduce the response time associated with effecting a change in boric acid concentration).
Figure 9.3-5 This figure has been revised to delete non-safety related point l
interfaces and to add piping and valves from the DHRS suction l
line to the reactor building sump to provide a single means i
for post LOCA long tern cooling.
i CHAPTER 10 t
Figure 10.1-1
- 1) One qualified startup range level recorder has been added for each steam generator (LR-10A2 & LR-10B2).
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- 2) One qualified pressure recorder has been added for each steam generator (PR-12A1 & PR-12B1).
- 3) Esin steam pressure inputs to the ICS revised to be con-sistent with philosophy used on other ICS inputs.
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4)
Revised drawing to show correct AFW connections to OTSG.
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- 5) Deleted non-safety related point interfaces.
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r B-SAR-205 Amendment 2 July 19,1976
- abcock & V/ilcox sTn 50-561 ATTACHMENT 1 (Cont'd)
CHAPTER 11 Table 11.1-1 Revised to include parameters for base-loaded operation.
11.1-4 Table 11.1-5 New tables to provide coolcat activities for base-loaded 11.1-Sa operation.
Table 11.1-6 Renumbered from 11.1-5 and 11.1-6 and a minor error corrected 11.1-6(a) in coolant activities at 4-day and 30-day time steps.
CHAPTER 14_
Table 14.2-1
- 1) The induced xenon oscillation test has been deleted on the basis that it is not a safety requirement.
- 2) Discussion of core pressure drop test revised to clarify that core pressure drop will be the measurad parameter.
Table 14.1-1 Reference to OTSG circulation system tests deleted.
This non-safety related system has been deleted from the B-S AR design.
CllAPTER 15 Table 15.1-2 This table has been included in new Appendix 15C.
Table 15.1-5 This table has been included in ncw Appendix 15C.
Figure 15.1.13-1 This figure has been revised in accordance with agreements with G. R. Mazetis (6/9/76) and included in new Appendix 15C.
Figure 15.1.13-2 This figure has been revised in accordance with agreements with G. R. Mazetis (6/9/76) and-included in new Appendix 15C.
Figure 15.1.13-3 This figure has been revised in accordance with agreements with G. R. Mazetis (6/9/76) and included in new Appendix 15C.
Table 15.13-3 Table number corrected to 15.1.13-3 and revised to clarify thaE there are 2 pumps in both DHR and RBS systems.
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15-SAR-205 Amendment 2 July 19, 1976 Jac0 Cit & V!i!cc:',
STN 50-561 ATTACll:fr.NT 2 The following Round One questions will be addressed in Amendment 2 when it is submitted on July 30, 1976.
1 212.212 231.27 4
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