ML20039F229
| ML20039F229 | |
| Person / Time | |
|---|---|
| Site: | 05000561 |
| Issue date: | 07/30/1976 |
| 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 8201120228 | |
| Download: ML20039F229 (10) | |
Text
{{#Wiki_filter:.. 53abcock & Wilcox w ceneren ce-p P.O. Bot 1260. Lynchburg, Va. 24505 - Telephone: (804) 384-5111 July 30,1976 DOCKET STN 50-561 3
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Director of Nuclear Reactor Regulation Atta: Mr. Roger S. Boyd, Director h Division of Project Managenent w. i U.S. Nuclear Regulatory Commission J Washington, D. C. 20555 [,
Subject:
B-SAR Transmittal of Amendment 2 References : (1) Letter, Kenneth E. Suhrke to J. F. Stolz, May 28, 1976, " Schedule for Responding to Requests for Information - B-S AR-205". (2) Letter, Kenneth E. Suhrke to Olan D. Parr, June 25, 1976, i " Schedule for Responding to Requests for Additional Information". (3) Letter, John F. Stolz to Kenneth Suhrke, May 14, 1976, with enclosure " Request for Additional Information". (4) Letter, John F. Stolz 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 enclosure " Request for Additional Information". (6) Letter, John F. Stolz to Kenneth E. Suhrke, June 2,1976, 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. MacMillan 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 Amendment 2 Proprietary Responses". (10) Letter, J. H. MacMillan to Roger S. Boyd, July 19, 1976, "B-SAR-205 - Advance Transmittal of Amendment 2". l
Dear Mr. Boyd:
i The Babcock & Wilcox Company herewith submits forty copies of B-SAR-205 Amendment 2 for review in accordance with the schedules stated in References (1) and (2). This amendment includes responses to NRC Round One questions included in References (3) through (7). The following coc=ents apply to Amendment 2: .p 8201120228 810403 PDR FOIA MADDEN 80-515 PDR j The Babcock & Wilcox Company / Established 1867
fabcock &Wilcox 2-July 30,1976 Mr. Roger S. Boyd (1) Responses to questions 212.71, 212.73 and part 5 of question 212.80 have been included in this amendment in accordance with the commitment stated in the B&W 1etter of transmittal 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 with the commitment stated in the B&W letter of transmittal for B-SAR Amendment 1. (These responses were included with Amendment 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 have been sub-mitted as a separate proprietary part of Amendment 2 under separate cover (Reference 9). (4) As stated in our response to q testion 000.2, we are including as Attach-ment 1 to this letter a listing of revisions to tables and drawings made by B&W and which are not referenced in the question responses. A su= mary of the technical changes of significance made to B-SAR 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 injection; (b) addition of a reactor coolant pu=p 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 1535 to 13 inches. (5) In accordance with an agreement reached with the NRC Staff, B&W is in-cluding with this amendeent a description of a proposed revision to the l l methods used for calculating mass and energy releases during LOCA. This i description is included as Appendix 6A. t 6 1
h Babcock 8.Wilcox \\ Mr. Roger S. Boyd July 30, 1976 (6) With regard to item 1 in Reference (3), a meeting was held at your offices with Messrs. T. H. Cox and G. R. Mazetis on June 9,1976, to define format, methods, terminology and goals of the remaining B&W failure modes and effects analyses and to define an acceptable submittal schedule for future 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 i for future analyses has been confirmed in Paference (8). In addition, to t simplify the organization of this material, all systems operating sequence diagrams and tabics have been combined in a new Appendix 15C. (7) With regard to item 8 in Reference (3), the B&W topical report describing the analysis code TRAP will be submitted to the NRC for review on August 15, 1976. (8) During the interim between Amendment 1 and Amendment 2 t > the B-SAR-205, the reorganization within the Nuclear Regulatory Commission has resulted in changes to the question nu::ber prefixes used by the various NRC review organizations. In accordanc.e with the desire of the NRC not to re:1 umber past questions and still maintain responses to questions originating in each review branch in a single location, we are herewith providing special index tabs and instructions for refiling existing questions / responses. (9) Responses to Round One questions 212.212 and 231.27, which were not in-cluded in the advance transmittal of this amendment on July 19, 1976 (Reference 10), have been included with this transnittal. Very truly yours, b John H. MacMillan Vice President Nuclear Power Generation Division JHM/dl Enclorures cc: R. B. Borsum (B&W) cc: U.S. Nuclear Regulatory Commission Office of Inspection and Enforcement - Region IV 611 Ryan Plaza Drive - Suite 1000 Arlington, Texas 76012 i
Babcock &Wilcox I i STATE OF VIRGINIA) t ) SS. Lynchburg CITY OF LYNCHBURG) f Russell M. Ball, being first duly sworn, deposes, and says: That he is I the Senior Technical Consultant of the Nuclear Pouer Generation Division, THE BABC0CK & WILCOX COMPANY, the applicant here19; that he is authorized ?:o submit the foregoing on behalf of said applicant; that he has read the foryoing and knows the contents hereof; and believes the same to be true to the best of l his knowledge. I DATED: ' i9 lim k N i i b.. Russell M. Ball r i Subscribg and sworn to before me, this 1 9 day of July, 1976. l t 44t@ w / i y 6 Notary Public in and for the State of Virginia, City of Lynchburg. My Comission expires: //-4f-72 f i i i i 5
B-SAR-205 Amendment 2 July 30,1976 Babcock & Wilcox STN 50-561 ATTACHME?rr 1 This 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. CHAPTER 1 Figure 1.1-2 Point interface flag symbol definition revised. Figure 1.2-1 Equipment identifications added. 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. CHAPTER 3 Figure 3.7-7 Title revised for clarification and ordinate scale corrected. Figure 3.7-12 & 13 Detail C reviced to delete box weldment assembly which is not in B-SAR scope. 9 CHAPTER 4 Table 4.2-1 CR guide tube dimension corrected from " wall" to I.D. Table 4.2-5 BPR 0.D. and cladding thickness dimensions corrected. Figure 4.2-6 Reactor internals vent assecbly revised to be consistent with Fir,ure 4.2-4. Figure 4.3-16 Units for abscissa cdded. \\ i t l I l L- - -----
B-SAR-205 .Amendrent 2 July 30,1976 STN 50-561 Babcock & \\Vilcox ATTACIDfENT 1 (Cont'd) CHAPTER S Figure 5.1-2
- 1) Revised to utilize in-core monitoring system in lieu of Gentile tubes to p ovide 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 TR-4 TR-4A2 d) An additional pressurizer pressure recorder (PR-16) has been added. I e) Pressurizer level reco'rder LR-14-5 moved 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. r 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. l 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. 6 Table 5.2-5 Heater cover plate data deleted. Design changed to individual bottom mounted heaters. Table 5.3-1 Tabic updated to reficce latest pressure distribution analysis. Figure 5.3-2 Curves restricted to 3 pump power limitation. l I Figure 5.3-3 Curves restricted to 2 pump power limitation. t Table 5.4-1 Revised to clininate various tests not required by Code. Figure 5.4-1 Dimensions and identifications clarified. I t
5-SAK-ZU3 . Amendment 2 July 30,1976 su 50-561 Babcock & Wilcox f .TTACHEIT 1 (Cont'd) OIAPTER 5 (Cont'd) Figure 5.5-7 ' Revised to reflect design change to individual bottom mounted heaters. Figure 5.5-8 Flow arrow in controlled bleedoff line to MU system corrected. CHAPTER 6 Table 6.3 Error in HPI flow at 200 psi corrected from 760 gym to 700 gpm. CHAPTER 7 Table 7.1-1 IEEE dates transferred frcm References section to IEEE Standards section in this table. Regulatory Guide revision levels added. Table 7.2-1) Revised in accordance with decision to utilize incore dp Table 7.2-2) type detectors for RCS flow ceasurement. Table 7.4-1 Revised to be consistent with text. Information also relocated to Table 7.5-1. Table 7.4-2 Revised to be consistent with text. 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 heater banks. Table 7.5-1 Revised to identify B-SAR scope 4 '4 to comply with redundancy requirements of Branch Position itCSB 23. Table 7.5-2 Revised BSN reco== ended BOP safety related display instrumen-tation to the basis of providing minimum display required for operator infor=ation. Table 7.5-3 Revised non-safety related indicator listing to agree with B-SAR scope and revised in accordance with decision.to utili::e incore dp type detectors for RCS flow measurement. Table 7.5-4 Revised manual safety actions table to delete non-safety related manual actions. Table 7.7-2 CRDM delay time corrected from 0.80 second to 0.08 second.
~ B-SAR-205 Amendment 2 July 30,1976 Babcock & Wilcox ~ su 50-561 ATTACIUCT 1 (Cont'd) GAPTER 7 (Cont'd) Figure 7.8-3 Revised to show change in detector azimuthal location. Figure 7.8-4 Revised to show location of incore dp type detector assemblies. CHAPTER 9 Figure 9.1-4 This figure depicted an option and has been replaced with a drawing of the Reactor Containment Fuel Storage Rack. Figure 9.1-5 Revised to 13-inch spacing. Figure 9.3-1 This figure revised to (1) delete non-safety related point 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 pu=p suction from the chemical addition and boron recovery system which bypasses the makeup tank (to reduce the response tice associated with effecting a change in boric acid concentration). ( Figure 9.3-5 This figure has been revised to delete non-safety related point interfaces and to add piping and valves from the DdRS suction line to the reactor building su=p to provide a single means for post LOCA long term cooling. CHAPTER 10 Figure 10.1-1
- 1) One qualified startup range level recorder has been added for each steam generator (LR-10A2 & LR-10B2).
- 2) One qualified pressure recorder has been added for each steam generator (PR-12Al & PR-12B1).
- 3) Main steam pressure inputs to the ICS revised to be con-sistent with philosophy used on other ICS inputs.
- 4) Revised drawing to show correct AW connections to OTSG.
1
- 5) Deleted non-safety related point interfaces.
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Amendmcat 2 July 30,1976 Babcock & Wilcox STN 50-561 i ATTACHMENT 1 (Cont'd) CHAPTER 11 s Table 11.1-1 Revised to include parameters for base-loaded operation. 11.1-4 Table 11.1-5 New tables to provide coolant activities for base-loaded 11.1-Sa operation. Table 11.1-6 Renucbered 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 measured parameter.
l Table 14.1-1 Reference to OTSG circulation system tests deleted. This non-safety related system has been deleted from the B-SAR l ( design. J ge QIAPTER 15 Table 15.1-2 This table has been included in new Appendix 15C. Table 15.1-5 This table has been included in new Appendix 15C. Figure 15.1.13-1 This figure has been revised in accordance with agreements with C. 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 C. 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. Hazetis (6/9/76) and included in new Appendix 15C. Tabic 15.13-3 Table nucber corrected to 15.1.13-3 and revised to clarify that there are 2 pumps in both DHR and RBS systems. i ~5-
o e. f,,NRC,rcnu 105 U.S. NUCLEAR REGULATORY COMMISSION DOCKET NUMilEn ,,,a STN-50-561 NRC DISTRIBUTION rol-{5 ART 50 DOCKET MATERIAL To. Mr. Roger S. Boyd FROM: Babcock & Wi1Cox DATE OF DOCUMENT i LynChburg, Va. 24505 7-30-76 J. H. MacMillan DATE RECEIVED 7-30-76 3 LETTER ENOTORIZED PROP INPUT FORM NU.MBER OF COPIES RECEIVED 5loRiciN AL QUNCLASSIFIED 3 g{gggd 37 CC . Q COP.Y oEsCnirvioN Ltr notarized 7-29-76 trans the ENCLOSU RE A12)T #2 to B-SAR-205 Consists of following: revised & addl pages to the SAR.... (40 Cys enel rec'd)~ DISTRIBUTION PER M. RUSHBROOKE 7-30-76 T. COX REQUESTING ADDL CYS FOR ACRS C FLANT NAME: B-SAR 4 SAFETY FOR ACTIOM/iNFORMAT'ON EtmT'to DHL 7-31-76 L UGNED AD: ASSIC'!ED AD! ANCH CHIEF: PAG R n m mn arrvr- [hPRETECTMANAGER: l# T - dMN PROJECT MANAGER: LIC. ASST.: K QI,th_9 1 00 K, LIC. ASST.! ... i i _' - l INTERNAL DISTRIBUTION REG FILE SYSTEMS SAFETY ,[ l pi m g--c,T ry g SITE SAFETY Es NRC PDR_ _ HEINEdAN '. -i% Trtirsen - LtR ENVI"O ANALYSIS _' I & E (O) SCHRCEDER IX BENAROYA M DEN"'ON & fiULLE"=L41 _RL_D \\LIAS COSSICK & STAFF ENGINEERING IPPOLITO ENVIRO TECH _ _ J1IFC = (SQ MACCAR.1Y M _KIRgu00D nngT , CASE = LfA ] KNIGHT PALIARD ltANAUER A' SIlrJEIL OPERATING REACTORS SPAT'CT en HARLFSS L% PAWLICKI STELLO t l i 9TTv Tern- _J_,R_0 JECT R\\NACEMENT l REACTOR SAFETT OPER/xTJEG_ TECH. CA WTLL BOYD 6 _ ROS_S
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