|
---|
Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20059J7501990-09-0707 September 1990 Requests RESAR SP/90 Technical Reviewer Support During Listed ACRS Meetings.Full Committee Meeting Scheduled for 901004,05 or 06 ML20245E8501989-08-0707 August 1989 Advises of Reassignments in Project Mgt Duties Due to Recent Reorganization of Standardization & Life Extension Project Directorate ML20246B8331989-07-0505 July 1989 Notification of 890714 Meeting W/Util in Rockville,Md to Discuss Severe Accident & Licensing Issues on RESAR SP/90 ML20236B3751989-03-0909 March 1989 Forwards to Wj Johnson,Forwarding NRC Draft SER Re RESAR SP/90 on Listed Technical Areas.Ltrs Provided to ACRS Members of Progress in Reviewing Pda Application ML20236D5751989-03-0909 March 1989 Forwards to Wj Johnson,Forwarding NRC Draft SER Re RESAR SP/90 on Listed Technical Areas.Ltrs Provided to Inform CRGR Members of Progress in Reviewing Pda Application ML20236A9721989-03-0707 March 1989 Forwards Feb 1989 Status Rept Re Current Review Milestones for Each Std Plant Project ML20196B6081988-11-29029 November 1988 Forwards Status Rept for Nov 1988 Re Std Plant Design Technical Reviews ML20195J3231988-11-18018 November 1988 Provides Responses Re Review of Resolution of USIs & Generic Safety Issues for RESAR SP/90,per 881027 Request ML20195D6891988-10-27027 October 1988 Proposes Review Responsibilities & Review Guidelines Re Resolution of USIs & Generic Safety Issues for RESAR SP/90. Encls Provide Matrices Delineating Proposed NRR Review Responsibilities for All Applicable USIs ML20195B6131988-10-26026 October 1988 Forwards Status Rept on Std Plant Design Technical Reviews ML20154E4051988-09-14014 September 1988 Forwards Status Rept for Aug 1988 Re Std Plant Design Technical Reviews ML20207E9601988-08-0909 August 1988 Forwards Status Rept for Jul Re Current Review Milestones for Each Std Plant Project.Requests Notification within 1 Wk of Receipt of Memo If Problems W/Input Dates Encountered ML20207E1421988-07-29029 July 1988 Forwards Proprietary BNL Repts Re Probability Safety Study for RESAR SP/90.Repts Withheld (Ref 10CFR2.740) ML20150C7751988-07-0101 July 1988 Forwards Status Rept on Std Plant Design Technical Reviews ML20154R5161988-06-0202 June 1988 Foorwards May Status Rept Re Current Review Milestones for Std Plants (Epri,Advanced Bwr,Resar SP/90 & C-E Sys 80+) ML20154F9981988-05-17017 May 1988 Notification of 880608 Meeting W/Westinghouse in Rockville, MD to Discuss QA Program Intended for Application to RESAR SP/90 & Westinghouse Responses to NRC Request for Addl Info ML20151W3301988-04-25025 April 1988 Forwards Apr 1988 Status Rept Re Current Review Milestones for Each Std Plant Design.Problems in Meeting Input Dates Should Be Reported within 1 Wk of Memo Receipt ML20151L3341988-04-14014 April 1988 Requests Draft SER Discussing Acceptability of Applicable design-specific Resolutions of Listed Generic Issues No Later than 880516 ML20148H4691988-03-23023 March 1988 Notification of 880331 Meeting W/Bnl & Westinghouse in Monroeville,Pa to Discuss Results of NRC Review of PRA for RESAR SP/90 ML20148J8961988-03-23023 March 1988 Forwards Mar 1988 Status Rept Re Std Plant Design Technical Reviews ML20148H4711988-03-22022 March 1988 Forwards BNL Draft Rept, Independent Assessment of Severe Accident Risks for Westinghouse Advanced PWR Design (SP/90). Encl Withheld (Ref 10CFR2.740) ML20150D5891988-03-21021 March 1988 Forwards Wj Johnson of Westinghouse Mar 1988 Ltr Forwarding Draft SER on front-end Portion of Module 16, Probabilistic Safety Study, to Inform of Progress of Review of Pda Application.W/O Encls ML20148D7511988-03-21021 March 1988 Forwards Author Mar 1988 Ltr to Wj Johnson Transmitting Draft SER on front-end Portion of Module 16, Probabilistic Safety Study of Pda Application for RESAR SP/90 Design. Rest of Pda Application Under Review.W/O Encl ML20149L9901988-02-19019 February 1988 Forwards Feb Status Rept Re Current Review Milestones for Std Plant Projects (Epri,Abwr,Resar SP/90 & C-E Sys 80+) ML20149M0251988-01-25025 January 1988 Forwards Revised Std Plant Review Program Plan. Four Standardization Projects & Expected Westinghouse Advanced Passive Plant Design Listed.Issuance of Revised Program Plan Constitutes Completion of Task Assignment 3 Per 871116 Memo ML20207L4251988-01-25025 January 1988 Forwards Info Re Advanced LWR Performance Goals.Info Assembled After Discussion W/Knowledgeable NRC Staff Members & During 880119 Meeting W/Erpi Representatives ML20148C9131988-01-19019 January 1988 Forwards Status Rept on Std Plant Design Technical Reviews for Jan 1988.Problems W/Meeting Listed Input Dates Requested within 1 Wk of Memo Receipt ML20237B3631987-12-14014 December 1987 Forwards Review Status Repts on GE Advanced Bwr,Westinghouse RESAR SP/90,C-E Sys 80+ & EPRI Advanced Lwr.Repts Will Be Issued Periodically Re Current Review Milestone for Each Std Plant Project.Expected Input Date Discussed ML20236J1531987-11-0202 November 1987 Advises That Technical Reviewers for Standardized LWR Plants Should Be Reminded of Responsibility for Assuring That safety-related Structures,Sys & Components within Scope of Review Classified as safety-related by Applicant ML20236J2401987-10-28028 October 1987 Notification of 871030 Meeting W/Nrc in Bethesda,Md to Discuss Westinghouse PWR Licensing Initiatives.Agenda Encl ML20235K8271987-09-29029 September 1987 Forwards Final List of Review Assignments Including Currently Assigned Review Staff,Former Reviewers,Psar Sections Listed by Branch & Staff Members & Listing of Draft SERs Received to Date ML20235K6431987-09-29029 September 1987 Notification of 871119 Meeting W/Westinghouse in Monroeville,Pa to Discuss Engineering & Human Factors Design Aspects of Westinghouse Advanced Control Room That Will Be Utilized in RESAR SP/90 Facility Design ML20237F8671987-08-27027 August 1987 Notification of Rescheduled 870903 Meeting to 870910 W/Westinghouse in Bethesda,Md to Provide NRC W/Background Info Re RESAR SP/90 Design.General Layout of Nuclear Power Block & Unique Features of Design to Be Discussed ML20237K9001987-08-25025 August 1987 Notifies of Meeting W/Westinghouse to Discuss General Layout & Unique Plant Design Features Due to Large Number of Staff Members Assigned to Review RESAR SP/90.Meeting Will Be Similar to June 1987 Meeting ML20237K9121987-08-25025 August 1987 Notification of 870903 Meeting W/Westinghouse in Bethesda,Md to Discuss RESAR SP/90 Design,Including General Layout of Nuclear Power Block & Unique Design Features ML20215M1261987-06-22022 June 1987 Discusses Review of Draft Sandia Rept, Observations on Sabotage Protection Capabilities of Advanced Pwr. Use of Relative Risk Techniques to Determine If Design Has Sabotage Weak Links Encouraged ML20215H3891987-06-18018 June 1987 Submits Addl Questions for Westinghouse Re Modules 2 & 3 of RESAR-SP/90 Preliminary Design Approval Application on Design Features to Reduce Sabotage Vulnerability ML20214P7881987-05-27027 May 1987 Forwards Notification of Meeting on 870603 to Discuss RESAR SP-90.Westinghouse Will Be Making Presentation Re General Layout & Unique Features of Plant Design.W/O Encl ML20214M8711987-05-21021 May 1987 Notification of 870603 Meeting W/Westinghouse in Bethesda,Md to Provide NRC W/Background Info Re RESAR SP/90 Design, Including General Layout of Nuclear Power Block & Unique Design Features ML20213H0521987-05-12012 May 1987 Requests Assignment of Technical Reviewers to Westinghouse Oct 1983 Advance PWR (RESAR SP/90) Application.Brief History & Status of Project,Tentative Review Schedule & Listing of Issued Sers,Former Reviewers & PSAR Modules Encl ML20206B6771987-04-0707 April 1987 Forwards 870319 Memo Detailing Status of Westinghouse RESAR-SP/90 Review & Safety Evaluations.W/O Encls ML20215G2641987-03-19019 March 1987 Submits Assessment of Status of Review for Westinghouse RESAR-SP/90 Design,Per 870310 Request.Most Technical Matl Needed for Review Submitted.Review Could Be Completed within Several Months If Priority Established IA-87-309, Submits Assessment of Status of Review for Westinghouse RESAR-SP/90 Design,Per 870310 Request.Most Technical Matl Needed for Review Submitted.Review Could Be Completed within Several Months If Priority Established1987-03-19019 March 1987 Submits Assessment of Status of Review for Westinghouse RESAR-SP/90 Design,Per 870310 Request.Most Technical Matl Needed for Review Submitted.Review Could Be Completed within Several Months If Priority Established ML20206J0821986-06-24024 June 1986 Notification of 860708 Meeting W/Westinghouse in Bethesda,Md to Outline Content & Discuss Format for Module 15 of RESAR-SP/90.Module 15 Will Contain Section 18 & Portions of Section 7 of PSAR Re Human Factors Issues & Control Room ML20155E0091986-04-10010 April 1986 Notification of 860423-24 Meetings W/Westinghouse in Monroeville,Pa to Discuss Preliminary Questions on Instrumentation & Control Section of Module 9 of RESAR-SP/90.Agenda Encl ML20155D9991986-04-10010 April 1986 Notification of 860423-24 Meetings W/Westinghouse in Monroeville,Pa to Discuss Preliminary Questions on Instrumentation & Control Section of Module 7 of RESAR-SP/90.Agenda Encl.W/O Encl ML20138R9501985-11-14014 November 1985 Notification of 851119-20 Meetings W/Westinghouse in Monroeville,Pa to Discuss PRA Submitted in RESAR-SP/90 ML20209G6011985-09-16016 September 1985 Notification of 850924 Meeting W/Westinghouse in Bethesda,Md to Discuss Questions on RESAR SP/90,Sections 1 & 15 of Module 1, Primary Side Safeguard Sys 1990-09-07
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20059J7501990-09-0707 September 1990 Requests RESAR SP/90 Technical Reviewer Support During Listed ACRS Meetings.Full Committee Meeting Scheduled for 901004,05 or 06 ML20245E8501989-08-0707 August 1989 Advises of Reassignments in Project Mgt Duties Due to Recent Reorganization of Standardization & Life Extension Project Directorate ML20246B8331989-07-0505 July 1989 Notification of 890714 Meeting W/Util in Rockville,Md to Discuss Severe Accident & Licensing Issues on RESAR SP/90 ML20236B3751989-03-0909 March 1989 Forwards to Wj Johnson,Forwarding NRC Draft SER Re RESAR SP/90 on Listed Technical Areas.Ltrs Provided to ACRS Members of Progress in Reviewing Pda Application ML20236D5751989-03-0909 March 1989 Forwards to Wj Johnson,Forwarding NRC Draft SER Re RESAR SP/90 on Listed Technical Areas.Ltrs Provided to Inform CRGR Members of Progress in Reviewing Pda Application ML20236A9721989-03-0707 March 1989 Forwards Feb 1989 Status Rept Re Current Review Milestones for Each Std Plant Project ML20196B6081988-11-29029 November 1988 Forwards Status Rept for Nov 1988 Re Std Plant Design Technical Reviews ML20195J3231988-11-18018 November 1988 Provides Responses Re Review of Resolution of USIs & Generic Safety Issues for RESAR SP/90,per 881027 Request ML20195D6891988-10-27027 October 1988 Proposes Review Responsibilities & Review Guidelines Re Resolution of USIs & Generic Safety Issues for RESAR SP/90. Encls Provide Matrices Delineating Proposed NRR Review Responsibilities for All Applicable USIs ML20195B6131988-10-26026 October 1988 Forwards Status Rept on Std Plant Design Technical Reviews ML20154E4051988-09-14014 September 1988 Forwards Status Rept for Aug 1988 Re Std Plant Design Technical Reviews ML20207E9601988-08-0909 August 1988 Forwards Status Rept for Jul Re Current Review Milestones for Each Std Plant Project.Requests Notification within 1 Wk of Receipt of Memo If Problems W/Input Dates Encountered ML20207E1421988-07-29029 July 1988 Forwards Proprietary BNL Repts Re Probability Safety Study for RESAR SP/90.Repts Withheld (Ref 10CFR2.740) ML20150C7751988-07-0101 July 1988 Forwards Status Rept on Std Plant Design Technical Reviews ML20154R5161988-06-0202 June 1988 Foorwards May Status Rept Re Current Review Milestones for Std Plants (Epri,Advanced Bwr,Resar SP/90 & C-E Sys 80+) ML20154F9981988-05-17017 May 1988 Notification of 880608 Meeting W/Westinghouse in Rockville, MD to Discuss QA Program Intended for Application to RESAR SP/90 & Westinghouse Responses to NRC Request for Addl Info ML20151W3301988-04-25025 April 1988 Forwards Apr 1988 Status Rept Re Current Review Milestones for Each Std Plant Design.Problems in Meeting Input Dates Should Be Reported within 1 Wk of Memo Receipt ML20151L3341988-04-14014 April 1988 Requests Draft SER Discussing Acceptability of Applicable design-specific Resolutions of Listed Generic Issues No Later than 880516 ML20148H4691988-03-23023 March 1988 Notification of 880331 Meeting W/Bnl & Westinghouse in Monroeville,Pa to Discuss Results of NRC Review of PRA for RESAR SP/90 ML20148J8961988-03-23023 March 1988 Forwards Mar 1988 Status Rept Re Std Plant Design Technical Reviews ML20148H4711988-03-22022 March 1988 Forwards BNL Draft Rept, Independent Assessment of Severe Accident Risks for Westinghouse Advanced PWR Design (SP/90). Encl Withheld (Ref 10CFR2.740) ML20150D5891988-03-21021 March 1988 Forwards Wj Johnson of Westinghouse Mar 1988 Ltr Forwarding Draft SER on front-end Portion of Module 16, Probabilistic Safety Study, to Inform of Progress of Review of Pda Application.W/O Encls ML20148D7511988-03-21021 March 1988 Forwards Author Mar 1988 Ltr to Wj Johnson Transmitting Draft SER on front-end Portion of Module 16, Probabilistic Safety Study of Pda Application for RESAR SP/90 Design. Rest of Pda Application Under Review.W/O Encl ML20149L9901988-02-19019 February 1988 Forwards Feb Status Rept Re Current Review Milestones for Std Plant Projects (Epri,Abwr,Resar SP/90 & C-E Sys 80+) ML20149M0251988-01-25025 January 1988 Forwards Revised Std Plant Review Program Plan. Four Standardization Projects & Expected Westinghouse Advanced Passive Plant Design Listed.Issuance of Revised Program Plan Constitutes Completion of Task Assignment 3 Per 871116 Memo ML20207L4251988-01-25025 January 1988 Forwards Info Re Advanced LWR Performance Goals.Info Assembled After Discussion W/Knowledgeable NRC Staff Members & During 880119 Meeting W/Erpi Representatives ML20148C9131988-01-19019 January 1988 Forwards Status Rept on Std Plant Design Technical Reviews for Jan 1988.Problems W/Meeting Listed Input Dates Requested within 1 Wk of Memo Receipt ML20237B3631987-12-14014 December 1987 Forwards Review Status Repts on GE Advanced Bwr,Westinghouse RESAR SP/90,C-E Sys 80+ & EPRI Advanced Lwr.Repts Will Be Issued Periodically Re Current Review Milestone for Each Std Plant Project.Expected Input Date Discussed ML20236J1531987-11-0202 November 1987 Advises That Technical Reviewers for Standardized LWR Plants Should Be Reminded of Responsibility for Assuring That safety-related Structures,Sys & Components within Scope of Review Classified as safety-related by Applicant ML20236J2401987-10-28028 October 1987 Notification of 871030 Meeting W/Nrc in Bethesda,Md to Discuss Westinghouse PWR Licensing Initiatives.Agenda Encl ML20235K8271987-09-29029 September 1987 Forwards Final List of Review Assignments Including Currently Assigned Review Staff,Former Reviewers,Psar Sections Listed by Branch & Staff Members & Listing of Draft SERs Received to Date ML20235K6431987-09-29029 September 1987 Notification of 871119 Meeting W/Westinghouse in Monroeville,Pa to Discuss Engineering & Human Factors Design Aspects of Westinghouse Advanced Control Room That Will Be Utilized in RESAR SP/90 Facility Design ML20237F8671987-08-27027 August 1987 Notification of Rescheduled 870903 Meeting to 870910 W/Westinghouse in Bethesda,Md to Provide NRC W/Background Info Re RESAR SP/90 Design.General Layout of Nuclear Power Block & Unique Features of Design to Be Discussed ML20237K9001987-08-25025 August 1987 Notifies of Meeting W/Westinghouse to Discuss General Layout & Unique Plant Design Features Due to Large Number of Staff Members Assigned to Review RESAR SP/90.Meeting Will Be Similar to June 1987 Meeting ML20237K9121987-08-25025 August 1987 Notification of 870903 Meeting W/Westinghouse in Bethesda,Md to Discuss RESAR SP/90 Design,Including General Layout of Nuclear Power Block & Unique Design Features ML20215M1261987-06-22022 June 1987 Discusses Review of Draft Sandia Rept, Observations on Sabotage Protection Capabilities of Advanced Pwr. Use of Relative Risk Techniques to Determine If Design Has Sabotage Weak Links Encouraged ML20215H3891987-06-18018 June 1987 Submits Addl Questions for Westinghouse Re Modules 2 & 3 of RESAR-SP/90 Preliminary Design Approval Application on Design Features to Reduce Sabotage Vulnerability ML20214P7881987-05-27027 May 1987 Forwards Notification of Meeting on 870603 to Discuss RESAR SP-90.Westinghouse Will Be Making Presentation Re General Layout & Unique Features of Plant Design.W/O Encl ML20214M8711987-05-21021 May 1987 Notification of 870603 Meeting W/Westinghouse in Bethesda,Md to Provide NRC W/Background Info Re RESAR SP/90 Design, Including General Layout of Nuclear Power Block & Unique Design Features ML20213H0521987-05-12012 May 1987 Requests Assignment of Technical Reviewers to Westinghouse Oct 1983 Advance PWR (RESAR SP/90) Application.Brief History & Status of Project,Tentative Review Schedule & Listing of Issued Sers,Former Reviewers & PSAR Modules Encl ML20206B6771987-04-0707 April 1987 Forwards 870319 Memo Detailing Status of Westinghouse RESAR-SP/90 Review & Safety Evaluations.W/O Encls ML20215G2641987-03-19019 March 1987 Submits Assessment of Status of Review for Westinghouse RESAR-SP/90 Design,Per 870310 Request.Most Technical Matl Needed for Review Submitted.Review Could Be Completed within Several Months If Priority Established IA-87-309, Submits Assessment of Status of Review for Westinghouse RESAR-SP/90 Design,Per 870310 Request.Most Technical Matl Needed for Review Submitted.Review Could Be Completed within Several Months If Priority Established1987-03-19019 March 1987 Submits Assessment of Status of Review for Westinghouse RESAR-SP/90 Design,Per 870310 Request.Most Technical Matl Needed for Review Submitted.Review Could Be Completed within Several Months If Priority Established ML20206J0821986-06-24024 June 1986 Notification of 860708 Meeting W/Westinghouse in Bethesda,Md to Outline Content & Discuss Format for Module 15 of RESAR-SP/90.Module 15 Will Contain Section 18 & Portions of Section 7 of PSAR Re Human Factors Issues & Control Room ML20155E0091986-04-10010 April 1986 Notification of 860423-24 Meetings W/Westinghouse in Monroeville,Pa to Discuss Preliminary Questions on Instrumentation & Control Section of Module 9 of RESAR-SP/90.Agenda Encl ML20155D9991986-04-10010 April 1986 Notification of 860423-24 Meetings W/Westinghouse in Monroeville,Pa to Discuss Preliminary Questions on Instrumentation & Control Section of Module 7 of RESAR-SP/90.Agenda Encl.W/O Encl ML20138R9501985-11-14014 November 1985 Notification of 851119-20 Meetings W/Westinghouse in Monroeville,Pa to Discuss PRA Submitted in RESAR-SP/90 ML20209G6011985-09-16016 September 1985 Notification of 850924 Meeting W/Westinghouse in Bethesda,Md to Discuss Questions on RESAR SP/90,Sections 1 & 15 of Module 1, Primary Side Safeguard Sys 1990-09-07
[Table view] |
Text
i[gno o UNITED STATES
, !** 7 n NUC:. . ' ?. ?.:C"L/d ORY COMMISSION 4'
WASHINGTON, D. C. 20555 k ... . . p# May 12, 1987 DOCKET NO. 50-601 MEMORANDUM FOR: Distribution (SeeAttached)
THRU: Herbert N. Berkow, Director Standardization and Non-Power Reactor Directorate Division of Reactor Projects III, IV, Y and Special Projects FROM: Thomas J. Kenyon, Project Manager Standardization and Non-Power Reactor Directorate Division rf Reactor Projects III, IV, V arid Special Projects
SUBJECT:
RE0 VEST FOR ASSIGNMENT OF TECHNICAL REVIEWERS TO THE RESAR SP-90 APPLICATION The purpose of this memo is to request you previde me with the name(s) of the technical reviewer (s) who will be assi the review of the WAPWR (RESAR SP/90) gned the application. Toresponsibility assist you inofyour completion of selection of these reviewers, I am forwarding the following information:
- 1. Enclosure 1 provides a brief history and status of the project.
- 2. Enclosure 2 provides a tentative review schedule which would result in issuance of a draft SER in April 1988, and the final SER by the end of 1988.
- 3. Enclosure 3 provides a listing of the SERs issued to date, the l former reviewers (if known), and the PSAR modules in which the SER sections are discussed. I have attempted to delineate which branch would have the primary responsibility over the SER sections. The ,
delineation may be in error in some cases as no official listing of l SRP responsibilities under the new organization has been issued to date.
As discussed during a May 7,1987 meeting with senior NRC management, PDSNP requests that, to the extent practicable, reviewers who have previously participated in the WAPWR review should be assigned to complete the review of this project. However, consideration must be given to the reviewer's ability to meet the proposed milestones for this review vs. those of other assigned projects. I Accordingly, I request you provide me with the name(s) of the assigned reviewer (s) i in your branch, concurrence (or non-concurrence) with the proposed SER assignments. l and concurrence with the proposed schedule or identification of any problems in i meeting that schedule.
0705190121 070512 PDR ADOCK0500g1
- . ___ - -- . _ - - - -1
May 12, 1987 . ~; <
\
2-Copies of the updated PSAR modules and the SERs can be ootained froc..te in Rooi.. P-908A. The Docket No. and PA No. are 50-601 and 141213, respectively.
My extension is X27064, ori Thomas J.ginal signed by Manager Kenyon, Project Standardization and Non-Power Reactor Project Directorate '
Division of Reactor Projects III, IV, V and Special Projects
Enclosure:
As stated cc: T. Murley F. Miraglia R. Starostecki D. Crutchfield L. Shao 4 J. Richardson i
A. Thadant s J. Partlow F. Congel
, H. Miller '
D. Ross i
DISTRIBUTION:
ipockettfiej NRC & Local PDR PDSNP Reading Ellylton TKenyon HBerkow OGC-BETH EJordan l ACRS (10)
! PDSN PDJW PDSNP M 6 E$ltoli TKeh :cw HBeM.o'w 05////87 05/j 87 05/sf/87 i
/
1
, . , - - , . - - - - , ,-,-,r, w.--, , a ,- , - , ,, . -c- --- . - n
'Y( ..
\
Copies of the updated PSAR modules and the SERs can be obtained from me in s Room P-908A. The Docket No. and PA No. are 50-601 and 141213, respectively.
My extension is X27064.
-l A- *
?
i l Th J. Kenyo , Project Manager Standardization and Non-Power Reactor Project Directorate Division of Reactor Projects III, IV, V and Special Projects
Enclosure:
As stated cc: T. Murley F. Miraglia R. Starostecki D. Crutchfield L. Shao J. Richardson A. Thadani J. Partlow F. Congel H. Miller D. Ross
DISTRIBUTION: C. Y. Cheng, Acting Chief Materials Engineering Branch T. Marsh, Chief Mechanical Engineering Branch G. Bagchi, Acting Chief Structural & Geosciences Branch ,
C. McCracken, Acting Chief Chemical Engineering Branch -
J. Mauk, Acting Chief Instrumentation & Control Systems Branch F. Rosa, Chief Electrical Systems Branch J. Craig, Acting Chief Plant Systems Branch M. W. Hodges, Chief Reactor Systems Branch R. Erickson, Chief Sateguards Branch L. J. Cunningham, Acting Chief Radiation Protection Eranch A. Beach, Acting Chief Quality Assurance Branch
~
W. Regan, Jr. , Chief Human Factors Assessment Branch J. Murphy, Acting Chief Risk Applications Branch
.4 t
v t
i-Enclosure 1 j RESAR SP/90 Backgrcund and Current Status
Background
Westinghouse tendered the RESAR SP/90 application in October,1983, and ;
the NRC determined the submittal was acceptable for docketing in January, 1984. '
The original concept consisted of a module-by-module staff review. Westinghouse '
submitted the PDA application in modular form, with each module containing i
! appropriate PSAR chapter sections to address plant features or design topics.
l The staff was to review each module individually and issue an SER for each
- module. Westinghouse's original submittal schedule began in October, 1983 and j was to end in February,1985. Due to resource restraints within Westinghouse, r
- the last module was not recefved until March, 1987. ;
1
" I Status Staff review was originally schedu;ed for completion in January,1986.
However, no SEPs have been issued to dato for any of the modules, although son draft SER sections have been completed. For the last year or so, except :
- for the review of the PRA (Module 16) by BNL, very little review effort took ;
{ place, due to resource restraints, lack of response by Westinghouse for l
extenced periods. and lack of completeness of individual modules.
It is difficult to accurately assess the review status quantitatively 4 because some of the earlier reviews might have to be at least partially redone
. by the current review crganizations. We estimate that the review is about 25%
{ complete.
i ,
! Proposed Action and Schedule
! Since all of the modules now have been submitted by Westinghouse, and all
! responses to RAls have been received, PDSNP proposes to perform en integrated review rather than a modular one. This will result in a more efficient review as well as a more comprehensive SER.
a As a result of the reorganization, approximately 30% of the former SP/90 ;
review staff have been transferred to other non-related positions. PDSP l proposes to establish a new review team with the intent of retaining former 1 reviewers to the extent practicable. SERs received to date will be distributed to the staff for reconcurrence by the new NRR management, and a review
, schedule for SP/90 will be established with the concurrence of the technical review branches. The review effort and schedule must, of course, be supported by Westinghouse. l Enclosure 2 of this package provides a tentative review schedule . This l schedule would result in the issuance of a draft SER in April,1988, and the ,
final SER by the end of 1988. The schedule is feasible only if the appropriate l level of priority is established by upper management of both the NRC and Westinghouse.
l i
_ ,_._ _ , _ _ -~ ._, __ _ . - - . _ . __ _ _ , _
Enclosure 2 Tentative Review Schedule 1
RESAR SP/90 1
1 Milestone Date
- Establish review team a review schedule, and 5/87 distribute SERs
- Q-1 inputs to P.M. 7/87
- Q-Is sent to Westinghouse 8/87 l - Westinghouse responses 12/f.7
- Draft SER inputs to P.M. 3/88
- Draft SER issued 4/88
- k'estinghouse responses to draft SER 7/88
- Final SER inputs to P.M. 10/88
- Final SER issued 12/88 T
.c . , . . . _ _ ,_
7 ..-_.-
r -r~--4 * - - ---r- --w-
~
ENCLOSURE 3 . .
SER SECTIONS FOR RESAR SP/90 Division / Former SER+
Branch Reviewer Reviewer Module Section Dates DEST /EMTB Smith 5 4.5.1 CRD Structur61 Materials 4/12/85 Johnsen/ 4 5.2.3 RC Pressure Boundary 8/19/25 Smith Materials 4/12/85 Johnson 4 5.2.4 RC Pressure Boundary 8/19/85 Inservice Inspection and Testing Johnson / 4 5.3.1 Reactor Vessel Materials 8/19/85 Smfth 4/12/85 Johnson 4 5.3.2 Pressure-Temperature Limits 8/19/85 Johnson 4 5.3.3 Reactor Vessel Integrity 8/19/85 Unknown 4 5.4.1.1 Reactor Coolant Pumps N/S (Flyv Feel Integrity) '
Johnson / 4 5.4.2.1 Steam Generator Materials 8/19/85-Smith 4/12/85 Smith 1, 10 6.1.1 Metallic Materials 4/12/85 7/15/85 Unknown TBD 6.2.7 fracture Prevention of N/S Contairment Pressure Boundary Unknown TBD 6.6 Inservice Inspection of N/S Class 2 and 3 components Unknown 658 10.2.3 Turbine Disk Integrity N/S Smith 688 10.3.6 Steam and Feedwater System 4/12/P5 Materials r
N/S = None Submitteo
l.
Division / Former SER*
Branch Reviewer Reviewer Module Section Dates DEST /EMEB Kirkwood/ 7 3.1.1 Conformance with GDC N/S Chan Kirkwood/Chan 7 3.1.2 Conformance with Industry N/S Codes and Standards Kirkwood 1, 7 3.2.1 Seismic Classification N/S Kirkwood 1, 7 3.2.2 Classification Systems N/S Chan 7 3.6.2 Determination of Break N/S Locations and Dynamic Effects Associated with the Postulated Rupture of Piping flou/ Sellers 5 3.9 Mechanical Systems and N/S Components Kirkwood 4 5.2.1 Compliance with Codes and N/S Code Cases (Integrity of RCP Poundary)
l.
Division / Former SER*
Branch Reviewer Reviewer Module Section Dates DEST /ESGR TBD 3 2.1 Geography and Demography 3/11/85 t
TBD 3 2.P Nearby Industrial, Transportation, 3/11/85 and Military Facilities Unknown 3 2.4 Hydraulic Engineering N/S Unknown 3 2.5.1 Basic Geologic and Seismic N/S Information Unknown 3 P.S.2 Vibratory Ground Motion N/S ;
IJnknown 3 2.5.3 Surface Faulting N/S Chan 3 2.5.4 Stability of Subsurface 3/5/85 Materials and Foundations Chan 3 2.5.5_ Stability of Slopes 3/5/85 -
Chan 3 2.5.6 Embankments and Dass 3/5/85 Chan 7 3.3 Wind and Tornado Loadings N/S Giese-Koch 7 3.7 Seismic Design N/S**
Chan 7 3.8 Design of Seismic Category I N/S Structures .
Jackson 7 3.10 Seismic and Dynamic 8/29/85 Oualification of Seismic Category I Instrumentation and Electrical Equipment
Division / Former SER*
Branch Reviewer Reviewer Module Section Dates DEST /ECEB Kirslis 1 6.1.2 Organic Materials 8/28/85 ,
Kirlis 1, 10 6.1.3 Post accident Emergency 8/28/85 Cooling Peters Kirs11s 6A8 10.3.5 Secondary Water Chenistry 8/28/85-Kirslis 688 10.4.6 Condensate Cleanup 8/28/85 System Kirslis 688 10.4.8 Steam Generator Blowdown 8/28/85 Processing System
l Division / Former SER*
Branch Reviewer Reviewer Podule Section Dates DEST /SICB Burrows 9 7.1 Introduction to Instrumentation Draft exists and Controls Burrows 9 7.2. Reactor Trip Draft exists Burrows 9 7.3 engineered Safety Features Draft exists Burrows 9 7.4 Systems Required for Safe Draft exists Shutdowns Burro.: 9 7.5 Instrumentation Important Draft exists to Safety Burrows 9 7.6 All Other Systems Required Draft exists for Safety Burrows 9 7.7 Control and Instrumentation Draft exists Systems Saba/ 15 7.8 Control Room N/S Weiss / (2ndary responsibility)
, Kennedy
l.
Division / Former SER*
Branch Reviewer Reviewer Section Module Dates DEST /SELB Unknown 7 3.11 Environmental Design of N/S Mechanical and Electrical Equipment Gill 9 8.1 Introduction to Electrical N/S-Power 9 8.2 Offsite Power System N/S 9 8.? Onsite Power Systems N/S 2
4 J
Division / Former SERO .
Branch Reviewer Reviewer Module Section Dates DEST /SPLB Unknown 3 2.3 t'eteorology N/S Giardina 7 3.4 Mater Level (Flood) Design N/S Giardina 7 3.5 Missile Protection N/S Unknown 7 3.6.1 Postulated Piping Failures in N/S Fluid Systems Inside and Outside Containment Giardina 4 5.2.5 RCP Boundary leakage N/S Detection Tinker 10 6.2.1 Primary Containment N/$
Functional Design Tinker 1, 10 6.2.2 Containment Heat Removal 7/11/83 System Tinker 10 6.2.3 Secondary Containment N/S Functional Design Tinker 10 6.2.4 Containment Isolation System N/S Tinker 10 6.2.5 Combustible Gas Control N/S in Ct,ntainment Tinker 10 6.2.6 Containment Leakage Testing N/S
, Unknown 13 6.4 Control Room Habitablity N/S Unknown 10 6.5.1 Engineered Safety Feature N/S Filters Read 1, 10 6.5.2 Containment Spray System 3/28/85 (Fission Product Removal)
Unknown 10 6.5.3 Fission Product Control N/S Systems
Division / Former SERO . .
Branch Reviewer Reviewer Module Section Dates DEST /SPLB Unknown 13 9.1 Fuel Storage and Handling N/S Unknown 13 9.2 Water Systems N/S Unknown 13 9.3.1 Compressed Air System N/S Unknown 13 9.3.2 Process and Post Accident N/S Sampling System Unknown 13 9.3.3 Equipment and Floor N/S Drainage System Unknown 13 9.3.6 Chlorine Supply System N/S Unknown 13 9.4.1 Control Equipment Area N/S Ventilation System Unknown 13 9.4.2 Reactor External Building N/S Ventilation System Unknown 13 9.4.3 Radwaste Building Ventilation N/S System Design Criteria Unknown 13 9.4.4 Turbine Building Ventilation N/S System Design Criteria Unknown 13 9.4.5 Annulas Air Clean up and N/S Fuel Building Exhaust System Unknown 13 9.4.6 Containment Cooling and N/S-Ventilation System Unkncwn 13 9.4.7 D/G Building Ventilation N/S System Unknown 13 9.4.8 Essential Service Water Pump N/S Structure Ventilation System Design Criteria Unknown 13 9.4.9 Plant Heating System Design N/S Cri',eria
Divisicn/ Former SER* -
Branch Reviewer Reviewer Module Section Dates DEST /SPLB (cont.) Unknown 13 9.4.10 Essential chilled Water System N/S Unknown 13 9.5.1 Fire Protection System N/S Unknown 13 9.5.2 Communication System N/S Unknown 13 9.5.3 Lighting Systems N/S Unknown 13 9.5.4 Emergency Diesel Engine Fuel N/S 011 Storage and Transfer Systems Unknown 13 9.5.5 Emergency Diesel Engine Cooling N/S Water System I!nknown 13 9.5.6 Emergency Diesel Engine N/S Starting System Unknown 13 9.5.7 Dnergency Diesel Engine N/S Lubrication System Unknown 13 9.5.8 Emergency Diesel Engine N/S Combustion Air Intake and Exhaust System Unknown 6&8 10.1 Description of Steam and N/S Power Conversion System Unknown 688 10.2.1 & 10.2.2 Turbine Generator N/S Unknown 688 10.3.1 Main Steam Supply System N/S
, (Up to and Including MSIVs)
Unknown 6&8 10.3.2, 10.3.3 and 10.3.4 Main N/S Steam Supply System Unknown 688 10.4.1 Main Condenser N/S Lee 6A8 10.4.2 Main Ccndenser Evacuation N/S System Lee 688 10.4.3 Turbine Gland Sealing System 2/8/85
Division / Former SER*
Branch Reviewer Reviewer Podule Section Dates OEST/SPLB (cont.) l!nknown 688 10.4.4 Turbine Bypass System N/S Unknown 6&B 10.4.5 Circulating Water Systen N/S Giardina 688 10.4.7 Condensate and Feedwater H/S System Giardina 6&8 10.4.9 Emergency Feedwater System N/S Unkncwn 6A8 10.4.10 Startup Feedwater. System N/S Unknown 688 10.4.11 Secondary I.fauid Waste N/S System Fell 12 11.1 Source Terms N/S Fell 12 11.2 Liquid Waste Management N/S System Fell 12 11.3 Gaseous Waste Processing N/S System Fell 12 11.4 Solid Waste Processing System N/S Fell IP 11.5 Process and Effluent Radiological N/S Monitoring and Sampling Systems
l.
Division / Former SER*
Branch Reviewer Reviewer Module Section Dates DEST /SRXB Unknown 5 4.1 Description of Reactor N/S Fu 5 4.2 Fuel System Mechanical Design 5/20/85 Richings/ 5 4.3 Nuclear Design 2/6/85 Schwenk Richings/ 5 4.4.1 Thermal-Hydraulic Design 2/6/85 Schwenk Basis Richings/ 5 4.4.2 Thermal-Hydraulic Design 2/6/85 Schwenk Methodology Richings/ 5 4.4.3 Design Abnormalities 2/6/85 Schwenk Richings 5 4.4.4 Hydrodynamic stability 2/6/85 Schwenk Richings/ 5 4.4.5 Loose Parts Monitoring 2/6/85 Schwenk Systems 1
Richings/ 5 4.4.6 Instrumentation for Inadequate 2/6/85 Schwenk Core Cooling Detection (II.F.2)
Richings/ 5 4.4.7 Summary and Conclusions 2/6/85~
Schwenk Giardina 5 4.6 Functional Design of Reactivity 4/4/86 Control Systems Lyon 4 5.2.2 Overpressure Protection N/S System Lyon 4 5.4 Component and Subsystem Design N/S i
(excluding 5.4.1.5 and 5.4.2.4)
Lyon 1 5.4.7 RHR Systems N/S
.i a
Division / Former SER*
Branch Reviewer Reviewer Module Section Dates DEST /SRXB (cont.) Lyon 1 6.3 Emergency Core Cooling System N/S Lyon 13 9.3.4 Chemical and Volume Control N/S System Lyon 13 9.3.5 Boron Recycle System N/S Lyon 4, 5, 15.1 General Discussion of Accident N/S 688 Analysis Methodology Lyon 6&8 15.2 Normal Operation and N/S Anticipated transients Richings/ 4, 5 15.2.4 Reactivity and Power 2/6/85 1
Schwenk Distribution Anomalies Lyon a, 5 15.3 Limiting Accidents N/S 688 Lyon 4, 5, 15.4 Radiological Consequences N/S 6A8 of Accidents Lyon 4, 5, 688 15.5 NUREG-0737 Items N/S
Division / Former SER*
Branch Reviewer Reviewer Module Section Dates DRIS/RSGB Unknown N/A I?.6 Physical Security **
DLPQ/LQA8 Unknown 13 17.0 Cuality Assurance N/S DLPQ/LHFB Weiss / 15 7.8 Control Room N/S Saba/ 18.0 Human Factors Engineering N/S Kennedy RES/PRA Hardin/ Hardin/ 16 Probabilistic Safety Study Draft Exists BNL FNL
, DREP/PRPB Skopec 11 12.0 Radiation Protection 4/10/87 Dunning / 2 Appendix C - USIs/ Generic -
N/S Minners Issues ***
- Sandia study addresses physical security considerations for WAPWR
- Westir.ghouse to postpone response to RAls until FDA
, ,