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Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20196J9371998-12-0808 December 1998 Notification of 990120 Meeting with Util in Peekskill,Ny to Inform Public of Licensee Plans for Decommissioning Indian Point Nuclear Generating Station Unit 1 ML20236X5861998-08-0505 August 1998 Summary of 980620 Meeting W/Members of W,Util & NRC in Rockville,Md Re best-estimate Small Break LOCA Model Issues. Attendees List & Nonproprietary Matl Presented at Meeting Encl ML20217E7381997-10-0202 October 1997 Forwards Operator Licensing Exam Administered on 970317-20 W/Outline & Initial Exam Submittal Designated for Distribution Under Rids Code A070 IR 05000247/19970021997-10-0202 October 1997 Forwards NRC Operator Licensing Exam Rept 50-247/97-02 (Including Completed & Graded Tests) for Tests Administered on 970317-20 ML20236N0661997-05-0202 May 1997 Responds to from Consolidated Edison Requesting Interpretation of TS as to Definition of Operable as It Applies to Afs Under Certain Scenarios ML20136C1031997-03-0606 March 1997 Forwards Correspondence Transmitted Via Internet to J Zwolinski from P Blanch During 970102-31.Requests Correspondence Be Placed in PDR ML20134N6211997-02-19019 February 1997 Forwards Response to SB Bram to EDO Re Proposed Corporate Reorganization of Consolidated Edison Co of Ny Approved W/Edit by Chairman for Dispatch ML20134N6371997-01-14014 January 1997 Requests Concurrence Re Proposed Response to SB Bram to EDO Concerning Proposed Corporate Reorganization of Consolidated Edison Co of Ny by Close of Business on 970117 ML20129K2561996-11-0505 November 1996 Notification of Significant Licensee Meeting 96-109 W/Listed Attendees on 961202-03 in Philadelphia,Pa to Provide Training,Resolve Interagency Exercise Scheduling Conflicts & Discuss Current Issues in Emergency Preparedness ML20211E9921995-11-0808 November 1995 Informs of Plan to Augment Plant,Unit 3 Resident Staff & Provide around-the-clock Insp Coverage During Plant Restart from Current Unplanned Outage.Primary Objectives of Insp Listed ML20211D9061995-08-14014 August 1995 Forwards Final Rev to Plant,Unit 3 Restart Action Plan Based Upon Completion of Insp Activities & Util Oversight ML20203B9821995-06-29029 June 1995 Discusses OI Repts 1-95-011,1-95-012 & 5-93-014 Re Fitness for Duty Incident,Falsification of Chemistry Records Involving EDG Fuel Oil & Falsification of Fire Protection Records ML20211F0441994-12-21021 December 1994 Requests That Plant,Unit 3 Restart Action Plan Be Replaced W/Encl Rev to Plan ML20236L5841994-11-0909 November 1994 Submits Interpretation of TS Requirement Re Fire Protection for Indian Point Unit 2 Per 940719 Memo NUREG-1299, Forwards Continuation of Curtiss Papers to Be Filed Under Commission Correspondence in Pdr.Advanced Copy Sent to Pdr. List of Documents Included in Four Boxes Encl1994-06-29029 June 1994 Forwards Continuation of Curtiss Papers to Be Filed Under Commission Correspondence in Pdr.Advanced Copy Sent to Pdr. List of Documents Included in Four Boxes Encl ML20211E9541994-05-12012 May 1994 Requests Approval of Process by Which Plant,Unit 3 Restart Issues,As Listed in Restart Action Plan,Will Be Closed. Restart Issue Closure Process Outlined in Encl to Memo ML20134B5061994-04-13013 April 1994 Submits Plants Which Will Be Discussed in Categories Indicated Re Results of Screening Meetings for June 1994. Partially Deleted ML20057C5721993-09-24024 September 1993 Forwards New Page 20,rev 12 of Security Plan Due to Rev 12 Copy Spillover from Page Nineteen Rev 13 Additions.Page Withheld ML20057B2111993-09-16016 September 1993 Forwards Update to Security Plan,Including Table of Contents,Rev 13 to Pages 18,19,21 & 24 & Chapter 11.Encl Withheld ML20056E4571993-08-0505 August 1993 Forwards Technical Review Rept Re, Tardy Licensee Actions Initiated Because of Delayed Replacement of Batteries in Uninterruptible Power Supplies at Plant IR 05000286/19900161990-10-25025 October 1990 Notification of Significant Licensee Meeting 90-127/ Enforcement Conference on 901105 in King of Prussia,Pa to Discuss Licensed Reactor Operator Inattentiveness to Duty Noted in Insp Rept 50-286/90-16 ML20059D1341990-08-30030 August 1990 Notification of 900913 Meeting W/Util in Rockville,Md to Discuss Util Proposal to Upgrade Emergency Diesel Generators at Facility ML20244E2681989-04-12012 April 1989 Summary of Operating Reactors Events Meeting 89-015 on 890412.Discussion of Events,List of Attendees & Three Significant Items Identified for Input Into NRC Performance Indicator Program & Summary of Reactor Scrams Also Encl ML20196C4751988-06-23023 June 1988 Notification of Licensee Requested Meeting 88-097 on 880629 in King of Prussia,Pa to Discuss Security Program Topics ML20151D4271988-03-24024 March 1988 Submits Summary of Actions Discussed at ACRS 335th Meeting on 880310-12 in Washington,Dc,Including ACRS Repts/ Recommendations,Other Actions,Agreements,Assignments & Requests & Future Agenda ML20148D9491988-03-15015 March 1988 Discusses 880315 Operating Reactors Events Meeting 88-11. List of Attendees,Events Discussed & Tabulation of long-term Followup Assignments Detailed in Encls ML20147E3621988-02-28028 February 1988 Summary of 880223 Operating Reactors Events Meeting 88-008. List of Attendees,Tabulation of long-term Followup Assignments to Be Completed & Summary of Reactor Scrams Encl ML20195H0201988-02-16016 February 1988 Forwards Proposed Updated SALP Evaluation for Plant. Evaluation Based on Insps & Examiner Reviews Conducted During SALP Period Form 860801-870207 ML20195H0081987-12-0101 December 1987 Forwards Input for SALP Rept for Aug 1986 - Nov 1987 ML20147F8761987-10-21021 October 1987 Discusses 871022 Meeting W/Staff to Discuss NRC Position Re Util Steam Generator Replacement Program.Brief Summary of Licensee Position on Why Replacement Can Be Accomplished Under 10CFR50.59 Listed in Encl 1 ML20204G2771987-03-23023 March 1987 Notification of 870326 Meeting W/Util in Bethesda,Md to Discuss Info Required to Support Decommissioning Plan & Need for Environ Statement.Meeting Originally Scheduled for 870324 ML20207R2151987-03-10010 March 1987 Notification of 870324 Meeting W/Util in Bethesda,Md to Discuss Environ Info Required to Support Facility Decommissioning Plan & Need for Environ Statement.Meeting Originally Scheduled for 870310 ML20212F9321987-03-0303 March 1987 Notification of 870310 Meeting W/Util in Bethesda,Md to Discuss Environ Info Required to Support Decommissioning Plan & Need for Environ Statement ML20211K9161987-02-19019 February 1987 Summary of Operating Reactor Events Meeting 87-04 on 870209. List of Attendees,Events Discussed,Significant Elements of Events & Summary of Events Encl ML20209H0831986-12-22022 December 1986 Summarizes INPO 861210 Accreditation Meeting in Atlanta,Ga. Listed Plants Presented Training Programs for Nonlicensed Operators,Reactor Operators,Senior Reactor Operators & Shift Technical Advisors ML20214T3041986-09-17017 September 1986 Notification of Rev 1 to Board Meeting 86-104 on 860923 at Region I to Discuss Regional Evaluation Phase of SALP ML20203N1921986-09-0808 September 1986 Notification of Board Meeting 86-104 W/Util on 860919 in King of Prussia,Pa to Discuss SALP Regional Evaluation Phase ML20207S2141986-08-0707 August 1986 Forwards Commission Directive to Staff to Respond to Shearon Harris Licensing Board Re Emergency Nighttime Alerting.Staff Should Address Alertability During Stormy Winter in Response to Indian Point Board 860609 & 0710 Ltrs ML20215A5931986-07-30030 July 1986 Forwards Request for Addl Info on Tech Spec Changes in Response to Generic Ltrs 85-09 & 83-28,Item 4.3 Re Reactor Trip Breaker Design Mods.Request Should Be Transmitted,Along W/Generic Ltr 85-09,to Licensee NUREG/CR-2655, Responds to Bl Brandenburg Re NRC on Facility Alert & Notification Sys.Ltr Info out-of-date But Not Inaccurate.Board Never Informed of NUREG/CR-2655.Served on 8607111986-07-10010 July 1986 Responds to Bl Brandenburg Re NRC on Facility Alert & Notification Sys.Ltr Info out-of-date But Not Inaccurate.Board Never Informed of NUREG/CR-2655.Served on 860711 ML20198H9381986-05-16016 May 1986 Notifies of 1986 Indian Point 2 full-participation Exercise on 860604 (Insp Rept 50-247/86-13).Team Assignments, Schedule,Exercise Event & Time Line,Open Items,Objective Lists & Synopsis of State & County Matl Encl.W/O Encl ML20199K4421986-05-10010 May 1986 Comments on Indian Point Special Proceeding.Severe Accident Policy Statement Should Be Reexamined ML20198E7621986-05-0808 May 1986 Informs of Next NRR Operating Reactor Events Briefing Scheduled for 850716 in Bethesda,Md.Guidelines for Participants Encl.Tentative Agenda for Meeting Listed ML20214G3971986-05-0808 May 1986 Forwards Sser on Review of Design for Automatic Shunt Trip for Reactor Trip Breakers.Util Response for Seismic Qualification Issue Acceptable.Licensee Will Be Required to Submit Tech Spec Changes ML20198E7981986-05-0808 May 1986 Informs That 850716 NRR Operating Reactor Events Briefing 85-12 Rescheduled for 850723 in Bethesda,Md.Agenda Encl ML20205N1051986-04-24024 April 1986 Requests Assistance in Review of Fuel Handling,Health Physics,Accidents & Environ Areas Per Encl Schedule of Decommissioning Actions ML20141N6651986-03-11011 March 1986 Responds to 860220 Request for Info Re Secy 85-306,including Licensees Using New Interpretations of App R to 10CFR50 & Effect of New Interpretations on Compliance Schedules in EDO 851226 Memo.List of Plants Requesting Evaluations Provided ML20140C9931986-01-17017 January 1986 Comments on Proposed Memo Re Draft Annual Rept to EDO Concerning Use of PRA in Insp Program.Memo Fails to Discuss Emergency Risk Projection (Erp) Initiative.Summary of Erp & Probabilistic risk-based Insp Guidance Encl ML20137B3601986-01-0303 January 1986 Notification of SALP Board Meeting 86-006 on 860121 W/Util in King of Prussia,Pa ML20138J8241985-12-10010 December 1985 Notification of Licensee Meeting 85-125 on 851213 W/Util in King of Prussia,Pa to Discuss Security Program 1998-08-05
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20196J9371998-12-0808 December 1998 Notification of 990120 Meeting with Util in Peekskill,Ny to Inform Public of Licensee Plans for Decommissioning Indian Point Nuclear Generating Station Unit 1 ML20236X5861998-08-0505 August 1998 Summary of 980620 Meeting W/Members of W,Util & NRC in Rockville,Md Re best-estimate Small Break LOCA Model Issues. Attendees List & Nonproprietary Matl Presented at Meeting Encl ML20217E7381997-10-0202 October 1997 Forwards Operator Licensing Exam Administered on 970317-20 W/Outline & Initial Exam Submittal Designated for Distribution Under Rids Code A070 IR 05000247/19970021997-10-0202 October 1997 Forwards NRC Operator Licensing Exam Rept 50-247/97-02 (Including Completed & Graded Tests) for Tests Administered on 970317-20 ML20236N0661997-05-0202 May 1997 Responds to from Consolidated Edison Requesting Interpretation of TS as to Definition of Operable as It Applies to Afs Under Certain Scenarios ML20136C1031997-03-0606 March 1997 Forwards Correspondence Transmitted Via Internet to J Zwolinski from P Blanch During 970102-31.Requests Correspondence Be Placed in PDR ML20134N6211997-02-19019 February 1997 Forwards Response to SB Bram to EDO Re Proposed Corporate Reorganization of Consolidated Edison Co of Ny Approved W/Edit by Chairman for Dispatch ML20134N6371997-01-14014 January 1997 Requests Concurrence Re Proposed Response to SB Bram to EDO Concerning Proposed Corporate Reorganization of Consolidated Edison Co of Ny by Close of Business on 970117 ML20129K2561996-11-0505 November 1996 Notification of Significant Licensee Meeting 96-109 W/Listed Attendees on 961202-03 in Philadelphia,Pa to Provide Training,Resolve Interagency Exercise Scheduling Conflicts & Discuss Current Issues in Emergency Preparedness ML20211E9921995-11-0808 November 1995 Informs of Plan to Augment Plant,Unit 3 Resident Staff & Provide around-the-clock Insp Coverage During Plant Restart from Current Unplanned Outage.Primary Objectives of Insp Listed ML20211D9061995-08-14014 August 1995 Forwards Final Rev to Plant,Unit 3 Restart Action Plan Based Upon Completion of Insp Activities & Util Oversight ML20203B9821995-06-29029 June 1995 Discusses OI Repts 1-95-011,1-95-012 & 5-93-014 Re Fitness for Duty Incident,Falsification of Chemistry Records Involving EDG Fuel Oil & Falsification of Fire Protection Records ML20211F0441994-12-21021 December 1994 Requests That Plant,Unit 3 Restart Action Plan Be Replaced W/Encl Rev to Plan ML20236L5841994-11-0909 November 1994 Submits Interpretation of TS Requirement Re Fire Protection for Indian Point Unit 2 Per 940719 Memo NUREG-1299, Forwards Continuation of Curtiss Papers to Be Filed Under Commission Correspondence in Pdr.Advanced Copy Sent to Pdr. List of Documents Included in Four Boxes Encl1994-06-29029 June 1994 Forwards Continuation of Curtiss Papers to Be Filed Under Commission Correspondence in Pdr.Advanced Copy Sent to Pdr. List of Documents Included in Four Boxes Encl ML20211E9541994-05-12012 May 1994 Requests Approval of Process by Which Plant,Unit 3 Restart Issues,As Listed in Restart Action Plan,Will Be Closed. Restart Issue Closure Process Outlined in Encl to Memo ML20134B5061994-04-13013 April 1994 Submits Plants Which Will Be Discussed in Categories Indicated Re Results of Screening Meetings for June 1994. Partially Deleted ML20057C5721993-09-24024 September 1993 Forwards New Page 20,rev 12 of Security Plan Due to Rev 12 Copy Spillover from Page Nineteen Rev 13 Additions.Page Withheld ML20057B2111993-09-16016 September 1993 Forwards Update to Security Plan,Including Table of Contents,Rev 13 to Pages 18,19,21 & 24 & Chapter 11.Encl Withheld ML20056E4571993-08-0505 August 1993 Forwards Technical Review Rept Re, Tardy Licensee Actions Initiated Because of Delayed Replacement of Batteries in Uninterruptible Power Supplies at Plant IR 05000286/19900161990-10-25025 October 1990 Notification of Significant Licensee Meeting 90-127/ Enforcement Conference on 901105 in King of Prussia,Pa to Discuss Licensed Reactor Operator Inattentiveness to Duty Noted in Insp Rept 50-286/90-16 ML20059D1341990-08-30030 August 1990 Notification of 900913 Meeting W/Util in Rockville,Md to Discuss Util Proposal to Upgrade Emergency Diesel Generators at Facility ML20244E2681989-04-12012 April 1989 Summary of Operating Reactors Events Meeting 89-015 on 890412.Discussion of Events,List of Attendees & Three Significant Items Identified for Input Into NRC Performance Indicator Program & Summary of Reactor Scrams Also Encl ML20196C4751988-06-23023 June 1988 Notification of Licensee Requested Meeting 88-097 on 880629 in King of Prussia,Pa to Discuss Security Program Topics ML20151D4271988-03-24024 March 1988 Submits Summary of Actions Discussed at ACRS 335th Meeting on 880310-12 in Washington,Dc,Including ACRS Repts/ Recommendations,Other Actions,Agreements,Assignments & Requests & Future Agenda ML20148D9491988-03-15015 March 1988 Discusses 880315 Operating Reactors Events Meeting 88-11. List of Attendees,Events Discussed & Tabulation of long-term Followup Assignments Detailed in Encls ML20147E3621988-02-28028 February 1988 Summary of 880223 Operating Reactors Events Meeting 88-008. List of Attendees,Tabulation of long-term Followup Assignments to Be Completed & Summary of Reactor Scrams Encl ML20195H0201988-02-16016 February 1988 Forwards Proposed Updated SALP Evaluation for Plant. Evaluation Based on Insps & Examiner Reviews Conducted During SALP Period Form 860801-870207 ML20195H0081987-12-0101 December 1987 Forwards Input for SALP Rept for Aug 1986 - Nov 1987 ML20147F8761987-10-21021 October 1987 Discusses 871022 Meeting W/Staff to Discuss NRC Position Re Util Steam Generator Replacement Program.Brief Summary of Licensee Position on Why Replacement Can Be Accomplished Under 10CFR50.59 Listed in Encl 1 ML20204G2771987-03-23023 March 1987 Notification of 870326 Meeting W/Util in Bethesda,Md to Discuss Info Required to Support Decommissioning Plan & Need for Environ Statement.Meeting Originally Scheduled for 870324 ML20207R2151987-03-10010 March 1987 Notification of 870324 Meeting W/Util in Bethesda,Md to Discuss Environ Info Required to Support Facility Decommissioning Plan & Need for Environ Statement.Meeting Originally Scheduled for 870310 ML20212F9321987-03-0303 March 1987 Notification of 870310 Meeting W/Util in Bethesda,Md to Discuss Environ Info Required to Support Decommissioning Plan & Need for Environ Statement ML20211K9161987-02-19019 February 1987 Summary of Operating Reactor Events Meeting 87-04 on 870209. List of Attendees,Events Discussed,Significant Elements of Events & Summary of Events Encl ML20209H0831986-12-22022 December 1986 Summarizes INPO 861210 Accreditation Meeting in Atlanta,Ga. Listed Plants Presented Training Programs for Nonlicensed Operators,Reactor Operators,Senior Reactor Operators & Shift Technical Advisors ML20214T3041986-09-17017 September 1986 Notification of Rev 1 to Board Meeting 86-104 on 860923 at Region I to Discuss Regional Evaluation Phase of SALP ML20203N1921986-09-0808 September 1986 Notification of Board Meeting 86-104 W/Util on 860919 in King of Prussia,Pa to Discuss SALP Regional Evaluation Phase ML20207S2141986-08-0707 August 1986 Forwards Commission Directive to Staff to Respond to Shearon Harris Licensing Board Re Emergency Nighttime Alerting.Staff Should Address Alertability During Stormy Winter in Response to Indian Point Board 860609 & 0710 Ltrs ML20207Q7071986-08-0707 August 1986 Staff Requirements Memo Requesting Provision of point-by- Point Response of Generic Safety Concerns Outlined in ASLB .Response to 860609 & 0710 Requests Re Adequacy of Alert Sys During Stormy Winter Nights Also Requested ML20215A5931986-07-30030 July 1986 Forwards Request for Addl Info on Tech Spec Changes in Response to Generic Ltrs 85-09 & 83-28,Item 4.3 Re Reactor Trip Breaker Design Mods.Request Should Be Transmitted,Along W/Generic Ltr 85-09,to Licensee NUREG/CR-2655, Responds to Bl Brandenburg Re NRC on Facility Alert & Notification Sys.Ltr Info out-of-date But Not Inaccurate.Board Never Informed of NUREG/CR-2655.Served on 8607111986-07-10010 July 1986 Responds to Bl Brandenburg Re NRC on Facility Alert & Notification Sys.Ltr Info out-of-date But Not Inaccurate.Board Never Informed of NUREG/CR-2655.Served on 860711 ML20198H9381986-05-16016 May 1986 Notifies of 1986 Indian Point 2 full-participation Exercise on 860604 (Insp Rept 50-247/86-13).Team Assignments, Schedule,Exercise Event & Time Line,Open Items,Objective Lists & Synopsis of State & County Matl Encl.W/O Encl ML20199K4421986-05-10010 May 1986 Comments on Indian Point Special Proceeding.Severe Accident Policy Statement Should Be Reexamined ML20198E7621986-05-0808 May 1986 Informs of Next NRR Operating Reactor Events Briefing Scheduled for 850716 in Bethesda,Md.Guidelines for Participants Encl.Tentative Agenda for Meeting Listed ML20214G3971986-05-0808 May 1986 Forwards Sser on Review of Design for Automatic Shunt Trip for Reactor Trip Breakers.Util Response for Seismic Qualification Issue Acceptable.Licensee Will Be Required to Submit Tech Spec Changes ML20198E7981986-05-0808 May 1986 Informs That 850716 NRR Operating Reactor Events Briefing 85-12 Rescheduled for 850723 in Bethesda,Md.Agenda Encl ML20205N1051986-04-24024 April 1986 Requests Assistance in Review of Fuel Handling,Health Physics,Accidents & Environ Areas Per Encl Schedule of Decommissioning Actions ML20141N6651986-03-11011 March 1986 Responds to 860220 Request for Info Re Secy 85-306,including Licensees Using New Interpretations of App R to 10CFR50 & Effect of New Interpretations on Compliance Schedules in EDO 851226 Memo.List of Plants Requesting Evaluations Provided ML20140C9931986-01-17017 January 1986 Comments on Proposed Memo Re Draft Annual Rept to EDO Concerning Use of PRA in Insp Program.Memo Fails to Discuss Emergency Risk Projection (Erp) Initiative.Summary of Erp & Probabilistic risk-based Insp Guidance Encl ML20137B3601986-01-0303 January 1986 Notification of SALP Board Meeting 86-006 on 860121 W/Util in King of Prussia,Pa 1998-08-05
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2006& 4001
\ *****/ August 5, 1998 MEMORANDUM TO: Thomas H. Essig, Acting Chief Generic issues and Environmental Projects Branch Division of Reactor Program Management Office of Nuclear Reactor Regulation
/
FROM: Peter C. Wen, Project Manager Generic Issues and Environmental Projects Branch fd C INA Division of Reactor Program Management Office of Nuclear Reactor Regulation
SUBJECT:
SUMMARY
OF JULY 20,1998, MEETING WITH WESTINGHOUSE REGARDING BEST-ESTIMATE SMALL BREAK LOCA MODEL ISSUES On June 20,1998, a public meeting was held at the U.S. Nuclear Regulatory Commission's (NRC's) offices in Rockville, Maryland, between members of Westinghouse, utility, and NRC staff. Attachment i lists attendees at the meeting. Attachment 2 is a copy of the non-proprietary material presented at the meeting.
The meeting started with a presentation by a Westinghouse representative of the meeting agenda and current loss-of-coolant accident (LOCA) model development activities within Westinghouse. Some of these activities include the program of developing the best-estimate small break LOCA model. This program is a joint partnership between Westinghouse / Consolidated Edison Company and Electric Power Research Institute. The lead plant to apply this methodology is Indian Point Unit 2.
Next, an utility representative presented the utility point of view. He stated that Con Edison was taking a lead role in the industry by having completed the best-estimate large break LOCA analysis project and initiating the best-estimate small break LOCA analysis project in response to the new 10 CFR 50.46 and Reg Guide 1.157. He emphasized that by using the best-estimate model they saw a real benefit in improving safety. He stated that this is achieved through better understanding of the transients, focusing on the real safety issues, and demonstrating more margins to the safety limits. He said that the increased flexibility in g operations would lead to better operator training and more flexible and safe operations. Also l through higher peaking factors, vessel fluence could be reduced. He also pointed out that the l best-estimate model could be a cost-beneficiallicensing action because of the significant saving \
through fuel management improvements, reduced reactor trips, and potential power uprating P and life extension.
p' b b Finally, another Westinghouse representative presented the overall technical approach of the best-estimate small break LOCA model. This portion of the presentation was involved in discussion on Westinghouse proprietary information.
g g 9808100121 990805 PDR ORG NRRA g $ 0 -f - 2 W W,. - FCCS PDR q
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T. Essig August 5, 1998 l
Major discussion points regarding the schedule for submitting the topical reports for NRC staff
! review and the format of the submittal are as follows:
l Westinghouse plans to submit the related topical reports in late 1998, and requested the staff to begin a review in early 1999. The approved methodology will then be used in the Indian Point Unit 2's reload safety analysis in 2001-2002 time frame.
l The staff emphasized the importance of following the code scaling, applicability and l uncertainty (CSAU) approach and providing documentation which is complete, comprehensive, and well formatted. The document is expected to be well indexed with a road map and comparison against the CSAU approach up-front. The staff stated that it would perform an acceptance review of the documentation to assure that these characteristics are evident.
. The staff indicated that there are no funds budgeted for contractor support; thus, the submitted topical reports' review would have to be performed in-house on a schedule i consistent with the staff's workload.
The representatives of the NRC, Westinghouse, and utility agreed that this meeting was useful in accelerating the information exchange.
L l Attachments: As stated cc w/atts: See next page l
1 I'
T. Essig -2 August 5, 1998 Major discussion points regarding the schedule for submitting the topical reports for NRC staff review and the format of the submittal are as follows:
Westinghouse plans to submit the related topical reports in late 1998, and requested the staff to begin a review in early 1999. The approved methodology will then be used in the Indian Point Unit 2's reload safety analysis in 2001-2002 time frame.
The staff emphasized the importance of following the code scaling, applicability and uncertainty (CSAU) approach and providing documentation which is complete, comprehensive, and well formatted. The document is expected to be well indexed with a road map and comparison against the CSAU approach up-front. The staff stcted that it would perform an acceptance review of the documentation to assure that these characteristics are evident.
The staff indicated that there are no funds budgeted for contractor support; thus, the submitted topical reports' review would have to be performed ir'-house on a schedule consistent with the staff's workload.
The representatives of the NRC, Westinghouse, and utility agreed that this meeting was useful in accelerating the information exchange.
Attachments: As stated cc w/atts: See next page DISTRIBUTION: See attached page
- See Previous Concurrence Dr.cument Name: g:\pxw\msum0720.wst OFFICE PM:PGEB:DRPM SC:SRXB SC:PGEffffvt, NAME PWen:sw M EWeiss* FAkstulewb DATE 8/5 /98 8/ 5 /98 8d/98 OFFICIAL OFFICE COPY
i
- l NRC/ WESTINGHOUSE MEETING ON BEST-ESTIMATE SBLOCA MODEL ISSUES LIST OF ATTENDEES l
July 20,1998 I
NAME ORGANIZATION Eric Weiss NRR/SRXB Ralph Caruso NRR/SRXB Frank Orr NRR/SRXB l Joseph Staudenmeier NRR/SRXB Ralph Landry NRR/SRXB Jefferey Harold NRR/DRPE Peter Wen NRR/PGEB Arthor Ginsberg Consolidated Edison Co.
Jeffrey Bass Westinghouse L Steve Bajorek Westinghouse i
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Attachment 1
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1 Westinghouse / Con Edison / EPRI l Best Estimate Small Break LOCA Methodology Development Program J. C. Bass Manager, LOCA Integrated Services Westinghouse Electric Co.
(412) 374-4262 July 20,1998 l
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l NRC..MTG_SB_BELOCA Ira
AGENDA I. Introduction (S. Ira) a) Introduction to Overall Plan and Objectives
)
II. Industry Needs and Benefits (A. Ginsberg) a) Utility Perspective b) Technical Henefits III. Technical Approach (S. M. Bajorek) a) CSAU Approach Applied to SBLOCA b) Small Break PIRT c) Code Revisions and V&V for BE-SBLOCA d) PWR Calculations / Scoping Study Results e) Statistical Methodology 0 Current Issues IV. Proposed Schedule for Submittals/ Review (S. M. Bajorek) ,
V. Discussion (All) 4 NRC_hfrG_SB_BELOCA_ Ira
INTRODUCTION WESTINGHOUSE IS COMMITTED TO THE DEVELOPMENT OF STATE-OF-THE-ART METHODOLOGIES FOR LOSS OF COOLANT LOCA ANAYSIS
> CONTINUED DEVELOPMENT INSURES:
>> SAFETY
>> COST EFFECTIVE OPERATION
>> ABILITY TO UNDERSTAND NEW & EVOLVING ISSUES
> LONG TERM LOCA DEVELOPMENT PLAN HAS INCLUDED:
>> APPENDIX K MODEL IMPROVEMENTS
>> INTERIM "SECY" METHODOLOGY FOR 2-LOOP UPI PWRS
>> BEST ESTIMATE LARGE BREAK LOCA l l
>> AP600 BELOCA ANALYSIS
> OUR INTENTION IS TO CONTINUE ADVANCED T/H CODE DEVEL-l OPMENT TO MEET CUSTOMER AND REGULATORY NEEDS l
> BEST ESTIMATE SMALL BREAK LOCA IS THE NEXT STEP NRC_MTG_SB_BELOCA_ Ira
BEST ESTIMATE SMALL BREAK LOCA PROGRAM JOINT PARTNERSHIP BETWEEN WESTINGHOUSE / CON EDISON (
AND EPRI
> LEAD PLANT IS INDIAN POINT UNIT 2 i
PROGRAM MAJOR OBJECTIVES
> DEVELOP AND LICENSE A BEST ESTIMATE SMALL BREAK METHODOLOGY GENERICALLY APPLICABLE TO CONVEN-TIONAL WESTINGHOUSE 3 and 4 LOOP PWRS.
> PERFORM A PLANT SPECIFIC APPLICATION FOR INDIAN POINT UNIT 2. l J
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NRC_MTG_SB_BELOCA_ Ira t
7
.o OHJECTIVES FOR TODAY'S MEETING l
- 1. DEMONSTRATE THAT THE FEASIBILITY OF CSAU TYPE OF l-METHODOLOGY FOR BEST ESTIMATE SMALL BREAK ANALYSIS &
SHOW THAT WESTINGHOUSE CAN AND WILL FORMAT THE METH-ODOLOGY TO ACCOMODATE AN EFFICIENT REVIEW.
- 2. IDENTIFY & DISCUSS ANY MAJOR ISSUES l
- 3. PROPOSE A REVIEW SCHEDULE l'
t NRC_MTG_SB_BELOCA_ Ira
s cc:
Mr. Nicholas Liparulo, Manager Equipment Design and Regulatory Engineering Westinghouse Electric Corporation Mail Stop ECE 4-15 P.O. Box 355 Pittsburgh, PA 15230-0355 Mr. Jack Bastin, Director Regulatory Affairs Westinghouse Electric Corporation 11921 Rockville Pike Suite 107 Rockville, MD 20852 Mr. Hank Sepp, Manager Regulatory and Licensing Engineering Westinghouse Electric Corporation PO Box 355 Pittsburgh, PA 15230-0355 Mr. Steve Bajorek Westinghouse Electric Corporation PO Box 355 Pittsburgh, PA 15230-0355 4
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1 l
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s Distribution: Mtg. Summary w/ Westinghouse Re Best-Estimate SBLOCA Model Issues Dated 8]5/9d Hard Cooy Docket File '
PUBLIC PGEB R/F-OGC ACRS PWen Eric Weiss Ralph Caruso Frank Orr Joseph 4taudenmeier Ralph Landry .
Jefferey Harold EMail SCollins/FMiraglia BSheron RZimmerman BBoger JRoe DMatthews TEssig FAkstulewicz TCollins GHolahan SNewberry GTracey, EDO I i
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