Summary of 750630 Meeting W/Mark II Owners,Aes & GE in Bethesda,Md Re Role of Mark II Owners,Status of Const of Various Mark II Units & Program for Determining Mark II LOCA & Safety/Relief Valve Loads| ML20214G779 |
| Person / Time |
|---|
| Site: |
Nine Mile Point, Susquehanna, Columbia, Limerick, LaSalle, 05000000, Zimmer, Shoreham, Bailly |
|---|
| Issue date: |
07/03/1975 |
|---|
| From: |
Cutchin J
Office of Nuclear Reactor Regulation |
|---|
| To: |
Office of Nuclear Reactor Regulation |
|---|
| References |
|---|
| CON-WNP-0032, CON-WNP-32 NUDOCS 8605220496 |
| Download: ML20214G779 (23) |
|
|
|---|
Category:MEETING MINUTES & NOTES--CORRESPONDENCE
MONTHYEARML20217D1001999-09-24024 September 1999
Summary of 990901 Meeting with Nmpc,Nyseg & Amergen Energy Co in Rockville,Maryland Re NMPC Plans & Pending Submittal Re Transfer of NMPC Interest & Authorities Under Operating Licenses for Nine Mile Point
ML20207K3831998-12-31031 December 1998
Summary of 981218 PRB Meeting Re 2.206 Petition Request from P Gunter to W Travers,Nrc Requesting That NRC Convene Public Hearing to Consider Revocation of Nine Mile Point,Unit 1 Operating License
ML20198J1651998-12-15015 December 1998
Summary of 981118 Meeting with Util in Rockville,Md Re Ampacity Validation Analyses.List of Attendees & Handouts Provided by Util Encl
ML20203H2091998-02-24024 February 1998
Summary of 980211 Telcon W/Niagara Mohawk Power Corp on Licensee Progress in Responding to NRC Request for Addl Info Requested During 970822 Telcon Re Licensee Application for License Amend to Change Rc Chemistry Requirements in TSs
ML20216G5171997-09-0404 September 1997
Summary of 970805 Meeting W/Util Re Thermo-Lag Corrective Actions at Peach Bottom & Limerick.List of Attendees & Meeting Handouts Encl
ML20141H9231997-05-20020 May 1997
Summary of 970516 Telcon W/Niagara Mohawk Power Corp Re Licensee Plans for non-code Repair to Reactor Water Cleanup Sys Piping at Nine Mile Point Nuclear Station 1. List of Participants & Info Submitted by Licensee Encl
ML20140F3561997-04-30030 April 1997
Summary of 970414 Meeting W/Util in Rockville,Md to Discuss Issues Associated W/Use of Thermo-Lag Fire Barrier Matl at Plants.Meeting Attendees & Handouts Encl
ML20137Z4011997-04-18018 April 1997
Summary of 970410-11 Telcon W/Util Re Licensee on Core Shroud Welds & Tie Rod Assemblies for Plant
ML20147J1271997-04-0707 April 1997
Summary of Telcon on 970403 W/Nmpc to Discuss Licensees Observations from Insp of Weld 32-WD-050 Between Recirculation Sys Suction Piping & Isolation Valve 32-376 at Plant
ML20134M3841997-02-13013 February 1997
Summary of 970128 Meeting W/Util to Discuss Program to Dispose of Weapons Grade Pu Through Use as Mixed Oxide Fuel. List of Attendees & Matl Used in Presentation Encl
ML20133G1401997-01-10010 January 1997
Summary of 961025 Meeting W/Peco in Delta,Pa Re Status of Licensing Actions Associated W/Plants.List of Attendees & Copy of Presentation Matl Encl
ML20059J0261994-01-24024 January 1994
Summary of 931214 Meeting W/Representatives of PECO to Discuss Risk of Performing 24 H Emergency DG Testing at Power.List of Attendees Encl
ML20059J8071994-01-19019 January 1994
Summary of Operating Reactors Events Meeting 94-02 on 940112
ML20217D4611993-12-0808 December 1993
Summary of 931206 Meeting W/Commonwealth Edison Co Re Items of Mutual Interest Re Operations at Utilities Nuclear Power Plants,W/Special Attention Devoted to Activities at Quad Cities Nuclear Station,Units 1 & 2
ML20058F0451993-11-24024 November 1993
Summary of 931103 Meeting W/Util in Rockville,Md Re Submittal Plans for Cost Beneficial Licensing Actions & to Get Feedback from NRC Staff.List of Attendees Encl
ML20059H9941993-11-0808 November 1993
Summary of 931019 Meeting W/Util Re Discussions on Status of Current MOV Testing Program & NRC GL 89-10.List of Attendees & Meeting Agenda Encl
ML20058M5891993-09-27027 September 1993
Summary of Operating Reactors Events Meeting 93-36 on 930922
ML20058M1861993-09-22022 September 1993
Summary of Operating Reactors Events Meeting 93-35 on 930915
ML20149D6051993-09-15015 September 1993
Summary of 930708 Region III Annual Training Managers Conference in Glen Ellyn,Il.Purpose of Meeting to Provide Forum for Discussion on Rev 7 of Operator Licensing Examiner Stds & to Discuss Operator Licensing Issues
ML20057B4771993-09-15015 September 1993
Summary of 930824 Meeting W/Util Re Implementation of dual-site Senior Reactor Limited to Fuel Handling (Lsr) Program.List of Meeting Attendees & Meeting Handouts Encl
ML20059C9731993-09-0808 September 1993
Summary of 400th ACRS Meeting on 930805-06 in Bethesda,Md Re Proposed Resolution of GSI 57, Effects of Fire Protection Sys Actuation on Safety-Related Equipment & Lessons Learned from LaSalle Fire & Report on ABWR Fire Safety Issues
ML20057A5691993-09-0202 September 1993
Summary of 930809 Meeting W/Util in Wayne,Pa Re Various Licensing Activities Re Plants.List of Attendees Encl
ML20056D7471993-07-27027 July 1993
Summary of 930617 Meeting W/Util to Discuss Steps Being Taken by Licensee to Resolve Reactor Vessel Water Level Instrumentation Degassing Issue.List of Attendees Encl
ML20128H6211993-02-0808 February 1993
Summary of 921123-24 Meeting in King of Prussia,Pa Re Positions on Operator Licensing Issues & to Solicit Input
ML20059C7311993-01-30030 January 1993
Summary of 391st ACRS Meeting on 921105-07 in Bethesda,Md Re NRC Regulatory Analysis Guidelines & Reactor Operating Events & Occurrences,Shearon Harris Plant Loss of High Head SI & LaSalle Overfill Due to Failure of MFW Pumps to Trip
ML20128C9371993-01-14014 January 1993
Summary of 921110 Meeting W/Util in Rockville,Md Re Two Issues Affecting Activities Performed During Refueling Outages
ML20125E5551992-12-14014 December 1992
Summary of 921123 Meeting W/Utils in Rockville,Md Re Temporary Radwaste Sys.Licensee Anticipates Making Formal Submittal to NRC of Proposed Temporary Spent Fuel Pool Cleanup Sys by 921215
ML20126F1241992-12-10010 December 1992
Summary of 921201 Meeting W/Util in Rockville,Md Re Various Licensing Activities.List of Attendees Encl
ML20125D0991992-12-0101 December 1992
Summary of 921022-23 Meeting W/Lipa Re Status of Plant Decommissioning Project
ML20127A4961990-06-0707 June 1990
Summary of 900529 Meeting W/Nrr Allegation Review Board Re Allegation NRR-89-A-0023, Molded Case Circuit Breakers Adjustment Procedures
ML20247R0161989-09-21021 September 1989
Summary of Operating Reactors Events Meeting 89-34 on 890920 to Brief Senior Managers & Regional Offices on Selected Events That Occured Since Last Meeting
ML20247E3641989-09-0606 September 1989
Summary of 890717 Meeting W/Numarc,B&W Owners Group & Representatives of Lead Plants Re Status of STS Amends & Outstanding Issues Associated W/Lead Plant STS Submittals
ML20247D5291989-09-0505 September 1989
Summary of Operating Reactors Events Meeting 89-31 on 890830.Significant Event for Input Into NRC Performance Indicator Program Identified
ML20247K2471989-08-24024 August 1989
Trip Rept of Staff 890718-19,21 & 0801-02 Visits to Nuclear Power Plants to Gather Info Re Industry Actions to Address Loss of Oil Malfunctions of Rosemount Models 1153 & 1154 Transmitters
ML20246K2171989-08-24024 August 1989
Summary of Operating Reactors Events Meeting 89-30 on 890823 Re Reactor Trip W/Multiple Instrumentation & Equipment Failures at DC Cook Unit 2 on 890814 & Auxiliary Feedwater Flows at Hb Robinson
ML20246E1531989-08-16016 August 1989
Summary of 890727 Meeting W/Util,Nus Corp,Conner & Wetterhahn,Bechtel,Bnl & State of PA in Rockville,Md Re Severe Accident Issues.Licensee Presented Info Re Comparison of Core Damage for Accident Classes in PRA
ML20248B5171989-08-0303 August 1989
Summary of 890725 Interface Meeting W/Util in Birrmingham,Al Re Sonopco/Util Corporate Organization Including Generic Activities & Initiatives Re Plants.Agenda & Viewgraphs Encl
ML20245G5421989-08-0303 August 1989
Summary of Operating Reactors Events Meeting 89-28 on 890802.List of Attendees,Events Discussed & Significant Elements of Events & Summaries of Reactor Scrams for Wks Ending 890723 & 30 Encl
ML20246P7771989-07-13013 July 1989
Summary of Operating Reactors Events Meeting 89-26 on 890712.Events Discussed & Significant Elements of Events Presented in Encl 2.List of Attendees Also Encl
ML20246F8691989-06-22022 June 1989
Summary of Operating Reactors Events Meeting 89-24 on 890621.On 890615,potential Unmonitored Primary Coolant Release Path to Environ Discovered at WPPSS-2.On 890617,loss of Offsite Power Occurred at Brunswick,Unit 2
ML20245G6411989-06-15015 June 1989
Summary of Operating Reactors Events Meeting 89-23 on 890614.On 890607,multiple Electrical Distribution Sys Problems Occurred at Oconee,Units 1,2 & 3.On 890610,unit Power Signal Caused Scram
ML20245F2221989-06-0808 June 1989
Summary of Operating Reactors Events Meeting 89-21 on 890531.List of Attendees & Related Info Encl
ML20245A3851989-05-30030 May 1989
Summary of Operating Reactors Events Meeting 89-20 on 890524.List of Meeting Attendees & Viewgraphs Encl
ML20247M7961989-05-24024 May 1989
Summary of 890502 Meeting W/Util,Sargent & Lundy & Rl Cloud Assoc in Rockville,Md Re Nonlinear Piping Analyses Used to Justify Removal of Snubbers & Pipe Supports.List of Attendees & Presentation by Licensee & Contractors Encl
ML20247K0901989-05-23023 May 1989
Summary of 890517 Meeting W/Inpo Re Similarities & Differences Between Performance Indicator Programs.Detailed Discussion Encl
ML20247J7051989-05-19019 May 1989
Summary of 890501 Meeting w/C-E Owners Group in Rockville,Md Re Diverse Emergency Feedwater Actuation Sys,Per 10CFR50.62 Requirements.List of Meeting Attendees & Viewgraphs Encl. Record Copy
ML20247J6991989-05-19019 May 1989
Summary of 890501 Meeting w/C-E Owners Group in Rockville,Md Re Diverse Emergency Feedwater Actuation Sys,Per 10CFR50.62 Requirements.List of Meeting Attendees & Viewgraphs Encl
ML20247K1011989-05-16016 May 1989
Summary of 890517 Meeting W/Inpo in Bethesda,Md Re Similarities & Differences Between INPO & NRC Performance Indicators
ML20247D3441989-05-16016 May 1989
Summary of Operating Reactors Events Meeting 89-19 on 890510.List of Attendees,Events Discussed & Significant Elements of Events & Rept of long-term Followup Assignments & Summary of Scrams for Wk Ending 890507 Encl
ML20247R6001989-05-15015 May 1989
Summary of ACRS Subcommittee on Limerick Unit 2 Meeting on 890425 in Philadelphia,Pa Re Application for Ol.Statement of Limerick Ecology Action Encl
1999-09-24
[Table view]
Category:MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
MONTHYEARML20217D1001999-09-24024 September 1999
Summary of 990901 Meeting with Nmpc,Nyseg & Amergen Energy Co in Rockville,Maryland Re NMPC Plans & Pending Submittal Re Transfer of NMPC Interest & Authorities Under Operating Licenses for Nine Mile Point
ML20207K3831998-12-31031 December 1998
Summary of 981218 PRB Meeting Re 2.206 Petition Request from P Gunter to W Travers,Nrc Requesting That NRC Convene Public Hearing to Consider Revocation of Nine Mile Point,Unit 1 Operating License
ML20198J1651998-12-15015 December 1998
Summary of 981118 Meeting with Util in Rockville,Md Re Ampacity Validation Analyses.List of Attendees & Handouts Provided by Util Encl
ML20203H2091998-02-24024 February 1998
Summary of 980211 Telcon W/Niagara Mohawk Power Corp on Licensee Progress in Responding to NRC Request for Addl Info Requested During 970822 Telcon Re Licensee Application for License Amend to Change Rc Chemistry Requirements in TSs
ML20216G5171997-09-0404 September 1997
Summary of 970805 Meeting W/Util Re Thermo-Lag Corrective Actions at Peach Bottom & Limerick.List of Attendees & Meeting Handouts Encl
ML20141H9231997-05-20020 May 1997
Summary of 970516 Telcon W/Niagara Mohawk Power Corp Re Licensee Plans for non-code Repair to Reactor Water Cleanup Sys Piping at Nine Mile Point Nuclear Station 1. List of Participants & Info Submitted by Licensee Encl
ML20140F3561997-04-30030 April 1997
Summary of 970414 Meeting W/Util in Rockville,Md to Discuss Issues Associated W/Use of Thermo-Lag Fire Barrier Matl at Plants.Meeting Attendees & Handouts Encl
ML20137Z4011997-04-18018 April 1997
Summary of 970410-11 Telcon W/Util Re Licensee on Core Shroud Welds & Tie Rod Assemblies for Plant
ML20147J1271997-04-0707 April 1997
Summary of Telcon on 970403 W/Nmpc to Discuss Licensees Observations from Insp of Weld 32-WD-050 Between Recirculation Sys Suction Piping & Isolation Valve 32-376 at Plant
ML20134M3841997-02-13013 February 1997
Summary of 970128 Meeting W/Util to Discuss Program to Dispose of Weapons Grade Pu Through Use as Mixed Oxide Fuel. List of Attendees & Matl Used in Presentation Encl
ML20133G1401997-01-10010 January 1997
Summary of 961025 Meeting W/Peco in Delta,Pa Re Status of Licensing Actions Associated W/Plants.List of Attendees & Copy of Presentation Matl Encl
ML20059J0261994-01-24024 January 1994
Summary of 931214 Meeting W/Representatives of PECO to Discuss Risk of Performing 24 H Emergency DG Testing at Power.List of Attendees Encl
ML20059J8071994-01-19019 January 1994
Summary of Operating Reactors Events Meeting 94-02 on 940112
ML20217D4611993-12-0808 December 1993
Summary of 931206 Meeting W/Commonwealth Edison Co Re Items of Mutual Interest Re Operations at Utilities Nuclear Power Plants,W/Special Attention Devoted to Activities at Quad Cities Nuclear Station,Units 1 & 2
ML20058F0451993-11-24024 November 1993
Summary of 931103 Meeting W/Util in Rockville,Md Re Submittal Plans for Cost Beneficial Licensing Actions & to Get Feedback from NRC Staff.List of Attendees Encl
ML20059H9941993-11-0808 November 1993
Summary of 931019 Meeting W/Util Re Discussions on Status of Current MOV Testing Program & NRC GL 89-10.List of Attendees & Meeting Agenda Encl
ML20058M5891993-09-27027 September 1993
Summary of Operating Reactors Events Meeting 93-36 on 930922
ML20058M1861993-09-22022 September 1993
Summary of Operating Reactors Events Meeting 93-35 on 930915
ML20149D6051993-09-15015 September 1993
Summary of 930708 Region III Annual Training Managers Conference in Glen Ellyn,Il.Purpose of Meeting to Provide Forum for Discussion on Rev 7 of Operator Licensing Examiner Stds & to Discuss Operator Licensing Issues
ML20057B4771993-09-15015 September 1993
Summary of 930824 Meeting W/Util Re Implementation of dual-site Senior Reactor Limited to Fuel Handling (Lsr) Program.List of Meeting Attendees & Meeting Handouts Encl
ML20059C9731993-09-0808 September 1993
Summary of 400th ACRS Meeting on 930805-06 in Bethesda,Md Re Proposed Resolution of GSI 57, Effects of Fire Protection Sys Actuation on Safety-Related Equipment & Lessons Learned from LaSalle Fire & Report on ABWR Fire Safety Issues
ML20057A5691993-09-0202 September 1993
Summary of 930809 Meeting W/Util in Wayne,Pa Re Various Licensing Activities Re Plants.List of Attendees Encl
ML20056D7471993-07-27027 July 1993
Summary of 930617 Meeting W/Util to Discuss Steps Being Taken by Licensee to Resolve Reactor Vessel Water Level Instrumentation Degassing Issue.List of Attendees Encl
ML20128H6211993-02-0808 February 1993
Summary of 921123-24 Meeting in King of Prussia,Pa Re Positions on Operator Licensing Issues & to Solicit Input
ML20059C7311993-01-30030 January 1993
Summary of 391st ACRS Meeting on 921105-07 in Bethesda,Md Re NRC Regulatory Analysis Guidelines & Reactor Operating Events & Occurrences,Shearon Harris Plant Loss of High Head SI & LaSalle Overfill Due to Failure of MFW Pumps to Trip
ML20128C9371993-01-14014 January 1993
Summary of 921110 Meeting W/Util in Rockville,Md Re Two Issues Affecting Activities Performed During Refueling Outages
ML20125E5551992-12-14014 December 1992
Summary of 921123 Meeting W/Utils in Rockville,Md Re Temporary Radwaste Sys.Licensee Anticipates Making Formal Submittal to NRC of Proposed Temporary Spent Fuel Pool Cleanup Sys by 921215
ML20126F1241992-12-10010 December 1992
Summary of 921201 Meeting W/Util in Rockville,Md Re Various Licensing Activities.List of Attendees Encl
ML20125D0991992-12-0101 December 1992
Summary of 921022-23 Meeting W/Lipa Re Status of Plant Decommissioning Project
ML20127A4961990-06-0707 June 1990
Summary of 900529 Meeting W/Nrr Allegation Review Board Re Allegation NRR-89-A-0023, Molded Case Circuit Breakers Adjustment Procedures
ML20247R0161989-09-21021 September 1989
Summary of Operating Reactors Events Meeting 89-34 on 890920 to Brief Senior Managers & Regional Offices on Selected Events That Occured Since Last Meeting
ML20247E3641989-09-0606 September 1989
Summary of 890717 Meeting W/Numarc,B&W Owners Group & Representatives of Lead Plants Re Status of STS Amends & Outstanding Issues Associated W/Lead Plant STS Submittals
ML20247D5291989-09-0505 September 1989
Summary of Operating Reactors Events Meeting 89-31 on 890830.Significant Event for Input Into NRC Performance Indicator Program Identified
ML20246K2171989-08-24024 August 1989
Summary of Operating Reactors Events Meeting 89-30 on 890823 Re Reactor Trip W/Multiple Instrumentation & Equipment Failures at DC Cook Unit 2 on 890814 & Auxiliary Feedwater Flows at Hb Robinson
ML20246E1531989-08-16016 August 1989
Summary of 890727 Meeting W/Util,Nus Corp,Conner & Wetterhahn,Bechtel,Bnl & State of PA in Rockville,Md Re Severe Accident Issues.Licensee Presented Info Re Comparison of Core Damage for Accident Classes in PRA
ML20248B5171989-08-0303 August 1989
Summary of 890725 Interface Meeting W/Util in Birrmingham,Al Re Sonopco/Util Corporate Organization Including Generic Activities & Initiatives Re Plants.Agenda & Viewgraphs Encl
ML20245G5421989-08-0303 August 1989
Summary of Operating Reactors Events Meeting 89-28 on 890802.List of Attendees,Events Discussed & Significant Elements of Events & Summaries of Reactor Scrams for Wks Ending 890723 & 30 Encl
ML20246P7771989-07-13013 July 1989
Summary of Operating Reactors Events Meeting 89-26 on 890712.Events Discussed & Significant Elements of Events Presented in Encl 2.List of Attendees Also Encl
ML20246F8691989-06-22022 June 1989
Summary of Operating Reactors Events Meeting 89-24 on 890621.On 890615,potential Unmonitored Primary Coolant Release Path to Environ Discovered at WPPSS-2.On 890617,loss of Offsite Power Occurred at Brunswick,Unit 2
ML20245G6411989-06-15015 June 1989
Summary of Operating Reactors Events Meeting 89-23 on 890614.On 890607,multiple Electrical Distribution Sys Problems Occurred at Oconee,Units 1,2 & 3.On 890610,unit Power Signal Caused Scram
ML20245F2221989-06-0808 June 1989
Summary of Operating Reactors Events Meeting 89-21 on 890531.List of Attendees & Related Info Encl
ML20245A3851989-05-30030 May 1989
Summary of Operating Reactors Events Meeting 89-20 on 890524.List of Meeting Attendees & Viewgraphs Encl
ML20247M7961989-05-24024 May 1989
Summary of 890502 Meeting W/Util,Sargent & Lundy & Rl Cloud Assoc in Rockville,Md Re Nonlinear Piping Analyses Used to Justify Removal of Snubbers & Pipe Supports.List of Attendees & Presentation by Licensee & Contractors Encl
ML20247K0901989-05-23023 May 1989
Summary of 890517 Meeting W/Inpo Re Similarities & Differences Between Performance Indicator Programs.Detailed Discussion Encl
ML20247J7051989-05-19019 May 1989
Summary of 890501 Meeting w/C-E Owners Group in Rockville,Md Re Diverse Emergency Feedwater Actuation Sys,Per 10CFR50.62 Requirements.List of Meeting Attendees & Viewgraphs Encl. Record Copy
ML20247J6991989-05-19019 May 1989
Summary of 890501 Meeting w/C-E Owners Group in Rockville,Md Re Diverse Emergency Feedwater Actuation Sys,Per 10CFR50.62 Requirements.List of Meeting Attendees & Viewgraphs Encl
ML20247D3441989-05-16016 May 1989
Summary of Operating Reactors Events Meeting 89-19 on 890510.List of Attendees,Events Discussed & Significant Elements of Events & Rept of long-term Followup Assignments & Summary of Scrams for Wk Ending 890507 Encl
ML20247K1011989-05-16016 May 1989
Summary of 890517 Meeting W/Inpo in Bethesda,Md Re Similarities & Differences Between INPO & NRC Performance Indicators
ML20247R6001989-05-15015 May 1989
Summary of ACRS Subcommittee on Limerick Unit 2 Meeting on 890425 in Philadelphia,Pa Re Application for Ol.Statement of Limerick Ecology Action Encl
ML20246L7281989-05-0505 May 1989
Summary of 890503 Meeting W/Util in Rockville,Md Re Containment Vessel Structural Integrity Tech Specs for Plants.List of Attendees & Licensee Presentation Encl
1999-09-24
[Table view] |
Text
i 1
l l
)
UNITED STATES NUCLEAR REGULATORY COMMfSSION W ASH 4NGTON. D. C. 20555 JVL s GIS l i
Docket Nos. 50-322, 50-352 & 5 353, 50-358, 50-367, 50-373 0-374, 50-387
& 50-388, 50-39 , 50-410 Applicants: Long Island Lighting Company, Philadephia Electric Company, Cincinnati Gas & Electric Company, Northern Indiana Public Service Company, Commonwealth Edison, Pennsylvania Power
& Light Company, Washington Public Power Supply System, Niagara Mohawk Power Corporation Facilities: Shoreham Nuclear Power Station, Unit 1; Limerick Generating Station, Units 1 & 2; Wm. H. Zimmer Nuclear Power Station, Unit 1; Bailly Generating Station, Nuclear 1; LaSalle County Station, Units 1 & 2; Susquehanna Steam Electric Station, Units 1 & 2; WPPSS Nuclear Project No. 2; Nine Mile Point Nuclear Station, Unit 2
SUMMARY
OF MEETING HELD ON JUNE 30, 1975 WITH MARK II OWNERS On June 30, 1975 representatives of the above-named utilities (denoted collectively the " Mark II Owners"), their architect-engineers, General EL itric Company and the NRC staff met in Bethesda, Maryland. The purpose of the neeting was to discuss the role of the Mark II owners, the status of construction of the various Mark II units and the program and schedule for determining Mark II LOCA and Safety /kelief Valve loads and their impact on design. An attendance list and copies of some of the slides used in presentations made at the meeting are enclosed.
Mr. Shelton, as Chairman of the Mark II Owners group, indicated that the group was set up primarily to coordinate resolution of the pool dynamic and safety / relief valve problem for the Mark II Owners and had no legal status.
Therefore, the individual applicants would be dealing with the NRC on all formal contacts. Mr. Shelton would serve as a point of contact with the NRC and the Mark II owners for informal transmittal of information, arranging group meetings and the like but could not speak for them officially.
Since representatives of Pennsylvania Power & Light Company and Philadelphia Electric Company had met with the NRC staff on June 17, they made no further presentations regarding the status of construction of the Susquehanna Steam Electric Station, Units 1 & 2 or the Limerick Generating Station, Units 1
& 2. Since Bailly Generating Station Nuclear 1 and Nine Mile Point Station, Unit 2 either had not begun, or had delayed, construction no presentations regarding the status of construction of those units were made by represent-atives of Northern Indiana Public Service Company or Niagara Mohawk Power Company.
s Wilo,'ll 9 m e z
( d
- 76-19N 8605220496 750703 PDR ADOCK 05000322 A PDR
JUL a D75 Representatives of the other Mark II Owners and their architect-engineers made presentations regarding the status of construction of their respective plants. Construction on all of these units had progressed (or soon should) beyond the wetwell into the drywell. Any design modifications determined to be required will have to be backfit.
A representative of Sargent & Lundy discussed the proposed outline for the
" Preliminary Forcing Function Report" to be submitted this fall.
A representative of General Electric discussed LOCA and Safety / Relief Valve related activities included in the analysis and test program being conducted in support of the Mark II units. He also stated that representatives of the NRC staff would be allowed to come to San Jose to view the German reports from which GE has extracted data applicable to the Mark II design. However, the reports would not be submitted and any notes made by the NRC staff must be labelled proprietary.
Representatives of the NRC staff asked a number of questions, most of which the representatives of the Mark II owners were unable to answer simply because the answers will not be determined until af ter the " Preliminary Forcing Function Report" is completed and available for.use in determining loads to be used in calculating design margins for the individual units.
The Mark II Owners were advised that the schedule proposed for providing information in response to the "10 CFR 50-54(f)" letters transmitted to them in April was obviously not going to result in a very prcept response.
They were further advised to provide us information as rapidly as it becomes available.
.- m ~ , ~ -
J. M. Cutchin IV, Project Manager Light Water Reactors Branch 1-2 Division of Reactor Licensing
Enclosures:
As stated i
k
1 ENCLOSURE 1 ATTENDEES MEETING WITH MARK II OWNERS JUNE 30, 1975 NRC Burns & Roe Bechtel J. M. Cutchin J. Forman J. R. Schmedel R. L. Cudlin B. Bedrosian J. A. Kudrick G. C. Lainas Cincinnati Gas A. L. Gluckman GE & Electric Company Isa Sihweil Pei-Ying Chen D. A. Rockwell E. A. Borgmann B. D. Liaw N. C. Shirley J. D. Flynn F. C. Cherny C. J. DeBevec J. C. Snell Commonwealth Edison Company Pennsylvania Power C. P. Tan & Light Company R. J. Stuart J. W. Johnson John F. Stolz D. P. Galle N. W. Curtis W. F. Kane J. S. Abel W. E. Barberich I
I. A. Peltier B. R. Shelton K. D. Desai G. Arndt P. F. Riehm Stone & Webster G. Bagchi C. I. Grimes D. J. Heesen J. C. Glynn J. P. Allen W. R. Butler R. E. Basso L. C. Shao R. Tedesco R. Maccary LILCO I. Villaiva R. DeYoung T. J. Burke J. P. Navarro WPPSS Niagara Mohawk O. E. Trapp G. L. Gelhaus S. F. Manno Sargent & Lundy NIPSCO G. F. Hoveke D. L. Holtzscher R. M. Crawford R. N. Bergstrom W. G. Hegener PECO R. H. Logue A
A
w JUNE 27, 1975 WM. H. ZIMMER DESCRIPTION OF SRV LOADS
& STRUCTURAL MARGINS WITH MODIFIED PEDESTAL ..
. MIN. MARGINS TYPE OF PEAK . BASE SRV LOAD SOURCE DISCliARGE PRESSURE FREQUENCY SLAB CONTAINMENT PEDESTAL I G.E. QUENCHER +30.7 4 1.76 1.54 1.15 SIMULTANEOUS 4
II G.E. 00ENCHER +30.7 4 2.36 1.98 1,29 SIMULTANEOUS
! III S&L RAMS HEAD +43.2 . 10.0 1.85 1.72 1.05 SIMULTANEOUS IV S&L RAMS HEAD +43.2 4.67 1.33 1.21 g,~1.0 _
SIMULTANEOUS )
V S&L STATIC +43.2 --
3.70 2.11 1.1 VI S&L STATIC +43.2 --
2.52 1.64 1.3
i.
JUNE 26, 1975 .
WN. H. ZIt1MER DESCRIPTI0fl 0F SRV LOADS IflVESTIGATED S0 FAR
^
WITH MODIFIED PEDESTAL TYPE OF ,' PEAK PRESSURES FREQUEflCY g SRV LOAD SOURCE DISCllARGE MAX. MIN. HZ p S o W :2 E D b h (
I G.E OUEflCllER +30,7 - 7.7 4 X X SIMULTAtlE00S -
II G.E. QUEtlCllER +30,7 - 7.7 4 X X SIMULTANE0US III S&L RAMS IIEAD +43.2 -10.8 10.0 X X SIMULTANE0US IV S&L RAMS IlEAD I
- SIMilLTANE0!!S +43.2 -10.8 4.67 X X V S&L STATIC +43.2 -10.8 --
X X VI S&L STATIC +43.2 -10.8 --
X X
~
JUNE 26, 1975 WM. II. ZIMMER
. DESCRIPTION OF LOADS SERVICE LOADS EaCJORED LOADS NORMAL LOADS SEVERE ENVIRONMENTAL LOADS D = DEAD LOADS W = WIND LOADS L = LIVE LOADS Eg = OPERATING BASIS EARTHQUAKE F = PRESTRESSING LOADS 11 = OPERATING FLOOD LOAD T = OPERATING IHERMAL LOADS EXTREME ENVIRONMENTAL LOADS o
Rg = OPERATING PIPE REACTIONS E = SAFE SHUTDOWN EARTHOUAKE SS Py = OPERATING PRESSURE LOADS W TORNADO LOADS T
SRV = SRV DISCHARGE LOAD ll' = MAXIMUM Fto0D LOAD l
TEST-LOADS ABNORMAL LOADS P = TEST PRESSURE Pg = ACCIDENT PRESSURE LOAD 7
T = TEST TEMPERATURE P = SMAtt BREAK PRESSURE LOAD 7 S T = ACCIDENT IEMPERATURE LOAD 3
i R = ACCIDENT PIPE REACTIONS 4
Rg = PIPE RUPTURE LOADS 11 = CONTAINMENT FLOODING LOAD 3
t 0
v
JUNE 26, 1975 Wm. H.-ZIMMER
~ ~ ~ "
CONTA!!EiENT LOAD COMBINATIONS AND LOAD FACTORS I FOR SRV LOADS -
~
LOAD CATEGORIES D L F P T T Eg Rg Rg Py SRV S o 3 ,
NORMAL OPERATING + SRV 1 1.0 1.3 1.0 1.0 1.0 1.0 1.5 SEVERE ENVIRONf1 ENTAL + SRV 2 1.0 1.3 1.0 1.0 1.2'5 1.0 1.0 1.25 ABNORNAL + SRV 3 1.0 1.0 1.0 1.25 1.0
1.0 1.25 ABN/SEY. ENv + SRV li 1.0 1.0 1.0 1.1 1.0 1.1 1.0 1.1 ALLOWABLE STRESSES FOR FACTORED LOADS LOAD DESCRIPTION D = DEAD LOADS SRV = SRV DISCHARGE LOAD l =' LIVE LOADS l Eg = OPERATING BASIS EARTHOUAKE -
F = PRESTRESSING LOADS .,P S
= SMALL BREAK PRESSURE LOAD T o= OPERATING LOADS Tg = ACCIDENT TEMPERATURE LOAD <
Rg= OPERATING PIPE REACTIONS R - ACCIDENT PIPE REACT'!ONS
~
3 Py= ,0PERATING PRESSURE LOADS 9
9
JUNE 26, 1975 WM. H. ZimER
. FSAR LOAD C0fiBINATIONS AND LOAD FACTORS ci LOADING
[- D L F P 7 P, T o T, Eg E ss W N T
R o R, Rg Py H, H W CATEG0P,Y $ .
CONSTR. I 1.0 1.0 1.0 1.0 TEST 2 1.0 1.0 1.0 1.0 1.0
(
NORML 3 1.0 1.0 1.0 1.0 1.0 . 1.0 SEV. ENV. 4 1.0 1.0 1.0 1.0 1.0 1.0 1.0 SEV. ENV. 5 1.0 1.0 1.0 1.0 1.0 1.0 1.0 SEV. ENV. 5 1.0 1.0 1.0 1.0 1.0 1.0 1.0 ABN. 7 1.0 '1.0 1.0 1.0 1.0 1.0 AEN. 8 1.0 1.0 1.0 1.0 1.0 1.0 ABN/S.E. 9 1.0 1.0 1.0 .1. 0 1.0 1.0 1.0 ABN/S.E. 10 1.0 1.0 1.0 1.0 1.0 1,0 '
1.0 -
( ,
AEN. 11 1.0 1.0 1.0 1.5 1.0 1.0 EXTR.ENV. .12 1.0 1.0 1.0 1.0 1.0 1,0 1.0 EXTR.ENV. 13 1.0 1.0 1.0 1.0 1.0 1.0 1.0 EXTR.ENV. 14 1.0 1.0 1.0 1.0 1.0 1.0 1.0 ABN/S.E.. 15 1.01.01.0 1.25 1.0 1.25 1.0 1.0
,_ABN/E.E.I'16 1.01.01.0 1.0 1.0 1.0 1.0 1.0 _
1TFfN NO 1 10 . REDVirr 10AD At i nWAnt t . TTtMe un 11 _.1c . cncTnocn e nnn ni i nunos cc
JuiTE26,1975 WM H. ZIMMER C0!!TAlfMENT LitlER CRITERIA L
PSAR RrouterMrnt LOAD COMBrHArrons TABLE 2 (LOAb FACTOR 1.0)
MAX. STRAIN 0.57, M IONA1. EEnUIREri@NTS l LDAD COMBIMATJ0tlS TABLE 3 (LOAD EACTOR 1.0) '
ASME Sect 10t Illj O!YISION 1, SUBSEcTron NE ,
"Ct. ASS MC COMDONEtiTs' (F.DITI0tl 1975) .
FATIGUE ANALYSIS (8000 engssuRE CYCLES)
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JUNE 26, 1975 .
LA SALLE COUNTY
- DESCRIPTION OF SRV LOADS .
& STRUCTilRAL MARGINS
- MIN. MARGINS TYPE OF- PEAK BASE SOURCE DISCHARGE PRESSURE FREQUENCY SLAB CONTAINMENT PEDESTAL SRV LOAD I G.Et* QUENCHER +30.7 4 1.37 1.18 1.9 SIMULTANEOUS 11 G .E f
- QuENCl!ER +30.7 4 2.7 1.36 2.0 i
SIMULTANEOUS III S&L RAMS HEAD +51.3 3.48 1.33 1.18 1.26 i SIMULTANEOUS
+51.3 7.14 1,58 1.8 1.15 IV S&L RAMS HEAD SIMULTANEOUS V S&L RAMS HEAD +51.3 4.88 0.85 1.0 1.0 -
i SIMULTANEOUS
+36.5 3.9 1.75 1.5 1.6 VI S&L RAMS HEAD ,
SEQUENTIAL VII S&L STATIC +51.3 -
1.07 1.96 2.2
+51.3 1.43 1.96 2.3 VIII S&L STATIC
" MARGIN = STRUCUTRE CAPACITY / MAXIMUM LOAD.
- PRELIMINARY LOADS BASED UPON S&L EXTRAPOLATION OF G.E. REFERENCE PLANT LOADS.
JUNE 26, 1975 LA SALLE COUNTY DESCRIPTION OF SRV LOADS ' '
INVESTIGATED S0 FAR .
r TYPE OF PEAK PRESSURES FREQUENCY sa SRV LOAD , SOURCE DISCHARGE MAX. MIN. HZ [j ,
gj 3g EE E :s t2 M e a M I G.E,** 00ENCHER +30.7 -7.7 4 X X SIMulTAtlEOUS-11 G.E.** ,
QuErCHEa +30.7 -7.7 4 X X SIMULTANEOUS III S&L RAMS HEAD +51.3 -12,8 3,48 X X SIMULTAtlE00S IV S&L RAMSHEAb +51.3 -12,8 7.14 X X SIMULTAtlEOU'S _
V S&L RAMS HEAD +51.3 -12,8 4,88 X X SIMULTANEOUS VI Sal' rat 1S.NEAD +36.5 -7.2 3,9 X X
- SEQUEtlTIAL VII S&L ' STATIC +51.3 -12.8 -
X X-VIII S&L STATIC +51,3 .-12.8 '
X X
- PRELIMINARY LOADS BASED UP0li S&L EXTRAPOLATION OF G.E. REFERBHEE PLANT LOADS. ,
JUNE 26, 1975 LA SALLE COUNTY DESCRIPTION OF LOADS SERVICE LOADS FACTORED LOADS NORMAL LOADS SEVERE ENVIRONMENTAL LOADS D = DEAD LOADS ,- W = WIND LOADS l = l!VE LOADS Eg = OPERATING BASIS EARTHQUAKE F = PRESTRESSING LOADS H = OPERATINn FLOOD LOAD T = OPERATING IHERMAL LOADS EXTREME ENVIRONMENTAL LOADS l .
o Rg = OPERATING PIPE REACTIONS E = SAFE SHUTDOWN EARTHOUAKE SS Py = OPERATING PRESSURE LOADS W = TORNADO LOADS T
SRV = SRV DISCHARGE LOAD H' = MAXIMUM FLOOD LOAD TEST LOADS ABNORMAL LOADS P = TEST PRESSURE P = ACCIDENT PRESSURE LOAD 7 3 T = TEST TEMPERATURE P = SMALL 3REAK PRESSURE LOAD 7 S T = ACCIDENT TEMPERATURE LOAD 3
R = ACCIDENT PIPE REACTIONS 3
Rg = PIPE RUPTURE LOADS H = CONTAINMENT FLOODING LOAD 3
. JUNE 26, 1975 ;
LASALLE COUNTY
~ '
1 CONTAINMENT l0AD COMBINATIONS AND LOAD FACTORS FOR SRV LOADS l LOAD CATEGORIES D L F P T T Eg R Rg P SRV S o 3 o y 1 ,
NORMAL OPERATING + SRV 1 1.0 1.3 1.0 1.0 1.0 1.0 1.5 SEVERE ENVIRONf1 ENTAL + SRV 2 1-0 1.3 1.0
. 1.0 1.2'S 1.0 -1.0 1.25 ABNORNAL + SRV 3 1.0 1.0 1.0 1.25 1.0 1.0 1.25 ABN/SEv. ENv. + SRV 4 1.0 1.0 1.0 1.1 1.0 1.1 1.0 1.1 d
ALLOWABLE STRESSES FOR FACTORED LOADS I
LOAD DESCRIPTION D = DEAD LOADS SRV = SRV DISCHARGE LOAD -
L = LIVE LOADS Eg = OPERATING BASIS EARTHOUAke F = PRESTRESSING LOADS ,P
, S SMLL BREAK PRESSURE LOAD j To= OPERATING LOADS T =
ACCIDENT TEMPERATURE LOAD
~
3 ,
Ro= OPERATING PIPE REACTIONS Rg -
ACCIDENT PIPE REACTIONS ,
Py= OPERATING PRESSURE LOADS 9
e
JUNE 26, 1975 LA SALLE COUNTY DESIGN LOAD COMBINATIONS .
AND LOAD FACTORS.'
! LOADING D L F P 7
P.3 T
o T
3 E
g E ss N N T
Rg R 3 R, P y H, CATEGORY j TEST 1 1.0 1.0 1.0 1.0 1.0 NORMAL 2 1.0 1.0 1.0 1.0 1.0 1.0 .
ABN. 3 1.0 1.0 1.0 1.5 1.0 1.5 1.0 -1.0 -
~
SEV. ENV. 11 1.0 1.0 1.0 1.0 1.7
! EXTR. ENV. 5 1.0 1.0 1.0 1.0 1.0 1.0 1.0 l EXTR ENV. 6 1.0 1.0 1.0 1.0 1.0 1.0 1.0 _
! ABN/SEV. ENV. 7 1.0 1.0 1.0 1.25 1.0 1.25 1.0 ABN/SEV. ENV. 8 1.0 1.0 -1.0 1.0 1.0 1.0 1.0 ABN/EXTR.ENV. 9 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 ITEMSN0.1-2:SERVICELOADALLOWABLIS ; ITEMS N0. 3 - 9 : FACTORED LOAD ALLOWABLE'
1 JUNE 26, 1975
~LA SALLE COUNTY CONTAlflMENT LINER CRITERIA PSAR REQUIREMENT LOAD COMBINATIONS IABLE 2 (LOAD FACTOR 1.0)
MAX. STRAIN 0.5%
A6DITIONALREQUIREMENTS LOAD COMBINATIONS IABLE 3 (LOAD FACTOR 1.0)
ASME SECTION III, DIVISION 1, SUBSECTION NE
" CLASS MC COMPONENTS" (EDITI0tl 1975)
FATIGUE ANALYSIS (8000 PRESSURE CYCLES)
CONCLUSION WALL LINER ACCEPTABLE. ' BASE SLAB LINER MAY REQUIRE ADDITIONAL ANCHORAGE.
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- FIGURE 5.2-1
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CONCRETE CONTAINMENT STRUCTURE
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. f .Gi. G- DYNAX COMPUTER Mock . -.
1 PFFR OBJECTIVES:
- 1. METHODOLOGY FOR PRELIMINARY DESIGN LOADS
- 2. JUSTIFICATION CONSISTENT WITH TEST DATA
- 3. TIMELY RESPONSE TO NRC QUESTIONS
)
- Report Outline I. Introduction and Brief History II. Description of Events A. Safety Relief Valve Discharge B. Loss of Coolant Accident C. Discussion Load Combination Criteria III. Safety Relief Valve Discharge A. Operating Experience and Test Data - Ramshead B. Operating Experience and Test Data - Diffuser C. High-Temperature Steam-Condensation Vibration IV. Loss of Coolant Accident A. Pressure-Temperature Transients B. Chugging Phenomena C. Lateral Loads on Downcomer Vents D. Pool Swell Phenomena E. Summary of Forcing Functions for Design Load Specification V. Discussion of Criteria for Design Load Combinations A. Suppression Chambers Walls, Basemat and Reactor Vessel Pedestal B. Suppression Chamber Lines C. Diaphragm Floor D. Diaphragm Floor Columns E. Downcomers F. Structures and Components Below Suppression Pool Surface G. Structures and Components Above Suppression Pool Surface e
NARK 11 SUPPORTING PROGRAM ACTIVITY TARGET TYPE SCHEDULE MARK 11 PROGRAM ACTIVITY A. LOCA RELATED TEST DEC. 1975
- 1. "4T" POOL SWELL TEST ANALYSIS MAY 1976
- 2. POOL SWELL VELOCITY BREAKTHROUGH MODEL TEST AUG. 1975
- 3. IMPACT TESTS ON P0OL INTERNAL STRUCTURES ANALYSIS DEC. 1975
- 4. QUALIFY IMPACT MODEL B. SAFETY / RELIEF VALVE RELATED ANALYSIS 9 TO 15 MONTHS
- 1. RELIEF VALVE PIPE CLEARING AFTER ACTIVITY MODEL (QUENCHER)
START ANALYSIS & JULY 1975
- 2. ' DOCUMENT RELIEF VALVE PIPE CLEARING MODEL TEST TEST SEPT 1975
- 3. SRL-1 TEST ANALYSIS 9 TO 15 MONTHS
- 4. CONTINGENCY PLAN -
AFTER ACTIVITY ANALYSIS OF ALTERNATE START LOAD MITIGATION DESIGN
e e
g'o- 39 2
(Meeting Summary)
Distribution R. 5. Boyd Docket File U. Garmill NRC PDR V. Benaroya Local PDR R. Vollmer NRR Reading C. Long V. A. !!oore G. Lainas R. C. DeYoung J. Knight D. Skovholt S. Pawlicki D. Muller L. Shao R. Denise T. Ippolito U. Butler R. Ilouston J. Stol: T. Novak R. Clark D. Ross T. Speis EP Project bbnager D. Vassallo Attorney, OELD K. Kniel IE (3)*
K. Coller M.
A. Schwencer R. Fraley (14)
P. Collins 0. Parr R. Purple G. Lear D. Ziemann LVR l-2 File G. Knighton G. Dicker B. Youngblood W. Regan S. Varga R. W. Klecker F. Schroeder
- 11. Denton R. Tedesco R. Maccary V. Stello B. Grimes M. Spangler R. Ballard Jacob Kastner
/
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