Letter Sequence Meeting |
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|
|
MONTHYEARML20029D9001994-05-0909 May 1994
Summary of 940426 Meeting W/Util & W in Rockville,Md Re TMI Issue II.d.1, Performance Testing of BWR & PWR Relief & Safety Valves. Attendees List & Handout Encl
Project stage: Meeting
1994-05-09
[Table View] |
|
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Category:MEETING MINUTES & NOTES--CORRESPONDENCE
MONTHYEARML20206L4921999-05-10010 May 1999
Summary of 990416 Meeting with Util in Rockville MD to Discuss Matter Re SG Operational Assessments for Current Operating Cycle at Plant,Unit 1
ML20206G1181999-05-0505 May 1999
Summary of 990419-20 Meeting with Southern Nuclear Operating Co,Inc in Rockville,Md Re Matters Related to Implementation of Improved Standard TSs at Farley Nuclear Plant,Units 1 & 2
ML20198S2581998-12-31031 December 1998
Summary of 981215 Meeting with Southern Nuclear Operating Co in Rockville,Md to Discuss Technical Issues Associated with Kaowool Fire Barriers Installed at Farley Nuclear Plant, Units 1 & 2
ML20198M7031998-12-29029 December 1998
Summary of 981215 Meeting with Southern Nuclear Operating Co,Inc in Rockville,Md Re Matters Related to Current Steam Generator Tube Insp at Farley Nuclear Plant,Unit 1.List of Attendees & Meeting Handouts,Encl
ML20195J1361998-11-17017 November 1998
Summary of 981026 Meeting with Util in Rockville,Md to Discuss Plant Analysis of Replacement SG & Evaluation of Other Small Changes for FNP Units 1 & 2 Best Etimate Large Break loss-of-coolant Accident
ML20155C2451998-10-29029 October 1998
Summary of 981008 Meeting with Southern Nuclear Operating Co in Rockville,Md Re Util Repair of Joseph M Farley Nuclear Plant,Unit 1 B SG Tubes & Eddy Current Test Data for Tube R25C51 Submitted by .List of Attendees Encl
ML20155C4141998-10-29029 October 1998
Summary of 981014 Meeting W/Southern Nuclear Operating Co, Inc in Rockville,Md Re Justification of Certain TS Changes Needed to Implement Improved Std TS & NRC Staff Request for Addl Info, .List of Attendees Encl
ML20203C5501997-12-0505 December 1997
Summary of 971120 Meeting W/Southern Nuclear Operating Co to Discuss Matters Related to Steam Generator Replacement Projects Proposed for Both Farley Nuclear Units.List of Attendees Enclosed
ML20199A0161997-10-30030 October 1997
Summary of 971022 Meeting W/Util in Rockville,Md Re Initiatives That Focus on Planned Licensing Actions & Corrective Measures Re Problems Considered by Mgt to Warrant Special Attention
ML20217E1531997-09-25025 September 1997
Summary of 970916 Meeting W/Southern Nuclear Operating Co, Inc in Rockville,Maryland Re Licensees Improved Std TS Conversion Application & Schedule for Submittal.List of Meeting Attendees & Meeting Handouts Encl
ML20217L8701997-08-14014 August 1997
Summary of 970731 Meeting W/Southern Nuclear Operating Co, Inc in Birmingham,Al Re Plant Status,Major Problems & Other Topics at Farley,Hatch & Vogtle Nuclear Plants.List of Attendees & Presentation Handouts Encl
ML20134K7521997-02-12012 February 1997
Summary of 970205 Meeting W/Util & W for Initial Discussion of Utils Plans & Schedule for Submitting Proposed TS Amend Request Re Use of Direct Tube Repair in Repair of SG Tubes. List of Participants & Matl Presented Encl
ML20029D9001994-05-0909 May 1994
Summary of 940426 Meeting W/Util & W in Rockville,Md Re TMI Issue II.d.1, Performance Testing of BWR & PWR Relief & Safety Valves. Attendees List & Handout Encl
ML20056C5231993-06-18018 June 1993
Summary of 930602 Meeting W/Util Re Plant Proposal for Removing 2C Emergency Diesel Generator from TS as Part of Farley Implementation of Station Blackout Rule.List of Attendees Encl
ML20056D6661993-06-0101 June 1993
Summary of Operating Reactors Events Briefing 93-19 on 930526
ML20128C1261992-11-25025 November 1992
Summary of 921026 Meeting W/Util in Houston County,Al Re Future Submittals Planned by Util,Status of NRC Review of Previous Submittals,Responses to Generic Communications,Nrc Concerns & General Coordination of Licensing Activities
ML20128A0111992-11-25025 November 1992
Summary of 920727 Meeting W/Util,Westinghouse & Pnl in Rockville,Md Re Discussions on Steam Line Break Leakage Issues Relating to Licensees SG Tube Alternate Plugging Criteria Proposal.List of Attendees Encl
ML20058K1841990-12-0404 December 1990
Summary of 901107 Meeting W/Util in Rockville,Md Re Steam Generator Tube Collapse Under Combined LOCA & Safe Shutdown Earthquake Loads
ML20044A1971990-06-25025 June 1990
Summary of 900607 Meeting W/Util & Westinghouse in Rockville,Md Re Planned Amends Covering Steam Generator Tube Sleeving in Tube Support Plate Area,Increase in Steam Generator Tube Plugging Limit & RTD Bypass Removal
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
ML20247K0901989-05-23023 May 1989
Summary of 890517 Meeting W/Inpo Re Similarities & Differences Between Performance Indicator Programs.Detailed Discussion Encl
ML20247K1011989-05-16016 May 1989
Summary of 890517 Meeting W/Inpo in Bethesda,Md Re Similarities & Differences Between INPO & NRC Performance Indicators
ML20150B2131988-07-0505 July 1988
Summary of 880601 Meeting W/Util in Rockville,Md Re Antitrust 2.206 Petition.Attendance List Encl
ML20153B0061988-06-17017 June 1988
Summary of CRGR Meeting 137 on 880608 Re Proposed Draft Rule 10CFR52 Concerning Site Permits,Design Certifications & Combined Licenses & Proposed NRC Bulletin Regarding Thermal Stresses in Piping.List of Attendees Encl
ML20153B0011988-06-17017 June 1988
Summary of CRGR Meeting 137 on 880608 Re Proposed Draft Rule 10CFR52 Concerning Site Permits,Design Certifications & Combined Licenses & Proposed NRC Bulletin Regarding Thermal Stresses in Piping.List of Attendees Encl.W/O Stated Encl
ML20151C9691988-04-0808 April 1988
Summary of 880406 Meeting W/Util & Alabama Electric Power Cooperative in Rockville,Md Re Status of Settlement Proposal Presented to NRC in Jan 1988,per 2.206 Antitrust Proceeding. List of Attendees Encl
ML20148L1801988-03-25025 March 1988
Summary of 880318 Meeting W/Utils in Rockville,Md Re Info That Would Be Required in Submittal of Amends to Licenses & CP Held by Utils.Attendees List & Viewgraphs Encl
ML20196J7851988-03-10010 March 1988
Summary of Operating Reactors Events Meeting 88-10 on 880308.List of Attendees & Significant Elements of Events Discussed Encl
ML20150C7261988-03-0909 March 1988
Summary of 880302 Meeting W/Utils in Rockville,Md Re Formation of Separate Operating Organization.List of Attendees & Viewgraphs Encl
ML20149M1771988-02-0808 February 1988
Summary of 880115 Meeting W/Util Discussing Generic Implications of Cracked 6-inch Safety Injection Pipe at Plant.Meeting Attendees & Agenda Encl
ML20196B1461988-01-11011 January 1988
Summary of CRGR Meeting 127 on 871223 Re Proposed Resolution of USI A-47, Safety Implications of Control Sys in LWR Nucl Nuclear Power Plants. Committee Recommended Forwarding Ofc Package to EDO Following Incorporation of CRGR Comments
ML20149F4741988-01-0707 January 1988
Summary of Operating Reactors Events Meeting 88-01 on 870105 Re Events That Occurred Since 871222.List of Attendees & Viewgraphs Encl
ML20237F2471987-12-18018 December 1987
Summary of Operating Reactor Events Meeting 87-44 on 871215. List of Attendees,Events Discussed,Significant Elements of Events & Summary of Reactor Scrams Encl
ML20236L3201987-11-0505 November 1987
Summary of 870924 Meeting W/Util,Bechtel & Rl Cloug Assoc Re Problems Concerning Qualification of V-Type Electrical Splices at Facility.Attendance List Encl
ML20236P2841987-11-0505 November 1987
Summary of Operating Reactors Events Meeting 87-38 on 871103.List of Attendees,Viewgraphs & Summary of Reactor Scrams Encl
ML20235W9431987-10-13013 October 1987
Summary of Operating Reactors Events Meeting 87-32 on 870922.Notes That Meeting 87-31 Did Not Occur.List of Attendees & Events Discussed & Significant Elements of Events Encl
ML20216J4431987-06-26026 June 1987
Summary of 870619 Meeting W/Util & Southern Co Svcs to Discuss Commission Policy Statement for Tech Spec Improvements on Plant Specific Basis.List of Attendees & Pilot Application of Commission Interim Policy... Encl
ML20214S9971987-06-0202 June 1987
Summary of 870505 Meeting W/Util Re Planned Safeguards Mods at Facility
ML20236S4401986-12-30030 December 1986
Summary of 861120 Meeting W/Util Re Proposed Tech Spec Changes to Snubber Surveillance Insp Intervals
ML20212E3601986-12-23023 December 1986
Summary of 861120 Meeting W/Bechtel,Southern Co,Svcs & Alabama Power Co in Bethesda,Md Re Proposed Tech Spec Changes to Snubber Surveillance Insp Intervals.Meeting Agenda,List of Attendees & Viewgraphs Encl
ML20147E8911986-08-20020 August 1986
Trip Rept of 860721-25 Visit to Plant to Observe INPO Accreditation Team Evaluation of Six Training Programs, Including Instrumentation & Control Technician,Mechanical Maint & Electrical Maint.List of Team Members Encl
ML20206L9081986-08-11011 August 1986
Summary of Operating Reactor Events Meeting 86-27 on 860804 W/Ofc Director,Div Directors & Representatives Re Briefing on Events Which Occurred Since Last Meeting on 860728.List of Attendees & Viewgraphs Encl
ML20211P1361986-07-16016 July 1986
Summary of 860707 Operating Reactor Events Meeting 86-23 W/ Div Directors & Representatives Re Events Since Last Meeting on 860630.Notification of Inability to Meet Assigned Target Completion Dates for Actions Requested.Viewgraphs Encl
ML20211G7781986-06-13013 June 1986
Summary of Operating Reactor Events Meeting 86-19 on 860609. List of Attendees,Events Discussed & Status of Previous Assignments Encl
ML20154P0071986-03-12012 March 1986
Summary of Operating Reactor Events 860303 Meeting 86-06 W/Ornl Re Events Occurring Since 860224 Meeting.Followup Review Assignments,Status of Previous Assignments,List of Attendees & Viewgraphs Encl
ML20154C9931986-02-24024 February 1986
Summary of Operating Reactors Event Meeting 86-04 on 860210.List of Attendees,Briefing & Reactor Scram Summaries Encl
ML20132C3761984-08-0808 August 1984
Trip Rept of 840618-20 Site Visit to Observe INPO Accreditation Team to Determine Adequacy of Process as Means of Implementing Sys Approach to Training in Commercial Nuclear Power Industry
ML20033C2231981-11-0909 November 1981
Summary of 811029 Meeting W/Util in Bethesda,Md Re Util Presentation of Diesel Generator Reliability Improvements Program.Agenda Encl
ML20031F1401981-10-0101 October 1981
Summary of 810918 Meeting W/Westinghouse Owners Group Re Pressurized Thermal Shock to Reactor Pressure Vessels. Attendance List & Handouts Encl
ML20010B7411981-08-10010 August 1981
Summary of 810803 Meeting W/Util in Bethesda,Md Re NRC Concerns Relating to Diesel Generator 1C Failures.Failures Possibly Related to Reg Guide 1.108 Testing.Relevant Tech Specs & Attendance Lists Encl
1999-05-05
[Table view]
Category:MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
MONTHYEARML20206L4921999-05-10010 May 1999
Summary of 990416 Meeting with Util in Rockville MD to Discuss Matter Re SG Operational Assessments for Current Operating Cycle at Plant,Unit 1
ML20206G1181999-05-0505 May 1999
Summary of 990419-20 Meeting with Southern Nuclear Operating Co,Inc in Rockville,Md Re Matters Related to Implementation of Improved Standard TSs at Farley Nuclear Plant,Units 1 & 2
ML20198S2581998-12-31031 December 1998
Summary of 981215 Meeting with Southern Nuclear Operating Co in Rockville,Md to Discuss Technical Issues Associated with Kaowool Fire Barriers Installed at Farley Nuclear Plant, Units 1 & 2
ML20198M7031998-12-29029 December 1998
Summary of 981215 Meeting with Southern Nuclear Operating Co,Inc in Rockville,Md Re Matters Related to Current Steam Generator Tube Insp at Farley Nuclear Plant,Unit 1.List of Attendees & Meeting Handouts,Encl
ML20195J1361998-11-17017 November 1998
Summary of 981026 Meeting with Util in Rockville,Md to Discuss Plant Analysis of Replacement SG & Evaluation of Other Small Changes for FNP Units 1 & 2 Best Etimate Large Break loss-of-coolant Accident
ML20155C2451998-10-29029 October 1998
Summary of 981008 Meeting with Southern Nuclear Operating Co in Rockville,Md Re Util Repair of Joseph M Farley Nuclear Plant,Unit 1 B SG Tubes & Eddy Current Test Data for Tube R25C51 Submitted by .List of Attendees Encl
ML20155C4141998-10-29029 October 1998
Summary of 981014 Meeting W/Southern Nuclear Operating Co, Inc in Rockville,Md Re Justification of Certain TS Changes Needed to Implement Improved Std TS & NRC Staff Request for Addl Info, .List of Attendees Encl
ML20203C5501997-12-0505 December 1997
Summary of 971120 Meeting W/Southern Nuclear Operating Co to Discuss Matters Related to Steam Generator Replacement Projects Proposed for Both Farley Nuclear Units.List of Attendees Enclosed
ML20199A0161997-10-30030 October 1997
Summary of 971022 Meeting W/Util in Rockville,Md Re Initiatives That Focus on Planned Licensing Actions & Corrective Measures Re Problems Considered by Mgt to Warrant Special Attention
ML20217E1531997-09-25025 September 1997
Summary of 970916 Meeting W/Southern Nuclear Operating Co, Inc in Rockville,Maryland Re Licensees Improved Std TS Conversion Application & Schedule for Submittal.List of Meeting Attendees & Meeting Handouts Encl
ML20217L8701997-08-14014 August 1997
Summary of 970731 Meeting W/Southern Nuclear Operating Co, Inc in Birmingham,Al Re Plant Status,Major Problems & Other Topics at Farley,Hatch & Vogtle Nuclear Plants.List of Attendees & Presentation Handouts Encl
ML20134K7521997-02-12012 February 1997
Summary of 970205 Meeting W/Util & W for Initial Discussion of Utils Plans & Schedule for Submitting Proposed TS Amend Request Re Use of Direct Tube Repair in Repair of SG Tubes. List of Participants & Matl Presented Encl
ML20029D9001994-05-0909 May 1994
Summary of 940426 Meeting W/Util & W in Rockville,Md Re TMI Issue II.d.1, Performance Testing of BWR & PWR Relief & Safety Valves. Attendees List & Handout Encl
ML20056C5231993-06-18018 June 1993
Summary of 930602 Meeting W/Util Re Plant Proposal for Removing 2C Emergency Diesel Generator from TS as Part of Farley Implementation of Station Blackout Rule.List of Attendees Encl
ML20056D6661993-06-0101 June 1993
Summary of Operating Reactors Events Briefing 93-19 on 930526
ML20128A0111992-11-25025 November 1992
Summary of 920727 Meeting W/Util,Westinghouse & Pnl in Rockville,Md Re Discussions on Steam Line Break Leakage Issues Relating to Licensees SG Tube Alternate Plugging Criteria Proposal.List of Attendees Encl
ML20128C1261992-11-25025 November 1992
Summary of 921026 Meeting W/Util in Houston County,Al Re Future Submittals Planned by Util,Status of NRC Review of Previous Submittals,Responses to Generic Communications,Nrc Concerns & General Coordination of Licensing Activities
ML20058K1841990-12-0404 December 1990
Summary of 901107 Meeting W/Util in Rockville,Md Re Steam Generator Tube Collapse Under Combined LOCA & Safe Shutdown Earthquake Loads
ML20044A1971990-06-25025 June 1990
Summary of 900607 Meeting W/Util & Westinghouse in Rockville,Md Re Planned Amends Covering Steam Generator Tube Sleeving in Tube Support Plate Area,Increase in Steam Generator Tube Plugging Limit & RTD Bypass Removal
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
ML20247K0901989-05-23023 May 1989
Summary of 890517 Meeting W/Inpo Re Similarities & Differences Between Performance Indicator Programs.Detailed Discussion Encl
ML20247K1011989-05-16016 May 1989
Summary of 890517 Meeting W/Inpo in Bethesda,Md Re Similarities & Differences Between INPO & NRC Performance Indicators
ML20150B2131988-07-0505 July 1988
Summary of 880601 Meeting W/Util in Rockville,Md Re Antitrust 2.206 Petition.Attendance List Encl
ML20153B0061988-06-17017 June 1988
Summary of CRGR Meeting 137 on 880608 Re Proposed Draft Rule 10CFR52 Concerning Site Permits,Design Certifications & Combined Licenses & Proposed NRC Bulletin Regarding Thermal Stresses in Piping.List of Attendees Encl
ML20153B0011988-06-17017 June 1988
Summary of CRGR Meeting 137 on 880608 Re Proposed Draft Rule 10CFR52 Concerning Site Permits,Design Certifications & Combined Licenses & Proposed NRC Bulletin Regarding Thermal Stresses in Piping.List of Attendees Encl.W/O Stated Encl
ML20151C9691988-04-0808 April 1988
Summary of 880406 Meeting W/Util & Alabama Electric Power Cooperative in Rockville,Md Re Status of Settlement Proposal Presented to NRC in Jan 1988,per 2.206 Antitrust Proceeding. List of Attendees Encl
ML20148L1801988-03-25025 March 1988
Summary of 880318 Meeting W/Utils in Rockville,Md Re Info That Would Be Required in Submittal of Amends to Licenses & CP Held by Utils.Attendees List & Viewgraphs Encl
ML20196J7851988-03-10010 March 1988
Summary of Operating Reactors Events Meeting 88-10 on 880308.List of Attendees & Significant Elements of Events Discussed Encl
ML20150C7261988-03-0909 March 1988
Summary of 880302 Meeting W/Utils in Rockville,Md Re Formation of Separate Operating Organization.List of Attendees & Viewgraphs Encl
ML20149M1771988-02-0808 February 1988
Summary of 880115 Meeting W/Util Discussing Generic Implications of Cracked 6-inch Safety Injection Pipe at Plant.Meeting Attendees & Agenda Encl
ML20196B1461988-01-11011 January 1988
Summary of CRGR Meeting 127 on 871223 Re Proposed Resolution of USI A-47, Safety Implications of Control Sys in LWR Nucl Nuclear Power Plants. Committee Recommended Forwarding Ofc Package to EDO Following Incorporation of CRGR Comments
ML20149F4741988-01-0707 January 1988
Summary of Operating Reactors Events Meeting 88-01 on 870105 Re Events That Occurred Since 871222.List of Attendees & Viewgraphs Encl
ML20237F2471987-12-18018 December 1987
Summary of Operating Reactor Events Meeting 87-44 on 871215. List of Attendees,Events Discussed,Significant Elements of Events & Summary of Reactor Scrams Encl
ML20236P2841987-11-0505 November 1987
Summary of Operating Reactors Events Meeting 87-38 on 871103.List of Attendees,Viewgraphs & Summary of Reactor Scrams Encl
ML20236L3201987-11-0505 November 1987
Summary of 870924 Meeting W/Util,Bechtel & Rl Cloug Assoc Re Problems Concerning Qualification of V-Type Electrical Splices at Facility.Attendance List Encl
ML20235W9431987-10-13013 October 1987
Summary of Operating Reactors Events Meeting 87-32 on 870922.Notes That Meeting 87-31 Did Not Occur.List of Attendees & Events Discussed & Significant Elements of Events Encl
ML20216J4431987-06-26026 June 1987
Summary of 870619 Meeting W/Util & Southern Co Svcs to Discuss Commission Policy Statement for Tech Spec Improvements on Plant Specific Basis.List of Attendees & Pilot Application of Commission Interim Policy... Encl
ML20214S9971987-06-0202 June 1987
Summary of 870505 Meeting W/Util Re Planned Safeguards Mods at Facility
ML20236S4401986-12-30030 December 1986
Summary of 861120 Meeting W/Util Re Proposed Tech Spec Changes to Snubber Surveillance Insp Intervals
ML20212E3601986-12-23023 December 1986
Summary of 861120 Meeting W/Bechtel,Southern Co,Svcs & Alabama Power Co in Bethesda,Md Re Proposed Tech Spec Changes to Snubber Surveillance Insp Intervals.Meeting Agenda,List of Attendees & Viewgraphs Encl
ML20206L9081986-08-11011 August 1986
Summary of Operating Reactor Events Meeting 86-27 on 860804 W/Ofc Director,Div Directors & Representatives Re Briefing on Events Which Occurred Since Last Meeting on 860728.List of Attendees & Viewgraphs Encl
ML20211P1361986-07-16016 July 1986
Summary of 860707 Operating Reactor Events Meeting 86-23 W/ Div Directors & Representatives Re Events Since Last Meeting on 860630.Notification of Inability to Meet Assigned Target Completion Dates for Actions Requested.Viewgraphs Encl
ML20211G7781986-06-13013 June 1986
Summary of Operating Reactor Events Meeting 86-19 on 860609. List of Attendees,Events Discussed & Status of Previous Assignments Encl
ML20154P0071986-03-12012 March 1986
Summary of Operating Reactor Events 860303 Meeting 86-06 W/Ornl Re Events Occurring Since 860224 Meeting.Followup Review Assignments,Status of Previous Assignments,List of Attendees & Viewgraphs Encl
ML20154C9931986-02-24024 February 1986
Summary of Operating Reactors Event Meeting 86-04 on 860210.List of Attendees,Briefing & Reactor Scram Summaries Encl
ML20033C2231981-11-0909 November 1981
Summary of 811029 Meeting W/Util in Bethesda,Md Re Util Presentation of Diesel Generator Reliability Improvements Program.Agenda Encl
ML20031F1401981-10-0101 October 1981
Summary of 810918 Meeting W/Westinghouse Owners Group Re Pressurized Thermal Shock to Reactor Pressure Vessels. Attendance List & Handouts Encl
ML20010B7411981-08-10010 August 1981
Summary of 810803 Meeting W/Util in Bethesda,Md Re NRC Concerns Relating to Diesel Generator 1C Failures.Failures Possibly Related to Reg Guide 1.108 Testing.Relevant Tech Specs & Attendance Lists Encl
ML20126L2331981-05-0101 May 1981
Summary of 810429 Meeting W/Pwr Owners Group Re Thermal Shock to Reactor Pressure Vessels.All Parties Agree That Thermal Shock W/Subsequent Repressurization Is Safety Concern Needing Prompt Evaluation
ML20003D9551981-03-17017 March 1981
Summary of 810204 Meeting W/Util Re Facility Startup Schedule
1999-05-05
[Table view] |
Text
.-.
- 4
+
emou g
') v UNITED STATES i
NUCLEAR REGULATORY COMMISSION i
j/
WASHINGTON, D.C. 20555-0001 g
- s, May 9. 1994 Docket Nos 50-348 and 50-364 LICENSEE:
Southern Nuclear Operating Company-FACILITIES:
Joseph M. Farley Nuclear Plant, Units 1 and 2
SUBJECT:
MEETING
SUMMARY
RELATED TO TMI ISSUE II.D.1 (TAC NOS. M84666 AND M84667)
On April 26, 1994, a meeting was held with Southern Nuclear Operating Company (SNC or the licensee) and Westinghouse at the NRC Offices at One White Flint North in Rockville, Maryland, to discuss resolution of TMI Issue II.D.1,
" Performance Testing of BWR and PWR Relief and Safety Valves".
The purpose of the meeting was for SNC to address staff concerns contained in a March 23, 1994, letter related to the licensee's October 12, 1993, response to the staff's request for additional information (RAI) on this issue.
contains a list of meeting attendees and Enclosure 2 contains a copy of the-licensee's handout.
In response to the RAI the staff identified several technical deficiencies in the licensee's analysis.
Specifically, SNC attempted to justify the existing design by the use of a non-linear analysis method, did not follow the load combination guidelines developed by the Electric Power Research Institute (EPRI) and did not use a technically appropriate. method of combining responses i
from the non-linear analysis. The licensee requested the meeting to clarify the information contained in its October 12, 1993, response and to obtain a better understanding of the staff's concerns. On the bases of the discussions with the technical staff during the meeting, SNC is going to modify its analysis to determine if some localized stresses in the piping down stream of 1
the power-operated relief valves can be reduced to meet faulted conditions and if a minimum safety factor of three on the anchor bolts can be achieved.
If the stresses cannot be reduced to acceptable limits, SNC has stated that modifications to the existing discharge piping will be made to withstand the loads '(i.e., removal of whip restraints and reinsulation or elimination of the loop seal).
The licensee has agreed to either provide the results 9405120154 940509
/1 PDR ADOCK 05000348 l l; P
pop jl i
100043 30l y
May 9, 1994 Meeting Summary of its reanalysis'or a commitment to make modifications within 90 days of the meeting date.
If SNC proposes modifications a schedule for implementation will be included.
ORIGINAL SIGNED BY:
Byron L. Siegel, Project Manager Project Directorate 11-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Enclosures:
1.
List of Participants 2.
Licensee Handout cc w/ enclosures:
See next page l
1 0FFICE LA:PD21:DRREhlPM:fD2hBAPE,
PDgPD21:,DR_PE s
NAME PAnderso}i W BSie N NtmSn DATE O/Y/94 7/N94 8 / 9 /94 0FFICIAL RECORD COPY Document Name: G:\\FARLEY\\FAR84666\\MTS 4
- S MEETING
SUMMARY
'0F April 26, 1994 DISTRIBUTION w/ enclosure 1 W. Russell /F Miraglia L. Reyes S. Varga G. Lainas W. Bateman B. Siegel P. Anderson 0GC E. Jordan C. Craig A. Thadani
- R. Zimmerman ACRS (10)
L. Plisco DISTRIBUTION w/ enclosures 1 & 2 Docket File PDR & LPDR PD 11-1 Reading File E. Mershoff, Region II J. Fair G. Hammer 4
I L-. - N-
+
Meeting Summary of its reanalysis or a commitment to make modifications within 90 days of the meeting date.
If SNC proposes modifications, a schedule for implementation will be included.
B on L. Siege, Project Manager oject Directorate 11-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Enclosures:
1.
List of Participants 2.
Licensae Handout cc w/ enclosures:
See next page i
I i
i
- - c Joseph M. Farley Nuclear Plant cc:
Mr. R. D. Hill, Jr.
State Health Officer General Manager - Farley Nuclear. Plant Alabama Department of Public Health Southern Nuclear Operating Co., Inc.
434 Monroe Street Post Office Box 470 Montgomery, Alabama 36130-1701 Ashford, Alabama 36312 Chairman Mr. B. L. Moore, Licensing Manager Houston County Commission Southern Nuclear Operating Co., Inc.
Post Office Box 6406 Post Office Box 1295 Dothan, Alabama 36302 Birmingham, Alabama 35201-1295 Regional Administrator, Region II James H. Miller, III, Esquire U. S. Nuclear Regulatory Commission Balch and Bingham Law Firm 101 Marietta St., N.W., Ste. 2900 Post Office Box 306 Atlanta, Georgia 30323 1710 Sixth Avenue North Birmingham, Alabama 35201 Resident Inspector U.S. Nuclear Regulatory Commission Mr. D. N. Morey Post Office Box 24 - Route 2 Vice President Columbia, Alabama 36319 Southern Nuclear Operating Co., Inc.
Post Office Box 1295 Birmingham, Alabama 35201-1295
April 26. 1994 TMI Issue II.D.1 Meetina list of Attendees HAME ORGANIZATION Byron Siegel NRR/DRP/PDII-I John Fair NRR/DE/EMEB Richard Morrison Westinghouse / Licensing Jeff Himler Westinghouse / Structural Eng.
Gary Hammer NRR/DE/EMEB T.H. Liu Westinghouse / Piping Eng Brad Moore SNC Licensing Paul Hayes SNC Licensing D.V. Jagannath Bechtel Plant Design M. Khianey Bechtel Plant Design
ENCLOSURE 2 NRC MEETING ON TMI ACTION NUREG-0737. II.D.1 For Farley Units 1 and 2 Introduction Historical Background NRC SER of 1986 1992 Elastic and inelastic Analyses Response to NRC Request for Additional Information b
3484e.fmk(940425):501
e s
INTRODUCTION Present FNP analysis confirms compliance with II.D.I by demonstrating that as-built discharge piping will not affect PZR safety valve operability.
Further physical changes require significant dose exposure and expenditure without a corresponding benefit to safety.
e I,
3484e.imk(940425)M15
HISTORICAL BACKGROUND 10/80 -
NUREG-0737 TMI action plan requirement issued.
EPRI test program results (7/81).
Plant specific submittal (1/82).
Completion of design basis analysis by 5/81 Westinghouse for Class 1 piping.
Farley past actions in addressing NUREG-0737 II.D.1
- 1/81 APCo initial response to NUREG-0737.
- 2/81 APCo clarification response to NUREG-0737.
- 6/81 APCo commitment to EPRI test program.
- 9/81 NRC request of evaluation supported by test re.sults to be submitted by 7/82.
- 4/82 APCo is a participant of EPRI generic PWR safety and relief valve test program. Valve tested by EPRI represent the Farley design and operating conditions. APCo committed plant specific evaluation done by 7/82.
- 7/82 APCo committed to complete further analysis of the downstream loads based on EPRI test program.
3484e.fmk(940425):50 3
I 11/82 APCo presented.W analysis report based on cold loop seal and using a very conservative evaluation criteria from EPRI test program (WCAP-10105) and its piping sub-committee recommendations. Potential overstress predicted in the NNS piping but concluded the overstress will not effect the operation of pressurizer nozzle, the inlet line, the safety valve. APCo considered the 7/82 commitment satisfactory.
12/86 In its SER, NRC expressed concern on the overstress condition stated in 11/82 submittal. Specific concerns were severe deformation in NNS piping would affect the operability of the safety valves and l
acceptable code qualification.
{
2/87 APCo committed to perform cost benefit study between options of plant modification and additional analysis. Schedule of resolution would be provided.
9/88 APCo informed NRC of alternative approach by raising the loop seal temperature (hot loop seal) via insulation in order to lower the stress in NNS piping. (Hot loop seal not completely obtained due to constraints in pressurizer cavity.)
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Current Issue in Addressing NUREG-0737 II.D.1 8/92 APCo submitted the current W elastic plastic analysis report based on variable loop seal and using a very conservative evaluation criteria from EPRI test program (WCAP-10105) and its piping sub-committee recommendations. To address NRC concerns in 12/86 SER, report concluded that only small plasticity predicted in the NNS piping and the piping will not collapse nor kink. It will maintain fully operable even at the conservative postulation of three safety valves open simultaneously.
1993 APCo response to NRC 1st round inquiry.
1994 NRC 2nd round inquiry.
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NRC SER of 1986 Approval of Farley 1982 Analysis bounding loading case was chosen (met item 3 of Section 1.2; maximum dynamic forces).
accepted load combination and acceptance criteria.
piping and support analysis verified that item 8 had been met for relief valve piping; safety valve piping up to ist support past the safety valve outlet on the discharge piping (essentially ASME Class 1 piping).
Remaining Issues on the rest of the discharge piping (NNS piping)
Safety valve operability could be affected by severely deformed pipe that would restrict flow.
To meet ANSI B31.1 requirement for emergency and faulted conditions for the seismically designed piping in order to satisfy the requirembnt of NUREG-0737.
3484e.fmk(940425).50-6
4 1992 ANALYSIS The need for 1992 Analysis Variable loop seal condition was obtained from field insulation instead of hot loop seal.
Address issues raised in NRC SER Demonstration of valve operability by showing no restriction of flow and meeting structural integrity for the NNS piping criteria.
Qualification of discharge piping to B31.1 criteria.
APCO's Position The intent of item II.D.1 from NUREG 0737 is met by demonstration that NNS piping will not be deformed such that there is any impact on the operation of the safety valve.
l 34sde Ank(940425) 50-7
6 1992 ANALYSIS FLOW DIAGRAM FSAR Classified NNS Piping of SV Discharge lf Hydraulic Forcing Function from Variable Iq Seal (40 msec for valve opening time; V
V V
inelastic Piping System Analysis Elastic Piping System Analysis V
V Pipe Strain Evaluation to address SER concem using structuralintegnty criteria y
y Pipe Stress Evaluation based on EPRI Pipe Support Structural Component ppng sutgar retiee recommended Evaluation based on structural integrity U
cntena criteria for NNS supports Very low strain from valve thrust loads faulted ( I Faulted (d Total strain <0.5%
(Elbow & Reducer)
No combinahon with SSE due to independent events V
U U
SER concem satisfied based on Pipe Stress Evaluation based on Base Plate Anctor Bolts Evaluation structuralintegnty criteria, structuralintegrity criteria based on structural integrity aiteria No hinge formation (+/)
Base Plate Faulted (e )
r Iow strain in pipe (+/)
with min. SF - 1.4 (Based on Faulted Load) i 3484e Imh(940425)50-8
RESPONSE TO INQUIRY #1 1
ITCHVALVE/ITCHVENT COMPUTER PROGRAMS Thermal hydraulic code.
Benchmarked to EPRI test program results.
WECAN Computer Program structural analysis code.
elastic / plastic analysis elements documented, verified, and benchmarked.
elastic / plastic analysis conservative.
verification problems are listed in WECAN User Manual, Table 5-2, Volume ll. They can be submitted to NRC for reviews if requested.
3464e.fmk(940425).50 9
RESPONSE TO INQUIRY #2 1
1986 SER approved load combination and acceptance criteria EPRI Piping Sub-committee of PWR PSARV Test Program The recommended load combination for Class 1 piping (WCAP-10105).
Relief valve discharge (upset transient)
- N, Rv < Level B.
Safety valve discharge (emergency transient)
- N, SV, < Level C Safety valve discharge in conjunction with SSE and LOCA (faulted)
- N, SV, SSE, LOCA < Level D Use SRSS for combining dynamic responses For NNS piping.
Option 1 -
Similar combination as Class 1 Piping using Class 2,3 rules.
Option 2 -
Structural Integrity Criteria No failure or restriction of flow are allowed.
3484e.imk(940425):50-10
~
I RESPONSE TO INQUIRY #3 EPRI PWR PSARV Test Program Results (1982) were used for the benchmarking of ITCHVALVE.
hydraulic forcing functions generated are conservative.
structural analysis results from WECAN Code with hydraulic forcing function input are conservative.
NNS Piping Needed only for Discharge of the Flow structural integrity criteria should be allowed.
criteria from EPRI Piping Subcommittee (1982) is unrealistically conservative.
b
t RESPONSE TO INQUIRY #4 SRSS combination of results from elastic and elastic /
plastic analyses are not used.
The combination of SSE with SV loads by SRSS method only for loads from elastic analysis results. No elastic / plastic analysis results were used in support or embedment evaluations.
l 3484e 1mk(940425):5012
_.l RESPONSE TO INQUIRY #5 All anchor bolts with less than SF = 4 are in NNS piping.
Structural integrity criteria should be allowed for NNS piping with the following reasons:
ensure proper delivery of flow after valve actuation.
simultaneous opening of 3 safety valves is a very conservative assumption.
extremely low number of actual safety valve actuations in operating plants.
for factored loadings (accident / extreme environmental loads), safety factors of 1.2 and 3.0 are used commensurate with the provisions of Section B.7.2 of ACI-349-90 and its supplement of 3/90. FS=1.2 for bolt material; FS = 3.0 for concrete shear cone.
high FS is required only for the failure mechanism of concrete shear cone not the bolts.
AISC Specification: FS = 1.7 for service loadings, FS = 1.1 for accident / extreme environment loadings.
3484e.fmk(940425).5013
RESPONSE TO INQUIRY #5 (cont.)
APCo has implemented 100% verification ~ testing in IEB 79-14/79-02 program with total quality control.
pull-out capacity increases with concrete aging.
j 1
I l
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