Letter Sequence Meeting |
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MONTHYEARML20209E9881986-09-0202 September 1986 Application for Amends to Licenses NPF-2 & NPF-8,changing Snubber Surveillance Requirements to Increase Allowable Time Interval Between Visual Surveillances When Snubber Sys Operating at High Level of Dependability.Fee Paid Project stage: Request ML20214D2161986-11-18018 November 1986 Notification of 861120 Meeting W/Util,Southern Co Svcs,Inc & Bechtel in Bethesda,Md to Discuss Proposed Change to Tech Specs Re Snubber Surveillances Project stage: Meeting ML20236S4401986-12-30030 December 1986 Summary of 861120 Meeting W/Util Re Proposed Tech Spec Changes to Snubber Surveillance Insp Intervals Project stage: Meeting ML20210G8471987-02-0909 February 1987 Proposed Tech Specs,Incorporating Revised Proposed Snubber Visual Insp Schedule Project stage: Other ML20210F8011987-02-0909 February 1987 Application for Amends to Licenses NPF-2 & NPF-8,changing Tech Specs Re Snubber Surveillance Requirements.Request Suppls 860902 Tech Spec Submittal by Providing Requested Revised Proposed Snubber Visual Insp Schedule.Fee Paid Project stage: Request ML20211P5691987-02-25025 February 1987 Proposed Tech Specs Re Snubber Surveillance Requirements & Visual Insp Schedule Project stage: Other ML20211P5001987-02-25025 February 1987 Application to Amend Licenses NPF-2 & NPF-8,revising Tech Specs to Allow Snubber Failures to Be Expressed as Percentage of Specific Snubber Population in New Snubber Visual Insp Schedule Project stage: Request ML20212C8781987-02-27027 February 1987 Forwards Info Re Plant Snubbers,Including Date of Failures & Current safety-related Snubber Population Project stage: Other ML20154E8471988-09-0909 September 1988 Forwards Proposed Schedules for Completion of Licensing Items,Including Prioritized Listing of License Amend & Other Requests & Listing of NRC-related Submittals Project stage: Other 1987-02-25
[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 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 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 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 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 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 NUREG-1192, Summary of Operating Reactor Events Meeting 87-37 on 871027. Viewgraphs & Summary of Reactor Scrams Encl1987-10-28028 October 1987 Summary of Operating Reactor Events Meeting 87-37 on 871027. 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 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 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 ML20062K3241980-11-28028 November 1980 Summary of 801030 Meeting W/Util & Bechtel Re Means by Which Power Cables in Containment Are Protected from Overcurrent. Draft Response to NRC Position 040.15 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 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 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 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 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 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 NUREG-1192, Summary of Operating Reactor Events Meeting 87-37 on 871027. Viewgraphs & Summary of Reactor Scrams Encl1987-10-28028 October 1987 Summary of Operating Reactor Events Meeting 87-37 on 871027. 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 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 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 ML20062K3241980-11-28028 November 1980 Summary of 801030 Meeting W/Util & Bechtel Re Means by Which Power Cables in Containment Are Protected from Overcurrent. Draft Response to NRC Position 040.15 Encl 1999-05-05
[Table view] |
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- n. - 3 o . 2),
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, I Docket Nos. 50-348 DISTRIBUTION and'50-364 Docket File % v Reeves (2) o NRC PDR D. M1iier ,
LICENSEE: Alabama Power Company (APCo) Local PDR- DELD ]
PAD #2 Rdg E. Jordan' FACILITY: Joseph M. Farley Nuclear Plant, J. Partlow B. Grimes:
Units 1 and 2 L. Rubenstein ACRS (10)
Gray File- NRC Participants
SUBJECT:
SUMMARY
OF MEETING HELD ON NOVEMBER 20, 1986, BETWEEN NRC AND AFCo REPRESENTATIVES TO DISCUSS APCo's PROPOSED TECHNICAL SPECIFICATION CHANGES TO SNUBBER SURVEILLANCE INSPECTION INTERVALS Introduction The NRC Project Manager (G. Requa, backup for E. Reeves) reviewed the purpose of the meeting which resulted from APCo's license amendment request proposed by letter dated September 2, 1986. The meeting was' held to assist the NRC staff's understanding of~APCo's proposal in order to meet the licensee's request amendment schedule of February 27, 1987. A' list of attendees is enclosed (Enclosure 1).
Discussion Southern Company Services (D.P. Hayes), representing Alabama Power Company (APCo), ,
used viewgraphs to present an overview of the proposed snubber visual inspection An outline of the discussion is enclosed as pages 1-4 of Enclosure methodolog(y.S.T.
- 2. APCo Burns) reviewed the refurbishment program of snubbers as follows:
- 1. All snubbers at Farley Unit No. I have been.. rebuilt.
- 2. All snubbers at Farley Unit No. 2 will be rebuilt by the end of the next outage.
- 3. The population of snubbers includes:
1
); Unit 1 Unit 2
~
596 431 INACCESSIBLE 272 223 ACCESSIBLE l M 'E TOTAL Bechtel (E.W. Thomas) used viewgraphs (Enclosure 2, pages 5-14) to review the details of the statistical methodology. The approach is to maintain a 95 percent confidence level that 90 percent of the group remains operable based on visual inspections. Table 1 on page 14 of the Enclosure 2 reflects the proposed changes based on a snubber group size larger than 200. This table has been proposed by APCo in a letter dated September 2, 1986, for replacing Technical J Specification 4.7.9.a. visual inspection schedule which is based on a fixed number of inoperable snubbers per inspection period. APCo contends that the existing requirements are overly conservative and result in excessive surveillance requirements.
l l
8711250163 861230 i PDR ADOCK 05000348 P PDR l
i
However, the staff indicated that the existing requirements are to maintain an approximately 95 percent confidence level that 90 to 100 percent of the snubbers are operable based on a combination of visual inspection and functional testing.
Conclusion Following discussions between the NRC staff and APCo's staff and their support organizations, APCo agreed to provide additional information at an early date to support the requested NRC staff action date of February 27, 1987.
l /- W MY I
Edward Reeves, Project Manager Project Directorate #2 Division of PWR-A Licensing
Enclosures:
As stated e
Mr. R. P. Mcdonald Alabama Power Company Joseph M. Farley Nuclear Plant cc:
Mr.- W. O. Whitt D. Biard MacGuineas, Esquire Executive Vice President Volpe, Boskey and Lyons Alabama Power Company 918 16th Street, N.W.
Post Office Box 2641 Washington, DC 20006 Birmingham, Alabama ' 35291-0400 Charles R. Lowman Mr. Louis B. , Long, . General Manager Alabama Electric Corporation Southern Company Services, Inc.-
Post Office Box 550 Post Office Box 26P5 Andalusia, Alabama 364?0 Birmingham, Alabama 3520?
-Chairman. Regional Administrator, Region II Houston County Commission U.S. Nuclear Reaulatory Commission Dothan, Alabama 36301 101 Marietta Street, Suite 2000 Atlanta, Georgia 30303 Ernest L. Blake,' Jr.,- Esquire Shaw, Pittman, Potts and Trowbridge Claude Earl Fox, M.D. i 2300 N Street, N.W. State Health Officer Washington, DC 20037 State Department of Public Health State Office Building Montgomery, Alabama 36130 Robert A. Buettner,' Esquire Balch, Bingham, Baker, Hawthorne, Mr. J. D. Woodard
. Williams and Ward General Manager - Nuclear Plant
. Post Office Box 306 Post Office Box 470 Birmingham,. Alabama 35201 Ashford, Alabama 36312
. Resident. Inspector U.S. Nuclear Regulatory Commission Post Office Box 24 - Route 2 Columbia, Alabama 36319 l
i e
i l
I ENCLOSURE 1 r.1 LIST OF ATTENDEES AT THE NOVEMBER 20, 1986 MEETING ROOM P-422 PHILLIPS BlflLDING BETHESDA, MARYLAND NAME ORGANIZATION G. Reoua PWR-A/ PAD #2 -
B. J. George Southern Company Services ,
D. P. Hayes Southern Company Services E. W. Thomas Bechtel Eastern Power Corporation S. Sue-Ung Bechtel Eastern Power Corporation K. Gandhi Bechtel Eastern Power Corporation
, K. Powers Southern Company Services S. T. Burns Alabama Power Company B. D. McKinney Alabama Power Company J. A. Ripple Alabama Power Company J. E. Garlington Alabama Power Company D. Terao NRC/NRR/DPLA/EB G. Johnson NRC/NRR/DPLA/EB S. Lee NRC/NRR/DPLA/EB H. Shaw NRC/NRR/ DBL /EB l H. L. Brammer NRC/NRR/PWP-A/EB T. Sullivan NRC/NRR/PWR-A/EB G. Bagchi NRC/NRR/PWR-A/EB d
ENCLOSURE 2 PROPOSED SNUBBER VISUAL INSPECTION INTERVAL TECHNICAL SPECIFICATION CHANGE PRESENTATION I. INTRODUCTION A. BACKGROUND B.
PROPOSEo SNUBBER TECHNICAL SPECIFICATIONS II. METHODOLOGY OVERVIEW III. COMPREHENSIVE METHODOLOGY REVIEW A. METHODOLOGY B. RESULTS IV.
SUMMARY
/ ACTION ITEMS A.
METHODOLOGY BASED ON SOUND STATISTICAL AND ENGINEERING PRINCIPLES B.
VISUAL INSPECTION INTERVALS 3ASED ON SAME CRITERIA AS FUNCTIONAL TESTING (95/90)
C. FOLLOW UP ACTION ITEMS 0825F G
o CHANGES TO VISUAL INSPECTION SCHEDULE 1
NO CHANGE TO 100% VISUAL INSPECTION REQUI"EMENT l
1 o
NO CHANGE TO ACTION STATEMENT OR LCO o
NO CHANGE TO VISUAL TEST ACCEPTANCE CRITERIA o
NO CHANGE TO FUNCTIONAL TEST REQUI'EMENT o
NO CHANGE TO FUNCTIONAL TEST ACCEPTANCE CRITERIA o
NO CHANGE TO SERVICE LIFE MONITORING REQUIREMENTS 0825F S
-l l
1
. STS METHODOLOGY !
l l
l o
DEVELOPED TO PROVIDE A 95% CONFIDENCE THAT AT LEA OF THE SNUBBERS ARE OPERABLE j o
BASED ON PROVIDING CONSTANT PROTE TION o
BASED ON TRADITIONAL STATISTICAL METHODS l
l 1
0825F 1 i
l
-_ _- _ o
l
. I 1
l i
I i
e METHODOLOGY BASED ON SOUND STATISTICAL AND ENGIN PRINCIPLES o
VISUAL INSPECTION INTERVALS BASED ON SAME CRITERIA A FUNCTIONAL TESTING (95/90) o PROPOSED CHANGE IS SMALL PART OF C0t1PREHENSIVE SNU PROGRAM 0825F
METHODOLOGY FOR SNUBBER OPERABILITY SURVEILLANCE APPROACH:
- Maintain 95% confidence level that 90% of group remains operable
- Assume unlimited frequency of defined accidents may occur (l. e., probability of occurrence = 1)
- Use exponential distribution to predict time to failure of a given snubber
-its hazard function constant with time
- Number of failed snubbers before time (t) follows a binomial ,
distribution
- Estimate failure rate using chi-squared function (with a confidence level of 95%)
- Assume for all snubbers that fall, they do so at start of Inspection period
- Results of previous inspection interval used to establish new inspection Interval
- New inspection interval can be increased by only one interval step
.. \
l
- Tolerances are provided on inspection Intervals. The extr. emes on tolerances that creates the most severe result is used in develop-ment of Inspection schedule.
G-WRW-11/86
DEVELOPMENT OF METHODOLOGY TIME TO FAILURE OF A GIVEN SNUBBER (X) FOLLOWS AN EXPONENTIAL DISTRIBUTION .
THEN PROBAEtLITY DENSITY FUNCTION CAN BE EXPRESSED AS :
-O* (I) x (X) = Oe WHERE O = FAILURE RATE PROBABILITY THAT AN INDIVIDUAL SNUBBER FAILS BEFORE TIME (t )
' -et (2)
Ps = P lI x < t ., = [. f x (fe ) d Ee = 1 - e i
IF Z IS THE NUMBER OF FAILED SNUBBERS BEFORE OR AT TIME (t ) , BY USE OF BINOMI AL DISTRIBUTION P(Z = z ) = zi(n_,33 Ps ( l - Ps )"~ * (3)
~
WHERE n = TOTAL NUMBER IN GROUP S
PROBABILITY THAT THERE ARE NO MORE THAN (s)
SNUBBERS INOPERABLE BEFORE OR AT TIME (t )
P[z cs } =z=O $ zicj_,), P*,( l - P,)"~' (4)
USE P[z <s ]r = CONFIDENCE LEVEL = 95 %
COMBINING EQ'S 284 P{ z <s } =,o,$n!(n-z)! I l- *~ *I ('- t)"-2 =.95 (5)
EST6 MATE THE F ALLURE RATE $
_ Total number of failures (6)
O avg. Total test time an failed & unfalled units g_ - oG , 2 I+ 2 (6a) 2T WHERE = Chi- SQUARED FUNCTION T = ( n-1) T l = TOTAL NUMBER OF SNUBBERS WITH DEFECTS 1 T = CURRENT INSPECTION PERIOD oc = 0.05 CORRESPONDING TO 95% CONFIDENCE LEVEL CD
i_
i !
1
~
) _
7
( _
5 9 . _
_ =
z n
)
t -
2
+
I 1 2 3
. 1 K- n- _
2l (
2
(
z
)
t 2
+
1 2
r
.I .
d- n -
2I (
% 2 i
(
)
z_ _
6 !
" (n ;
8 n .
5 o .
S s z z_
=
Q .
E }
s G. < -
NI z NI
{
B P M 4 O
C l l .
O
JUSTIFICATION:
- 95% Confidence level of 90% Reliability
-Representative of criteria for safety systems l
- Produces very strict acceptance criteria
- Rigorous - less than 0.0076 failure rate to maintain same :
Inspection interval l
- Unlimited frequency of accident events is a most conservative assumption
- Use of exponential distribution to predict time-to-fallure:
- Common ly used for simliar analysis of mechanical systems
-Inplace inspection and maintenance program leads to expectation that if snubber survives to a given time (t), -
its chance of survival the next instant is constant with time (Hazard Function)
- Exponential distribution ~ assumed in other approaches to 3 snubber inspection J
- Use of binomial probability function is appropriate for determining number of failures before time (t)
I
- Failure of each snubber independent of others
- Represents a success-fallure event
- Mathematical exact
- Use of Chi-Squared Function
- For a exponential distribution, estimate of failure rate follows Chi-Squared distribution (mathematical exact)
- Conservatively uses a failure rate at 95% probability that l Its actual value will be lower G-WRW-11/86
l
- j JUSTIFICATION CONTINUED
- Establishment of failure rate conservatively assumed all snubbers which fall do so at beginning of inspection interval
- Used latest information in establishing next interval
- Further restricted by allowing only one inspection interval step up from current interval
- Used most severe tolerance in estimate of failure rate and calculation of next inspection interval
- Use lower bound T to establish current failure rate
- Use upper bound T to establish % allowable Inoperative
- Minimum group size used to minimize next inspection j interval .
- rn /100 = I
- droup size limit tailored to Farley
- Methodology based on rigorous probabilistic and statistical procedures excerpted from standard texts i
i I
i 4
t .' ,
'i 1
Ws)
)
'I ,
l
.i l
- 80 8:
j Fig. 313 Typical hazard funcuon I
l l
i Mt) 10.0 -
9.0 -
8.0 -
7.0 -
Untform distnbubon%
--
5.0 ,
4.0 -
3.0 -
/
Normal (stribubon g _ i Exponential 1.0
/distnbubon
.g 0 1.0 2.0 3.0 4.0 5.0 6.0 7.0 8.0 9.0 10.0 Fig. 314 . Hazard functions for normal, uniform, and exponential distributions.
2
l 1
4 .
'l l
-l 1 j
4, /,( s) '
0.3 -
e CH (2) 0,2 - .(mEX(b)) ,
0.1 -
I 0 ' 1 5 10 15 s O
o /f (n) i 0.2 -
CH (5) '
0.1 -
i 8 1- :
O 5 10 15 s 0
L /y(s1 0.2 -
CH (10) 0.1 -
R l l l .
0 0 5 10 15 s Fig. SA3 x' distributions. (Adapted from R. B.
Durington and D.C. May,"Bandbook of Probability and Ekstistics," Handbook Publishers, Inc., fian-desity Ohio,1953.)
,e 09
y.
.. H 3
l
.< '1 i s -!
kl D
I b
RESULTS:
- Method is' valid for group of 200.or more
! - As group size increases, conservatism increases l
- Requires more frequent inspections with increasing failures
- Number of inoperative influenced by size of group
~
- Applicable to each unit i
l l
G-WRW-11/86
py F q
s.
x ,
';, _I j~ b'o. ,
4
, 1N '
}
4 [
q
.j +
,;(,
TAB 1.E 1 g 3
Visu']s:1 inspection schedule for any group (cate ory) of snubbers
[ .. of the *loseph M. Farley Nuclear Power" Plant Un ts 3 and 2.
4 j' <
3 .
~ ~'
'I y Cu vent Visual j Percerr. c) Saubrytrs Found Inoperabl6 'r, prr Current >
Next Visual Inspection Period
- Visus 1 Inspectit, Perir,d Inspection Period l
4q , ,
.(,
24 Months.+** 25% r < 0.76% 24 Months + tsN f 0.76% >T r <x 0.99% 18 Months 7 25% D <
- <, 0.991. /< r 'l 1.40% ' 12 Honths T 25% A 1
i 1.40% < r 7 i .43%2 - 69tonths 7 25%
l
" r > 2,471' 3 Months 7 25%.
5
L.
18 Months + 25% ' %. i r < 0.62% 24,#cnths + 25%
f' .
A ' ~'
O.62% T r < 0.76% :16 Months 7 25%
l' # T 1.09%.
p Cs.75%; 12 Months 7 25%
l N , 1.09% <r f. r (i 1.96% '
6 Months 7 25%
l
r > 1.9T% -,
3 Months [25%
~12 Kenths ~~
25 % r < c.585- 18 Months + 25%
6.68% T r < U.76% 12 Months 7 25%
0.76% <ri 1.80% 6 Monthe 7 25%
r > 1.4T% 3 Months [25%
~
6 Months +~ 25% r=0 12 Months + 25%
0<r < 0.76% 6 Months 7 25%
r > 0.7T% 3 Months [ 25%
3 Months +~~ 25% r=0 6 Months + 25%
Notes:
- 1. The above table is generated based on 95% confidence that at least 90% of the snubbers (in a group) being operable all the time.
- 2.
- Ear 21er visual inspection periods than required may be utilized. If this option is chosen, the criteria for determining the next visual inspection period shall be the criteria associated with the earlier visual insepetion period selected.
- 3. The above table is not. applicable for the snubber group' size (n) smaller than 200 .