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Category:MEETING MINUTES & NOTES--CORRESPONDENCE
MONTHYEARML20210L5231999-08-0505 August 1999 Summary of 990708-09 Meeting with Detroit Edison Co in Rockville,Md Re Issues Related to Fermi 2 Submittal for Conversion of Current TSs to Improved Standard Tss.List of Participants & RAI Tracking Numbers Encl ML20209E7641999-07-0707 July 1999 Summary of 990617 Meeting with Licensee Re Util Plans to Add Racks to & Replace Older Racks in Sfp.List of Attendees Encl ML20206A3111999-04-16016 April 1999 Summary of 990412-13 Meeting with Detroit Edison Co Re Issues Related to Fermi 2 Submittal for Conversion to Improved Std Ts.List of Meeting Participants,Revised Conversion Schedule & List of Beyond Scope Issues Encl ML20205Q7481999-04-14014 April 1999 Summary of 990319 Meeting W/Util & Excel,Inc in Rockville,Md Re Improved STS Conversion.Attendee List,Request for Addl Info & Viewgraphs Encl ML20202H9211999-01-26026 January 1999 Summary of 990111-12 Meetings with Util at NRC Headquarters to Discuss Issues Related to Fermi 2 Submittal for Conversion to Improved Sts.List of Questions for Sections 3.5 & 3.6 & Meeting Participants Encl ML20198J6911998-12-23023 December 1998 Summary of 981201-04 Meetings with Util in Rockville,Md Re Improved STS Conversion ML20196F6001998-11-20020 November 1998 Summary of 981109-10 Meeting with Util Re Issues Related to Fermi Unit 2 Submittal for Conversion to Improved Std Tss. Primary Focus Was to Discuss Proposed Questions for RAI for Sections 3.4,3.7 & 3.9 of Conversion.Meeting Attendees Encl ML20155A8741998-10-26026 October 1998 Summary of 980928,29,30,1007 & 08 Meetings with Detroit Edison Co to Discuss Plant Improved Std TSs Conversion. List of Participants Encl ML20153G4541998-09-21021 September 1998 Summary of 980908-09 Meeting W/Detroit Edison Co in Rockville,Md Re Fermi 2 Submittal for Conversion to Improved Standard Tss.List of Attendees Encl ML20238F2261998-08-27027 August 1998 Summary of 980805-06 Meeting with Detroit Edison Co in Rockville,Md Re Issues Related to Fermi 2 Submittal for Conversion to Improved Standard TS ML20237C5751998-08-20020 August 1998 Summary of 980728-29 Meeting W/De in Rockville,Md Re Issues Related to Fermi 2 Submittal for Conversion to Improved TS W/Primary Focus on Review of Section 3.6.List of Meeting Participants Encl ML20236S0791998-07-14014 July 1998 Summary of 980707 & 08 Meeting W/Util at NRC Headquarters Re Issues Related to Plant,Unit 2 Submittal for Conversion to Improved Std Tss.Primary Focus of Meeting Was Review of Section 3.4 of Std Ts.List of Meeting Participants Encl ML20197B6751998-03-0505 March 1998 Summary of 980220 Telcon Re Quality of Licensing Submittals for Plant Unit 2.Submittals for Discussion & Participants in Call Listed in Encl ML20203D9551998-02-12012 February 1998 Summary of 980130 Meeting W/Util Re General Status of Plant & Status of Selected Licensing Issues.List of Attendees Encl ML20199G6801997-11-19019 November 1997 Summary of 971104 Meeting W/Util Re Issues Related to Improved STS for Fermi 2.List of Meeting Attendees Encl ML20140H8481997-05-0505 May 1997 Summary of 970422 Meeting W/Licensee at NRC Headquarters Re Issues Related to EECW Sys at Plant ML20133A4881996-12-23023 December 1996 Summary of 961218 Meeting W/Util in NRC Headquarters Re State of Licensee Corrective Action Program,Performance of Operations & Sys Engineering Personnel & Activities Re Control of Plants Design Basis.List of Attendees Encl ML20135B4411996-11-21021 November 1996 Summary of 960927 Meeting W/Util Re Status of Plans to Decommission Fermi 1 Facility.Concern Areas & Resulting Discussions,Listed.Decommissioning Project Plan,Encl ML20059J1471994-01-10010 January 1994 Summary of Operating Reactors Events Briefing 94-01 Conducted on 940105 to Inform Senior Managers of Listed Ofcs of Selected Events That Occurred Since Last Briefing on 931222.Attendees Listed in Encl 1 ML20057G3571993-10-15015 October 1993 Summary of 930913 Meeting W/Util in Rockville,Md Re Concerns W/Thermal Binding & Pressure Locking of Gate Valves.List of Meeting Attendees & Handout Matls Encl ML20058M5891993-09-27027 September 1993 Summary of Operating Reactors Events Meeting 93-36 on 930922 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 ML20057E6271993-09-13013 September 1993 Summary of Operating Reactors Events Meeting 93-34 on 930908 ML20056D7151993-05-21021 May 1993 Summary of 930428 Periodic Mgt Meeting in Rockville,Md to Discuss Recent Independent Verification Program at Facility. Attendees Listed in Encl 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 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 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 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 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 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 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 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 ML20246C3261989-05-0404 May 1989 Summary of Operating Reactors Events Meeting 89-18 on 890503 ML20246B5161989-04-28028 April 1989 Summary of 890419 Operating Reactors Events Meeting 89-16. List of Attendees & Handouts Encl ML20248K3761989-04-10010 April 1989 Summary of Operating Reactors Events Meeting 89-014 on 890405.List of Attendees,Events Discussed & Significant Elements of Events & Summary of Reactor Scrams for Wk Ending 890402 Encl ML20247F1991989-03-24024 March 1989 Summary of Operating Reactors Events Meeting 89-12 on 890322.List of Attendees,Events Discussed & Significant Elements,Summary of Reactor Scrams & Comparison of Weekly Statistics W/Industry Averages for Wk Ending 890319 Encl ML20247A8971989-03-16016 March 1989 Summary of Operating Reactors Events Meeting 89-11 on 890315.List of Attendees,Events Discussed & Significant Elements of Events & Four Events Identified for Input to NRC Performance Indicator Program & Summary of Scrams Encl ML20246N9201989-03-16016 March 1989 Summary of Operating Reactors Events Meeting 89-010 on 890308.List of Attendees,Significant Events Identified for Input to NRC Performance Indicator Program & Summary of Reactor Scrams for Wk Ending 890305 Encl ML20245H8011989-02-23023 February 1989 Summary of Operating Reactors Events Meeting 89-08 on 890222.Attendee List & Events Discussed & Significant Elements of Events Encl 1999-08-05
[Table view] Category:MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
MONTHYEARML20210L5231999-08-0505 August 1999 Summary of 990708-09 Meeting with Detroit Edison Co in Rockville,Md Re Issues Related to Fermi 2 Submittal for Conversion of Current TSs to Improved Standard Tss.List of Participants & RAI Tracking Numbers Encl ML20209E7641999-07-0707 July 1999 Summary of 990617 Meeting with Licensee Re Util Plans to Add Racks to & Replace Older Racks in Sfp.List of Attendees Encl ML20206A3111999-04-16016 April 1999 Summary of 990412-13 Meeting with Detroit Edison Co Re Issues Related to Fermi 2 Submittal for Conversion to Improved Std Ts.List of Meeting Participants,Revised Conversion Schedule & List of Beyond Scope Issues Encl ML20205Q7481999-04-14014 April 1999 Summary of 990319 Meeting W/Util & Excel,Inc in Rockville,Md Re Improved STS Conversion.Attendee List,Request for Addl Info & Viewgraphs Encl ML20202H9211999-01-26026 January 1999 Summary of 990111-12 Meetings with Util at NRC Headquarters to Discuss Issues Related to Fermi 2 Submittal for Conversion to Improved Sts.List of Questions for Sections 3.5 & 3.6 & Meeting Participants Encl ML20198J6911998-12-23023 December 1998 Summary of 981201-04 Meetings with Util in Rockville,Md Re Improved STS Conversion ML20196F6001998-11-20020 November 1998 Summary of 981109-10 Meeting with Util Re Issues Related to Fermi Unit 2 Submittal for Conversion to Improved Std Tss. Primary Focus Was to Discuss Proposed Questions for RAI for Sections 3.4,3.7 & 3.9 of Conversion.Meeting Attendees Encl ML20155A8741998-10-26026 October 1998 Summary of 980928,29,30,1007 & 08 Meetings with Detroit Edison Co to Discuss Plant Improved Std TSs Conversion. List of Participants Encl ML20153G4541998-09-21021 September 1998 Summary of 980908-09 Meeting W/Detroit Edison Co in Rockville,Md Re Fermi 2 Submittal for Conversion to Improved Standard Tss.List of Attendees Encl ML20238F2261998-08-27027 August 1998 Summary of 980805-06 Meeting with Detroit Edison Co in Rockville,Md Re Issues Related to Fermi 2 Submittal for Conversion to Improved Standard TS ML20237C5751998-08-20020 August 1998 Summary of 980728-29 Meeting W/De in Rockville,Md Re Issues Related to Fermi 2 Submittal for Conversion to Improved TS W/Primary Focus on Review of Section 3.6.List of Meeting Participants Encl ML20236S0791998-07-14014 July 1998 Summary of 980707 & 08 Meeting W/Util at NRC Headquarters Re Issues Related to Plant,Unit 2 Submittal for Conversion to Improved Std Tss.Primary Focus of Meeting Was Review of Section 3.4 of Std Ts.List of Meeting Participants Encl ML20197B6751998-03-0505 March 1998 Summary of 980220 Telcon Re Quality of Licensing Submittals for Plant Unit 2.Submittals for Discussion & Participants in Call Listed in Encl ML20203D9551998-02-12012 February 1998 Summary of 980130 Meeting W/Util Re General Status of Plant & Status of Selected Licensing Issues.List of Attendees Encl ML20199G6801997-11-19019 November 1997 Summary of 971104 Meeting W/Util Re Issues Related to Improved STS for Fermi 2.List of Meeting Attendees Encl ML20140H8481997-05-0505 May 1997 Summary of 970422 Meeting W/Licensee at NRC Headquarters Re Issues Related to EECW Sys at Plant ML20133A4881996-12-23023 December 1996 Summary of 961218 Meeting W/Util in NRC Headquarters Re State of Licensee Corrective Action Program,Performance of Operations & Sys Engineering Personnel & Activities Re Control of Plants Design Basis.List of Attendees Encl ML20135B4411996-11-21021 November 1996 Summary of 960927 Meeting W/Util Re Status of Plans to Decommission Fermi 1 Facility.Concern Areas & Resulting Discussions,Listed.Decommissioning Project Plan,Encl ML20059J1471994-01-10010 January 1994 Summary of Operating Reactors Events Briefing 94-01 Conducted on 940105 to Inform Senior Managers of Listed Ofcs of Selected Events That Occurred Since Last Briefing on 931222.Attendees Listed in Encl 1 ML20057G3571993-10-15015 October 1993 Summary of 930913 Meeting W/Util in Rockville,Md Re Concerns W/Thermal Binding & Pressure Locking of Gate Valves.List of Meeting Attendees & Handout Matls Encl ML20058M5891993-09-27027 September 1993 Summary of Operating Reactors Events Meeting 93-36 on 930922 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 ML20057E6271993-09-13013 September 1993 Summary of Operating Reactors Events Meeting 93-34 on 930908 ML20056D7151993-05-21021 May 1993 Summary of 930428 Periodic Mgt Meeting in Rockville,Md to Discuss Recent Independent Verification Program at Facility. Attendees Listed in Encl 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 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 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 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 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 ML20246C3261989-05-0404 May 1989 Summary of Operating Reactors Events Meeting 89-18 on 890503 ML20246B5161989-04-28028 April 1989 Summary of 890419 Operating Reactors Events Meeting 89-16. List of Attendees & Handouts Encl ML20248K3761989-04-10010 April 1989 Summary of Operating Reactors Events Meeting 89-014 on 890405.List of Attendees,Events Discussed & Significant Elements of Events & Summary of Reactor Scrams for Wk Ending 890402 Encl ML20247F1991989-03-24024 March 1989 Summary of Operating Reactors Events Meeting 89-12 on 890322.List of Attendees,Events Discussed & Significant Elements,Summary of Reactor Scrams & Comparison of Weekly Statistics W/Industry Averages for Wk Ending 890319 Encl ML20246N9201989-03-16016 March 1989 Summary of Operating Reactors Events Meeting 89-010 on 890308.List of Attendees,Significant Events Identified for Input to NRC Performance Indicator Program & Summary of Reactor Scrams for Wk Ending 890305 Encl ML20247A8971989-03-16016 March 1989 Summary of Operating Reactors Events Meeting 89-11 on 890315.List of Attendees,Events Discussed & Significant Elements of Events & Four Events Identified for Input to NRC Performance Indicator Program & Summary of Scrams Encl ML20245H8011989-02-23023 February 1989 Summary of Operating Reactors Events Meeting 89-08 on 890222.Attendee List & Events Discussed & Significant Elements of Events Encl ML20235M1671989-02-17017 February 1989 Summary of Operating Reactors Events Meeting 89-07 on 890215.List of Attendees,List of Events Discussed,Summary of Events for Long Term Followup or Input to NRC Performance Indicator Program & Summary of Reactor Scrams Encl 1999-08-05
[Table view] |
Text
jf 'c, UNITED STATES fRIC;ITY FOUTI!;;
$. % NUCLEAR REGULATORY COMMISSION 6
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LICENSEE: Detroit Edison Company FACILITY: Fermi-2 SUB.1ECT: MEETING SUMMAD.Y FOR DECEMPER 11, 1986, MEETING ON MAIN STEAM TUPBINE BYPASS FLOW LINE FAILURE On December 11, 1986, members o' the NRR staff met with the licensee to discuss failures experienced with the main steam turbine bypass flow line and corrective actions taken by the licensee to rectify the problems. Enclosure (11 is a copy of the meetina agenda and the slide presentation made by the licensee at the meetino. Enclosure (71 is a list of the meeting participants. Enclosure (3T documents the NRR's staff's position and corrents expressed at the meetine with respect to actions taken by the licensee to identify the root cause of the problen, corrective actions taken as of the date of the meetina, and the follow-on surveillances planned by the licensee.
The meetino was noticed in the PDR by memorandum dated November 76, 1986.
7 w
Jo 'n'D. Stef ,S dorPro.iectManaaer
, Pkt r P'o.iec iirec/ censing ate No. 3 I vis RWD
Enclosures:
As stated 1
cc: See next page l
1 l 8702180226 870209 PDR FOIA PUNTENNE87-So pga Id Jl !, - o sEI l
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. )
l Pr. R. Ralph Sylvia Detroit Edison Company Femi-? Facility !
cc:
Mr. Harry H. Voigt, Esq. Ronald C. Callen LeBoeuf Lamb, Leiby & PacRae Adv. Planning Review Section 1333 New Hampshire Avenue, N. W. Michigan Public Service Commission Washington, D. C. E0036 6545 Mercantile Vay P. O. Box 30221
.lohn Flynn, Esa. Lansing, Michigan 48900 Senior Attorney Detroit Edison Company Regional Administrator, Region III 2000 Second Avenue U. S. Nuclear Regulatory Comission Detroit, Michigan 48226 799 Roosevelt Road Glen Ellyn, Illinois 60137 Mr. Dennis R. Hahn, Chief Nuclear Facilities and Environmental Monitoring Section Office Division of Padiological Health P. O. Box 30035 Lansing, Michigan 48909 Mr. Steve Frost Supervisor-Licensing Detroit Edison Company Femi Unit 2 6400 North Dixie Highway Newport, Michigan 48166 Mr. Thomas Randazzo Director, Regulatory Affairs Detroit Edison Company Fermi Unit 2 6400 North Dixie Highway Newport, Michigan 48166 Pr. Walt Rogers U. S. Muclear Regulatory Comission Resident Inspector's Office 6450 W. Dixie Highway Newport, Michigan 48166 Ponroe County Office of Civil i Preparedness 963 South Raisinville Monroe, Michigan 48161 l
(!PV/d AGENDA Objective of Presentation:
The actions and essential facts surrt>unding the initial reports of leakage on the main steam bypass lines, the corrective actions taken, and the followup measures implemented by Detroit Edison will be the subject of this presentation.
Detroit Edison believes that the root cause of.the problem has been identified and adequately dealt with. Further, that the bypass lines in their current configtration will support normal operations for the 110 year design life of the plant.
9
.t
AGENDA i
- 1. Initial Failu-e of the Main Steam Bypass Lines Initial detection of the leakage Determination of Root Cause
- 2. Modification of the Bypass Lines Industry experience search Consultants and A/E's Synthesis of the modifications NDE performed
- 3. Post Construction Testing Hopper report on fatigue life Testing program Results of test data analysis
- 4. Supplemental Testing Location of additional strain gages defined Testing program Results of testing
- 5. Service Life of the Lines Operational modes of the syste Extrapolation to a 40 plant life
- 6. Fesidual Concerns Relative to the Bypass Systm
- 7. Line Monitoring and Contingency Plans
- 8. Summary i
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The mainsteam bypass lines are acceptable f or the 40 year normal operating life of the Permi plant due to the following:
- 1. The lines meet or exceed the e mperical requirements for avoid-ance of acoustically induced pipe vall cracking.
- 2. The lines meet or exceed the req-uirements of the ANSI B 31.1 code to which they were designed.
- 3. Two separate rigorus evaluations, which utilize two different methods, predict 100 days of cumulative life in the least desireable range of valve positions.
- 4. The pipe wall strains measured since the lines were modified show signif-icantly reduced pipe wall strain are present.
- 5. The bypass line hangers and supports and snubbers meet or exceed the req-ments of the ANSI B 31.1 and AISC codes to which they were designed.
- 6. The least desireable valve position range is not a hold point in the normal plant operating proceedures.
- 7. The lines have operated for a peroid of 8 cumulative days in the valve position range of interest with:
a) Minor loosening of clamp nuts, which was resolved.
b) Some snubber clamp and one instance of hanger tube steel cracking which could have occurred during
,' operation of the original
- 3/8" wall line. Also, an analysis of the line shows that the supports could have been removed with no detremental effects.
ENCLOSIIRE (2)
DECEMBER 11, 1986 MEETING WITH DECO RE:
MAIN STEAM TtIRBINE BYPASS LINE FLOW-INDilCED VIBRATIDN MAME DPGANIZATION John Stefano NRC - Project Manager P. Wavne Houston NRR - Division of BVR Licensino John Tsao NRR - DRL/En Thomas Randazzo Detroit Edison Frank Aposti Detroit Edison Duane Danielson NRC - RIII John Jacobson NRC - RIII J. J. Harrison NPC - RIII, Chief Eng. Rranch Pob Hermann NRC - DRL/Section Chief EB E. G. Adensar NRC - DDL/8WD-3 Stephanie Murphy NIRS - 1616 P. St. NW, #160 D. G. La Grance NRC - DBL /ER T. Yano Stone F: Webster Steve Frost Detroit Edison Gene Preston netroit Edison Lawrence Sir.pkin Detroit Edison Pavid Spiers Detroit Edison John Conroni Detroit Edison David Hocper Hopper 8. Assoc.
- Johseph Cohen ne troit Edison i
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%....+/ N li ppyi Docket No.: 50-341 MEMORANDUM FOR: Elinor G. Adensam, Director /
Project Directorate No. 3 Division of BWR Licensing FROM: Gus C. Lainas, Assistant Director Division of BWR Licensing
SUBJECT:
FERMI UNIT 2: MAIN STEAM BYPASS LINE FAILURE (TAC #63376) i Introouction In September 1985, Detroit Edison (DECO) discovered through-wall cracks in two main steam bypass lines at Fermi Unit 2. Subsequently, DECO replaced both lines with a thicker wall pipe, redesigned some of the pipe supports, and analyzed the piping vibration. DECO has identified the root cause of the problem to be acoustically induced flutter of the pipe wall. On December 11, 1986 a meeting was held in Bethesda, Maryland for DECO to present their assess-ment of the problem and corrective actions that they have taken to resolve
- the issue. The Engineering Branch and Region III staff have evaluated this
! issue from the viewpoint of sound engineering practices rather than from assessment of meeting license requirements since the lines in question are a
! part of balance of plant. The assessment by the staff is to critique Deco on the basis of performance for this issue as an indicator of how they might address a similar problem in the " safety-related" part of the plant.
Both bypass lines (the West line and East line) are made of 30 inch diameter
- carbon steel pipe (API SL Grade B) and are reduced to 24 inch diameter at the inlet to condenser. The cracks were found at various locations on the pipe surface including, pipe support lug attachments, small test connections, and flow measurement orifices. DECO replaced the original 0.375 inch thick pipe with a 1.0 inch thick pipe for the 30-inch diameter section and 1.25 inch
- thick pipe for the 24-inch diameter section. Deco also eliminated all pipe weld attachments. As a part of the modification, Deco conducted a test program j to obtain as-built stresses and strains at various locations of the lines and contracted Hopper and Associates and Stone and Webster to predict the service life of the pipe using the test data. After resolutions of disagreements l
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Contact:
- 4. Tsao x29408 l
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Elinor G. Adensam regarding the fatigue life of the pipe predicted by the two contractors, Deco concluded that the west line is acceptable if cumulative operation with bypass valve position between 30% and 45% opened for a period not to exceed 100 days, and that the east line can be operated indefinitely.
Discussion and Evaluation The staff believes the licensee has properly identified the root cause of this vibration as acoustically induced pipe wall fluttering resulting from high pressure drop across the bypass dump valve seat. The dump valve opening is about 9 inches whereas the pipe opening is 28 inches. The supersonic steam entering the pipe is choked at the valve exit. When the steam is expanded into the larger pipe, the flow becomes turbulent and generates the acoustic j vibrations.
i The modification that has been perfonned by the licensee has not been success-i ful in elminating the acoustically induced vibration from the piping system.
, The arguments presented by the licensee on alternative designs and why they could not be implemented at the facility appear plausible. However, in the design of the modification, it does not appear that sufficient considerations were given to this system with its inherent vibration problem. For instance, several supports on the system have cracked and nuts on clamps have fallen off. We understand that fillet welds rather than full penetration welds were used in the support design. Although this practice would meet the usual code requirements for supports of this type for power pipings, we believe that the fillet welds, with their inherent stress raisers, were not appropriate for i
this application. Further, no special care appears to have been taken by the licensee to preclude loosening of bolting in the system. As with the supports, no special considerations were taken with regard to the circumferential weldments in the piping. Weldments were made using backing rings. This type of joint is less desirable than an full penetration weldment made without a backing ring.
A joint made without a backing ring would not only have been more readily I
inspectable but also would have been less likely to provide a site for potential fatigue crack initiation. With regard to inspection, volumetric examinations
- i of the girth weld following fabrication could have provided added assurance that discontinuities from fabrication would not be present to serve the fatigue l crack initiation sites. Also, no volumetric inservice inspection has been proposed to monitor if service-induced degradation has occurred.
CONCLUSION The staff concludes that the licensee has been triorough and effective in identifying the root cause of the pipe vibration. However, the modification which is admittedly a compromise because of physical limitations and cost appear to have been done without going significantly beyond what the applicable ASME Codes would require. The licensee has attempted to reduce some stress raisers but has neglected quite a few others. Further, non-destructive inspections per-formed in past and those proposed by the licensee for the future are minimal.
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JAN 1 2 E"I Elinor G. Adensam -
3-Had this problem occurred in the " safety-related" part of the facility, the staff would have expected the licensee to have been more attentive to design, fabrication and inspection factors discussed above.
This completes our action on this TAC.
$. py Gus C. Lainas, Assistant Director Division of BWR Licensing cc: R. Bernero W. Houston G. Lainas J. Stefano E. Adensam B. D. Liaw R. Hermann J. Jacobson, R III D. Danielson, R III i
J. Harrison, R III J. Tsao
Contact:
J. Tsao X-29408 l
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