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Category:MEETING MINUTES & NOTES--CORRESPONDENCE
MONTHYEARML20210H6681999-07-29029 July 1999
Summary of 990329 Meeting with Gpu in Forked River,Nj Re Possibility of Decommisssioning of Oyster Creek Nuclear Generating Station.List of Attendees & Licensee Handouts Provided
ML20195G1391998-11-16016 November 1998
Summary of 981103 Meeting with Gpu in Rockville,Md Re Possible Shutdown & Decommissioning of Oyster Creek Nuclear Generating Station in Year 2000.List of Attendees & Handout Encl
ML20216E3421997-09-0303 September 1997
Summary of 970826 Meeting W/Gpu in Rockville,Md Re Possibility of Decommissioning of Plant.Agenda,Meeting Handouts & Primarily Centered Activities Associated W/Decommissioning Plant in Yr 2000 Encl
ML20148D8531997-05-28028 May 1997
Summary of 970502 Meeting W/Util to Discuss Status of Implementation Schedule for Completion of Installation of Thermo-lag at Plants.List of Attendees Encl
ML20149J5251994-12-29029 December 1994
Summary of 941219 Meeting W/Util Re Status of Licensing Actions.List of Attendees & Activities Encl
ML20058K1831993-11-26026 November 1993
Summary of 931119 Meeting W/Licensee in Rockville,Md Re Licensing Issues Involved in Construction & Loading of Independent Spent Fuel Storage Installation to Be Constructed at Plant
ML20059F3931993-10-27027 October 1993
Summary of 931020 Meeting W/Gpu Nuclear Corp in Rockville,Md Re Status of Plant Licensing Actions.List of Attendees Encl
ML20128K8261993-02-0909 February 1993
Summary of 921123-24 Meeting in King of Prussia,Pa Re Region I Positions on Operator Licensing Issues & Solicit Input from Util Training Staffs
ML20127M5941993-01-26026 January 1993
Summary of 930112 Meeting W/Util in Rockville,Md Re Reactor Bldg Access Control Mod & Operational Safeguards Response Evaluation.List of Attendees & Handouts Encl
ML20127F6681993-01-14014 January 1993
Summary of 930112 Meeting W/Util in Rockville,Md Re Status of Licensing Actions.List of Individuals Participating in Discussion & Marked Up Copy of Staff Pmr Encl
ML20127E1281993-01-13013 January 1993
Summary of 930106 Meeting W/Util in Rockville,Md Re Insp of Plant Core Spray Spargers.List of Discussion Participants & Licensee Agenda Encl
ML20125C2461992-12-0707 December 1992
Summary of 921118 Meeting W/Util in Rockville,Md Re Status of Licensing Actions
ML20058K1871990-12-11011 December 1990
Summary of 901114 Progress Review Meeting at Plant Site Re Status of Licensing Actions.List of Attendees Encl
ML20062F1121990-11-15015 November 1990
Summary of 901107 Meeting W/Util in Rockville,Md,Re Fuel Channel Bowing & Reuse of Fuel Channels at Facility
ML20059N5951990-10-0303 October 1990
Summary of 900919 Meeting W/Util in Rockville,Md to Discuss Matters Re Plant Drywell Corrosion.Viewgraphs Encl
ML20246M5871989-08-29029 August 1989
Summary of 890802 Meeting W/Util in Rockville,Md Re full-term OL & Other Licensing Activities.List of Attendees & marked-up Regulatory Info Tracking Sys List of Unresolved SEP Topics & TAC Numbers Encl
ML20246L4001989-07-10010 July 1989
Summary of 890627 Meeting W/Util in Rockville,Md Re Combustible Gas Control for Plant.List of Individuals Attending Meeting,Proposed Meeting Agenda,Matl Used by Util in Discussion & Condensed History of Gas Control Issue Encl
ML20245J7191989-06-20020 June 1989
Summary of 890607 Meeting W/Util in Forked River,Nj to Discuss Status of Plant Licensing Actions.List of Attendees & marked-up Copy of Regulatory Info Tracking Sys Encl
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
ML20245J0141989-04-26026 April 1989
Summary of 890413 Meeting W/Util in Rockville,Md Re Status of Licensing actions.Marked-up Regulatory Info Tracking Sys List Encl
ML20235N0661989-02-21021 February 1989
Summary of 890213 Meeting W/Util & State of Nj Re Air Sys Relating to MSIVs & Reactor Bldg to Torus Vacuum Breakers. Util Should Document Overall Methodology Used for MSIV Leakage Problems Prior to Startup.Viewgraphs Encl
ML20235H0521989-02-10010 February 1989
Summary of 890130 Meeting W/Util in Rockville,Md to Discuss SSOMI (SSOMI-design Phase) Issue 2 Re Setpoints for Process Variables & Actions to Be Taken Before Startup.List of Attendees & Agenda Encl
ML20195H9671988-11-23023 November 1988
Summary of 881110 Meeting W/Util in Rockville,Md Re Status of Facility Licensing Actions
ML20155F4801988-10-0606 October 1988
Summary of 880928 Progress Review Meeting W/Util in Forked River,Nj Re Status of Plant Licensing Actions
ML20207M0771988-10-0505 October 1988
Summary of Operating Reactors Events Meeting 88-39 on 881004.List of Attendees & Viewgraphs Encl
ML20154F7971988-09-15015 September 1988
Summary of 880901 QA Meeting W/Util in Rockville,Md to Discuss Rev 2 of Util Operational QA Plan for Plants.Agenda & List of Participants Encl
ML20207F4451988-08-0909 August 1988
Summary of 880721 Meeting W/Util in Rockville,Md Re Retran Analytical Model & Cycle 12 Fuel Reload Analyses.Attendance List & Matl Used by Licensee in Meeting Encl
ML20151L8991988-07-28028 July 1988
Summary of 880713 Progress Review Meeting W/Util in Rockville,Md Re Status of Licensing Actions.List of Participants & marked-up Copy of Staff Regulatory Info Tracking Sys Encl
ML20150B3271988-07-0606 July 1988
Summary of 880628 Meeting W/Util in Rockville,Md Re Facility Outage IGSCC Insp/Stress Improvement Plans
ML20150C0101988-06-22022 June 1988
Summary of 880525 Meeting W/Gpu in Rockville,Md Re Matters Related to site-specific Response Spectra.Viewgraphs Encl
ML20195K0451988-06-16016 June 1988
Summary of 880526 Meeting W/Util in Rockville,Md Re Matters on Oyster Creek-12R Outage 1GSCC Insp/Stress Improvement Plan as Described in Licensee Ltr .Inps/stress Improvement Plans Rept Encl
ML20154C6511988-05-0909 May 1988
Summary of 880414 Progress Review Meeting W/Util & State of Nj Re Status of Facility Licensing Actions.List of Attendees Encl
ML20196J9901988-03-0707 March 1988
Summary of 880224 Meeting W/Util in Rockville,Md Re Status of Plant Licensing Actions.List of attendees,marked-up Licensing Action Rept & Updated SEP Issues Encl
ML20149L5861988-02-16016 February 1988
Summary of 871221 Meeting W/Util in Bethesda,Md Re Licensee Proposed Methodology to Develop New Seismic Floor Response Spectra.Attendance List Encl
ML20149H8331988-02-10010 February 1988
Summary of 880106 Meeting W/Util & State of Nj in Bethesda,Md Re Status of Plant Licensing actions.Marked-up Licensing Action Rept,List of Attendees,Util Topical Rept on Fuel Reload Review & Cycle 12 Reload Schedule Encl
ML20236W3801987-11-30030 November 1987
Summary of 871113 Meeting W/Util in Bethesda,Md Re Drywell Corrosion Problem at Facility.List of Attendees,Proposed Meeting Agenda & Util Presentation 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
ML20239A6721987-09-11011 September 1987
Summary of 870903 Meeting W/Util in Bethesda,Md Re Util Proposed Methodology to Develop New Seismic Floor Response Spectra for Plant.List of Meeting Attendees & Viewgraphs Encl
ML20237K6461987-08-0606 August 1987
Summary of 870619 Meeting W/Util in King of Prussia,Pa Re Changes to Util Emergency Plan for Plants Based on Changing Plant Status & Reclassification to Post Defueling Monitored Storage
ML20235U3351987-07-14014 July 1987
Summary of 870707 Meeting W/Util in Bethesda,Md Re Proposed Methodology to Develop New Seismic Floor Response Spectra for Plant.List of Meeting Attendees & Licensee Agenda Encl
ML20215K0041987-06-18018 June 1987
Summary of 870611 Meeting W/Util in Bethesda,Md Re Drywell Corrosion at Plant & Status of Sep.Attendance List & Util Agenda for Proposed Actions Encl
ML20214L1171987-05-22022 May 1987
Summary of 870515 Meeting W/Util in Bethesda,Md Re Status of Station Licensing Actions.Attendance List & marked-up Licensing Action Rept Encl
ML20207A5221987-05-15015 May 1987
Summary of Operating Reactors Event Meeting 87-13 on 870507 Re Events Which Occurred Since 870428.List of Attendees, Events Discussed & Significant Elements of Events & Summary of Events Presented Encl
ML20207S3431987-03-13013 March 1987
Summary of 870226 Meeting W/Util in Bethesda,Md Re Plans to Mitigate Corrosion of Drywell Shell.List of Attendees & Meeting Agenda Encl
ML20207S1651987-03-13013 March 1987
Summary of 870120 Meeting W/Bwr Owners Group in Bethesda,Md Re Sys for Combustible Gas Control During Loca.Viewgraphs & Attendees List Encl
ML20207R9701987-03-0909 March 1987
Summary of 870211 Meeting W/Util in Bethesda,Md Re Conceptual Design of Isolation Condensers Drywell Piping Penetrations.Attendee List Encl
ML20207Q0871987-01-14014 January 1987
Summary of 861219 Third Meeting W/Util in Bethesda,Md Re Corrosion of Outer Drywell Shell at Elevation Just Below Downcomers.Supporting Documentation Encl
ML20207N2271987-01-0505 January 1987
Summary of 861210 Meeting W/Util,Niagara Mohawk Power Corp, GE & Chicago Bridge & Iron in Bethesda,Md Re Corrosion of Outer Surface of Drywell Shell.List of Attendees,Drywell Figures,Meeting Notice & Licensee Handout Encl
1999-07-29
[Table view]
Category:MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
MONTHYEARML20210H6681999-07-29029 July 1999
Summary of 990329 Meeting with Gpu in Forked River,Nj Re Possibility of Decommisssioning of Oyster Creek Nuclear Generating Station.List of Attendees & Licensee Handouts Provided
ML20195G1391998-11-16016 November 1998
Summary of 981103 Meeting with Gpu in Rockville,Md Re Possible Shutdown & Decommissioning of Oyster Creek Nuclear Generating Station in Year 2000.List of Attendees & Handout Encl
ML20216E3421997-09-0303 September 1997
Summary of 970826 Meeting W/Gpu in Rockville,Md Re Possibility of Decommissioning of Plant.Agenda,Meeting Handouts & Primarily Centered Activities Associated W/Decommissioning Plant in Yr 2000 Encl
ML20148D8531997-05-28028 May 1997
Summary of 970502 Meeting W/Util to Discuss Status of Implementation Schedule for Completion of Installation of Thermo-lag at Plants.List of Attendees Encl
ML20149J5251994-12-29029 December 1994
Summary of 941219 Meeting W/Util Re Status of Licensing Actions.List of Attendees & Activities Encl
ML20058K1831993-11-26026 November 1993
Summary of 931119 Meeting W/Licensee in Rockville,Md Re Licensing Issues Involved in Construction & Loading of Independent Spent Fuel Storage Installation to Be Constructed at Plant
ML20059F3931993-10-27027 October 1993
Summary of 931020 Meeting W/Gpu Nuclear Corp in Rockville,Md Re Status of Plant Licensing Actions.List of Attendees Encl
ML20128K8261993-02-0909 February 1993
Summary of 921123-24 Meeting in King of Prussia,Pa Re Region I Positions on Operator Licensing Issues & Solicit Input from Util Training Staffs
ML20127M5941993-01-26026 January 1993
Summary of 930112 Meeting W/Util in Rockville,Md Re Reactor Bldg Access Control Mod & Operational Safeguards Response Evaluation.List of Attendees & Handouts Encl
ML20127F6681993-01-14014 January 1993
Summary of 930112 Meeting W/Util in Rockville,Md Re Status of Licensing Actions.List of Individuals Participating in Discussion & Marked Up Copy of Staff Pmr Encl
ML20127E1281993-01-13013 January 1993
Summary of 930106 Meeting W/Util in Rockville,Md Re Insp of Plant Core Spray Spargers.List of Discussion Participants & Licensee Agenda Encl
ML20125C2461992-12-0707 December 1992
Summary of 921118 Meeting W/Util in Rockville,Md Re Status of Licensing Actions
ML20058K1871990-12-11011 December 1990
Summary of 901114 Progress Review Meeting at Plant Site Re Status of Licensing Actions.List of Attendees Encl
ML20062F1121990-11-15015 November 1990
Summary of 901107 Meeting W/Util in Rockville,Md,Re Fuel Channel Bowing & Reuse of Fuel Channels at Facility
ML20059N5951990-10-0303 October 1990
Summary of 900919 Meeting W/Util in Rockville,Md to Discuss Matters Re Plant Drywell Corrosion.Viewgraphs Encl
ML20246M5871989-08-29029 August 1989
Summary of 890802 Meeting W/Util in Rockville,Md Re full-term OL & Other Licensing Activities.List of Attendees & marked-up Regulatory Info Tracking Sys List of Unresolved SEP Topics & TAC Numbers Encl
ML20246L4001989-07-10010 July 1989
Summary of 890627 Meeting W/Util in Rockville,Md Re Combustible Gas Control for Plant.List of Individuals Attending Meeting,Proposed Meeting Agenda,Matl Used by Util in Discussion & Condensed History of Gas Control Issue Encl
ML20245J7191989-06-20020 June 1989
Summary of 890607 Meeting W/Util in Forked River,Nj to Discuss Status of Plant Licensing Actions.List of Attendees & marked-up Copy of Regulatory Info Tracking Sys Encl
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
ML20245J0141989-04-26026 April 1989
Summary of 890413 Meeting W/Util in Rockville,Md Re Status of Licensing actions.Marked-up Regulatory Info Tracking Sys List Encl
ML20235N0661989-02-21021 February 1989
Summary of 890213 Meeting W/Util & State of Nj Re Air Sys Relating to MSIVs & Reactor Bldg to Torus Vacuum Breakers. Util Should Document Overall Methodology Used for MSIV Leakage Problems Prior to Startup.Viewgraphs Encl
ML20235H0521989-02-10010 February 1989
Summary of 890130 Meeting W/Util in Rockville,Md to Discuss SSOMI (SSOMI-design Phase) Issue 2 Re Setpoints for Process Variables & Actions to Be Taken Before Startup.List of Attendees & Agenda Encl
ML20195H9671988-11-23023 November 1988
Summary of 881110 Meeting W/Util in Rockville,Md Re Status of Facility Licensing Actions
ML20155F4801988-10-0606 October 1988
Summary of 880928 Progress Review Meeting W/Util in Forked River,Nj Re Status of Plant Licensing Actions
ML20207M0771988-10-0505 October 1988
Summary of Operating Reactors Events Meeting 88-39 on 881004.List of Attendees & Viewgraphs Encl
ML20154F7971988-09-15015 September 1988
Summary of 880901 QA Meeting W/Util in Rockville,Md to Discuss Rev 2 of Util Operational QA Plan for Plants.Agenda & List of Participants Encl
ML20207F4451988-08-0909 August 1988
Summary of 880721 Meeting W/Util in Rockville,Md Re Retran Analytical Model & Cycle 12 Fuel Reload Analyses.Attendance List & Matl Used by Licensee in Meeting Encl
ML20151L8991988-07-28028 July 1988
Summary of 880713 Progress Review Meeting W/Util in Rockville,Md Re Status of Licensing Actions.List of Participants & marked-up Copy of Staff Regulatory Info Tracking Sys Encl
ML20150B3271988-07-0606 July 1988
Summary of 880628 Meeting W/Util in Rockville,Md Re Facility Outage IGSCC Insp/Stress Improvement Plans
ML20150C0101988-06-22022 June 1988
Summary of 880525 Meeting W/Gpu in Rockville,Md Re Matters Related to site-specific Response Spectra.Viewgraphs Encl
ML20195K0451988-06-16016 June 1988
Summary of 880526 Meeting W/Util in Rockville,Md Re Matters on Oyster Creek-12R Outage 1GSCC Insp/Stress Improvement Plan as Described in Licensee Ltr .Inps/stress Improvement Plans Rept Encl
ML20154C6511988-05-0909 May 1988
Summary of 880414 Progress Review Meeting W/Util & State of Nj Re Status of Facility Licensing Actions.List of Attendees Encl
ML20196J9901988-03-0707 March 1988
Summary of 880224 Meeting W/Util in Rockville,Md Re Status of Plant Licensing Actions.List of attendees,marked-up Licensing Action Rept & Updated SEP Issues Encl
ML20149L5861988-02-16016 February 1988
Summary of 871221 Meeting W/Util in Bethesda,Md Re Licensee Proposed Methodology to Develop New Seismic Floor Response Spectra.Attendance List Encl
ML20149H8331988-02-10010 February 1988
Summary of 880106 Meeting W/Util & State of Nj in Bethesda,Md Re Status of Plant Licensing actions.Marked-up Licensing Action Rept,List of Attendees,Util Topical Rept on Fuel Reload Review & Cycle 12 Reload Schedule Encl
ML20236W3801987-11-30030 November 1987
Summary of 871113 Meeting W/Util in Bethesda,Md Re Drywell Corrosion Problem at Facility.List of Attendees,Proposed Meeting Agenda & Util Presentation 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
ML20239A6721987-09-11011 September 1987
Summary of 870903 Meeting W/Util in Bethesda,Md Re Util Proposed Methodology to Develop New Seismic Floor Response Spectra for Plant.List of Meeting Attendees & Viewgraphs Encl
ML20237K6461987-08-0606 August 1987
Summary of 870619 Meeting W/Util in King of Prussia,Pa Re Changes to Util Emergency Plan for Plants Based on Changing Plant Status & Reclassification to Post Defueling Monitored Storage
ML20235U3351987-07-14014 July 1987
Summary of 870707 Meeting W/Util in Bethesda,Md Re Proposed Methodology to Develop New Seismic Floor Response Spectra for Plant.List of Meeting Attendees & Licensee Agenda Encl
ML20215K0041987-06-18018 June 1987
Summary of 870611 Meeting W/Util in Bethesda,Md Re Drywell Corrosion at Plant & Status of Sep.Attendance List & Util Agenda for Proposed Actions Encl
ML20214L1171987-05-22022 May 1987
Summary of 870515 Meeting W/Util in Bethesda,Md Re Status of Station Licensing Actions.Attendance List & marked-up Licensing Action Rept Encl
ML20207A5221987-05-15015 May 1987
Summary of Operating Reactors Event Meeting 87-13 on 870507 Re Events Which Occurred Since 870428.List of Attendees, Events Discussed & Significant Elements of Events & Summary of Events Presented Encl
ML20207S1651987-03-13013 March 1987
Summary of 870120 Meeting W/Bwr Owners Group in Bethesda,Md Re Sys for Combustible Gas Control During Loca.Viewgraphs & Attendees List Encl
ML20207S3431987-03-13013 March 1987
Summary of 870226 Meeting W/Util in Bethesda,Md Re Plans to Mitigate Corrosion of Drywell Shell.List of Attendees & Meeting Agenda Encl
ML20207R9701987-03-0909 March 1987
Summary of 870211 Meeting W/Util in Bethesda,Md Re Conceptual Design of Isolation Condensers Drywell Piping Penetrations.Attendee List Encl
ML20207Q0871987-01-14014 January 1987
Summary of 861219 Third Meeting W/Util in Bethesda,Md Re Corrosion of Outer Drywell Shell at Elevation Just Below Downcomers.Supporting Documentation Encl
ML20207N2271987-01-0505 January 1987
Summary of 861210 Meeting W/Util,Niagara Mohawk Power Corp, GE & Chicago Bridge & Iron in Bethesda,Md Re Corrosion of Outer Surface of Drywell Shell.List of Attendees,Drywell Figures,Meeting Notice & Licensee Handout Encl
1999-07-29
[Table view] |
Text
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ACRS Henbara DRL MEETING ON OYS'rtt CRIEK trNIT 1 - PtnUULY PIPING, VALVES, AND MAIN STEAM STOP VALVES Attached for your information is a summary of discussions bald by #ftL
! with Jersey Centra $ Power Coerpany, Gen.aral Electric, and Berns & Roe, regarding the alleged piping deficiencies, used valves, and the mah steam stop valve leakage problem.
\ < .N.f 9.,n.n/A y AY 0
y r/w t J. C. McKinley
/ 8taf f Assistant
Attachment:
Minutes of DRL Meeting on Oyster Creek Unit 1, i F.ay 14, 1969 1
Table of Valves believed to have come from surplus suppliers l.
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+ .GE $1gf 4 N&-
m k _ JERSEY CENTRAL l'0VER & LIGilT COMPA';Y MEETING ATTEN11ANCE J
MAY 14, 1969 AEC Jerer' Cent ral General Electric M. M. Mann DR G. l? Rit+er D. 1:. Uillett
, J. C. Mcl;inley , ACRS D. R. Rees R. A. liuggins l t
T. Schroeder, DR', G. F. Trowbrid t:e J. Barnard i R. S. Boyd DRL B. G. Avers J. Omer --
S. Levine, DRL 9, g , p p 7 ,--
V. Stello, DRL 11. D. I,owell R. L. Tedesco DRL R. A. Dieterich J. R. Scara, DRL L, . \, . l,o e A. W. Dromerick, DRL M. Wetterhahn
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CC - CO j ];.c p}qq gp g g, ,g L. D. Lou L. Kornblith 11 . :1. Gustafson :;. M . Cole -
R. H. Engelken A. L. Holt R. N. Zogran J. P. O'Reilly -
m J. Keppler A. F. Ryan Burnn & Roo R. T. Carlson G. A. Lari W. J. Collins a G. W. Reinnuth B. A. Lofy (Parameter, Inc.)
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EETNISDA, MARYLAND {M MAY 14, 1969 $.1
'M5 on May 14, 1969 Dal. held a meeting with retpresentoivos of Jersey Central, General Electrie, and 'derne 4. Roe to hear the progress on the et investt-gation into the allegations of deficient piping in the Oyster Creek primary system, as well as to hear the progress on the investigation into the appar-ent use of seccad hand valves, and finally to hear the status of the repairs or leak terting of the primary system steam stop valves. N status of each af these issues is summarised below.
i primary System mina i
1.
I CE presented this report in tuder to see if the material they had developed wes adequat6 to satisfy the needs of the Regulatory Staff. They opened by stating that they had reviewed the material used to determine if it was i
suitable for the service it was to see, according to the CE design eriteria.
The primary difficulty related to piping procured from the Allied Tube and Fipe Company (ATApCO). During the investigation CE triad to account for f,
all of the piping that was utilised in high pressure systems. N y reviewed their documentation and then removed the tasulation from the piping to ideu-tify it by marking on the pipe and also to perform mondestructive tests in order to identify and esttify that tais was the pipe. They used a magnette test to determine the ferrite content at the welds: they used a spectrometer analysis to determine the chee.ical content of the pipe: they reviewed the radiographs of the circoferentiel welds, primarily to re-examine ".nat por-l tion of the longitudinal seen weld shat was visible in each of these radio-graphs. This amounted to approximately four linear inches of longitudinal weld la each radiograph. They used sa 11trasonic test for piping thickness: ,
- , they made hardness testst they nada e destructive test of a sample of l t piping found in one of the suppliers yards that was the same as the pi3ing j vesd in the plant, although it was not from the same section; they ran a hydro-static test of a six foot section of the twelve inch pipe. GE plans to sub-mit through the applicant a report on this inveetigation in about three weeks, l
which would be about Jane 9, 1969. CE had made a chart, wbM,b will be in-t cluded in the firal report, whowing the systems involved, tha total foot i
footage of piping inside and outside of the primary containment strue.ture, the vendor for the piping dad for the fittings, the heat unmber of the piping '
and fittings, whether the x-ray records were svailable or met, and for which vendor the radiographic records were imeonplete. Where radiographs were not available, CE is going hack and re-radiographing. They are satisfied that the piping was radiographed, however, the records cannot be releected, The systems in question are those related to the emergency condenser, the asce spray, and the shutdown cooling system. Other systess were investigated, but the accounting showed that only these systems are deficient in documen*
l
-tattaa, using stainless eteel seas welded pies. CE has upgLthis a orrxx > - -- -
WRnust > . . . . ..-
DATE > . . . - _ _ . . . - - - - . - . .
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%snte A N0-819 (Rev. S 4D U 5 emmanenwr re'ams waxt i ow+ s.'s l
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J c>aparative swthod on other systems to assure that the other pipe is mented and that the pipe was not mislabeled. In this area it appears that j only the pipe is in question. The fittings are p+digreed as me+ded, the corporations of Tube Turas and Tsitor Forge state that if their corporats markings appear en the fitting the corporation will eartify that the na-terial used in these fittings meets the specifications La all respects.
In the final report, CE plans to state that they have looked at varteus systvss, and identified those systems, and that they have the macessary certifications on all pipe and fittinge sucept for these three systema, med then to describe tbstr investigetton of the piping in these three systems.
, Mr. O'Iteilly pointed ov*, that since cartification had been received from ATAPCO on this piping, it cast out on the validity of the other cartifica-l tions received fro:n other vendors. CE reported that in reviewing the radiographs of this piping, they teve found evidence of repairs made to the welds, but have found no unacceptable defelte, therefore, they are settsfied that the piping was actually x-rayed and corrective setion taken, however, the documentation of this is not available. No repairs have been requirett so f ar as a rough result of CE's review of the x-rays of all of the twelve-inch saatt welded stainless staal pipe. Some place in thi records there was indication that one 20'-length of piping (12") had an indication of leek of penetration. GE has to.ated approximately 19' of this pipe. Tour feet of it indicates sonething appearing tc h.a. lack:of pene-tration. The remainder has a different appearance. The internal weld on sea welded pipe is usually made in a single pass, however, it is possible I to use a double hass technique leaving a small valley between the weld j papses. This wwld give an appearanei of a lack of penetration or a lack _
{ of fusion. By using an angle fadiography technique they have been able to j determine that the indications are within approximately 1/16 et an inch from the inside surface of the weld, and the indications are *.herefore coa-sidered te be non injurious. In a aearch through the supply house, an 8' section of 12" pipe from this same heat was found and a section was taken l through the saan veld. h was bent and tested and found to be completely I acceptable. CE is in the process of doing 100% radiography es all of the I
questionable 12 and 16 inch stainless steel seam welded pipe. They have taken at least one spectrographic sample en each sheet of pipe Lavolved, I and have land in all cases that the spectrographic analysis shows this to be 316 material. The largest unber of samples and tests have been ude outside of the drywall due to the accessibility problems in;ide. However, CE feels that the tests and results are representative due to the fact that 3
~
l the materiale are from the same heats, etc. CE has performai vitresonie t; '
thickness testing and found that all of the material is within ASME destien L '
timits. CE estimattd that they keye re reviewed, atther by leeking at pre-views radiography or re taking radiographs, about 70% of the ATAPCO pipe la , '
the re-radiograthy program they had fwnd two indications which evententif turn rd out so be grt R ng marka, I CH1CE > _. .. . , . . .. - - - -
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'n 16, u Mr. O'Reilly pointed out that noe of the allegattens made was that the y p piping stilised was under weight. In reply CE pofated out that the 16"-
pipe . hchedule 40, which would reguire a moninal wall thichsess of 0.644".
Now if the pipe was purchased to A312 specifications, it would be permitted to deviate from this thickness by 112%1 and the pipe stilised would be within specification. Eowever, if the pipe had been purchased to spuification A358, which allows only 10.010", then the pipe utilised would be indeed under weight. In examining this, one would see that the 12" pipe would be 0.017" thin, the 10" pipe would be 0.014" thin, and the 8" pipe would be 0.010" thin. However, CE has calculated the hoop stress in this pipe l and points out that the allowable design stress in 1965 was 17,125 pai, l
howcVer, this was changed in 1969 to allow only 16,000 psi. Their cateu. '
laced stress for the 16" pipe is 11,600 pai, for the 14" pipe it is 11.450 psi, for the 12" pipel 11,870 pai, for the 10" pipe g 11,4FJipei, and for the 8" pipe 10.680 pet. The current calculations show that this pipe f sieets the requirements of USA standard 831.1. All of the aechanical tests have exceeded the minisam requirements.
i Mr. Engelken pointed out that even though the stress calculations indicate lov stresses, the f act is that this pipe was purchased to a specification, and it failed to meet that specification. It fails to meet either 312 or 358, and he suggested that CE was askint che AEC to approvo pipe that does not meet any code, but is believed to be adequate from the testing program.
Mr. Ecyd suggestad that CE should spell out in the forthcoming andadment the basis on which they would like to havs this piping and their anedysis judged. The record should cisarly show the status of this pipe, the action
. taken to assure its integrity, and any agreement reached between the appli-cant and the construction people,
- 2. Use of Apparently 86cond-Hand Ysives CE arplaimed that late in construction, sometime betveen May and August of 1967, four purchase orders were placed for wiscellaneous valves, and con-trary to usual practica, these orders were placed with a supply house, and involved approximately 263 valves. Two-thirds of these valves came from bonified suppliers, and it has been subsequently established that 40 come from a surplus valve dealer. The purchase order was isen d by Burne 4 Roe.
The investigation thus far has traced 54 valves from the Metropoliten Flumbing Company or some othat source, and CE is currently trying to establish what kind of valves they have, where they are located, and where they came frem.
Tkte tavestigation has not progressed to the degree of the pipe investigaties.
It wea peinted out that the ASTM requirements for marking of the heat number and material on valves is rather tenient, med in investigating these velyss, they ea=*a fa=mA en e-17 with thm AMM Jaqui r mamen ts . Thars h however. a gajgf disagreement jbetwoca the rivision of C pliance and thisappitcash, regardisf ths"sppitcability aClhe"Weelhar" anses"te1SA" Standard-131T1.
wmMif,0pplicant clain;e that the helear Code C ses are not applicable while
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4 the Hvisieu of Compliance feels that they are saadatory. Of partiestar interest are six carbon steel, 10" shock valves. Neo are serboe steel valves, sad so ekek has been made of the heat traitment er kareness of g
these valve bodies. Noe were manufactured by the Crane Corporattom, sad four of the six valve bodies have the heat member indicated. OE is working I
to establish W beat meeners for the other bodies. Best members are also fo6ind on five of the six bonnets. From Crane records it appears that j
these valves w re fabriested in & marly 1950's. A11 of these valves were f abricated as flanged valves, and at the rogvest of harms & Roe the flenges were a4chined of f to provide htt weld end preparaties. It is met clear if tkse are new or used valvas, however, a factory reyrasenta-tive from the Crano Corporation has been at the site when the valves were opened and be 1.aspected the internals and osv me evidence of waar. The appitesat is satisfied that these valves are suitable for the servies in-tended.
It was pelated out that all of the valves of this type are hydro-statically tested to 1100 pai. CE has saleviated the number of eyeles that could be permitted on these valves at 360 poi, 300'T and found that tk valves could withstand 100,000 eyeles, therefore, they seestede there is no fatigue problem from this stress level for the use of new valves, however, they have no indleation of the prior history or was of thsee nives. Other valves of guestionable origin are 900 lb., 1", 1/2", 3/4",
socket welded valves. The feet that tt.ese are socket welded valves and the end preparation is wedamaged, indleates that they are not used, but merely surplus valves. N markings en these valves are quite complete and meet code requirements.
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- 3. Fittinas l
CE pedigree. believes that they can show that all of the fittlegs used have the proper 4
Leak _ Rete of the Main Steam stwo Valves CE reported that they had flushed and emereised the main stea step valves and have been able to achieve a leak rate of 1 3ft /kr of air at 30 poi en one set et step valves. N ether set has aise be however, its leak rate ranges between 60 and 30 f tgn/hr. exercised and flushed, GE reported they were continuieg measureewats en this set of valves, however, they felt that l
they had deseastrated compliance with the Technteal Specificattens using the Technical Specification leak rata, of 68 ft3 /hr, and the latest values are lass than 50% et the allowable. GE peinted out that they are waabte to make a ansaingful test of having both valves in series elesed and pree-surising the reactor vessel to 20 psi with air to determina the actual leak rate.
It was noted that the valve used la the state line taats had en initial laak rate of approximately 9 f t /hr atJQJat air mainta 4-a _it 3
==a Heat' insta lled. N spplicant potated out that be is required Tntythree1 months according tar the tschates1 specifieatists, to test thess' valves sumue e
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DESCklPTION OF SurJ'LUS VALVES B&R SPEC B & R P.O. SOURCE' NO. OF DESCRIP- SYS.
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Iten ho. VALVES TION 276 304 Metro 6 10"300#CH CS N f.
395 177 2 1"150#GL SS ?
' 396 177 1 1/2"150#GL SS ?
398 177 1 1-1/2"150#CH SS ?
j 399 177 4 2"150#G SS ?-
416 304 1 2"50#GL CS Ai r 418 304 10 1"900#GL SS Reci '
l 419 304 8 1"900#GL SS NE 420 304 2 3/4"900#GL CS MS 421 304 2(37) 1/2"900eGL SS Reci 422 304 1 2-1/2"150#G CS Oil 423 304 1 2-1/2"150#CH CS 011 31i 164 X 2 1/2"150#G CS ?
327 164 X 2 4"125#G Cl Air
, 352 164 X 2 3/4"900fG CS Heac 354 164 X 2 2"150#CH CS Radw l 356 164 X 2 1-1/2"300#G CS Off-392 177 X 2 1-1/2"600hG SS Radw 427 304 X 2 1"1506GL BR Air
}
2 LML:etb 5/12/69
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