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Category:MEETING MINUTES & NOTES--CORRESPONDENCE
MONTHYEARML20210A6941999-07-16016 July 1999
Summary of 990628 Meeting with Util in Rockville,Md Re Arkansas Nuclear One,Unit 2 Steam Generator Operational Assessment.List of Meeting Attendees & Licensee Handout Used During Meeting Encl
ML20196J2351999-06-29029 June 1999
Summary of 990617 Meeting with B&Wog & FTI Re B&Wog Emergency Operating Procedure Program.List of Meeting Attendees & Presentation Slides Encl
ML20196H1471999-06-24024 June 1999
Summary of 990609 Meeting with Duke Energy Corp Re NRC Conclusions for TIA-98008 on Use of Compensatory Actions for Control Room Emergency Ventilation System & to Present Positions.List of Participants & Licensee Handouts Encl
ML20206L4921999-05-10010 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
ML20205J6351999-04-0505 April 1999
Summary of 990303 Meeting with Entergy Operations,Inc in Rockville,Maryland Re Status of Arkansas Nuclear One Backlog for Open Licensing Actions & Activities.List of Meeting Attendees & Licensee Handout Encl
ML20207M9251999-03-11011 March 1999
Summary of 990302 Meeting with Entergy Operations,Inc in Rockville,Md Re Arkansas Nuclear One Steam Generator Insp & Repair Plans for Upcoming Unit 1 Refueling Outage.List of Attendees & Licensee Handout Used at Meeting Encl
ML20203C2351999-02-0404 February 1999
Summary of 990127 Meeting with Duke Energy Corp Re Proposed License Amend to Take Credit for Soluble Boron & Partial Credit for Boraflex in Sf Pools at McGuire Nuclear Station. List of Attendees & Handouts Provided by Duke Encl
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
ML20198G5501998-12-18018 December 1998
Summary of 981201-02 Workshop with Entergy Operations,Inc in Taft,La Re Licensing Processes,Licensing Submittals & Other Topics That May Affect Licensing Processes & Submittals. Copy of Slides Presented During Workshop 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
ML20206S8501998-11-13013 November 1998
Summary of 456th ACRS Meeting on 980930-1002 in Rockville,Md Re Appropriate Action on Items Listed in Attached Agenda
ML20155H3931998-11-0202 November 1998
Summary of 981007 Meeting with Util Re Review Status of Standard Quality Assurance Manual for All Util Sites.List of Meeting Attendees Encl
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
ML20154A0271998-09-25025 September 1998
Summary of 980909-10 Meeting with Entergy Operations,Inc Re Implementation of risk-informed Inservice Insp Program. List of Attendees & Rept Prepared by Structural Integrity Associates,Inc Encl
ML20151X0011998-09-10010 September 1998
Summary of 980827 Meeting W/Util to Discuss Status of Review of Std QA Manual.List of Attendees Encl
ML20237E1611998-08-25025 August 1998
Summary of 980728 Meeting W/Util in Rockville,Md Re Replacement of SG at ANO Unit 2.List of Attendees & Handouts Encl
ML20236P1761998-07-13013 July 1998
Summary of 980709-10 Meeting W/Util Re Technical Matters Related to Proposed Improved TS for Catawba & McGuire Nuclear Stations.List of Meeting Participants Encl
ML20236M0501998-07-0808 July 1998
Summary of 980702 Meeting W/Entergy Operations,Inc to Discuss Review Status of Std QA Manual for All Entergy Sites.List of Attendees Encl
ML20249C7711998-06-29029 June 1998
Summary of 980617 & 18 Meetings W/Duke Energy Corp Re Technical Matters Related to Proposed Improved TSs for Catawba & McGuire Nuclear Stations.List of Meeting Attendees Encl
ML20249B4361998-06-17017 June 1998
Summary of 980514 Meeting W/Duke Energy Corp Re Info Related to Ice Condenser Issues,Ice Weight Redistribution & Reduction & Block Ice Utilization.List of Participants & Handout Provided by Util,Encl
ML20248E7911998-06-0101 June 1998
Summary of 980518 Meeting W/Duke Energy Corp Re Technical Matters Related to Proposed Improved TS for Catawba & McGuire Nuclear Stations.List of Meeting Participants Encl
ML20217K3461998-04-24024 April 1998
Summary of 980401 Meeting W/Entergy Operations,Inc Re Licensing Issues & Regulatory Performance Efficiencies.List of Attendees & Agenda for Meeting Encl
ML20217K5141998-04-24024 April 1998
Summary of 980416 Meeting W/Entergy Corp Re Standardization of site-specific Security Plans.List of Meeting Attendees & Agenda for Meeting Encl
ML20217F4811998-03-26026 March 1998
Summary of 980319 Meeting W/Licensee to Discuss Status of Development of Std QA Manual for All Entergy Sites.List of Attendees Encl
ML20203L9501998-02-19019 February 1998
Summary of 980204 Meeting W/Util to Discuss Info Re Design, Operabiliy & Qualifications of Grinnell Snubbers at Plant. Meeting Scheduled to Resolve Issues Re Staff Rai.List of Participants & Handouts Provided by Util Encl
ML20203B5741998-02-11011 February 1998
Summary of 980122 Meeting W/Entergy in Rockville,Maryland Re Licensing Issues & Standardization of Licensing Documents. List of Meeting Attendees & Meeting Agenda Encl
ML20203B7081998-02-10010 February 1998
Summary of 980127 Meeting W/Duke Energy Corp Re Proposed Rev of Topical Repts.List of Attendees & DEC Slides Encl
ML20198G2131997-12-23023 December 1997
Summary of 971118 Meeting W/Duke Energy Corp in Rockville, Md,Re non-vital Electrical Bus,Kxa,Dual Unit Reactor Trip on 970906.List of Meeting Attendees & Licensee Handout 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
ML20202E6761997-11-26026 November 1997
Summary of 971030 Meeting W/Duke Energy Corp Re Matters Related to Proposed Improved TS for Catawba & McGuire Nuclear Stations.List of Attendees,Meeting Agenda & Licensee Handout Matl Encl
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
ML20212G8521997-10-29029 October 1997
Summary of 971022 Meeting W/Entergy Svcs,Inc Re Development & Implementation of Common or Std QAP for All Sites.List of Meeting Attendees & Viewgraphs Encl
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
ML20211A0161997-09-16016 September 1997
Summary of 970828 Meeting W/B&Wog Re Mgt of Aging Effects for Reactor Vessel Internals & Activities Related to Baffle Bolting Integrity Issues.List of Attendees & Their Affiliation & Handouts Encl
ML20217P0651997-08-22022 August 1997
Summary of 970709 Meeting W/Util Re Issues Related to 1996 Rev of McGuire Ufsar.List of Attendees & Verbal Response 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
ML20140H9181997-05-0909 May 1997
Trip Rept of 970410-11 Visit to Ul to Observe full-scale Fire Endurance Test of 1 & 3 Hour Versawrap Fire Barrier Sys.List of Participants Encl
ML20137W3311997-04-17017 April 1997
Summary of 970407 Meeting W/Util & Transco Products,Inc Re Versawrap,New Electrical Raceway Firewrap Sys.Attachment 1 Describes Components of Typical Veraswrap Barrier & Attachment 2 Re Transco Products,Inc Test Procedure 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
ML20149M3611996-12-11011 December 1996
Summary of 96111 Meeting W/Licensee in Rockville,Md to Discuss Comments Developed in Response to NRC Advance Notice of Proposed Rulemaking on Financial Assurance Requirements for Decommissioning Nuclear Reactors.List of Attendees Encl
ML20129K3791996-11-21021 November 1996
Summary of 961016 Meeting W/Dpc at Plant Re Ongoing Current Licensing Issues & Safety Initiatives at Three Nuclear Stations.Meeting Attendees,Agenda & Handouts Encl
ML20134M6611996-11-21021 November 1996
Summary of 961114 Meeting W/Listed Licensees in Rockville,Md to Discuss Results of Self Assessment of Accuracy of Info in FSARs for Four Nuclear Reactor Sites.List of Attendees & Licensee Handout Encl
ML20129G4921996-08-29029 August 1996
Summary of 433rd ACRS Meeting on 960808-10 Re Design Changes Proposed by Asea Brown Boveri - C-E Re Certification of Sys 80+ Design,Secy 96-128,proposed Rev 3 to Reg Guide 1.8,revs to Reg Guides 1.84,1.85 & 1.147 & Rev 3 to Reg Guide 1.105
ML20059L0651994-01-26026 January 1994
Summary of 931201 Meeting W/Util in Rockville,Md Re Presentation by Licensee on SG Replacement Project. Attendees Listed in Encl 1
ML20059C4041993-12-27027 December 1993
Summary of 931206 Meeting W/Entergy Operations,Inc in Rockville,Md to Discuss Licensee Proposed Changes to Security Plans for Plant,Units 1 & 2.List of Attendees Encl
ML20058P4491993-12-15015 December 1993
Summary of 931206 Meeting W/Entergy Operations,Inc in Rockville,Md Re 931021 Submittal of Proposed Alternative to 10CFR50.55a(f) & (g),10-Year Inservice Insp & Inservice Testing Update. List of Attendees Encl
ML20058H0351993-12-0808 December 1993
Summary of 930830 Meeting W/Entergy Operations,Inc Re Operation of ANO-2 W/O SG Exam Until Mar 1994 Scheduled Refueling Outage.List of Attendees & Handouts Encl
1999-07-16
[Table view]
Category:MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
MONTHYEARML20210A6941999-07-16016 July 1999
Summary of 990628 Meeting with Util in Rockville,Md Re Arkansas Nuclear One,Unit 2 Steam Generator Operational Assessment.List of Meeting Attendees & Licensee Handout Used During Meeting Encl
ML20196J2351999-06-29029 June 1999
Summary of 990617 Meeting with B&Wog & FTI Re B&Wog Emergency Operating Procedure Program.List of Meeting Attendees & Presentation Slides Encl
ML20196H1471999-06-24024 June 1999
Summary of 990609 Meeting with Duke Energy Corp Re NRC Conclusions for TIA-98008 on Use of Compensatory Actions for Control Room Emergency Ventilation System & to Present Positions.List of Participants & Licensee Handouts Encl
ML20206L4921999-05-10010 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
ML20205J6351999-04-0505 April 1999
Summary of 990303 Meeting with Entergy Operations,Inc in Rockville,Maryland Re Status of Arkansas Nuclear One Backlog for Open Licensing Actions & Activities.List of Meeting Attendees & Licensee Handout Encl
ML20207M9251999-03-11011 March 1999
Summary of 990302 Meeting with Entergy Operations,Inc in Rockville,Md Re Arkansas Nuclear One Steam Generator Insp & Repair Plans for Upcoming Unit 1 Refueling Outage.List of Attendees & Licensee Handout Used at Meeting Encl
ML20203C2351999-02-0404 February 1999
Summary of 990127 Meeting with Duke Energy Corp Re Proposed License Amend to Take Credit for Soluble Boron & Partial Credit for Boraflex in Sf Pools at McGuire Nuclear Station. List of Attendees & Handouts Provided by Duke Encl
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
ML20198G5501998-12-18018 December 1998
Summary of 981201-02 Workshop with Entergy Operations,Inc in Taft,La Re Licensing Processes,Licensing Submittals & Other Topics That May Affect Licensing Processes & Submittals. Copy of Slides Presented During Workshop 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
ML20206S8501998-11-13013 November 1998
Summary of 456th ACRS Meeting on 980930-1002 in Rockville,Md Re Appropriate Action on Items Listed in Attached Agenda
ML20155H3931998-11-0202 November 1998
Summary of 981007 Meeting with Util Re Review Status of Standard Quality Assurance Manual for All Util Sites.List of Meeting Attendees Encl
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
ML20154A0271998-09-25025 September 1998
Summary of 980909-10 Meeting with Entergy Operations,Inc Re Implementation of risk-informed Inservice Insp Program. List of Attendees & Rept Prepared by Structural Integrity Associates,Inc Encl
ML20151X0011998-09-10010 September 1998
Summary of 980827 Meeting W/Util to Discuss Status of Review of Std QA Manual.List of Attendees Encl
ML20237E1611998-08-25025 August 1998
Summary of 980728 Meeting W/Util in Rockville,Md Re Replacement of SG at ANO Unit 2.List of Attendees & Handouts Encl
ML20236P1761998-07-13013 July 1998
Summary of 980709-10 Meeting W/Util Re Technical Matters Related to Proposed Improved TS for Catawba & McGuire Nuclear Stations.List of Meeting Participants Encl
ML20236M0501998-07-0808 July 1998
Summary of 980702 Meeting W/Entergy Operations,Inc to Discuss Review Status of Std QA Manual for All Entergy Sites.List of Attendees Encl
ML20249C7711998-06-29029 June 1998
Summary of 980617 & 18 Meetings W/Duke Energy Corp Re Technical Matters Related to Proposed Improved TSs for Catawba & McGuire Nuclear Stations.List of Meeting Attendees Encl
ML20249B4361998-06-17017 June 1998
Summary of 980514 Meeting W/Duke Energy Corp Re Info Related to Ice Condenser Issues,Ice Weight Redistribution & Reduction & Block Ice Utilization.List of Participants & Handout Provided by Util,Encl
ML20248E7911998-06-0101 June 1998
Summary of 980518 Meeting W/Duke Energy Corp Re Technical Matters Related to Proposed Improved TS for Catawba & McGuire Nuclear Stations.List of Meeting Participants Encl
ML20217K3461998-04-24024 April 1998
Summary of 980401 Meeting W/Entergy Operations,Inc Re Licensing Issues & Regulatory Performance Efficiencies.List of Attendees & Agenda for Meeting Encl
ML20217K5141998-04-24024 April 1998
Summary of 980416 Meeting W/Entergy Corp Re Standardization of site-specific Security Plans.List of Meeting Attendees & Agenda for Meeting Encl
ML20217F4811998-03-26026 March 1998
Summary of 980319 Meeting W/Licensee to Discuss Status of Development of Std QA Manual for All Entergy Sites.List of Attendees Encl
ML20203L9501998-02-19019 February 1998
Summary of 980204 Meeting W/Util to Discuss Info Re Design, Operabiliy & Qualifications of Grinnell Snubbers at Plant. Meeting Scheduled to Resolve Issues Re Staff Rai.List of Participants & Handouts Provided by Util Encl
ML20203B5741998-02-11011 February 1998
Summary of 980122 Meeting W/Entergy in Rockville,Maryland Re Licensing Issues & Standardization of Licensing Documents. List of Meeting Attendees & Meeting Agenda Encl
ML20203B7081998-02-10010 February 1998
Summary of 980127 Meeting W/Duke Energy Corp Re Proposed Rev of Topical Repts.List of Attendees & DEC Slides Encl
ML20198G2131997-12-23023 December 1997
Summary of 971118 Meeting W/Duke Energy Corp in Rockville, Md,Re non-vital Electrical Bus,Kxa,Dual Unit Reactor Trip on 970906.List of Meeting Attendees & Licensee Handout 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
ML20202E6761997-11-26026 November 1997
Summary of 971030 Meeting W/Duke Energy Corp Re Matters Related to Proposed Improved TS for Catawba & McGuire Nuclear Stations.List of Attendees,Meeting Agenda & Licensee Handout Matl Encl
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
ML20212G8521997-10-29029 October 1997
Summary of 971022 Meeting W/Entergy Svcs,Inc Re Development & Implementation of Common or Std QAP for All Sites.List of Meeting Attendees & Viewgraphs Encl
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
ML20211A0161997-09-16016 September 1997
Summary of 970828 Meeting W/B&Wog Re Mgt of Aging Effects for Reactor Vessel Internals & Activities Related to Baffle Bolting Integrity Issues.List of Attendees & Their Affiliation & Handouts Encl
ML20217P0651997-08-22022 August 1997
Summary of 970709 Meeting W/Util Re Issues Related to 1996 Rev of McGuire Ufsar.List of Attendees & Verbal Response 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
ML20137W3311997-04-17017 April 1997
Summary of 970407 Meeting W/Util & Transco Products,Inc Re Versawrap,New Electrical Raceway Firewrap Sys.Attachment 1 Describes Components of Typical Veraswrap Barrier & Attachment 2 Re Transco Products,Inc Test Procedure 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
ML20149M3611996-12-11011 December 1996
Summary of 96111 Meeting W/Licensee in Rockville,Md to Discuss Comments Developed in Response to NRC Advance Notice of Proposed Rulemaking on Financial Assurance Requirements for Decommissioning Nuclear Reactors.List of Attendees Encl
ML20129K3791996-11-21021 November 1996
Summary of 961016 Meeting W/Dpc at Plant Re Ongoing Current Licensing Issues & Safety Initiatives at Three Nuclear Stations.Meeting Attendees,Agenda & Handouts Encl
ML20134M6611996-11-21021 November 1996
Summary of 961114 Meeting W/Listed Licensees in Rockville,Md to Discuss Results of Self Assessment of Accuracy of Info in FSARs for Four Nuclear Reactor Sites.List of Attendees & Licensee Handout Encl
ML20129G4921996-08-29029 August 1996
Summary of 433rd ACRS Meeting on 960808-10 Re Design Changes Proposed by Asea Brown Boveri - C-E Re Certification of Sys 80+ Design,Secy 96-128,proposed Rev 3 to Reg Guide 1.8,revs to Reg Guides 1.84,1.85 & 1.147 & Rev 3 to Reg Guide 1.105
ML20059L0651994-01-26026 January 1994
Summary of 931201 Meeting W/Util in Rockville,Md Re Presentation by Licensee on SG Replacement Project. Attendees Listed in Encl 1
ML20059C4041993-12-27027 December 1993
Summary of 931206 Meeting W/Entergy Operations,Inc in Rockville,Md to Discuss Licensee Proposed Changes to Security Plans for Plant,Units 1 & 2.List of Attendees Encl
ML20058P4491993-12-15015 December 1993
Summary of 931206 Meeting W/Entergy Operations,Inc in Rockville,Md Re 931021 Submittal of Proposed Alternative to 10CFR50.55a(f) & (g),10-Year Inservice Insp & Inservice Testing Update. List of Attendees Encl
ML20058H0351993-12-0808 December 1993
Summary of 930830 Meeting W/Entergy Operations,Inc Re Operation of ANO-2 W/O SG Exam Until Mar 1994 Scheduled Refueling Outage.List of Attendees & Handouts Encl
ML20059H9901993-10-29029 October 1993
Summary of 930929 Meeting W/Util in Rockville,Md to Discuss Results of Util Investigation Into Unit 1 SG Tube Leaks. Licensee Agreed to Investigate Leakage Monitoring Program
1999-07-16
[Table view] |
Text
e p Cyl June 1,.1993 Q MEMORANDUM FOR: Brian K. Grimes, Director :
Division of Operating Reactor Support t
FROM: Alfred E. Chaffee, Chief ;
Eveints Assessment Branch '
Division of Operating Reactor Support
SUBJECT:
OPERATING REACTORS EVENTS BRIEFING MAY 26, 1993 - BRIEFING 93-19 On May 26, 1993, we conducted an Operating Reactors Events Briefing (93-19) to inform senior managers from offices of the l Commission, ACRS, NRR, RES, AEOD, and regional offices of !
selected events that occurred since our last briefing on May 19, 1993. Enclosure 1 lists the attendees. Enclosure 2 presents the significant elements of the discussed events.
Enclosure 3 contains reactor scram statistics for the week ending May 23, 1993. No significant events were identified for input into the NRC performance indicator program.
- original signed by Edward F. Goodwin for -
Alfred E. Chaffee, Chief ;
Events Assessment Branch '
Division of Operating Reactor Support ,
Enclosures:
As stated DISTRIBUTION:
1 Central, Files; cc w/ attachments: PDR See next page LKilgore, SECY EAB R/F
- KGray RDennig EGoodwin DSkeen U \
'AB/ DORS .B E EAB/ DORS EAB/ DORS KGray EMurphy EGoodwin AChaffee
[/p/93 ( /l /93 //)/93 [/)/93 OFFICIAL RECORD COPY DOCUMENT NAME: ORTRANS.KAG (G:KAG) '
9308170301 930601
~fDy'f?-S l 0fW Nf PDR DRG NRRB PDR
&TVG M-lr3 V
t
y : O~ O:
a ec:
T Murley, NRR (12G18) E. Murphy (EMCB)_
F. Miraglia, NRR (12G18) J.-Strosnider (EMCB)- i F._Gillespie, NRR (12G18)
S. Varga, NRR (14E4)
J. Calvo, NRR (14A4) '
G. Lainas, NRR (14H3) i J. Roe, NRR (13E4)
J. Zwolinski, NRR (13H24) i E. Adensam, NRR (13E4)
W. Russell, NRR (12G18)
J. Richardson, 10U1 (7D26) t A. Thadani, NRR (BE2) '
S. Rosenberg, NRR (10E4)
C. Rossi, NRR (9A2)
B. Boger, NRR (10H3)
F. Congel, NRR (10E2)
D. Crutchfield, NRR (11H21)
W. Travers, NRR (11B19) -
D. Coe, ACRS (P-315) ;
E. Jordan, AEOD (MN-3701)
G. Holahan, AEOD (MN-9112) ,
L. Spessard, AEOD (MN-3701)
K. Brockman, AEOD (MN-3206)
~
M. Harper, AEOD (MN-9112)
G. Grant EDO (17G21)-
R. Newl ,
GPA (2GS)
E. Beck;ord, RES (NLS-007) '
A. Bates, SECY (16G15)
G. Rammling, OCM (16G15)
T. Martin,-Region I W. Kane, Region I C. Hehl, Region I S. Ebneter, Region II E. Herschoff, Region II S. Vias, Region II :
J. Martin, Region III E. Greenman, Region III J. Milhoan, Region IV B. Beach, Region IV_
l B. Paulkenberry, Region V K. Perkins, Region V
-bec: Mr. Sam Newton, Manager Events Analysis Department Institute of Nuclear Power Operations I 700 Galleria Parkway.
Atlanta, GA '30339-5957 L. m
L : O O ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS FULL BRIEFING (93-19)
MAY 26, 1993 NAME OFFICE NAME OFFICE A. CHAFFEE NRR G. MARCUS NRR R. DENNIG NRR J. HANNON NRR K. GRAY NRR G. ZECH NRR
[
E. MURPHY NRR G. JOHNSON NRR ;
E. GOODWIN NRR J. STROSNIDER NRR t B. GRIMES NRR M. VIRGILIO NRR :
T. ALEXION NRR J. ROE NRR T. KIM NRR W. DEAN NRR.
M. WILLIAMS NRR E. BENNER NRR M. SHUAIBI NRR/RIII J. RICHARDSON NRR D. CARTER NRR D. COE ACRS T. CHAN NRR J. SCARBOROUGH OCM/KR T. TJADER NRR G. BURDICK RES j W. LYON NRR V. BENAROYA AEOD :
7 TELEPHONE ATTENDANCE' l (AT ROLL CALL) i f
Recions -Resident Inspectors f Region I Palo Verde !
Region II j Region III Region IV ,
Region V !
IIT/AIT Team Leaders Misc.
Technical Training Center f
t t
t r'
,- f -
ENCLOSURE-2.-
'l I
.i OPERATING REACTORS EVENTS BRIEFING 93-19 LOCATION: 10 B11, WHITE FLINT i WEDNESDAY, MAY~26, 1993, 11:00 A.M. ll; l1 i
VARIOUS PLANTS RECENT EXPERIENCE WITH l STEAM. GENERATOR TUBES l
1 l
L!
l li i
j
.j l
1 PRESENTED-BY:
EVENTS ASSESSMENT BRANCH l DIVISION 0F OPERATING REACTOR ;
SUPPORT, NRR- !
l l !
l
O.
, .O RECENT EXPERIENCE WITH STEAM GENERATOR TUBES l t
- l, OPERATING REACTOR EVENTS BRIEFING-93-19 MAY 26, 1993 EMMETT MURPHY MATERIALS AND: CHEMICAL ENGINEERING BRANCH
-DIVISION OF ENGINEERING, NRR
~ '
~
.. OUTLINE: :j i
e INTRODUCTION !
o -SG TUBE DEGRADATION MECHANISMS -
l t
e GENERAL HISTORICAL TRENDS l 1
.i e .RECENT TRENDS OF CONCERN j ,
e SGTR EVENT AT PALO VERDE 2 j i
o CIRCUMFERENTIAL CRACKS AT ANO-2 1
-o LARGE-VOLTAGE INDICATIONS AT SUMMER-l
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. EXPERIENCE - PWR STEAM GENERATORS i
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ei STEAM GENERATOR' TUBE DEGRADATION PROBLEMS-ARE si 1
WIDESPREAD THROUGHOUT-THE INDUSTRY l
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- 7 SGTR EVENTS :j
- NUMEROUS FORCED OUTAGES .!
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- EXTENSIVE TUBE REPAIRS AND OUTAGE EXTENSIONS l t L,i
- SG REPLACEMENT AT ELEVEN PLANTS TO DATE (ABOUT 1' PLANT- I PER YEAR SINCE 1980) j t
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- SIGNIFICANT RADIATION EXPOSURE-TO-WORKERS i e
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THERE IS NO END IN SIGHT TO THESE PROBLEMS FOR-PLANTS OPERATING WITH THEIR ORIGINAL ~ STEAM' GENERATORS j h
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O O: eartriuG 932, DRAWING 1 of 5- !
EXAMPLES OF SG TUBE DEGRADATION l MECHANISMS !
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RECENT TRENDS OF CONCERN e SCC IS DOMINANT DEGRADATION MECHANISM AFFECTING SGS
- 40% THROUGH WALL CRACKS CANNOT BE RELIABLY DETECTED
- CRACKS CAN BE RELIABLY DETECTED BEFORE TUBE INTEGRITY IS IMPAIRED, BUT ONLY IF THE LICENSEE USES THE ,
APPROPRIATE TEST EQUIPMENT (INCLUDING PROBES), TEST
~ PROCEDURES, AND DATA ANALYSIS PROCEDURES AND IF THE '
ANALYSTS HAVE BEEN ADEQUATELY TRAINED AND TESTED ON THESE PROCEDURES
- THERE HAVE BEEN WIDESPREAD DEFICIENCIES IN INSPECTION PROGRAMS THROUGHOUT THE INDUSTRY (SEE INFORMATION NOTICES 92-80, ETC.)
- APPARENT CRACK GROWTH RATES CAN BE HIGH; MID-CYCLE INSPECTIONS ARE SOMETIMES NECESSARY (E.G., MCGUIRE 1 AND 2, ANO-2) e SCC IN FREESPAN IS BECOMING MORE PREVALENT E.G., MCGUIRE 1 AND 2, PALO VERDE 2, FARLEY l
- CAUSED THE TWO MOST RECENT RUPTURES (MCGUIRE 1, PALO VERDE 2)
- EXTRAORDINARY MEASURES TO ENSURE A QUALITY INSPECTION HAVE BEEN NECESSARY TO PROVIDE ASSURANCE OF. TUBE INTEGRITY AT MCGUIRE AND PALO VERDE l
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1r CIRCUMFERENTIAL SCC IS BECOMING MORE PREVALENT '(SEE IN.
.92-80)~
- ~HIGH TUBE INTEGRITY SIGNIFICANCE 'i l
- - CAN ONLY BE DETECTED IF LICENSEES USE-RPC PROBES AT -i SUSCEPTIBLE LOCATIONS j i
e -SINCE BEGINNING OF 1992, AT LEAST 4' PLANTS EXPERIENCED. y PERIODS DURING WHICH'1 OR MORE TUBES.HAD INSUFFICIENTE l MARGINS PER RG 1.121 TO SUSTAIN MSLB PRESSURE
- MCGUIRE 1, 2 (1 TUBE EACH) 3
.I
--ANO-2 (AT LEAST 3 TUBES) l
- PALO VERDE 2 (POSSIBLY 4 TUBES)-
l o EXPERIENCE SHOWS1THAT TUBES WITH FREESPANL AXIAL U
- CRACKING OR WITH CIRCUMFERENTIAL CRACKING MAY BECOME ]
VULNERABLE TO RUPTURE WITHOUT SIGNIFICANT: PRECURSOR- j LEAKAGE i q
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a e ;SGTR EVENT PALO VERDE UNIT 2 j q
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- max LEAK RATE: ABOUT 240 GPM "
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- PRECURSOR LEAKAGE: 5 TO 15 GPD !
o SGS ARE CE SYSTEM 80, 2 LOOPS, 11000 TUBES PER SG :
1
- HOT LEG TEMPERATURE:- 621 DEGREES F ;
q e RUPTURE LOCATION: R117C44 IN SG B,.BELOW 09H EGG. CRATE 'l IN FREESPAN l e RUPTURE DESCRIPTION: !
- AXIAL FISHMOUTH, 2-1/2 INCHES LONG
- EDDY CURRENT INDICATES TOTAL CRACK LENGTH OF 8 INCHES BELOW 09H 1'
e NO EC INDICATION AT PREVIOUS INSPECTION' l.
-e AXIAL FREESPAN INDICATION WAS OBSERVED IN 1991 j
- i
- MEASURED 1.1 INCHES LONG, 76% DEEP, ABOVE 09H; TUBE PLUGGED !
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.* 100% BOBBIN-INSPECTION PERFORMED FULL' LENGTH j 1
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- 45 INDICATIONS (38 TUBES) IDENTIFIED WHICH WERE'FOUND' TO AXIAL BY MRPC l e SUPPLEMENTAL INSPECTIONS WITH MRPC !
- 13 AXIAL INDICATIONS FOUND WHICH WERE-NOT FOUND BY l BOBBIN l
- MRPC SCOPE HAS BEEN EXPANDED !
o VIDEO CAMERA INSPECTIONS INDICATE VERY HEAVY DEPOSITS j
.ON TUBES e RESINS FOUND ABOVE TUBE BUNDLE t
e EIGHT TUBES PULLED.FROM SG TO EVALUATE: !
' CRACK MORPHOLOGY l
- CAUSAL MECHANISMS l
- EC EFFECTIVENESS j
- PLANT STARTUP SCHEDULED : FOR END OF JUNE .
1
- NEED FOR CAL UNDER CONSIDERATION ,
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i e1 . ISSUES: ] 4
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- ADEQUACY OF INSPECTIONS ij
- -- METHODS i
SCOPE !
-t FAILURE CAUSE; POTENTIAL MITIGATING ACTIONS ,
CRACK GROWTH RATES LEAK RATE LIMITS / MONITORING PROCEDURES -!
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() BRIEFING 93-19 DRAWING 3 of 5 PVNGS SYSTEM DESCRIPTION MANUAL Page 117 of139 -
TITLE REACTOR CODIANT SYSTEM IDENTD1ER RC RCS \ j REvtstON O LEADDISCDUNE Mechanical Figure RC RCS 15 SIG DETAILED DIAGRAM STE AM DRYER _
SE 4
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MOISTURE -
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- // SUPPORT PLATE ORAIN MOI 5TURE SEPARATOR S ORT ME '
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NOZZLE h l 4 i 3
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- STAY TUBE
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INLET NOZZLE Tr.n , ~ . n -sr.
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BRIEFING 93-19 DRAWING 4 of 5 Q
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FIGURE 11. CE STEAM GENERATOR EGG CRATE b8E SUPPORT PLATE DESIGN j .
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.. . O O CIRCUMFERENTIAL CRACKS AT ANO-2 e SHUT DOWN IN MARCH 1992 DUE TO 0.25 GPM LEAK
- DUE TO CIRCUMFERENTIAL CRACKING AT EXPANSION TRANSITION AT TOP OF TUBESHEET
- THREE TUBES HAD CRACKS EXTENDING 360 DEGREES AROUND TUBE CIRCUMFERENCE WITH AVERAGE DEPTHS BETWEEN 88 AND 94% OF TUBE WALL THICKNESS 1
INADEQUATE MARGINS TO SUSTAIN MSLB
- THESE CIRCUMFERENTIAL CRACKS HAD NOT BEEN DETECTED PREVIOUSLY IN 1991 BECAUSE OF:
USE OF INAPPROPRIATE PROBE (I.E., BOBBIN)
INADEQUATE EC TEST PROCEDURES
- SUBJECT OF IN 92-80 o 100% MRPC INSPECTION PERFORMED IN MARCH 1992 WITH IMPROVED PROCEDURES '
o ANO-2 OPERATED FOR ABOUT 4 MONTHS PRIOR TO THE REFUELING OUTAGE INSPECTION IN SEPT 1992
- 100% MRPC INSPECTION 9
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- --J25'CIRCUMFERENTIAL INDICATIONS
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WORST MEASURED 87% THROUGH WALL'0VER 239 DEGREES'OR- !
AVERAGE ~OF'58%-0VER 360 DEGREES j; a
WORST TUBE WAS PULLED; 360 DEGREE AVERAGE CRACK-DEPTH WAS 65%
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ALLOWABLE 360' DEGREE CRACK DEPTH IS 79%, CONSISTENT:
WITH RG 1.121 l L 1 L e RESULTS INDICATED POTENT!?.LLY HIGH CRACK GROWTH RATES l j
t AND/OR INABILITY TO DETECT CRACKS-UNTIL THEY ARE DEEP I
e ACCORDINGLY, LICENSEE COMMITTED A MID-CYCLE INSPECTION '
L o- OTHER-ACTIONS AT THAT TIME INCLUDED: ;j
\ l
- I(HOT) REDUCTION; FROM 607 TO 599 DEGREES F. !
- ADMINISTRATIVE LEAKAGE LIMIT: 0.1 GPM 1
. - N-16-MONITORS .
1
-i L - 100%-MRPC EXAMINATION 1
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RESULTS FROM MID-CYCLE INSPECTION IN SPRING 1993: gi
- 48 CIRCUMFERENTIAL' INDICATIONS 1 i I
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-- r - RANGING TO A MAXIMUM OF: b 252 DEGREES AROUND THE CIRCUMFERENCE l
-i 95% MAX THROUGH WALL 360 DEGREE AVERAGE WALL LOSS OF 51% i e PLANT RESTARTED IN MAY 1993 l
- LICENSEE WILL MEET WITH STAFF IN JUNE 1993.TO JUSTIFY I OPERATION FOR THE BALANCE OF THE CURRENT CYCLE (ABOUT 9 .
MONTHS) PRIOR TO PERFORMING THE NEXT SG INSPECTION n
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.. . O O LARGE VOLTAGE INDICATIONS AT SUMMER e SUMMER HAS WESTINGHOUSE MODEL D3 STEAM GENERATORS e THE SUMMER SGS ARE SCHEDULED FOR REPLACEMENT AT THE END OF THE CURRENT OPERATING CYCLE e ODSCC AT THE TUBE SUPPORT PLATES (TSPS) IS AMONG SUMMER'S DEGRADATION PROBLEMS
- SUMMER HAD REQUESTED A 1 VOLT IPC FOR THE JUST COMPLETED SPRING 1993 REFUELING OUTAGE, BUT WITHDREW THE REQUEST e SEVERAL INDICATIONS RANGING FROM 7 TO 22 VOLTS WERE FOUND DURING THE SPRING 1993 INSPECTION AT THE FLOW DISTRIBUTION BAFFLE PLATES
- THESE RESULTS WERE NELL BEYOND THE ENVELOPE OF DOMESTIC INDUSTRY EXPERIENCE; LARGEST INDICATIONS HAVE NOT EXCEEDED ABOUT 5 VOLTS
. - PREVIOUS INSPECTIONS FOR THESE LOCATIONS INDICATED NO OR VERY LOW LEVEL INDICATIONS SUGGESTS HIGH VOLTAGE GROWTH RATE AND POSSIBLY HIGH CRACK GROWTH RATE
- EXISTING DATA INDICATES THAT BURST PRESSURES CORRESPONDING TO 22 VOLTS-RANGE BETWEEN 2000 AND 6000 PSI 12
0:
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e _ TUBE SPECIMENS WITH9THE LARGE VOLTAGE INDICATIONS'HAVE i BEEN PULLED "00 CHARACTERIZE THE INDICATIONS AND THEIR I TUBE INTEGRITY SIGNIFICANCE. l l
INDICATIONS'AT STANDARD SUPPORT PLATE LOCATIONS WERE WITHIN THE EXPECTED RANGE.(I.E., 5 VOLTS) l i
e PENDING COMPLETION OF PULLED TUBE EVALUATION, LICENSEE CONCLUDES THAT PLANT CAN BE OPERATED'FOR 3.6 MONTHS- .
L
.WITH ADEQUATE TUBE INTEGRITY
-I e LICENSEE WILL MEET WITH STAFF IN LATE -JUNE / JULY 1993 TO l DISCUSS THE TUBE PULL RESULTS AND ITS PLANS FOR THE. j BALANCE OF THE OPERATING CYCLE (INCLUDING WHETHER IT
]
PLANS A MID-CYCLE INSPECTION) ll
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ENCLOSURE 3 REACTOR SCRAM
-4 Reportins Period: 05/17/93 to 05/23/93-YTD YTD ABOVE SELOW YTD EAll PtANT E UNff pours g CAvsE COMPticAT10ws m 3 g.
05/20/93 DAVIS BESSE 1 100 SA Equipment Falture No -
1 0 1.
05/20/93 SEABR00C 1 100 SM cperating Error No 3 0 3 05/20/93 COMANCHE PEAK 2 72 SA Equipment Falture No 2 0 2 05/21/93 $AINT LUCIE 2 72 SM Equipment Falture No 1 0 1 05/21/93 liATCH 2 65 SM operating Error No 1 0 1 C2ts: Year To Date (YTD) Totals inctu:le Events Within The Calendar fear Indicated By The End Date of The specified Reporting Period
[15-10 Pope:1 05/27/93
r.
D
., , LJ s.
CDMPARISDN OF WEEKLY SCRAM STATISTICS WITH INDUSTRY AVERAGES ,
PER10D ENDING e 05/23/93 NUMBER 1993 1992 1991* 1990* 1989*
OF WEEKLY WEEKLY WEEKLY WEEKLY bEEKLY SCRAM CAUTE SCRANS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE (YTD) ,
POWER GREATER THAN DR EDUAL TO 15%
EDUlPMENT FAILURE
- 3 2.2 2.6 2.9 3.4 3.1 CESIGN/1kSTALLATION ERRDR* 0 0.1 - - - --
DPERATING ERRDR* 2 0.4 0.2 0.6 0.5 1.0 MAINTENANCE ERRDR* O 0.5 0.4 - - -
EXTERNAL
OTHER* O 0.0 0.2 - -
0.1 Subtetet 5 3.3 3.4 3.5 3.9 4.2 POWER LESS THAN 15%
EDUIPMENT FAILURE
- O 0.4 0.4 0.3 0.4 0.3 DESIGN / INSTALLATION ERRDR* 0 0.0 - - - -
OPERATING ERRDR* O 0.1 0.1 0.2 0.1 0.3 MAlWTEhANCE ERROR
EXTERNAL
OTHER* 0 0.0 0.1 - - -
Subtotat 0 0.5 0.7 0.5 0.5 0.6 ,
TOTAL 5 3.8 4.1 4.0 4.4 4.8 h
. 1 993 1992 1991 '1990 1989 ND. OF WEEKLY WEEKLY WEEKLY WEEKLY bEEKLY SCRAM TYPE SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE ,
(YTD)
TOTAL AUTOMATIC SCRAMS 2 2.5 3.1 3.3 3.2 3.9 TOTAL MANUAL SCRAMS 3 1.3 1.0 0.7 1.2 0.9 i TOTALS MAY DIFFER BECAUSE OF RDUNDING OFF
- Detailed breakdown not in database for 1991 and earlier
- EXTERNAL cause included in EQUIPMENT FAILURE k
- MAINTENANCE ERRDR and DESIGN / INSTALLATION ERRDR causes included in DPERAf tkG ERRDR
- CTHER cause included in EDUIPMENT FAILURE 1991 and 1990 3
5 ETS-15 Page: 1 05/27/93
O O FOTES
{
.1. PLANT SPECIFIC DATA BASED ON INITIAL REVIEW OF 50.72 REPORTS FOR THE WEEK OF INTEREST. PERIOD IS MIDNIGHT SUNDAY THROUGH MIDNIGHT SUNDAY. :
0-SCRAMS ARE DEFINED AS REACTOR PROTECTIVE ACTUATIONS WHICH RESULT IN ROD [
MOTION, AND EXCLUDE PLANNED TESTS OR SCRAMS AS PART OF PLANNED SHUTDOWN !
IN ACCORDANCE.WITH A PLANT PROCEDURE. THERE ARE Ill REACTORS HOLDING AN l OPERATING LICENSE. i
- 2. PERSONELL RELATED PROBLEMS INCLUDE HUMAN ERROR, PROCEDURAL DEFICIENCIES, !
AND MANUAL STEAM GENERATOR LEVEL CONTROL PROBLEMS.
~
- 3. COMPLICATIONS: RECOVERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL-ERRORS UNRELATED TO CAUSE OF SCRAM. L I
- 4. "OTHER" INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIRONMENTAL CAUSES :
(LIGHTNING), SYSTEM DESIGN, OR UNKNOWN CAUSE. [
i OEAB SCRAM DATA Manual and Automatic Scrams for 1987 ------------------ 435 l Manual and Automatic Scrams for 1988 ------------------ 291 '!
Manua) and Automatic Scrams for 1989 ------------------ 252 i Manual and Automatic Scrams for 1990 ------------------ 226 Manual and Automatic Scrams for 1991 ------------------ 206
-Manual and Automatic Scrams for 1992 ------------------ 212 -
Manual and Automatic Scrams for 1993 --(YTD 05/23/93)-- 78 ;
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