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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 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 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 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 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 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 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 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 ML20203C5501997-12-0505 December 1997 Summary of 971120 Meeting W/Southern Nuclear Operating Co to Discuss Matters Related to Steam Generator Replacement Projects Proposed for Both Farley Nuclear Units.List of Attendees Enclosed ML20199A0161997-10-30030 October 1997 Summary of 971022 Meeting W/Util in Rockville,Md Re Initiatives That Focus on Planned Licensing Actions & Corrective Measures Re Problems Considered by Mgt to Warrant Special Attention 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 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 ML20137F2351997-03-24024 March 1997 Summary of 970207 Meeting W/Listed Attendees in Rockville,Md to Discuss Nuclear Energy Inst Concerns Re Graded Quality Assurance Activities W/Volunteer Plants 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 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 ML20140H5981996-11-11011 November 1996 Summary of 435th Meeting of ACRS on 961009-12 Re Capability of NRC SCDAP/RELAP5 Code to Predict Temps & Flows in SGs Under severe-accident Conditions ML20148B5761996-10-0404 October 1996 Summary of 434th Meeting of ACRS on 960912-13 Re Capability of SCAP/RELAP5 Code to Predict SG Temps During Severe Accidents 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 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 ML20058N7741993-12-0303 December 1993 Summary of Operating Reactors Events Meeting 93-45 on 931201 ML20059A5941993-10-14014 October 1993 Summary of 930929 Meeting W/B&W Re Generic Implications for of Steam Generator Leak for Similar Sleeves Installed at Other Facilities.List of Attendees & Meeting Handouts Encl ML20057A5221993-07-28028 July 1993 Summary of Operating Reactors Events Meeting 93-27 on 930721 ML20056C5231993-06-18018 June 1993 Summary of 930602 Meeting W/Util Re Plant Proposal for Removing 2C Emergency Diesel Generator from TS as Part of Farley Implementation of Station Blackout Rule.List of Attendees Encl ML20056E2031993-06-15015 June 1993 Summary of Operating Reactors Events Meeting 93-20 on 930602 ML20056D6661993-06-0101 June 1993 Summary of Operating Reactors Events Briefing 93-19 on 930526 ML20128P8491993-02-18018 February 1993 Summary of Operating Reactors Events Briefing 93-05 on 930210 ML20126G0721992-12-22022 December 1992 Summary of 921203 Meeting W/Entergy Operations,Inc Re Results of ANO-2 Steam Generator Tube Exam During Most Recent Scheduled Outage & Licensee Plan for mid-cycle Tube Insp,Scheduled to Begin 930430 ML20128A0111992-11-25025 November 1992 Summary of 920727 Meeting W/Util,Westinghouse & Pnl in Rockville,Md Re Discussions on Steam Line Break Leakage Issues Relating to Licensees SG Tube Alternate Plugging Criteria Proposal.List of Attendees Encl ML20128C1261992-11-25025 November 1992 Summary of 921026 Meeting W/Util in Houston County,Al Re Future Submittals Planned by Util,Status of NRC Review of Previous Submittals,Responses to Generic Communications,Nrc Concerns & General Coordination of Licensing Activities 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 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 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 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 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 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 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 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 ML20203C5501997-12-0505 December 1997 Summary of 971120 Meeting W/Southern Nuclear Operating Co to Discuss Matters Related to Steam Generator Replacement Projects Proposed for Both Farley Nuclear Units.List of Attendees Enclosed ML20199A0161997-10-30030 October 1997 Summary of 971022 Meeting W/Util in Rockville,Md Re Initiatives That Focus on Planned Licensing Actions & Corrective Measures Re Problems Considered by Mgt to Warrant Special Attention 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 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 ML20137F2351997-03-24024 March 1997 Summary of 970207 Meeting W/Listed Attendees in Rockville,Md to Discuss Nuclear Energy Inst Concerns Re Graded Quality Assurance Activities W/Volunteer Plants 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 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 ML20140H5981996-11-11011 November 1996 Summary of 435th Meeting of ACRS on 961009-12 Re Capability of NRC SCDAP/RELAP5 Code to Predict Temps & Flows in SGs Under severe-accident Conditions ML20148B5761996-10-0404 October 1996 Summary of 434th Meeting of ACRS on 960912-13 Re Capability of SCAP/RELAP5 Code to Predict SG Temps During Severe Accidents 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 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 ML20058N7741993-12-0303 December 1993 Summary of Operating Reactors Events Meeting 93-45 on 931201 ML20059A5941993-10-14014 October 1993 Summary of 930929 Meeting W/B&W Re Generic Implications for of Steam Generator Leak for Similar Sleeves Installed at Other Facilities.List of Attendees & Meeting Handouts Encl ML20057A5221993-07-28028 July 1993 Summary of Operating Reactors Events Meeting 93-27 on 930721 ML20056C5231993-06-18018 June 1993 Summary of 930602 Meeting W/Util Re Plant Proposal for Removing 2C Emergency Diesel Generator from TS as Part of Farley Implementation of Station Blackout Rule.List of Attendees Encl ML20056E2031993-06-15015 June 1993 Summary of Operating Reactors Events Meeting 93-20 on 930602 ML20056D6661993-06-0101 June 1993 Summary of Operating Reactors Events Briefing 93-19 on 930526 ML20128P8491993-02-18018 February 1993 Summary of Operating Reactors Events Briefing 93-05 on 930210 ML20126G0721992-12-22022 December 1992 Summary of 921203 Meeting W/Entergy Operations,Inc Re Results of ANO-2 Steam Generator Tube Exam During Most Recent Scheduled Outage & Licensee Plan for mid-cycle Tube Insp,Scheduled to Begin 930430 ML20128C1261992-11-25025 November 1992 Summary of 921026 Meeting W/Util in Houston County,Al Re Future Submittals Planned by Util,Status of NRC Review of Previous Submittals,Responses to Generic Communications,Nrc Concerns & General Coordination of Licensing Activities ML20128A0111992-11-25025 November 1992 Summary of 920727 Meeting W/Util,Westinghouse & Pnl in Rockville,Md Re Discussions on Steam Line Break Leakage Issues Relating to Licensees SG Tube Alternate Plugging Criteria Proposal.List of Attendees Encl ML20217C5121991-07-0303 July 1991 Summary of Operating Reactors Events Meeting 91-12 on 910626 1999-07-16
[Table view] |
Text
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4 September 21, 1989
- e. s MEMORANDUM FOR: Charles E. Rossi, Director Division of Operational Events Assessment FROM: Charles J. Haughney, Chief Events Assessment Branch Division of Operational Events Assessment
SUBJECT:
THE OPERATING REACTORS EVENTS MEETING September 20, 1989 - MEETING 89-34 On September 20, 1989, we conducted an Operating Reactors Events meeting (89-34) to brief senior managers from NRR, ACRS, AE00, RES, Commission staff, and regional offices on selected events that occurred since our last meeting on September 13, 1989. Enclosure 1 lists the attendees.
Enclosure 2 presents the significant elements of the discussed events.
Enclosure 3 contains a summary of reactor scrams for the week ending 09/17/89.
We identified two significant events for input into the NRC performance indicator program.
/r/
Charles J. Haughney, Chief Events Assessment Branch Division of Operational Events Assessment
Enclosures:
As stated cc w/ Encl.:
See Next Page DISTRIBUTION Central File 4 EAB Reading File !
Circulating Copy, EAB Staff MLReardon, EAB BBenedict. EAB LKilgore, SECY o.PDR; ,
l T
0FC :EAB/DOEA :C:EAB/D0yt : : : : :
.....:. g /8s....:............:............:............:............:............:...........
, NAME :MLReardon :CJHaughney : : : : :
DATE :09/2 / /89 :09/ Al/89 : : : : :
OFFICIAL RECORD COPY 8909290147 890921 PDR ORG NRRD
,)[d Lv PNU 8 l
w_-____________-_____.
T. Murley. NRR C. Poslusny 'NRR l F. Miraglia, NRR F..Hebdon, NRR' i
'J. 'Sniezek, NRR E. Reeves, NRR J. Partlow, NRR. E. Adensam, NRR F. Jordan, AEOD T. Chan. NRR-J. Taylor. EDO G. Knighton, NRR E. BeckJord, RES-p W. Russell, RI.
i S. Ebneter, RII-B.' Davis, RIII R.D. Martin, RIV J.B. Martin..RV-
'W. Kane. RI L. Reyes, RII E. Greenman. RIII J. Milhoan, RIV R. Zimmerman, RV-S. Varga,.NRR B. Boger, NRR G. Lainas. NRR
- 0. Holahan. NRR F. Congel, NRR E. Weiss, AE00 T. Martin, EDO J. Lieberman, OE
'J. Guttrann, SECY A. Thadani, NRR J. Richardson. NRR
- 5. Rubin, AEOD J. Forsyth, IhF0
-R. Barrett, NRR fi. Harper.-AE00 R. Newlin, GFA J. Roe, NRR I! . Alderman. ACRS
&i k,, UNITED STATES
- se, g NUCLEAR REGULATORY COMMISSION.
' 7n ' '; j WASHINGTON, D. C. 20555
.. k ,4
September 21, 1989 -
l
)
. MEMORANDUM FOR: Charles E. Rossi, Director .{
Division of Operational Events Assessment 1 FROM: Charles J. Haughney, Chief Events Assessment Branch j Division of Operational Events Assessment l
1
SUBJECT:
THE OPERATING REACTORS EVENTS MEETING September 20, 1989 - MEETING 89-34 On September 20, 1989, we cor. ducted an Operating Reactors Events meeting (89-34) to brief senior managers f rom NRR, ACRS, AE0D, RES, Comission staff, and regional offices on selected events that occurred since our last meeting on September 13, 1969. Enclosure 1 lists the attendees.
Enclosure 2 presents the significant elements of the discussed events.
Enclosure 3 contains a summary of reactor scrams for the week ending 09/17/89.
We identified two significant ever.ts for input into the NPC performance indicator program.
j [, b .t ' bo ' - %
Charles J. Haughney. Chief Events Assessment Branch Division cf Operational Events Assessment
Enclosures:
As stated cc w/ Encl.:
See Next Page
ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS BRIEFING (89-34)
Sep't ember 20. 1989-NAME ORGANIZATION NAME ORGANIZATION D. Trimble. OCM/JC W. Troskoski OE R. Nease NRR/DLPQ N. Trehan NRR/ DST T. Chan NRR/PD-5 R. Benedict NPR/00EA.
S. Long ACRS G. Hammer NRR/DET-S. tiatthews NRR/DRIS A. Vietti-Cook 0CM/KC R. Perfetti OE . F. Cherny RES/EID M. Wegner AEOD/R0AB M. Chiramal AEOD/ROAG P. Baranowsky NRR/00EA M. Davis NRR/PD-5 C. Posiusny NRR/PD-4 G. Knighton NRR/FD-5 F. Hebdon NRR/PD-4 A. Howell RIV L. Plisco NRR/LPEB E. Butcher NRR/ILPB R. Lo NRR-PD2-1 J. Donohew NRR/ADSP M. Reardon NRR/00EA B. Clayton OED0 W. Minners RES/DSIR E. Reeves NER/PD2-1 A. Gilbert NRR/DOEA N. Fields NRR/00EA P. Bobe AEOD/DSP k. Lobel NRR/00EA J. Carter NRR/DOEA R. Karsch NRR/00EA l
ENOLOSURE 2 OPERATING REACTORS EVENTS BRIEFING 89-34 EVENTS ASSESSMENT BRANCH LDCATION: 1EE-11, WHITE FLINT WEDNESDAY, SEPTEMBER 20, 1989, 11:00 A.M.
ARKANSAS UtilTS 3 8 2 DISCREPANCIES BETWEEN ELECTRICAL DIAGRAl'S AND AS-BulLT CONFIGURATION
- FARLEY ADECUACY OF SERVICE ktTER FLOWS PA.LO VERDE UNIT 2 MAIN STEAM SAFETY VALVES -
IMPRCPER BLOWDOWN RING SETTlf4S 1*
t' it..mm_._,.. . .. . . . . .
89-34 ARKANSAS UNITS 1 & 2 DISCREPANCIES BETWEEN ELECTRICAL DIAGRAMS AND AS-BUILT CONFIGURATION SEPTEMBER 13, 1989 PROBLEB
. DISCREPANCIES WERE FOUNL BETWEEN ELECTRICAL LIAGRAMS'Ahr THE AS-BUILT CONFIGURATION OF THE INITIATION CIRCulTRY FOR TWO OUT .
OF THREE SERVICE WATER PUMPS. -
LAUSE LACK OF APECUATE QUALITY CONTROL OF CIRCUIT MODIFICATIONS DURING CONSTRUCTION AND STARTUP, SAFETY SIGNIFICANCE o DIFFICULlY IN PREDICTING lHE EFFECTIVENESS OF CIRCUIT MODIFICATIONS.
c UhEXPECTED PLANT RESPONSE TO A SET OF CONDITIONS.
ILLSLLSSJE 0 AEOD DIAGNOSTIC EVALUATION TEAM FOUND SEVERAL DISCREPANCIES BEThEEN ELECTRICAL CONNECTich DRAWINGS AND THE AS-BU1LT C0hFIGURATION CF INITIATION CIRCUITRY FOR UNIT 1 SERVICE WATER PUMPS "A" ANL "C" (THE "E" PUMP WAS UNAFFECTEL).
0 LICENSEE LETERMINED THAT THE TWO SERVICE WATER PUMPS WERE lECllN1CALLY INOPERABLE DUE TO A LOGIC ERROR. ThE LOGIC ERROR HAD BEEN LISCOVERED PREVIOUSLY AT THE COMPLET10N OF UNIT CONSTRUCTION IN LATE 1974.
o ON A REACTOR TRIP COINCIDENT WITH AN ESF ACTUATION, PUMPS "A" ALD "C" WOULD FAIL TO RESTART ON A SLOW (10 CYCLE TO 1 SEC)
TRANSFER FROM THE AUX XFMR TO THE STARluP XFMR LUE TO THE ACTICh 0F THE ANTI-PUMP CIRCulTLY. (NRC INFORMATION NOTICE EL-75, AS SUPPLEMENTED, EESCRIBES EVENTS LURING kHICH ANTI-PUMP CIRCUITRY PREVENTED THE DESIREL CLOSURE OF CIRCUIT BREAKERS).
CONTACT: N. FIELDS SIGEVENT: _YES_
REFERENCE:
10 CFR SC.71 #16583 thI MORNINC REPORTS OF SEPTEMBER 13 ANI 14,1989
ARKANSAS UNITS 1 t. 1 --
89-34 o WHEN THE ERROR WAS DISCOVERED (1974), LICENSEE ALTERED SCHEMATIC DIAGRAMSLTO REFLECT THE CORRECTION IN CIRCulT LOGIC. HOWEVER, TilE ACTUAL AS-BUILT' CONFIGURATION WAS NOT CHANGED FOR PUMPS "A" AND "C".
o TO DATE, LICENSEE HAS DETERMINED TilAT THE HARDWARE WAS POSSIELY.
NOT CCREECTED TO CCNFORM TO THE ALTERED SCHEMATIC BECAUSE THE LOCATIONS OF THE CIRCulT CONNECTIONS FOR THE RELAY CONTACTS WERE o
DIFFERENT FROM,THOSE INDICATED ON THE APPLICABLE CIRCull CCNNECTIO!! DI AGRAMS MISLEADING Tile CRAFTSPERSON INTO BELIEVING g THAT THE CONNECTIONS DID NOT-EXIST.
o CTHER PROBLElis FOUND INCLULED-SEVERAL UNATTACHED, UNLABELED WIRES l WITH TERMlHAL LUGS: AFFIXED, INDICATIONS THAT CABLES LOCATED ON !
i Tl:E CABINET FLOOR ARE IJECESSARILY TREAD UPON BY CRAFTSPEOPLE IN PERFCRMING CERTAIN TASKS-INSIDE CABINET, RELAY DUST COVERS MISSINC, AND CABLE FIRE WRAP DAMAGE.
- EDLLDEE '
o LICENSEE HAS BEGUN AN lhSFECTIOh 0F A COMPREHENSIVE SAfiPLING OF SAFETY RELATED ELECTf.lCAL COMFCNENTS AND ECulFMENT Al UNITS 3 f t:T 2 . f o THERE IS A SPECIAL INSPECTION TEAM COMPOSED CF REGIONAL AND HEADQUARTERS PERSCNNEL AT THE SITE.
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89-34 EhBLEX ALEGUhfY OF SERVICE WATER fl01S SEPTEMBER 14, 1989 EED31EB Ut'CERTAIM SERV!CE WATER FLOW RATE TO SAFETY RELATED COMPONENTS F0LLOWING A POSTULATED SEISMIC EVENT.
CAUSE COMPRESSED AIR SYS1EM NOT CONSIDERED NECESSARY F0f, SAFE SHUTDOWN.
SAFETY S10f.'IFICANCE THERE MAY LE INADECUATE COOLING WATER FLOW TO THE EMERGEf4CY DIESEL GENERATORS; INTERIM COMPENSATORY MEASbEES INVOLVE OPERATOR ACTION.
DlBLDSSlDb o LICENSEE INITIATED SAFETY SYSTEM ASSESSMENT OF SERVICE WATER SYSTEM IfJ MAY 1929.
O POSTULATED SEISMIC EVENT MAY CAUSE LOSS OF AIR SYSTEM.
SEISMIC CATEGORY 11 DESICN VS PLANT SSE OF 0.1 C AIR OPERATED VALVES IN SERVICE WATER SYSTEM.
FSAR STATES THAT SAFETY RELATEC VALVES FAIL TO " SAFE" POSITION.
c ASSESSMENT EETERMINED TlitT WITH A LOSS CF AIR SYSTEF., NOT ALL NCN-ESSEt:TITL C00LINC WATER LOADS WCULD EE ISCLATED.
- SOME VALVES T0 f:0N-ESSENTIAL LOADS FAIL OPEN, o MAY h0l HAVE ADECUATE FLOW TO SAFETY RELATEC LOADS.
PARTICULAR CONCERN IS DIESEL COOLING.
~
o ANALYSIS OF SERVICE WATER SYSTEM SCHEDULED FOR COMPLETI0f' IN FEBRUARY 199C.
0 /S INTERIM "FIX", LICENSEE HAS MODIFIED PROCEDURES.
0FErl. TORS TO SHUT OTHER VALVES (MOTOR) FROM CONTRCL E00M.
ONLY A FEW VALVES f.EED 10 BE CLOSED.
EDLLDEDE REG 10h TO IChlTOR LICENSEE'S ASSESSMENT CONCLUSIONS. ,
IIT: f.0- I CONTACT: J. CARTER SIGEVEf!T : _NO
REFERENCES:
]C CFF 50.71 #10591 I
89-34 PALO VERDE UNIT _2 ULIN STEAM SAFETY VALVES - IMPROPER ELOWDOWN RING SETTINGS SEPTEMBER 1, 1989 EEDELEB
'PALO VERDE UNIT 3 MAIN STEAM SAFETY VALVES (MSSVs), SUPPLIED BY CONSOLIDATED VALVE CORP / DRESSER, HAD IMPROPER BLOWDOWh RING SE1 TINGS WHICH COULD AFFECT VALVE CHATTER, VALVE BLOWDOWN TIME, AND VALVE RELIEF CAPACITY.
'fAUSE STILL UNDER INVESTIGATION.
I SAFETY SIGNIFICANCE IMPROPER SETTINGS ON BLOWDOWN RINGS (GUIDE RING AND N0ZZLE RING)
COULD RESULT IN MAIN STEAM REllEF WITH EXTENDED BL0hDOWN AND INSUFFICIENT STEAh RELIEF, BOTH OF WHICH ARE OUTSIDE OF THE DESIGN BASIS.
DISCUSSION o Oh AUGUST 31, 1559, PALO VERDE RECEIVED RESULTS OF TESTS DONE AT WYLE LAES ON UNIT 3 MSSVs WHICH lhDICATED IMPRCPER BLOWDOWN
- l. RING SETTlh6S (BOTH, CUIDE AND N0ZZLE RING SETTINGS). THE LICENSEE RECOGNIZED THE PROLLEM ON SEPTEMEER 1. ON SEPTEMBER 6,
- AFTER C0hSULTING WITH DRESSER THE LICENSEE IMMEDIATELY SHUTDOWN UNIT 2 (UNIT 1 WAS.ALREADY SHUTDOWN) TO INVESTIGATE MSSV RINC SETTINGS ON OTHER UNITS.
O fslNG SETTINGS V/RIED IN BOTH THE HIGH DIRECTION AND LOW DIRECTION.
THE NOMINAL SETTING WAS +100 AND -8 FOR THE TWO RINCS, SETTINGS WERE FOUNE AS hlGH AS +371 AND +2, AND AS LOW AS +136 AND -28.
ALL VALVES TESTED WERE FCLI.D TO BE IMPROFERLY SET.
c lhE TESTS CONE AT WYLE INDICATE THAT THESE WERE THE AS-FOUND SETTINGS OF THE UNll 3 MSSVs. THIS WAS THE FIRST GUTAGE FOR UNIT 3. THEFEFORE, THE VALVES MAY HAVE EEEN INITIALLY SUPPLIED !
WITH IMPROPER RING SETTINGS.
00hlACT: A. f. CILBERT SILEVENT: __TEL J
REFERENCE:
30 CFR 50.71 #16513
o SS '
.PALO VERDE UNIT-2
. i o UNIT 2 MSSVs ARE NOW EEING CHECKEDs STAR 1LP UNIT 2 IS SCHEDULED FOR LATER THIS WEEK. THE OTHER TWO UNITS' MSSVs WILL BE TESTED PR10R TO THEIR RESPECTIVE-STARTUPS.
c GENERIC COMMUNICATION!!S:
INFORMATION NOTICE 86-05: MAIN STEAM SAFETY VALVE TEST.
FAILURE AND RING SETTING ADJUSTMENTS WAS= ISSUED OF JANUARY 31, 1986 IN- RESPONSE TO IMPROPER RING SETTINGS AFTER
- TESTING AT WYLE LABS.
PROPOSED 50.54(F) LETTER ON INADECUATE FLOW CAPACITY OF MAIN .
STEAM CODE SAFETY VALVES WAS TRANSMITTED FOR CRGR REVIEW ON AUGUST- 31, 1987, EUT WAS NEVEF. ISSUED.
FOLLOWUP THE' LICENSEE IS INVESTIGATING THE ROOT CAUSE FOR THE IMPROPER RING SE111NCS . REGION V IS FOLLOWING THIS EVENT AND ASSOCIATED ACTIVITY CLOSELY. AEOD ANC EMEB WILL CONTINUE TO FOLLOW FOR POTENTIAL GENERIC IMPLICATIONS AND/0R A NEEL FOR A PART 21 SUBMITTAL, A
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J PA O VERDE UNIT 2 TYPICAL PMIN STEAM SAFETY VALVE I
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.Fa;e No. !
ggf39;g9 ENCLOSURE 3 j
. FERFDRMANLE INDICATDRS SIGNIFICANT EVENTS {
PLANT NAME EVENT EVENT DESCRIFT]DN GTR SIGNIFICANCE l DATE ARrAN5AS 1 1 2 09/13/B9 A DISCREPANCY hAS FDUND BETWEEN PLANT ELECTRICAL LEAWINSS 1 UNEIFECTED PLANT RESFDNSE TD A SET AND AS-BUILD ELECTRICAL CCMFDNENTS/EDUlF' MENT. DF CDNDITIDNS GCSUIF.E 2 09/05/P9 DVERPREESURIIATION DF iHE CONTAINMENT SPEAY SYSTEM 1 FDTENTIAL FDR DR ACTUAL DESEADATIDN RESULTED IN LEAK DF REACTOR CDDLANT AND REFUELING WATER. DF FRIP.ARY CDDLANT FRESSURE EDUCARY l
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FEACTDRSCRAM
SUMMARY
1
. WEEK ENDING 09/17/E9
- 1. PLANT SPECIFIC DATA DATE $1TE Uhli POWER 516hAL CAUSE COMPLI- Y1D YTD YTD CAllDNS ABDVE PELOW TDTAL 151 151 09/13/69 ST LU:IE 1 100 A ~ PEP.SDNNEL ND 1 0 1 09/15/69 TUF: LEY PDIKT 4 100 M EDUIPMENT ND 1 0 1 09/16/09 $Uf:RY 2 0M EQUIPMENT ND 0 1 1 l
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1 I- II. COMPARISON OF WEEKLY STATISTICS WITH INDUSTRY AVERAGES i
l SCRAMS FOR WEEK ENDING l .
09/17/89 SCRAM CAUSE POWER NUMBER 1989 1988 1987 1986 1985 OF WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY SCRAMS (5) AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE YTD (3)(4) (B)(9) l
EQUIP. RELATED >1b% 1 3.1 3.1 3.9 4.3 5.4 PERS. RELATED(6) >15% 1 1.1 1.0 1.3 1.8 2.0 OTHER(7) >15% 0 O<1 0.5 1.2 0.4 0.6
~*t Subtotal **
2 4.3 4.6 6.4 6.5 0.0
EQUIP. RELATED <15% 1 0.4 0.5 1.2 1.4 1.3 PERS. RELATED <15% 0 0.3 0.3 0.6 0.8 0.9 OTHER <15% O O.O O.1 0.3 0.2 0.2
1 0.7 0.9 2.1 2.4 2.4
- Total 444 3 5.0 5.5 8.5 8.9 10.4 MANUAL VS AUTO SCRAMS 7YPE NUMPER 1989 1988 1987 1986 1985 OF WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE YTD MANUAL SCRAMS 2 0.9 1.0 1.4 1.0 1.0 AUTOMATIC SCRAMS 1 4.1 4.5 7.0 7.9 9.4
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(~' NOTES
. 1. PLANT SPECITIC DATA BASED ON INITIAL PEVIEW OF EC.72 REPORTS FOR THE WEEr,OF INTEREST. PERIOD IS MIDNIGHT SUNDAY THROUGH MIDNIGHT SUNDAY. SCPAMS ARE DEFINED AS REACTOR FRO *. IVE ACTUATIONS WHICH RESULT IN RCD MOTICN, AND EXCLUDE PL dNE0 TESTS OR SCRAMS AS PART OF PLANNED SHUTDOWN IN ACCORDANCE Wild A PLANT-PROCEDURE. THERE APE 111 REACTORS HOLDING AN OPERATING LICENSE.
I
- 2. COMPLICATIONS: RECOVERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL ERRORS UNRELATED TO CAUSE OF SCRAM.
- 3. FERSONNEL RELATED PROELEMS INCLUCE HUMAN EPRCR, PROCEDURAL DEffr7?CIES, AND MANUAL STEAM GENEPATOR LEVEL CONTROL P RGt!,1"'.3.
4 "0THER" INCLUDES AUTOMATIC SCEAMS ATTRIBUTED TO ENVIP.0hMENTAL CAUSES (LIGHTNING), SYSTEl' DESIGN, OR UllKNOWN CAUSE.
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