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Category:MEETING MINUTES & NOTES--CORRESPONDENCE
MONTHYEARML20210L5231999-08-0505 August 1999 Summary of 990708-09 Meeting with Detroit Edison Co in Rockville,Md Re Issues Related to Fermi 2 Submittal for Conversion of Current TSs to Improved Standard Tss.List of Participants & RAI Tracking Numbers Encl ML20209E7641999-07-0707 July 1999 Summary of 990617 Meeting with Licensee Re Util Plans to Add Racks to & Replace Older Racks in Sfp.List of Attendees Encl ML20206A3111999-04-16016 April 1999 Summary of 990412-13 Meeting with Detroit Edison Co Re Issues Related to Fermi 2 Submittal for Conversion to Improved Std Ts.List of Meeting Participants,Revised Conversion Schedule & List of Beyond Scope Issues Encl ML20205Q7481999-04-14014 April 1999 Summary of 990319 Meeting W/Util & Excel,Inc in Rockville,Md Re Improved STS Conversion.Attendee List,Request for Addl Info & Viewgraphs Encl ML20202H9211999-01-26026 January 1999 Summary of 990111-12 Meetings with Util at NRC Headquarters to Discuss Issues Related to Fermi 2 Submittal for Conversion to Improved Sts.List of Questions for Sections 3.5 & 3.6 & Meeting Participants Encl ML20198J6911998-12-23023 December 1998 Summary of 981201-04 Meetings with Util in Rockville,Md Re Improved STS Conversion ML20198J1651998-12-15015 December 1998 Summary of 981118 Meeting with Util in Rockville,Md Re Ampacity Validation Analyses.List of Attendees & Handouts Provided by Util Encl ML20196F6001998-11-20020 November 1998 Summary of 981109-10 Meeting with Util Re Issues Related to Fermi Unit 2 Submittal for Conversion to Improved Std Tss. Primary Focus Was to Discuss Proposed Questions for RAI for Sections 3.4,3.7 & 3.9 of Conversion.Meeting Attendees Encl ML20155A8741998-10-26026 October 1998 Summary of 980928,29,30,1007 & 08 Meetings with Detroit Edison Co to Discuss Plant Improved Std TSs Conversion. List of Participants Encl ML20153G4541998-09-21021 September 1998 Summary of 980908-09 Meeting W/Detroit Edison Co in Rockville,Md Re Fermi 2 Submittal for Conversion to Improved Standard Tss.List of Attendees Encl ML20238F2261998-08-27027 August 1998 Summary of 980805-06 Meeting with Detroit Edison Co in Rockville,Md Re Issues Related to Fermi 2 Submittal for Conversion to Improved Standard TS ML20237C5751998-08-20020 August 1998 Summary of 980728-29 Meeting W/De in Rockville,Md Re Issues Related to Fermi 2 Submittal for Conversion to Improved TS W/Primary Focus on Review of Section 3.6.List of Meeting Participants Encl ML20236S0791998-07-14014 July 1998 Summary of 980707 & 08 Meeting W/Util at NRC Headquarters Re Issues Related to Plant,Unit 2 Submittal for Conversion to Improved Std Tss.Primary Focus of Meeting Was Review of Section 3.4 of Std Ts.List of Meeting Participants Encl ML20197B6751998-03-0505 March 1998 Summary of 980220 Telcon Re Quality of Licensing Submittals for Plant Unit 2.Submittals for Discussion & Participants in Call Listed in Encl ML20203D9551998-02-12012 February 1998 Summary of 980130 Meeting W/Util Re General Status of Plant & Status of Selected Licensing Issues.List of Attendees Encl ML20203B4761998-02-11011 February 1998 Summary of 980128 Meeting W/Util in Rockville,Md Re Licensee Application for License Amend .List of Attendees & Licensee Response to Questions Encl ML20199G6801997-11-19019 November 1997 Summary of 971104 Meeting W/Util Re Issues Related to Improved STS for Fermi 2.List of Meeting Attendees Encl IR 05000424/19970991997-10-0202 October 1997 Summary of 970924 Meeting to Discuss NRC SALP Repts 50-424/97-99 & 50-425/97-99,dtd 970915 for Facility.List of Attendees,Summary of Matls Used & Presentation Encl ML20216G5171997-09-0404 September 1997 Summary of 970805 Meeting W/Util Re Thermo-Lag Corrective Actions at Peach Bottom & Limerick.List of Attendees & Meeting Handouts Encl ML20217L8701997-08-14014 August 1997 Summary of 970731 Meeting W/Southern Nuclear Operating Co, Inc in Birmingham,Al Re Plant Status,Major Problems & Other Topics at Farley,Hatch & Vogtle Nuclear Plants.List of Attendees & Presentation Handouts Encl ML20140H8481997-05-0505 May 1997 Summary of 970422 Meeting W/Licensee at NRC Headquarters Re Issues Related to EECW Sys at Plant ML20140F3561997-04-30030 April 1997 Summary of 970414 Meeting W/Util in Rockville,Md to Discuss Issues Associated W/Use of Thermo-Lag Fire Barrier Matl at Plants.Meeting Attendees & Handouts Encl ML20138C8081997-04-25025 April 1997 Summary of 970410 Meeting W/Peach Bottom Atomic Power Station in Rockville,Md Re Planned Construction of Sf Dry Cask Storage Facility for Units 2 & 3.List of Attendees & Copy of PECO Meeting Handout Encl ML20133G1401997-01-10010 January 1997 Summary of 961025 Meeting W/Peco in Delta,Pa Re Status of Licensing Actions Associated W/Plants.List of Attendees & Copy of Presentation Matl Encl ML20133A4881996-12-23023 December 1996 Summary of 961218 Meeting W/Util in NRC Headquarters Re State of Licensee Corrective Action Program,Performance of Operations & Sys Engineering Personnel & Activities Re Control of Plants Design Basis.List of Attendees Encl ML20135B4411996-11-21021 November 1996 Summary of 960927 Meeting W/Util Re Status of Plans to Decommission Fermi 1 Facility.Concern Areas & Resulting Discussions,Listed.Decommissioning Project Plan,Encl ML20059J0261994-01-24024 January 1994 Summary of 931214 Meeting W/Representatives of PECO to Discuss Risk of Performing 24 H Emergency DG Testing at Power.List of Attendees Encl ML20059J1471994-01-10010 January 1994 Summary of Operating Reactors Events Briefing 94-01 Conducted on 940105 to Inform Senior Managers of Listed Ofcs of Selected Events That Occurred Since Last Briefing on 931222.Attendees Listed in Encl 1 ML20058G7841993-12-0202 December 1993 Summary of 931103 Meeting W/Util in Rockville,Md Re Evaluation of Core Shroud Indications at Plant.List of Attendees & Meeting Handouts Encl ML20058F0451993-11-24024 November 1993 Summary of 931103 Meeting W/Util in Rockville,Md Re Submittal Plans for Cost Beneficial Licensing Actions & to Get Feedback from NRC Staff.List of Attendees Encl ML20059H9941993-11-0808 November 1993 Summary of 931019 Meeting W/Util Re Discussions on Status of Current MOV Testing Program & NRC GL 89-10.List of Attendees & Meeting Agenda Encl ML20059B0971993-10-20020 October 1993 Summary of Operating Reactors Events Meeting 93-39 on 931013 ML20057G3571993-10-15015 October 1993 Summary of 930913 Meeting W/Util in Rockville,Md Re Concerns W/Thermal Binding & Pressure Locking of Gate Valves.List of Meeting Attendees & Handout Matls Encl ML20058N0011993-09-30030 September 1993 Summary of 930902 Meeting W/Peco Re Installation of Certain Planned analog-to-digital Retrofit Mods During Scheduled Sept 1993 Facility Outage ML20058M9451993-09-29029 September 1993 Summary of 930908-09 Meeting W/Util in Rockville,Md Re Status of Current Licensing Activities for Plants ML20058M5891993-09-27027 September 1993 Summary of Operating Reactors Events Meeting 93-36 on 930922 ML20058M1861993-09-22022 September 1993 Summary of Operating Reactors Events Meeting 93-35 on 930915 ML20057B6051993-09-16016 September 1993 Summary of 930831 Meeting W/Util in Rockville,Md Re Two Potential Mod Currently Being Considered to Enhance Util Electric Power Sys ML20149D6051993-09-15015 September 1993 Summary of 930708 Region III Annual Training Managers Conference in Glen Ellyn,Il.Purpose of Meeting to Provide Forum for Discussion on Rev 7 of Operator Licensing Examiner Stds & to Discuss Operator Licensing Issues ML20057B4771993-09-15015 September 1993 Summary of 930824 Meeting W/Util Re Implementation of dual-site Senior Reactor Limited to Fuel Handling (Lsr) Program.List of Meeting Attendees & Meeting Handouts Encl ML20057E6271993-09-13013 September 1993 Summary of Operating Reactors Events Meeting 93-34 on 930908 ML20057A5691993-09-0202 September 1993 Summary of 930809 Meeting W/Util in Wayne,Pa Re Various Licensing Activities Re Plants.List of Attendees Encl ML20056F8171993-08-0909 August 1993 Summary of Operating Reactors Events Meeting 93-29 on 930804.List of Attendees & Viewgraphs Encl ML20056D7151993-05-21021 May 1993 Summary of 930428 Periodic Mgt Meeting in Rockville,Md to Discuss Recent Independent Verification Program at Facility. Attendees Listed in Encl ML20056D9841993-05-18018 May 1993 Summary of Operating Reactors Events Meeting 93-17 on 930512 ML20128K0041993-02-11011 February 1993 Summary of 930107 Meeting W/Utils in Rockville,Md to Provide Forum for Licensees to Present Staff W/Info Re Design, Operational & Testing Experience & Justification for long- Term Operability of Alternate Min Flow Path ML20128H6211993-02-0808 February 1993 Summary of 921123-24 Meeting in King of Prussia,Pa Re Positions on Operator Licensing Issues & to Solicit Input ML20128C9371993-01-14014 January 1993 Summary of 921110 Meeting W/Util in Rockville,Md Re Two Issues Affecting Activities Performed During Refueling Outages ML20126K5111992-12-30030 December 1992 Summary of Operating Reactors Events Meeting 92-022 on 921223.Reactor Scram Statistics for Wk Ending 921230 Encl & List of Attendees Encl ML20126F1241992-12-10010 December 1992 Summary of 921201 Meeting W/Util in Rockville,Md Re Various Licensing Activities.List of Attendees Encl 1999-08-05
[Table view] Category:MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
MONTHYEARML20210L5231999-08-0505 August 1999 Summary of 990708-09 Meeting with Detroit Edison Co in Rockville,Md Re Issues Related to Fermi 2 Submittal for Conversion of Current TSs to Improved Standard Tss.List of Participants & RAI Tracking Numbers Encl ML20209E7641999-07-0707 July 1999 Summary of 990617 Meeting with Licensee Re Util Plans to Add Racks to & Replace Older Racks in Sfp.List of Attendees Encl ML20206A3111999-04-16016 April 1999 Summary of 990412-13 Meeting with Detroit Edison Co Re Issues Related to Fermi 2 Submittal for Conversion to Improved Std Ts.List of Meeting Participants,Revised Conversion Schedule & List of Beyond Scope Issues Encl ML20205Q7481999-04-14014 April 1999 Summary of 990319 Meeting W/Util & Excel,Inc in Rockville,Md Re Improved STS Conversion.Attendee List,Request for Addl Info & Viewgraphs Encl ML20202H9211999-01-26026 January 1999 Summary of 990111-12 Meetings with Util at NRC Headquarters to Discuss Issues Related to Fermi 2 Submittal for Conversion to Improved Sts.List of Questions for Sections 3.5 & 3.6 & Meeting Participants Encl ML20198J6911998-12-23023 December 1998 Summary of 981201-04 Meetings with Util in Rockville,Md Re Improved STS Conversion ML20198J1651998-12-15015 December 1998 Summary of 981118 Meeting with Util in Rockville,Md Re Ampacity Validation Analyses.List of Attendees & Handouts Provided by Util Encl ML20196F6001998-11-20020 November 1998 Summary of 981109-10 Meeting with Util Re Issues Related to Fermi Unit 2 Submittal for Conversion to Improved Std Tss. Primary Focus Was to Discuss Proposed Questions for RAI for Sections 3.4,3.7 & 3.9 of Conversion.Meeting Attendees Encl ML20155A8741998-10-26026 October 1998 Summary of 980928,29,30,1007 & 08 Meetings with Detroit Edison Co to Discuss Plant Improved Std TSs Conversion. List of Participants Encl ML20153G4541998-09-21021 September 1998 Summary of 980908-09 Meeting W/Detroit Edison Co in Rockville,Md Re Fermi 2 Submittal for Conversion to Improved Standard Tss.List of Attendees Encl ML20238F2261998-08-27027 August 1998 Summary of 980805-06 Meeting with Detroit Edison Co in Rockville,Md Re Issues Related to Fermi 2 Submittal for Conversion to Improved Standard TS ML20237C5751998-08-20020 August 1998 Summary of 980728-29 Meeting W/De in Rockville,Md Re Issues Related to Fermi 2 Submittal for Conversion to Improved TS W/Primary Focus on Review of Section 3.6.List of Meeting Participants Encl ML20236S0791998-07-14014 July 1998 Summary of 980707 & 08 Meeting W/Util at NRC Headquarters Re Issues Related to Plant,Unit 2 Submittal for Conversion to Improved Std Tss.Primary Focus of Meeting Was Review of Section 3.4 of Std Ts.List of Meeting Participants Encl ML20197B6751998-03-0505 March 1998 Summary of 980220 Telcon Re Quality of Licensing Submittals for Plant Unit 2.Submittals for Discussion & Participants in Call Listed in Encl ML20203D9551998-02-12012 February 1998 Summary of 980130 Meeting W/Util Re General Status of Plant & Status of Selected Licensing Issues.List of Attendees Encl ML20203B4761998-02-11011 February 1998 Summary of 980128 Meeting W/Util in Rockville,Md Re Licensee Application for License Amend .List of Attendees & Licensee Response to Questions Encl ML20199G6801997-11-19019 November 1997 Summary of 971104 Meeting W/Util Re Issues Related to Improved STS for Fermi 2.List of Meeting Attendees Encl IR 05000424/19970991997-10-0202 October 1997 Summary of 970924 Meeting to Discuss NRC SALP Repts 50-424/97-99 & 50-425/97-99,dtd 970915 for Facility.List of Attendees,Summary of Matls Used & Presentation Encl ML20216G5171997-09-0404 September 1997 Summary of 970805 Meeting W/Util Re Thermo-Lag Corrective Actions at Peach Bottom & Limerick.List of Attendees & Meeting Handouts Encl ML20217L8701997-08-14014 August 1997 Summary of 970731 Meeting W/Southern Nuclear Operating Co, Inc in Birmingham,Al Re Plant Status,Major Problems & Other Topics at Farley,Hatch & Vogtle Nuclear Plants.List of Attendees & Presentation Handouts Encl ML20140H8481997-05-0505 May 1997 Summary of 970422 Meeting W/Licensee at NRC Headquarters Re Issues Related to EECW Sys at Plant ML20140F3561997-04-30030 April 1997 Summary of 970414 Meeting W/Util in Rockville,Md to Discuss Issues Associated W/Use of Thermo-Lag Fire Barrier Matl at Plants.Meeting Attendees & Handouts Encl ML20138C8081997-04-25025 April 1997 Summary of 970410 Meeting W/Peach Bottom Atomic Power Station in Rockville,Md Re Planned Construction of Sf Dry Cask Storage Facility for Units 2 & 3.List of Attendees & Copy of PECO Meeting Handout Encl ML20133G1401997-01-10010 January 1997 Summary of 961025 Meeting W/Peco in Delta,Pa Re Status of Licensing Actions Associated W/Plants.List of Attendees & Copy of Presentation Matl Encl ML20133A4881996-12-23023 December 1996 Summary of 961218 Meeting W/Util in NRC Headquarters Re State of Licensee Corrective Action Program,Performance of Operations & Sys Engineering Personnel & Activities Re Control of Plants Design Basis.List of Attendees Encl ML20135B4411996-11-21021 November 1996 Summary of 960927 Meeting W/Util Re Status of Plans to Decommission Fermi 1 Facility.Concern Areas & Resulting Discussions,Listed.Decommissioning Project Plan,Encl ML20059J0261994-01-24024 January 1994 Summary of 931214 Meeting W/Representatives of PECO to Discuss Risk of Performing 24 H Emergency DG Testing at Power.List of Attendees Encl ML20059J1471994-01-10010 January 1994 Summary of Operating Reactors Events Briefing 94-01 Conducted on 940105 to Inform Senior Managers of Listed Ofcs of Selected Events That Occurred Since Last Briefing on 931222.Attendees Listed in Encl 1 ML20058G7841993-12-0202 December 1993 Summary of 931103 Meeting W/Util in Rockville,Md Re Evaluation of Core Shroud Indications at Plant.List of Attendees & Meeting Handouts Encl ML20058F0451993-11-24024 November 1993 Summary of 931103 Meeting W/Util in Rockville,Md Re Submittal Plans for Cost Beneficial Licensing Actions & to Get Feedback from NRC Staff.List of Attendees Encl ML20059H9941993-11-0808 November 1993 Summary of 931019 Meeting W/Util Re Discussions on Status of Current MOV Testing Program & NRC GL 89-10.List of Attendees & Meeting Agenda Encl ML20059B0971993-10-20020 October 1993 Summary of Operating Reactors Events Meeting 93-39 on 931013 ML20057G3571993-10-15015 October 1993 Summary of 930913 Meeting W/Util in Rockville,Md Re Concerns W/Thermal Binding & Pressure Locking of Gate Valves.List of Meeting Attendees & Handout Matls Encl ML20058N0011993-09-30030 September 1993 Summary of 930902 Meeting W/Peco Re Installation of Certain Planned analog-to-digital Retrofit Mods During Scheduled Sept 1993 Facility Outage ML20058M9451993-09-29029 September 1993 Summary of 930908-09 Meeting W/Util in Rockville,Md Re Status of Current Licensing Activities for Plants ML20058M5891993-09-27027 September 1993 Summary of Operating Reactors Events Meeting 93-36 on 930922 ML20058M1861993-09-22022 September 1993 Summary of Operating Reactors Events Meeting 93-35 on 930915 ML20057B6051993-09-16016 September 1993 Summary of 930831 Meeting W/Util in Rockville,Md Re Two Potential Mod Currently Being Considered to Enhance Util Electric Power Sys ML20149D6051993-09-15015 September 1993 Summary of 930708 Region III Annual Training Managers Conference in Glen Ellyn,Il.Purpose of Meeting to Provide Forum for Discussion on Rev 7 of Operator Licensing Examiner Stds & to Discuss Operator Licensing Issues ML20057B4771993-09-15015 September 1993 Summary of 930824 Meeting W/Util Re Implementation of dual-site Senior Reactor Limited to Fuel Handling (Lsr) Program.List of Meeting Attendees & Meeting Handouts Encl ML20057E6271993-09-13013 September 1993 Summary of Operating Reactors Events Meeting 93-34 on 930908 ML20057A5691993-09-0202 September 1993 Summary of 930809 Meeting W/Util in Wayne,Pa Re Various Licensing Activities Re Plants.List of Attendees Encl ML20056F8171993-08-0909 August 1993 Summary of Operating Reactors Events Meeting 93-29 on 930804.List of Attendees & Viewgraphs Encl ML20056D7151993-05-21021 May 1993 Summary of 930428 Periodic Mgt Meeting in Rockville,Md to Discuss Recent Independent Verification Program at Facility. Attendees Listed in Encl ML20056D9841993-05-18018 May 1993 Summary of Operating Reactors Events Meeting 93-17 on 930512 ML20128K0041993-02-11011 February 1993 Summary of 930107 Meeting W/Utils in Rockville,Md to Provide Forum for Licensees to Present Staff W/Info Re Design, Operational & Testing Experience & Justification for long- Term Operability of Alternate Min Flow Path ML20128H6211993-02-0808 February 1993 Summary of 921123-24 Meeting in King of Prussia,Pa Re Positions on Operator Licensing Issues & to Solicit Input ML20128C9371993-01-14014 January 1993 Summary of 921110 Meeting W/Util in Rockville,Md Re Two Issues Affecting Activities Performed During Refueling Outages ML20126K5111992-12-30030 December 1992 Summary of Operating Reactors Events Meeting 92-022 on 921223.Reactor Scram Statistics for Wk Ending 921230 Encl & List of Attendees Encl ML20126F1241992-12-10010 December 1992 Summary of 921201 Meeting W/Util in Rockville,Md Re Various Licensing Activities.List of Attendees Encl 1999-08-05
[Table view] |
Text
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'f elON 9 9 E MEMORANDUli FOR: Charles E. Rossi, Director Division of Operational Events Assessment Office of Nuclear Reactor Regulation FROM: Wayne Lanning, Chief Events Assessment Branch Division of Operational Events Assessment Office of Nuclear Reactor Regulation SUdJECT: THE OPERATING REACTORS EVENTS HEETING June 7, 1988 - MEETlHG 88-23 On June 7, 1988 an Operating Reactors Events meeting (88-23) was held to brief senior managers from NRR and Regional Offices on events which occurred since our last meeting on May 31, 1988. The list of attendees is included as Enclosure 1.
The events discussed and the significant elements of these events are presented in Enclosure 2. Enclosure 3 presents a summary of reactor scrams. One signi-ficant event was identified for input to NRC's performance indicator program.
One event was suggested for long-term followup.
fi4ita:az., .
u I
' W coLV ! o a m
{ Wayne Lanning, Chief Events Assessment Branch Division of Operational Events Assessment Office of Nuclear Reactor Regulation
Enclosures:
As stated i cc w/Enclo.:
l See Next Page DISTRIBUTION Central File- . j EAB Reading File /
Circulating Copy EAB Staff MLReardon, EAB ,J h ,, g '3.j 00udinot, EAB V ) t' g/O. 3(
LKilgore, SECY, PDR l#
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NAME :MLRe rdon :WLa'n ling : : : : :
.L.....:.....g/88 ......:..........__:.....__..__.:..._____....:............:...........
- 06/Os : : :
DATE :06/ I88 : :
i 0FFICIAL RECORD COPY 8806210342 890608 PDR ORG NRRB
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gr CC; T. Murley, 12G-18 J. Sniezek,12G-18 F. kiraglia, 12G-18 J. Forsyth INP0 E. Jordan, AEOD D. Kubicki, 8H-7 E. Beckjord, NL-007 D. McPherson, 12G-18 W. Russell, RI W. Lyon, 8E-23 B. Davis, RIII D. Moran, 13D-18 9 d. Nelson Grace, O!! H. Berkow, 14H-22 R. D. itartin, RIV J. B. Martin, RV W. Kane, RI L. Reyes, RII E. Greenman, RIII J. Callan, Rly D. Kirsch, RV S. Varga, 14E-4 D. Crutchfield, 13A-2 B. Boger, 14A-2 G. Lainas, 14H-3 G. Holahan, 13E-4 L. Shao, 8E-2 J. Partlow, 70-24 B. Grir,es, 9A-2 F. Cengei, 10E-4 E. Weiss, AEOD S. Black, 12E-4 T. Martin, 12G-18 J. Stone, 9D-4 R. Hernan, 13H-3 H. Bailey, AE0D J. Guttnenn, SECY A. Thadani, 7E-4 S. Rubin, AE00 i
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I
</ # 'o UNITED STATES 0
[ 't NUCLEAR REGULATORY COMMISSION j > ? j WASHINGTON, D. C 20555 l
\...s/j JUN 4 4 S iEMORANDUM FOR: Charles E. Rossi, Director Division of Operational Events Assessment Office of heclear Reactor Regulation FROM: Wayne Lanning, Chief Events Assessment Branch Division of Operational Events Assessment Office of Nuclear Reactor Regulation
SUBJECT:
THE OPERATING REACTORS EVENTS HEETING June 7, 1988 - NEETING 88-23 On June 7, 1988 an Operating Reactors Events meeting (88-23) was held to ,
brief senior managers from NRR and Regional Offices on events which occurred '
since our last meeting on May 31, 1988. The list of attendees is included as Enclosure 1.
The events discussed and the significant elements of these events are presented in Enclosure 2. Enclosure 3 presents a summary of reactor scrams. One signi-ficant event was identified for input to NRC's performance indicator program.
Cr.e event was suggested for long-term followup.
v ,
lN E WaynpLanning, Chief Events Assessment Branch Division of Operational Events Assessment Office of Nuclear Reactor Regulation i
Enclosures:
As stated 1 cc w/Enclo.: l See Next Page )
i 1
l l
I
4 ENCLOSURE 1 QSTOFATTENDEES i OPERATING REACTORS EVENTS,BRIEFlhG (68-23)
June 7, 1988 :
NAME ORGANIZATION NAME ' 0RGANIZATION W.Lanning NRR/00EA P. Baranowsky - NRR/00EA J. Carter NRR/00EA R. Scholl - NRR/00EA-T. Iturley NRR E. Rossi NRR/00EA D. Kubicki NRR/ECEB D. McPherson NRR/00NRR W. Lyon NRR/SRXB D. Moran OSP/TVA ,
H. Berkow NRR/PD22
)
1
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ENCLOSURE 2
- 0PERATING REACTORS EVENTS BRIEFING 88-23 EVENTS ASSE.SSMENT BRANCH LOCATION: 12-B-ll WHITE FLINT-TUESDAY, JUNE 7, 1988.,_11:00 A.M. ,
V0GTLE WATER LEAKAGE INTO CONTROL ROOM PEACH BOTTOM 2/3 CARD 0X SYSTEM IN CONTROL ROOM GENERIC ISSUE LOCA DURING SHUTDOWN I
l
'l I
3
-e-- , --***v ~-*r- ~~ ~ c' -
s wc-m- - = r~w-* w e,~ e-~ ~,-- n - ~~~~ ~ - v- w- + em vrww e r r-n c -v rm , = w- e c m w,4 9 - = r ~+-m
88-23 V0GTLE WATER LEAKAGE INTO CONTROL ROOM JUNE 3, 1988 PROBLEM ADVERSE SYSTEMS INTERACTION BETWEEN FIRE SUPPRESSION SYSTEM AND PLANT SAFETY SYSTEM CAUSE POTENTIAL PLANT DESIGN INADEQUACIES SIGNIFICANCE FIRE IN "B" TRAIN CABLE SPREADING ROOM COULD RESULT IN LOSS OF ALL CONTROL ROOM MONITORING CAPABILITY DISE)M108
- ON JUNE 3, 1988 WITH UNIT AT 100% POWER, SPURIOUS ACTUATION OF FIRE SYSTEM CAUSED DELUGE SYSTEM PRE-ACTUATION VALVE TO OPEN
- DRAIN COULD NOT HANDLE BLEED LINE FLOW
- SMALL AMOUNT OF WATER OVERFLOWED AND FOUND WAY UNDER DOOR TO "B" TRAIN CABLE SPREADING ROOM
- WATER SEEPED THROUGH PENETRATION SEAL INTO CONTROL ROOM BELOW, WETTING THREE PROCESS PANELS AND CAUSING ONE PORV TO OPEN
- LICENSEE EVENT REVIEW INDICATES POTENTIAL ADVERSE SYSTEMS INTERACTION l
- IN THE EVENT OF A FIRE IN THE "B" TRAIN CABLE SPREADING ROOM A) THE "B" TRAIN ACCIDENT MONITORING INSTRUMENTATION COULD BE DISABLED B) THE "A" TRAIN ACCIDENT MONITORING INSTRUMENTATION COULD BE DISABLED BY FIRE SUPPRESSION SYSTEM WATER LEAKING INTO THE ,
CONTROL ROOM
88-23 2
FOLLOWUP
- LICENSEE HAS COMPLETED THE FOLLOWING CORRECTIVE ACTIONS
-SEALED ELECTRICAL PENETRATIONS WATERTIGHT i
-lNSTALLED TEMPORARY DRAIN LINES FROM THE PRE-ACTUATION FIRE SUPPRESSION DELUGE VALVES
-BUILT AN EIGHT INCH BERM WITH SANDBAGS AT ENTRANCE TO "B" TRAIN CABLE SPREADING ROOM
-DISABLED THE "B" TRAIN CABLE SPREADING ROOM FIRE SUPPRESSION SYSTEM AND ESTABLISHED CONTINU0US FIREWATCH
- REGION 11 HAS DISPATCHED A FIRE PROTECTION SPECIALIST TO THE SITE
- INFORMATION NOTICE UNDER CONSIDERATION i l CONTACT: D. OUDINOT
REFERENCE:
50,72 # 12471 4
6
-.m , . _ -
,,-__y. -, ,, , , , , . , _ , . , . - ,
88-23 PEACH BOTTOM 2/3 CARD 0X SYSTEM IN CONTROL ROOM PROBLEM CARBON DIOXIDE UNDER PRCSSURE (285 PSIG) WAS INTRODUCED INTO THE CONTROL ROOM (FIRE PROTECTION SYSTEM). A POSTULATED RUPTURE WOULD CAUSE BOTH CONTROL ROOMS TO BE UNINHABITABLE.
CA!1SE THE CARD 0X SYSTEM WAS ARMED BY LIFTING A N0ZZLE OFF ITS HOOK SIGNif!CANCE CONSECUENCES OF HOSE FAILURE IN CONTROL ROOM AND DISCHARGE OF CO2 NOT EVALUATED. INSUFFICIENT TIME TO TAKE ACTIONS TO ACTUATE ALTERNATE SHUTDOWN PANEL.
DISCUSSION
- BLISTERED HOSES DISCOVERED OCT 1, 1987
- CARD 0X SYSTEM FOR C.R AND TURBINE DECK TAKEN OUT-0F-SERVICE OCT 1, 1987 ;
- NEW H0SES INSTALLED NOV 19, 1987 ,
- DURING VERIFICAT10!i TEST MARCH 24, 1988 A HOSE ON TURBINE DECK i
RUPTURED
- LICENSEE QUOTED AS SAYING CONTROL ROOM COULD BECOME UNIHABITABLE 2 MINUTES AFTER FAILURE OF H0SE l
EOLLQWUP
- ASSESS FIX AT PEACH BOTTOM FOR ACCEPTABILITY l
- PREPARE GENERIC C0hMUNICATION THAT IDENTIFIES ADVERSE SYSTEM l
!NTERACTION CAUSED BY FIRE PROTECTION SYSTEMS /0PERATION l
CONTACT: JERRY CARTER
REFERENCE:
50.72 # 12455
' L 88-23 GENERIC ISSUE LOSS OF RCS INVENTORY DURING LOW COOLANT LEVEL OPERATION JUNE 8, 1988 PROBLEM SUDDEN LOSS OF REACTOR COOLANT SYSTEM INVENTORY WHILE CONDUCTING STEAM GENERATOR TUBE INSPECTIONS AND MODIFICATIONS WITH HOT LEG N0ZZLE DAMS IN PLACE 1
CAUSE PROCEDURAL INADEQUACIES COMBINED WITH OPERATOR ERRORS AND l TNSTRUMENTATION INACCURACIES (RVRLIS)
SIGNIFICANCE THE LOSS OF RESIDUAL HEAT REMOVAL CAPABILITY DURING LOW REACTOR COOLANT LEVEL OPERATION HAS LED IN SEVERAL CASES TO B0ILING IN THE REACTOR VESSEL. IF THIS SHOULD OCCUR, PRESSURIZATION OF THE REACTOR VESSEL CAN LEAD TO SUDDEN UNCOVERING OF THE CORE BY THE EXPULSION C00LANT THROUGH ANY OPENING IN THE COLD LEG SIDE OF THE REACTOR COOLANT SYSTEM.
DISCUSS 10_N
- DURING THE SECOND REFUELING 0F DIABLO CANYON UNIT 1, IN THE SPRING 0F 1988, DEFICIENCIES IN THE PROCEDURES TO BE USED DURING THE STEAM GENERATOR TUBE INSPECTIONS WERE IDENTIFIED THAT C0'lLD i SIGNIFICANTLY INCREASE THE PROBABILITY OF A SUDDEN EJECTION OF REACTOR COOLANT FOLLOWED BY UNCOVERING 0F THE CORE ;
- WITH THE RCS DRAINED DOWN TO MID-LOOP OPERATION, THE LICENSEE l REMOVED THE S/G MANWAY COVERS FOR ACCESS TO HOT & COLD LEG PLENUMS, ;
- N0ZZLE DAMS ARE THEN PLACED IN THE HOT AND COLD LEG SIDES IN I
THE S/G PLENUM N0ZZLES S0 THAT THE Rx VESSEL LEVEL CAN BE RAISED T0 INCREASE NPSH FOR THE RHR PUMPS WITHOUT REFILLING THE S/G's.
- THE PROBLEM-!F TilF H0T LEG DAMS ARE INSTALLED BEFORE THE COLD LEG DAMS, THEN A SMALL INCREASE IN Rx VESSEL , PRESSURE (APPR0X 2.5 PSI), AS WOULD BE SEEN FROM A LOSS OF RHR CAUSING STEAM BUILDUP IN THE VESSEL, WOULD CAUSE Rx COOLANT TO BE EXPELLED RAPIDLY FROM THE OPEN COLD LEG MANWAYS, AND UNC0VER THE TOP 0F THE CORE
88-23 2
- LOSS OF RHR CAPABILITY (WITH DAMS IN PLACE) COULD CAUSE BOILING IN THE CORE WITHIN 8-15 MINUTES
- AN OPENING IN A RCS COLD LEG, SUCH AS ONE CAUSED BY THE OPENING OF A REACTOR COOLANT SYSTEM PUMP OR A LOOP ISOLATION VALVE (IN SOME PLANTS), WOULD VENT THE SPACE OF THE AFFECTED COLD LEG, MAltlTAINING THIS SPACE AT ATMOSPHERIC PRESSURE, ANY PRESSURE INCREASE WOULD BE PROPAGATED THROUGHOUT THE REMAINDER OF THE REACTOR COOLANT SYSTEM AND FORCE THE COOLANT LEVELS IN THE VESSEL DOWN WHILE THE DISPLACED COOLANT THAT WOULD BE FORCED UP AND OUT OF THE AFFECTED COLD LEG OPENIN
- NOTE THAT THIS MECHANISM, INVOLVING COOLANT EXPULSION THROUGH A COLD LEG OPENING, DOES NOT REQUIRE PLUGGING 0F THE STEAM GENERATOR N0ZZLES
- IN 88-36 (T0 BE ISSUED JUNE 8, 1988) STATES 30 MINUTES AS APPR0X TIME TO B0ll-THIS IS DIABLO CANYON SPECIFIC, ASSUMING REAL-WORLD NUMBERS
- POSSIBLE FIXES WOULD BE TO ENSURE THAT A S/G HOT LEG MANWAY AND i ASSOCIATED HOT LEG PIPE ARE KEPT OPEN TO PROVIDE AN ADECUATE VENT PATH WHEN OPENING UP THE COLD LEG SIDE
- IN ADDITION, NOT INSTALLING THE LAST HOT LEG N0ZZLE DAM UNTIL A SUFFICIENT VENT PATH HAS BEEN ESTABLISHED WOULD HELP PREVENT A PRESSU DIFFERENTIAL FROM EJECTING A N0ZZLE DAM.
EOLLOWUE
- NRR AND RV T0 ISSUE IN 88-36, "POSSIBLE SUDDEN LOSS OF RCS INVENTORY DURING LOW COOLANT LEVEL OPERATION"
- RSB HAS LEAD FOR ISSUING A BULLETIN ON LOSS OF RllR DURING LOW l
RCS INVENTORY CONTACT: JOHN THOMPSON (x21175) ,
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I 1 F4;e N:. 1 06/03/03 FERFCRMahCE !OlCATORS 5!SN1FICANT EVINi$
FiANT 41TI EVENT E'iE%TCESCRIFTICN GiR $16h!FICAkCE IATE FEDI : (4/Ci!!! IWi!CnN CCOLINS LOST Wlfii CNLY AVAILAILE RWR PLPP 0 FCIENTIAL FCR CR AtigAL g[p;;At tg DEAthEAOED. OF SAFETY RELATED Eh!8 PENT l
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j ENCLOSURE 3 REACTOR SCRAM SUMMAM NEEK ENDIN6 05/29/00
- 1. PLANT SPECIFIC DATA i SITE UNii F0sER SI6 MAL CAUSE COMPLl- YTD yid fiD DATE i CAi!0NS A60VE BELON TOTAL 151 151 0 2 2 05/30/88 BRAIDWOOD 2 0M EQUIPMENT NO 1 38 A UNKNOWN NO 2 0 2 06/01/89 SUMMER NATURAL PHENOM NO 2 0 2 06/01/09 SUSQUEHANNA 1 100 A i YES 2 1 3 06/01/896!N%A 1 98 A EQUIPMENT 06/02/8BIqRC4 2 94 A 0%tN0tN N3 3 0 3 l 21 A E2VIFRENT NO 2 0 2 06/02/93 N!b!MILEPOINT 2 3 1 4 06/04/69 CATAnlA 2 38 M OFERATOR ERROR NO 4 ;
8A 0FERATOR ERECR NO 1 3 06/05/2iFERRf 1 l
SUMMARY
OF CCMPLICAi!0NS
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S!TE UNIT CCRPLICAi!CNS l
l 61N%A 12 M0Y FAILED 10 0FE5 ATE AS EIPECTED.A doric ACID TANK LEVEL SENSOR FAILED I HI6H,THERE NAS A RUID FR!MARf SYSTEM COOLDOWN AND A LEAKlh6 REACTOR VESSEL HEAD l VENT I ;
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- 1. PLANT SPECIFIC DATA BASED ON INITIAL REVIEW OF 50.72 REPORTS FOR THE WEEK OF INTEREST. PERIOD IS MIDNIGHT SUNDAY THROUGH l
MIDNIGHT SUNDAY. SCRAMS ARE DEFINED AS REACTOR PROTECTIVE ACTUATIONS WHICH RESULT IN ROD MOTION, AND EXCLUDE PLANNED i
TESTS OR SCRAMS AS PART OF PLANNED SHUTDOWN IN ACCORDANCE WITH A PLANT PROCEDURE. THERE ARE 109 REACTORS HOLDING AN OPERATING LICENSE.
- 2. COMPLICATIONS: RECOVERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL ERRORS UNRELATED TO CAU5F. OF SCRAM, ;
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- 3. PERSONNEL RELATED PROBLEMS INCLUDE HUMAN ERROR, PROCEDURAL '
DEFICIENCIES, AND RAhUAL STEAM GENERATOR LEVEL CONTROL PROBLEMS.
i 4 "0THER" INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIRONMENTAL CAUSES (LIGHTNING), SYSTEM DESIGN, OR UNKNOWN CAUSE. j l
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