|
---|
Category:MEETING MINUTES & NOTES--CORRESPONDENCE
MONTHYEARML20205Q7561999-04-19019 April 1999 Summary of 990318 Meeting W/Util & ABB/C-E in Rockville,Md Re GL 97-04, Assurance of Sufficient Net Positive Suction Head for Emergency Core Cooling & Containment Heat Removal Pumps. List of Attendees & Presentation Matl Encl ML20236X8941998-08-0707 August 1998 Summary of 980710 Meeting W/Omaha Public Power District at Plant to Discuss Util Approach to Conduct of Planned Switchyard Upgrade Project.Meeting Attendees & Documents Used in Util Presentation Encl ML20198B2401997-12-22022 December 1997 Summary of 971113 Meeting W/Omaha Public Power District in Rockville,Md Re Proposed TS Submittals,Status of USAR Verification Effort & Results of Recent Fire Protection Program self-assessments.List of Attendees & Handouts Encl ML20058K1301993-11-29029 November 1993 Summary of Operating Reactors Events Meeting 93-44 on 931124 ML20059C7781993-06-0606 June 1993 Summary of 395th ACRS Meeting on 930311-12 in Bethesda,Md Re Current License Renewal Issues,Computer Issues,Reactor Operating Experience,W/Regard to Fort Calhoun Station loss- of-coolant Event of 920703-04 & ISO Quality Stds ML20128N0871993-02-14014 February 1993 Summary of 930203 Meeting W/Util in Rockville,Md Re Mgt Issues for Facility.Meeting Consisted of OPPD Mgt Discussing Issues Re Pts,Design Basis Reconstruction & Spent Fuel Pool Reracking at Facility ML20126F4111992-12-23023 December 1992 Summary of 921215 Meeting W/Omaha Public Power District in Rockville,Md Re Spent Fuel Pool Rerack for Fort Calhoun Station ML20062D4871990-11-0707 November 1990 Summary of 901015 Meeting W/Util Re Revising of Fuel Handling Accident in Updated Sar,Per Air Bypassing Spent Fuel Pool Charcoal Filter.Conclusion That No License Action Required Not Valid.Attendees List,Agenda & Viewgraphs Encl ML20062C8111990-10-16016 October 1990 Summary of Operating Reactors Events Meeting 90-25 on 901010.List of Attendees,Reactor Scram Statistics & Tabulation of Events Encl ML20059N2091990-09-21021 September 1990 Summary of 900919 Operating Reactors Events Meeting 90-023 to Discuss Significant Elements ML20247K0901989-05-23023 May 1989 Summary of 890517 Meeting W/Inpo Re Similarities & Differences Between Performance Indicator Programs.Detailed Discussion Encl ML20247K1011989-05-16016 May 1989 Summary of 890517 Meeting W/Inpo in Bethesda,Md Re Similarities & Differences Between INPO & NRC Performance Indicators ML20206A5861988-10-25025 October 1988 Summary of 880922 Meeting W/Util in Arlington,Tx Re Station Security Improvement Plan.Attendance List Encl ML20153E1011988-08-29029 August 1988 Summary of 880825 Meeting W/Util Re Independent Mgt Analysis of Plant Operation.All Phases of Program Discussed Including Identification of Problems,Improvement Programs,Response to Appraisal & Actions to Address Problem Root Causes ML20151V2361988-08-12012 August 1988 Summary of 880725 Meeting W/Util in Arlington,Tx Re 15 Deficiencies Identified During June 1988 Emergency Exercise. List of Attendees & Supporting Info Encl ML20151W5141988-04-21021 April 1988 Summary of Operating Reactors Events Meeting 88-016 on 880419 in Rockville,Md.List of Attendees & Viewgraphs Encl ML20151B7621988-03-30030 March 1988 Enforcement Conference Rept 50-285/88-05 on 880321.Major Areas Discussed:Circumstances Surrounding Six Apparent Violations & Seven Significant Findings & Radiological Improvement Project ML20236S1441987-11-16016 November 1987 Summary of 871014 & 15 Inservice Testing Program Working Meetings W/Util & Eg&G at Site to Discuss Questions & Comments Resulting from Review of Pump & Valve Inservice Testing.List of Attendees Encl ML20236R0071987-11-13013 November 1987 Summary of 871113 Meeting W/Util in Bethesda,Md to Discuss Recent Instances of Water Intrusion Into Instrument Air Sys at Facility.List of Attendees & Slides Provided at Meeting by Licensee Also Encl ML20236N1911987-11-0909 November 1987 Summary of 871105 Meeting W/Util in Bethesda,Md to Discuss Recent Instances of Water Intrusion Into Instrument Air Sys at Facility.List of Attendees & Presentation Handouts Encl ML20236P2841987-11-0505 November 1987 Summary of Operating Reactors Events Meeting 87-38 on 871103.List of Attendees,Viewgraphs & Summary of Reactor Scrams Encl ML20214J4991987-05-15015 May 1987 Summary of Operating Reactors Events Meeting 87-09 on 870330 Re Events Which Occurred Since 870316 Meeting.List of Attendees,Events Discussed & Significant Elements of Events & Summary of Events Presented Encl ML20207G1801986-12-23023 December 1986 Summary of 861217 Meeting W/Util Re Util Request for Relief from Commitment to Inspect Core Support Barrel/Thermal Shield During Cycle 11 Refueling Outage.List of Attendees Encl ML20211P1361986-07-16016 July 1986 Summary of 860707 Operating Reactor Events Meeting 86-23 W/ Div Directors & Representatives Re Events Since Last Meeting on 860630.Notification of Inability to Meet Assigned Target Completion Dates for Actions Requested.Viewgraphs Encl ML20137F6561985-11-21021 November 1985 Summary of 851108 Meeting W/Util in Bethesda,Md Re Reliability of Auxiliary Feedwater Sys.Agenda,Attendance List & Viewgraphs Encl ML20058A7781982-07-13013 July 1982 Summary of 820709 Meeting W/Util in Bethesda,Md Re Identifying Addl Info for Development of Regulatory Position Concerning Pressurized Thermal Shock.List of Attendees Encl ML20054H8631982-06-16016 June 1982 Summary of 820608-10 Meetings W/Util in Washington County,Ne Re Procedures & Operator Training Dealing W/Pressurized Thermal Shock.Viewgraphs Encl ML20126L2331981-05-0101 May 1981 Summary of 810429 Meeting W/Pwr Owners Group Re Thermal Shock to Reactor Pressure Vessels.All Parties Agree That Thermal Shock W/Subsequent Repressurization Is Safety Concern Needing Prompt Evaluation ML20148G8601976-11-15015 November 1976 Summary of 761103 Meeting W/Utils,Nus Co,C-E & Lowenstein, Newman,Reis & Axelrad Re Submission of Proposed Measures to Prevent Reactor Vessel Overpressurization in Operating C-E Facilities.Attendance List Encl 1999-04-19
[Table view] Category:MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
MONTHYEARML20205Q7561999-04-19019 April 1999 Summary of 990318 Meeting W/Util & ABB/C-E in Rockville,Md Re GL 97-04, Assurance of Sufficient Net Positive Suction Head for Emergency Core Cooling & Containment Heat Removal Pumps. List of Attendees & Presentation Matl Encl ML20236X8941998-08-0707 August 1998 Summary of 980710 Meeting W/Omaha Public Power District at Plant to Discuss Util Approach to Conduct of Planned Switchyard Upgrade Project.Meeting Attendees & Documents Used in Util Presentation Encl ML20198B2401997-12-22022 December 1997 Summary of 971113 Meeting W/Omaha Public Power District in Rockville,Md Re Proposed TS Submittals,Status of USAR Verification Effort & Results of Recent Fire Protection Program self-assessments.List of Attendees & Handouts Encl ML20058K1301993-11-29029 November 1993 Summary of Operating Reactors Events Meeting 93-44 on 931124 ML20059C7781993-06-0606 June 1993 Summary of 395th ACRS Meeting on 930311-12 in Bethesda,Md Re Current License Renewal Issues,Computer Issues,Reactor Operating Experience,W/Regard to Fort Calhoun Station loss- of-coolant Event of 920703-04 & ISO Quality Stds ML20128N0871993-02-14014 February 1993 Summary of 930203 Meeting W/Util in Rockville,Md Re Mgt Issues for Facility.Meeting Consisted of OPPD Mgt Discussing Issues Re Pts,Design Basis Reconstruction & Spent Fuel Pool Reracking at Facility ML20126F4111992-12-23023 December 1992 Summary of 921215 Meeting W/Omaha Public Power District in Rockville,Md Re Spent Fuel Pool Rerack for Fort Calhoun Station ML20062D4871990-11-0707 November 1990 Summary of 901015 Meeting W/Util Re Revising of Fuel Handling Accident in Updated Sar,Per Air Bypassing Spent Fuel Pool Charcoal Filter.Conclusion That No License Action Required Not Valid.Attendees List,Agenda & Viewgraphs Encl ML20062C8111990-10-16016 October 1990 Summary of Operating Reactors Events Meeting 90-25 on 901010.List of Attendees,Reactor Scram Statistics & Tabulation of Events Encl ML20059N2091990-09-21021 September 1990 Summary of 900919 Operating Reactors Events Meeting 90-023 to Discuss Significant Elements ML20247K0901989-05-23023 May 1989 Summary of 890517 Meeting W/Inpo Re Similarities & Differences Between Performance Indicator Programs.Detailed Discussion Encl ML20247K1011989-05-16016 May 1989 Summary of 890517 Meeting W/Inpo in Bethesda,Md Re Similarities & Differences Between INPO & NRC Performance Indicators ML20206A5861988-10-25025 October 1988 Summary of 880922 Meeting W/Util in Arlington,Tx Re Station Security Improvement Plan.Attendance List Encl ML20153E1011988-08-29029 August 1988 Summary of 880825 Meeting W/Util Re Independent Mgt Analysis of Plant Operation.All Phases of Program Discussed Including Identification of Problems,Improvement Programs,Response to Appraisal & Actions to Address Problem Root Causes ML20151V2361988-08-12012 August 1988 Summary of 880725 Meeting W/Util in Arlington,Tx Re 15 Deficiencies Identified During June 1988 Emergency Exercise. List of Attendees & Supporting Info Encl ML20151W5141988-04-21021 April 1988 Summary of Operating Reactors Events Meeting 88-016 on 880419 in Rockville,Md.List of Attendees & Viewgraphs Encl ML20151B7621988-03-30030 March 1988 Enforcement Conference Rept 50-285/88-05 on 880321.Major Areas Discussed:Circumstances Surrounding Six Apparent Violations & Seven Significant Findings & Radiological Improvement Project ML20236S1441987-11-16016 November 1987 Summary of 871014 & 15 Inservice Testing Program Working Meetings W/Util & Eg&G at Site to Discuss Questions & Comments Resulting from Review of Pump & Valve Inservice Testing.List of Attendees Encl ML20236R0071987-11-13013 November 1987 Summary of 871113 Meeting W/Util in Bethesda,Md to Discuss Recent Instances of Water Intrusion Into Instrument Air Sys at Facility.List of Attendees & Slides Provided at Meeting by Licensee Also Encl ML20236N1911987-11-0909 November 1987 Summary of 871105 Meeting W/Util in Bethesda,Md to Discuss Recent Instances of Water Intrusion Into Instrument Air Sys at Facility.List of Attendees & Presentation Handouts Encl ML20236P2841987-11-0505 November 1987 Summary of Operating Reactors Events Meeting 87-38 on 871103.List of Attendees,Viewgraphs & Summary of Reactor Scrams Encl ML20214J4991987-05-15015 May 1987 Summary of Operating Reactors Events Meeting 87-09 on 870330 Re Events Which Occurred Since 870316 Meeting.List of Attendees,Events Discussed & Significant Elements of Events & Summary of Events Presented Encl ML20207G1801986-12-23023 December 1986 Summary of 861217 Meeting W/Util Re Util Request for Relief from Commitment to Inspect Core Support Barrel/Thermal Shield During Cycle 11 Refueling Outage.List of Attendees Encl ML20211P1361986-07-16016 July 1986 Summary of 860707 Operating Reactor Events Meeting 86-23 W/ Div Directors & Representatives Re Events Since Last Meeting on 860630.Notification of Inability to Meet Assigned Target Completion Dates for Actions Requested.Viewgraphs Encl ML20137F6561985-11-21021 November 1985 Summary of 851108 Meeting W/Util in Bethesda,Md Re Reliability of Auxiliary Feedwater Sys.Agenda,Attendance List & Viewgraphs Encl ML20058A7781982-07-13013 July 1982 Summary of 820709 Meeting W/Util in Bethesda,Md Re Identifying Addl Info for Development of Regulatory Position Concerning Pressurized Thermal Shock.List of Attendees Encl ML20054H8631982-06-16016 June 1982 Summary of 820608-10 Meetings W/Util in Washington County,Ne Re Procedures & Operator Training Dealing W/Pressurized Thermal Shock.Viewgraphs Encl ML20126L2331981-05-0101 May 1981 Summary of 810429 Meeting W/Pwr Owners Group Re Thermal Shock to Reactor Pressure Vessels.All Parties Agree That Thermal Shock W/Subsequent Repressurization Is Safety Concern Needing Prompt Evaluation ML20148G8601976-11-15015 November 1976 Summary of 761103 Meeting W/Utils,Nus Co,C-E & Lowenstein, Newman,Reis & Axelrad Re Submission of Proposed Measures to Prevent Reactor Vessel Overpressurization in Operating C-E Facilities.Attendance List Encl 1999-04-19
[Table view] |
Text
4 DEC 2 31986 Docket No. 50-285
~ MEMORANDUM FOR: Ashok C. Thadani, Director PWR Project Directorate #8 Division of PWR Licensing-B FROM: Donald E. Sells, Project Manager PWR Project Directorate #8 Division of PWR Licensing-B
SUBJECT:
SUMMARY
OF MEETING HELD ON DECEMBER 17, 1986 REGARDING CORE SUPPORT BARREL / THERMAL SHIELD On Wednesday, December 17, 1986, a meeting was held between the staff and the Omaha Public Power District (0 PPD). The meeting was held to discuss the recent request by OPPD for relief from its commitment to do a complete core support barrel / thermal shield inspection during the Cycle 11 refueling outage. A list of attendees is enclosed.
After a brief introduction by J. Fisicaro of OPPD, T. Patterson, OPPD, discussed the thermal shield support system at Fort Calhoun and described the '
physical, thermal-hydraulic and design differences found at Fort Calhoun when compared to other Combustion Engineering (CE) plants tha't have or had thermal shields. Specifically, the major differences include 1) one less support lug; .2) fewer positioning pins; 3) use of locking collars vs. locking bars;
- 4) lower flow in the annulus; 5) lower positioning pins well'below the active core boundary; and 6) smaller delta T across the lower pins.
T. McIvor presented a short discussion of the results of the 1982/83 inspection. The visual inspection was somewhat more extensive than would have been conducted because of the thermal shield support problems that had been discovered at Maine Yankee in 1982. The visual inspection provided a good head-on view of four of the lugs and over half of the positioning pins with an oblique view of the remainder. There was no indication of any degradation in the welds nor around the support system components.
Subsequent to this visual inspection, the core support barrel / thermal shield damage was detected at St. Lucie Plant, Unit No. 1, and Millstone Unit 2. A great deal of analysis was performed by CE and the results of the St. Lucie analysis were provided to the staff in a proprietary report in the fall of 1984. This report is available through the St. Lucie Project Manager. It was determined that one of the frequency shifts noted in the reduction of internal vibration monitoring data showed that the thermal shield was in fact decoupled and could have been used as the warning signal that problems were developing.
Unfortunately, this was after-the-fact knowledge and was of no benefit to either St. Lucie 1 or Millstone 2.
DOho$0k$85 PDR
B. Longo, CE, in his presentation went over the resalts of the St. Lucie analysis and then presented Fort Calhoun data, including data taken at 0%
power in July 1986. He concluded that there is no evidence of a decoupling occurring at Fort Calhoun and therefore a St. Lucie or Millstone type failure is not imminent. In fact, the data shows no unexplained frequency shift in the Fort Calhoun data in the critical area.
Based on this information OPPD, stated their confidence that Fort Calhoun has not lost pre-load, a necessary failure prior to thermal shield support failure, ,
and that inspection of the core support. barrel / thermal shield should be conducted on the normal 10 year ISI inspection cycle.
The staff agreed in principle with that position, but pointed out that meeting more than normal ISI requirements at the next 10 year inspection may be appropriate. The staff indicated that the results of the meeting would be documented in the near future and that they would be likely to approve the OPPD request with requests for further action in some areas, such as more detailed inspection than required in the ISI program, in the future.
ongmalsigre oy Donald E. Sells, Project Manager PWR Project Directorate #8 Division of PWR Licensing-B
Enclosure:
List of Attendees cc w/ enclosure:
See next page i
f PBD# 8 PBD#8 er Sells;cf AThadani 1/ /86 12/)]/86 12/ 86
LIST OF ATTENDEES DECEMBER-17, 1986 CORE SUPPORT BARREL / THERMAL SHIELD MEEING NRC OPPD C. Y. Cheng H isicaro M. Hum R. Longo (CE)
L. Marsh D. Rollins W. Paulson T. Patterson J.-Rajan J. Mullooly (CE)'
C. D. Sellers T. McIvor D. Sells A. Thadani M. Wambsganss 2
6
. . _ ._ , _ . . _ , - . . - - . _ _ , . _ . . _ _ , ., .- _ - . _ ~ . - . . - _ , . _ . , - - - - . - _ . _ - - -
-_------.-.J
]
Mr. R. L.Andrews Fort Calhoun Station Omaha Public Power District Unit No. 1 cc:
Harry H. Voigt, Esq.
LeBoeuf, Lamb, Leiby & MacRae 1333 New Hampshire Avenue, NW Washington, D.C. 20036 Mr. Jack Jensen,-Chairman Washington County Board of Supervisors Blair, Nebraska 68008 Mr. Phillip Harrell, Resident Inspector U.S. Nuclear Regulatory Commission P. O. Box 309 Fort Calhoun, Nebraska ~ 68023 Mr. Charles B. Brinkman, Manager Washington Nuclear Operations C-E Power Systems 7910 Woodmont Avenue Bethesda, Maryland 20814 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission Office of Executive Director for Operations 611 Ryan Plaza Drive,' Suite 1000 Arlington, Texas 76011 Harold Borchert, Director Division of Radiological Health
' Department of Health 301 Centennial Mall, South -
P.O. Box 95007 Lincoln, Nebraska 68509
.1 M G 0 /(o MEETING
SUMMARY
DISTRIBUTION
-PWR PROJECT DIRECTORATE #8 Docket "I POI, Fi y L PDR PBD#8 Rdg AThadani PKreutzer OELD EJordan BGrimes ACRS-10 NRC Participants CYCheng MHum LMarsh-WPaulson JRajan CSellers AThadani DSe,lls
)
I i
t I
t E . - _ _ . _ . . - . . _ _ . _ _ _ . - . - _ . _ - . _ _ _ _ .._._ _ _ _-