|
---|
Category:MEETING MINUTES & NOTES--CORRESPONDENCE
MONTHYEARML20210H6271999-07-29029 July 1999 Summary of 990622 Meeting with EOI Re NRC Briefing by RBS on Issues Associated with Root Cause Investigation Into Fuel Cladding Failures That Occurred During Recent Cycle 8 Operation.List of Attendees Provided ML20205D4831999-03-25025 March 1999 Summary of 990222 Public Hearing with Util Re Gathering Addl Info Related to Two Petitions Filed Pursuant to 10CFR2.206 by Ucs Re Operation of River Bend Station & Perry Nuclear Power Plant.List of Attendees & Transcript of Hearing 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 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 ML20154C4771998-10-0202 October 1998 Summary of 980908 Meeting with Cleveland Electric Illuminating Co,Entergy Operations,Inc & Illinois Power Co Re Joint Effort to Propose TSs to Reduce Requirements on Secondary Containment Integrity During Refueling ML20151X0011998-09-10010 September 1998 Summary of 980827 Meeting W/Util to Discuss Status of Review of Std QA Manual.List of Attendees 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 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 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 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 ML20148F0391997-05-30030 May 1997 Summary of 970521 Meeting W/Entergy Operations,Inc Re Proposed Removal of MSL Lcs,Removal of Pvlc Sys & Increase of MSIV Leakage Requirements in TS ML20140C1681997-03-28028 March 1997 Summary of 970313 Meeting W/Entergy Operations,Inc to Discuss Proposed ECCS Suction Strainer Mod.List of Attendees & ECCS Suction Strainer Mod 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 ML20056C5251993-06-18018 June 1993 Summary of 930513 Meeting W/Util Re Changes to Security & Response Plans.Meeting Agenda & List of Attendees Encl ML20059C7421993-03-0202 March 1993 Summary of 392nd ACRS Meeting on 921209-11 in Bethesda,Md Re SBO Rule,Ts Improvement Program,Advanced BWR Design,River Bend Nuclear Plant Reliability Monitoring Program & Generic Issue 120,online Testability of Protection Sys ML20055G8611990-07-18018 July 1990 Summary of 900712 Meeting W/Util Re Reload Design Methods. List of Attendees Encl ML20055F0941990-07-10010 July 1990 Summary of 900620 Meeting W/Util Re Proposed License Amends, Including Removal of Snubber Requirements from Tech Specs for Relocation Into Inservice Insp Program & Util Responses to Generic Ltrs 88-01 & 87-09 ML20246B6901989-08-0101 August 1989 Summary of 890727 Meeting W/Util in Arlington,Tx Re Plant Security Enhancement Program & Personnel Changes ML20205A7431988-10-12012 October 1988 Summary of 880928 Meeting W/Util Re 880825 Reactor Trip & Followup Actions by Licensee.Viewgraphs Encl ML20153G6331988-08-30030 August 1988 Summary of Operating Reactor Events Meeting 88-35 on 880830, Including Summary of Reactor Scrams for Wk Ending 880828. Significant Event Identified for Input to NRC Performenance Indicator Program ML20151Z4211988-08-25025 August 1988 Summary of 880818 Meeting W/Util in Rockville,Md Re License Amend Application to Permit Performance of Leak Rate Tests of Containment Isolation Valves in Parallel W/Refueling Operations ML20151Z7921988-08-25025 August 1988 Summary of 880817 Meeting W/Util in Rockville,Md Re Util 5-yr Business Plan to Improve Safety & to Reduce Operating Costs at Plant.List of Attendees & Handouts Encl ML20151R5391988-08-0808 August 1988 Summary of 880623 Meeting W/Mark III Containment Hydrogen Control Owners Group Re Emergency Procedure Guidelines. Resolution of Issues Listed ML20151R8701988-08-0505 August 1988 Summary of 880726 Meeting W/Util in Arlington,Tx Re 5-yr Business Plan.Handouts Encl ML20154J4061988-05-17017 May 1988 Summary of 880414 Meeting W/Representatives & Contractors of Licensee in Rockville,Md Re 870605 Amend Application for Util.Highlights of Discussion Listed.Nrc Indicated That Request for Addl Info Would Be Prepared If Needed ML20148H6621988-01-15015 January 1988 Summary of Operating Reactors Events Meeting 88-02 on 880112 Re Events Which Occurred Since Last Meeting on 880105.List of Attendees,Significant Elements of Events & Tabulation of long-term Followup Assignments to Be Completed Encl ML20147C8041988-01-0606 January 1988 Summary of 871215 & 16 Meetings W/Util in St Francisville,La Re Questions & Comments Resulting from Review of Inservice Testing Program.Inel Trip Rept,List of Attendees & Questions & Comments Encl ML20147C8201987-12-28028 December 1987 Trip Rept of 871215-16 Site Visit to Discuss Pump & Valve Inservice Testing Program ML20236J2291987-10-30030 October 1987 Summary of 871007 Meeting W/Hydrogen Control Owners Group (Hcog) Re Hcog Submittals on Methods for Calculating Equipment Temp Based on Quarter Scale Test Data & Impact of Station Blackout Considerations on Hcog Programs.W/Encl ML20235M9151987-07-19019 July 1987 Summary of 870615 Meeting W/Util in Bethesda,Md Re Revs to Util Emergency Operating Procedures & to Satisfy Sser Requirement.Attendee List Encl ML20214A2151987-05-13013 May 1987 Summary of 870508 Meeting W/Util & GE Re Licensee Plans for Fuel Reload.List of Attendees & Meeting Viewgraphs Encl ML20215L3281987-05-0505 May 1987 Summary of Operating Reactors Events Meeting 87-11 on 870420.List of Attendees,Viewgraphs & Input to NRC Performance Indicator Program Encl ML20212Q9681987-04-21021 April 1987 Summary of 870217 Meeting W/Util to Discuss Issues Re Containment Vending,Reg Guide 1.97,TDI Diesels,Util Plans for First Refueling Outage,Engineering Expertise on Shift, UHS Monitor & OL Amends ML20211M9761987-02-24024 February 1987 Summary of 870203 Meeting W/Mark III Containment Hydrogen Control Owners Group Re CLASIX-3 Computer Code Validation & Emergency Procedure Guidelines.List of Attendees Encl ML20207B0141986-10-31031 October 1986 Summary of 861022 Meeting W/Mark III Containment Hydrogen Control Owners Group Re Emergency Procedure Guidelines for Hydrogen Generation Event & Validation of Methods for Calculating Heat Transfer.Viewgraphs Encl ML20203G6921986-07-25025 July 1986 Summary of 860619 Meeting W/Mark III Containment Hydrogen Control Owners Group Re Mods of Clasix-3 Computer Code & Secondary Burning in Quarter Scale Test.List of Meeting Attendees & Handouts Encl ML20207E2811986-07-16016 July 1986 Summary of Operating Reactors Events Meeting 86-24 on 860714 Re Events Occurring Since 860707 Meeting ML20211G7781986-06-13013 June 1986 Summary of Operating Reactor Events Meeting 86-19 on 860609. List of Attendees,Events Discussed & Status of Previous Assignments Encl ML20206G6571986-06-10010 June 1986 Summary of 860529 Meeting W/Util Re Licensing Priorities & Matters Associated W/Forthcoming Transition of Util from Startup Test to Commercial Operation.Attendees List & Viewgraphs Encl ML20211G9361986-06-0606 June 1986 Summary of Operating Reactor Events Meeting 86-18 on 860602 Re Events Occurring Since 860519 Meeting.Attendee List, Events,Significant Elements of Events & Completion Dates for Assignments Encl ML20210R8471986-05-13013 May 1986 Summary of Operating Reactors Events Meeting 86-16 on 860512 Re Events Occurring Since Last Meeting.List of Attendees & Related Info Encl ML20197F1691986-05-0808 May 1986 Summary of Operating Reactors Events 860428 Meeting W/Listed Divs Re Chernobyl Nuclear Accident & Events at Us Reactors ML20197F7721986-05-0808 May 1986 Summary of Operating Reactors Events Meeting 86-15 on 860505.List of Attendees,Events Discussed & Status of Previous Assignments Encl ML20203M9431986-04-25025 April 1986 Summary of Operating Reactors Events Meeting 86-13 on 860421 Re Events Occurring Since 860414 Meeting.Attendance List, Viewgraphs & Supporting Documentation Encl ML20141G2901986-04-0707 April 1986 Summary of 860313 Meeting W/Mark III Containment Hydrogen Control Owners Group in Bethesda,Md Re Heat Loss Analysis. List of Attendees,Handout & Viewgraphs Encl ML20210J0261986-03-24024 March 1986 Summary of Operating Reactor Events Meeting 86-08 on 860317 to Discuss Events Occurring Since Last Meeting on 860310 ML20154P0071986-03-12012 March 1986 Summary of Operating Reactor Events 860303 Meeting 86-06 W/Ornl Re Events Occurring Since 860224 Meeting.Followup Review Assignments,Status of Previous Assignments,List of Attendees & Viewgraphs Encl 1999-07-29
[Table view] Category:MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
MONTHYEARML20210H6271999-07-29029 July 1999 Summary of 990622 Meeting with EOI Re NRC Briefing by RBS on Issues Associated with Root Cause Investigation Into Fuel Cladding Failures That Occurred During Recent Cycle 8 Operation.List of Attendees Provided ML20205D4831999-03-25025 March 1999 Summary of 990222 Public Hearing with Util Re Gathering Addl Info Related to Two Petitions Filed Pursuant to 10CFR2.206 by Ucs Re Operation of River Bend Station & Perry Nuclear Power Plant.List of Attendees & Transcript of Hearing 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 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 ML20154C4771998-10-0202 October 1998 Summary of 980908 Meeting with Cleveland Electric Illuminating Co,Entergy Operations,Inc & Illinois Power Co Re Joint Effort to Propose TSs to Reduce Requirements on Secondary Containment Integrity During Refueling ML20151X0011998-09-10010 September 1998 Summary of 980827 Meeting W/Util to Discuss Status of Review of Std QA Manual.List of Attendees 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 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 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 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 ML20148F0391997-05-30030 May 1997 Summary of 970521 Meeting W/Entergy Operations,Inc Re Proposed Removal of MSL Lcs,Removal of Pvlc Sys & Increase of MSIV Leakage Requirements in TS ML20140C1681997-03-28028 March 1997 Summary of 970313 Meeting W/Entergy Operations,Inc to Discuss Proposed ECCS Suction Strainer Mod.List of Attendees & ECCS Suction Strainer Mod 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 ML20056C5251993-06-18018 June 1993 Summary of 930513 Meeting W/Util Re Changes to Security & Response Plans.Meeting Agenda & List of Attendees Encl ML20059C7421993-03-0202 March 1993 Summary of 392nd ACRS Meeting on 921209-11 in Bethesda,Md Re SBO Rule,Ts Improvement Program,Advanced BWR Design,River Bend Nuclear Plant Reliability Monitoring Program & Generic Issue 120,online Testability of Protection Sys ML20055G8611990-07-18018 July 1990 Summary of 900712 Meeting W/Util Re Reload Design Methods. List of Attendees Encl ML20055F0941990-07-10010 July 1990 Summary of 900620 Meeting W/Util Re Proposed License Amends, Including Removal of Snubber Requirements from Tech Specs for Relocation Into Inservice Insp Program & Util Responses to Generic Ltrs 88-01 & 87-09 ML20246B6901989-08-0101 August 1989 Summary of 890727 Meeting W/Util in Arlington,Tx Re Plant Security Enhancement Program & Personnel Changes ML20205A7431988-10-12012 October 1988 Summary of 880928 Meeting W/Util Re 880825 Reactor Trip & Followup Actions by Licensee.Viewgraphs Encl ML20153G6331988-08-30030 August 1988 Summary of Operating Reactor Events Meeting 88-35 on 880830, Including Summary of Reactor Scrams for Wk Ending 880828. Significant Event Identified for Input to NRC Performenance Indicator Program ML20151Z7921988-08-25025 August 1988 Summary of 880817 Meeting W/Util in Rockville,Md Re Util 5-yr Business Plan to Improve Safety & to Reduce Operating Costs at Plant.List of Attendees & Handouts Encl ML20151Z4211988-08-25025 August 1988 Summary of 880818 Meeting W/Util in Rockville,Md Re License Amend Application to Permit Performance of Leak Rate Tests of Containment Isolation Valves in Parallel W/Refueling Operations ML20151R5391988-08-0808 August 1988 Summary of 880623 Meeting W/Mark III Containment Hydrogen Control Owners Group Re Emergency Procedure Guidelines. Resolution of Issues Listed ML20151R8701988-08-0505 August 1988 Summary of 880726 Meeting W/Util in Arlington,Tx Re 5-yr Business Plan.Handouts Encl ML20154J4061988-05-17017 May 1988 Summary of 880414 Meeting W/Representatives & Contractors of Licensee in Rockville,Md Re 870605 Amend Application for Util.Highlights of Discussion Listed.Nrc Indicated That Request for Addl Info Would Be Prepared If Needed ML20148H6621988-01-15015 January 1988 Summary of Operating Reactors Events Meeting 88-02 on 880112 Re Events Which Occurred Since Last Meeting on 880105.List of Attendees,Significant Elements of Events & Tabulation of long-term Followup Assignments to Be Completed Encl ML20147C8041988-01-0606 January 1988 Summary of 871215 & 16 Meetings W/Util in St Francisville,La Re Questions & Comments Resulting from Review of Inservice Testing Program.Inel Trip Rept,List of Attendees & Questions & Comments Encl ML20236J2291987-10-30030 October 1987 Summary of 871007 Meeting W/Hydrogen Control Owners Group (Hcog) Re Hcog Submittals on Methods for Calculating Equipment Temp Based on Quarter Scale Test Data & Impact of Station Blackout Considerations on Hcog Programs.W/Encl ML20235M9151987-07-19019 July 1987 Summary of 870615 Meeting W/Util in Bethesda,Md Re Revs to Util Emergency Operating Procedures & to Satisfy Sser Requirement.Attendee List Encl ML20214A2151987-05-13013 May 1987 Summary of 870508 Meeting W/Util & GE Re Licensee Plans for Fuel Reload.List of Attendees & Meeting Viewgraphs Encl ML20215L3281987-05-0505 May 1987 Summary of Operating Reactors Events Meeting 87-11 on 870420.List of Attendees,Viewgraphs & Input to NRC Performance Indicator Program Encl ML20212Q9681987-04-21021 April 1987 Summary of 870217 Meeting W/Util to Discuss Issues Re Containment Vending,Reg Guide 1.97,TDI Diesels,Util Plans for First Refueling Outage,Engineering Expertise on Shift, UHS Monitor & OL Amends ML20211M9761987-02-24024 February 1987 Summary of 870203 Meeting W/Mark III Containment Hydrogen Control Owners Group Re CLASIX-3 Computer Code Validation & Emergency Procedure Guidelines.List of Attendees Encl ML20207B0141986-10-31031 October 1986 Summary of 861022 Meeting W/Mark III Containment Hydrogen Control Owners Group Re Emergency Procedure Guidelines for Hydrogen Generation Event & Validation of Methods for Calculating Heat Transfer.Viewgraphs Encl ML20203G6921986-07-25025 July 1986 Summary of 860619 Meeting W/Mark III Containment Hydrogen Control Owners Group Re Mods of Clasix-3 Computer Code & Secondary Burning in Quarter Scale Test.List of Meeting Attendees & Handouts Encl ML20207E2811986-07-16016 July 1986 Summary of Operating Reactors Events Meeting 86-24 on 860714 Re Events Occurring Since 860707 Meeting ML20211G7781986-06-13013 June 1986 Summary of Operating Reactor Events Meeting 86-19 on 860609. List of Attendees,Events Discussed & Status of Previous Assignments Encl ML20206G6571986-06-10010 June 1986 Summary of 860529 Meeting W/Util Re Licensing Priorities & Matters Associated W/Forthcoming Transition of Util from Startup Test to Commercial Operation.Attendees List & Viewgraphs Encl ML20211G9361986-06-0606 June 1986 Summary of Operating Reactor Events Meeting 86-18 on 860602 Re Events Occurring Since 860519 Meeting.Attendee List, Events,Significant Elements of Events & Completion Dates for Assignments Encl ML20210R8471986-05-13013 May 1986 Summary of Operating Reactors Events Meeting 86-16 on 860512 Re Events Occurring Since Last Meeting.List of Attendees & Related Info Encl ML20197F1691986-05-0808 May 1986 Summary of Operating Reactors Events 860428 Meeting W/Listed Divs Re Chernobyl Nuclear Accident & Events at Us Reactors ML20197F7721986-05-0808 May 1986 Summary of Operating Reactors Events Meeting 86-15 on 860505.List of Attendees,Events Discussed & Status of Previous Assignments Encl ML20203M9431986-04-25025 April 1986 Summary of Operating Reactors Events Meeting 86-13 on 860421 Re Events Occurring Since 860414 Meeting.Attendance List, Viewgraphs & Supporting Documentation Encl ML20141G2901986-04-0707 April 1986 Summary of 860313 Meeting W/Mark III Containment Hydrogen Control Owners Group in Bethesda,Md Re Heat Loss Analysis. List of Attendees,Handout & Viewgraphs Encl ML20210J0261986-03-24024 March 1986 Summary of Operating Reactor Events Meeting 86-08 on 860317 to Discuss Events Occurring Since Last Meeting on 860310 ML20154P0071986-03-12012 March 1986 Summary of Operating Reactor Events 860303 Meeting 86-06 W/Ornl Re Events Occurring Since 860224 Meeting.Followup Review Assignments,Status of Previous Assignments,List of Attendees & Viewgraphs Encl ML20154C9931986-02-24024 February 1986 Summary of Operating Reactors Event Meeting 86-04 on 860210.List of Attendees,Briefing & Reactor Scram Summaries Encl 1999-07-29
[Table view] |
Text
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rs UNITED STATES
- jg ,j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20066-0001 f
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July 29,1999 LICENSEE: Entergy Operations, Inc.
FACILITY: River Bend Station, Unit 1
SUBJECT:
SUMMARY
OF MEETING BETWEEN THE NUCLEAR REGULATORY COMMISSION (NRC) STAFF AND ENTERGY OPERATIONS, INC. (EOI),
RIVER BEND STATION MANAGEMENT, JUNE 22,1999 On Tuesday, June 22,1999, a meeting was held between members of the NRC staff and representatives of EOl, the licensee for the River Bend Station (RBS). The purpose of the meeting was to permit representatives from RBS to brief the NRC staff on, and to discuss issues associated with, the root cause investigation into fuel cladding failures that occurred during the recent cycle 8 operation. A portion of the meeting involved discussions pertaining to proprietary information and was closed to the public. The meeting lasted approximately 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.
The meeting began at 9:00 a.m. In the Commissioners' Hearing Room located at NRC Headquarters, Rockville, Maryland. A list of meeting attendees is provided as Enclosure 1 to this summary. EOl presented a nonproprietary information overview of their root cause investigation. Topics during this session included:
- Evaluation Approach a Core Design
- Conclusions EOl opened by characterizing the issue as (1) a higher than-expected and non-uniform deposition of corrosion products on the fuel pins, and (2) the occurrence of fuel cladding f perforations in several once-burned, higher heat flux fuel rod locations. A total of seven fuel j bundles were discovered with cladding perforations, which correlated to the number of [
suspected failures suspected prior to the plant shutting down in April 1999. All seven bundles were "first burned" fuel coming from the "HGE" batch. The cladding perforations observed in these fuel bundles were attributed to an insulating thermal barrier failure mechanism.
Following an exchange of background information and initial inspection findings, EOl reviewed
/ D\
5) its organizational response, causal investigation approach, and various core design issues, y EOl formed a root cause investigation team, comprising of members from EOi, General Electric (GE), Electric Power Research institute (EPRI), and other independent consultants. The investigation was headed by Mr. Dan Pace, Director, Engineering (RBS).
9900040061 990729 M
PDR ADOCK 05000458 P PDR
2 EOl continued with a discussion on the various differences between Cycle 7 and Cycle 8 operations. Some of the differences included the removal of low cross-linked resins from the demineralizers, initiation of zine injection into the primary water, use of the extended operating domain-Maximum Extended Load Line Limit Analysis (MELLA)-operating strategy, extended control blade sequence exchange intervals, and higher iron and copper concentrations in the reactor water than in previous cycles. This discussion was followed by an overview of various chemistry issues.
Based upon the information uncovered to date, as well as the conclusions drawn by EOl and outside consultants, EOl has determined that the most probable cause of the fuel cladding perforations was a result of " thermally-induced accelerated corrosion, due to the combined effects of elevated iron and copper deposits with a chemistry excursion early in the operating cycle." Consequently, EOl has decided to undertake the following actions:
- 1. Remove all once-burned fuel assemblies from the HGE batch;
- 2. Redesign the reactor core to accommodate a new reload batch for Cycle 9;
- 3. Change the RBS chemistry program to (a) reduce metals transport to the reactor, (b) improve chemistry monitoring capability, and (c) increase chemistry monitoring;
- 4. Cycle 9 will operate as a "short cycle"(approximately half of the normal 18-month operating cycle); and
- 5. RBS will perform confirmatory inspection during the ninth refueling outage.
The public portion of the meeting was concluded and members of the pubiic were given the opportunity to provide comments to the NRC staff. A copy of the slides used during the public, nonproprietary session are provided as Enclosure 2. The meeting reconvened with a briefing on additional details, including information requested by EOl to be considered proprietary under Title 10 of the Code of Federal Reaulations. Section 2.790. The briefing included presentations by EOl and GE.
( // o obert J. Fretz, Proje anager, Section 1 Project Directorate IV & Decommissioning Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-458
Enclosures:
- 1. List of Meeting Attendees
- 2. EOl Slide Presentation cc w/encis: See next page
F . .
, + e River Bend Station cc:
Winston & Strawn Executive Vice President and 1400 L Street, N.W. Chief Operating Officer Washington, DC 20005-3502 Entergy Operations, Inc.
P. O. Box 31995 Manager - Licensing Jackson, MS 39286 Entergy Operations, Inc.
River Bend Station General Manager - Plant Operations P. O. Box 220 Entergy Operations, Inc.
St. Francisville, LA 70775 River Bend Station ,
P. O. Box 220 Senior Resident inspector St. Francisville, LA 70775 P. O. Box 1050 St. Francisville, LA 70775 Director - Nuclear Safety Entergy Operations, Inc.
President of West Feliciana River Bend Station Police Jury P. O. Box 220 P. O. Box 1921 St. Francisville, LA 70775 St. Francisville, LA 70775 Vice President - Operations Support Regional Administrator, Region IV Entergy Operations, Inc.
U.S. Nuclear Regulatory Commission l
P. O. Box 31995 j 611 Ryan Plaza Drive, Suite 1000 Jackson, MS 39286-1995 j Arlington,TX 76011 Attorney General Ms. H. Anne Plettinger State of Louisiana 3456 Villa Rose Drive P. O. Box 94095 Baton Rouge, LA 70806 Baton Rouge, LA 70804-9095 Administrator Mr. Randall K. Edington Louisiana Radiation Protection Division Vice President - Operations P. O. Box 82135 Entergy Operations, Inc.
Baton Rouge, LA 70884 2135 River Bend Station P. O. Box 220 Wise, Carter, Child & Caraway St. Francisville, LA 70775 P. O. Box 651 Jackson, MS 39205 May 1999
7, ,
'4 't 1
LIST OF ATTENDEES NRC - EOl MEETING ON FUEL INTEGRITY ISSUES <
JUNE 22,1999 i
NRC Staff I Stuart Richards Project Director, Project Directorate IV & Decommissioning Dale Powers - Chief, Engineering and-Maintenance Branch, Region IV Robert Gramm L Section Chief, Project Directorate IV, Section 1 Ralph Caruso Section Chief, Reactor Systems Branch Robert Fretz RBS Project Manager, Project Directorate IV, Section 1 Muffet Chatterton Nuclear Engineer, Reactor Systems Branch Shih-Lang Wu Nuclear Engineer, Reactor Systems Branch ,
Joseph Donoghue Reactor Engineer, Reactor Systems Branch Anthony Ulses Nuclear Engineer, Reactor Systems Branch Edward Kendrick Reactor Engineer, Reactor Systems Branch Ronald Framm Reactor Engineer, Reactor Systems Branch H. F. Conrad Senior Materials Engineer, Materials and Chemical Engineering Branch K. Parczewski Senior Chemical Engineer, Materials and Chemical Engineering Branch Edward Goodwin Senior Reactor Engineer, Events Assessment Branch Robert Spence Reactor Systems EnDi neer, Office of Nuclear Regulatory Research Carl Beyer NRC Consultant, Pacific Nothwest Laboratory Enterav Ooerations. Inc.
Fred Titus VP, Engineering (Corporate)
Dan Pace Director, Engineering (RBS)
Dwight Mims RBS Plant Manager Rick King Director, Nuclear Safety and Regulatory Affairs Brian Thumm Licensing Engineer David Smith Senior Engineer Jerome Holmes Manager, Radiation Protection / Chemistry C. B. Franklin Manager, Nuclear Engineering (Corporate)
Dean Burnett Chemistry Specialist General Electric Corooration G. A. Watford Manager, Nuclear Fuel Engineering G. A. Potts Fuel Performance Robert Cowan Chief Technologist Public Observers David Stellfox McGraw-Hill ENCLOSURE 1
ENCLOSURE 2 ENTERGY OPERATIONS, INC.
SLIDE PRESENTATION
i River Bend Station
)
Fuel Recovery Overview I
June 22,1999 Overview
- Background
- Contingency Planning Prior to the Eighth Refueling Outage (RF-8)
-Inspection Findings
- Response to Inspection Findings
- Evaluation Approach
- Core Design
- Conclusions 2
i
. . 1 a a River Bend Core Map ,,
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Fuel Performance Summary Good past fuel performance prior to Cycle 8 No fuel clad perforation in over 1400 days of operation No previous corrosion-related clad perforations
- First fuel clad perfbration identified Sept.18, 1998, during Cycle 8 Seven fuel bundles total suspected before end of cycle (EOC) l
RF-8 InitialInspection Findings 1
Shutdown unit for RF-8 on 4/3/99 Performed 100% core sipping
- 7 bundles with clad perforations - all identified during Cycle 8 '
All were "first burned" fuel (HGE batch)
Heavier-than-expected non-uniform crud patterns
- Result : clad perforation mechanism observed was attributed to an insulating thermal barrier i
l i " CRUD" l
l
. An industry term for corrosion and wear products
{
Activated particles are referred to as " crud"
{
. Crud is present in all nuclear plants 1 In a boiling water reactor (BWR), corrosion products plate out in the core because they do not carry over in the steam f
1
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mumm. unus* I
,e
, , l Organization Structure 1
)
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13
. 1 Independent Reviews / Oversight
- EPRI- Fuel Corrosion NWT Corporation - Radiochemistry
- G. Sossi- Core Design and Licensing
- Independent Lab - Materials
- Corrective Action Review Board ,
- Facility Review Committee Safety Review Committee S. Levy - Entergy Nuclear Committee of the Board of Directors
~
I Fuel Operating Experience Review Foreign and domestic Various fuel types Search for similar conditions Parallel effort by General Electric '
Perspective
- Foreign and domestic occurrences
- Multiple causes
{
Fuel Operating Experience Review l
l Results
- Good team insights No fuel performance experience parallels the River Bend condition
- Fuel clad perforations typically caused by the combination of several factors Broad response treats symptoms effectively
- Aoot cause conclusions typically longer term i.
L h
j
l Chemistry Program
= Based on BWR Water Chemistry Guidelines
- Reactor water
- Feedwater / condensate chemistry Identified an increase in feedwater metals average
- Higher than in previous cycles
- Within guidelines
- Related to resin usage 2t Chemistry Review
. October 15-17,1997 (during refueling outage 7 (RF-7))
- Conductivity excurrion (6.1 pS/cm peak)
- Associated with chendcals introduced by residual heat removal (RHR) heat exchanger cleaning October 24-26,1997 (startup from RF-7)
- Conductivity excursion (0.946 S/cm peak)
- Contaminants in extraction / drain piping n
. 1 Cause ofFuel Clad Perforations Thermally-induced accelerated corrosion, due to the combined effects of elevated iron and copper deposits with a chemistry ,
excursion early in the operating cycle j
29 Cause ofFuel Clad Perforations l l
cw Cycle 6 sf.yFli< Cu c-l Cycle 7 Cu
$Fe7 Cycle 8 EM!T6I)3 Cu BOC Excursion >
l Cycle 9 g.*.?pfi'h Cu Improved feedwater treatment improved cleanup / monitoring 1s i
- c. n6*
Conclusions
. Quickly and accurately identified and suppressed perforated fuel rods during Cycle 8
. Extensively investigated to determine the cause and to prevent recurrence
. Determined that an insulating thermal barrier of crud -
caused accelerated fuel rod corrosion
. Ultimately bounded the cause in order to attsin reasonable assurance that no similar fuel clad perforations will occur
. Concluded that River Bend is safe to startto and operate a
I i
J
I
..W July 29,1999 f@f filP EOl continued with a discussion on the various differences between Cycle 7 and Cycle 8 operations. Some of the differences included the removal of low cross-linked resins from the
' demineralizers, initiation of zinc injection into the primary water, use of the extended operating
- domain-Maximum Extended Load Line Limit Analysis (MELLA)-operating strategy, extended control blade sequence exchange intervals, and higher iron and copper concentrations in the reactor water than in previous cycles. This discussion was followed by an overview of various -
chemistry issues.
Based upon the information uncovered to date, as well as the conclusions drawn by EOl and
. outside consultants, EOl has determined that the most probable cause of the fuel cladding perforations was a result of " thermally-induced accelerated corrosion, due to the combined effects of elevated iron and copper deposits with a chemistry excursion early in the operating cycle." ' Consequently, EOl has decided to undertake the following actions:
- 1. Remove all once-burned fuel assemblies from the HGE batch;
- 2. Redesign the reactor core to accommodate a new reload batch for Cycle 9;
- 3. Change the RBS chemistry program to (a) reduce metals transport to the reactor, (b) improve chemistry monitoring capability, and (c) increase chemistry monitoring;
- 4. Cycle 9 will operate as a "short cycle" (approximately half of the normal 18-month operating cycle); and
- 5. ' RBS will perform confirmatory inspection during the ninth refueling outage.
The public portion of the meeting was concluded and members of the public were given the opportunity to provide comments to the NRC staff. A copy of the slides used during the public, nonproprietary session are provided as Enclosure 2. The meeting reconvened with a briefing on additional details, including information requested by EOl to be considered proprietary under Title 10 of the Code of Federal Reaulations, Section 2.790. The briefing included presentations by EOl and GE.
ORIG. SIGNED BY Robert Ji Fretz, Project Manager, Section 1 Project Directorate IV & Decommissioning Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-458 DISTRIBUTION
~ Docket File OGC
Enclosures:
PUBLIC ACRS
- 1. List of Meeting Attendees PDIV-1 RF - G. Hill (4)
- 2. EOl Slide Presentation S. Richards K. Brockman, RIV R. Gramm J. Zwolinski/S. Black cc w/encis: See next page R.Fretz Meeting Attendees Document Name: G:\PDIV-1\RiverBend\MtgSummary NRC-EOl 062299,wpd j To receive co y of document indicate - E = copy w/onci c = copy w/o enci N = no copy l OFFICE PM/PDIV 1 ' nE LA/PDIV 'i )E .SCkDk4 E NAME RFretz:db LBerry hh krkm <
DATE 7 / 7], /99 h/ [99 N
OFFICIAL RECORD COPY !