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| On Tuesday, July 12, 1994, a public meeting was held at the U.S. Nuclear Regulatory Commission (NRC) offices located at One White Flint North, Rockville, Maryland with GPU Nuclear Corporation (GPUN), the licensee for TMI-1. The purpose of the meeting was to discuss results of the control rod drop testing and subsequent control rod drive mechanism (CRDM) testing during the week of June 1, 1994. Enclosure 1 is the list of participants at the meeting. Enclosure 2 is a copy of the handouts used during the meeting. | | On Tuesday, July 12, 1994, a public meeting was held at the U.S. Nuclear Regulatory Commission (NRC) offices located at One White Flint North, Rockville, Maryland with GPU Nuclear Corporation (GPUN), the licensee for TMI-1. The purpose of the meeting was to discuss results of the control rod drop testing and subsequent control rod drive mechanism (CRDM) testing during the week of June 1, 1994. Enclosure 1 is the list of participants at the meeting. Enclosure 2 is a copy of the handouts used during the meeting. |
| The first time that control rod drop times exceeded the Technical Specification (TS) limit of 1.66 seconds was October 1993, at the conclusion of the 10R refueling outage. At that time three rods exceeded the requirement and were brought back within the TS requirement by additional testing. During a scheduled outage in March 1994, surveillance testing indicated that 12 of 61 rods exceeded the TS requirement. All rods were again brought below the TS requirement by additional testing. However, following a meeting with GPUN on March 25, 1994, the staff issued a confirmatory action letter (CAL) to GPUN on March 29, 1994, requiring GPUN to establish a program of per, iodic control rod monitoring, development of evaluation criteria, a contingency plan, and a long term plan for corrective action. | | The first time that control rod drop times exceeded the Technical Specification (TS) limit of 1.66 seconds was October 1993, at the conclusion of the 10R refueling outage. At that time three rods exceeded the requirement and were brought back within the TS requirement by additional testing. During a scheduled outage in March 1994, surveillance testing indicated that 12 of 61 rods exceeded the TS requirement. All rods were again brought below the TS requirement by additional testing. However, following a meeting with GPUN on March 25, 1994, the staff issued a confirmatory action letter (CAL) to GPUN on March 29, 1994, requiring GPUN to establish a program of per, iodic control rod monitoring, development of evaluation criteria, a contingency plan, and a long term plan for corrective action. |
| THI-l was shut down on June 1, 1994, to conduct rod drop time testing. On that date, three control rods were determined to exceed the time required by the TS. GPUN removed those three CRDMs plus one other for inspection and replacement of the CRDM thermal barriers. Enclosure 2 summarizes the results of the testing and inspections. GPUN confirmed that the root cause of the lengthened control rod drop times is deposition of crud in the thermal barrier of the CRDMs. GPUN restated that the crud buildup has probably been aggravated by operating at a lower reactor coolant system (RCS) pH than normal as a result of higher boric acid concentrations required for the extended-life cores. Corrective action proposed in a March 26, 1994, letter from GPUN, and repeated in the staff's CAL, consists primarily of raising pH and lithium hydroxide levels in the RCS, and exercising control rods through 10% of their total travel on a biweekly basis. GPUN expects that these actions will result in an improvement in rod drop time. The drop times of the refurbished CRDMs were determined to be satisfactory by testing following refurbishment. p GPUN was advised in a meeting on May 3, 1994, that the staff would consider a temporary revision to the TS limit if it could ba justified by GPUN from a ( : | | THI-l was shut down on June 1, 1994, to conduct rod drop time testing. On that date, three control rods were determined to exceed the time required by the TS. GPUN removed those three CRDMs plus one other for inspection and replacement of the CRDM thermal barriers. Enclosure 2 summarizes the results of the testing and inspections. GPUN confirmed that the root cause of the lengthened control rod drop times is deposition of crud in the thermal barrier of the CRDMs. GPUN restated that the crud buildup has probably been aggravated by operating at a lower reactor coolant system (RCS) pH than normal as a result of higher boric acid concentrations required for the extended-life cores. Corrective action proposed in a {{letter dated|date=March 26, 1994|text=March 26, 1994, letter}} from GPUN, and repeated in the staff's CAL, consists primarily of raising pH and lithium hydroxide levels in the RCS, and exercising control rods through 10% of their total travel on a biweekly basis. GPUN expects that these actions will result in an improvement in rod drop time. The drop times of the refurbished CRDMs were determined to be satisfactory by testing following refurbishment. p GPUN was advised in a meeting on May 3, 1994, that the staff would consider a temporary revision to the TS limit if it could ba justified by GPUN from a ( : |
| safety standpoint and GPUN was encouraged to submit a TS change request as j | | safety standpoint and GPUN was encouraged to submit a TS change request as j |
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MONTHYEARML20149F4911994-08-0303 August 1994 Summary of 940712 Meeting W/Util at NRC Office in Rockville,Md to Discuss Results of Control Rod Drop Testing & Subsequent Control Rod Drive Mechanism Testing During Week of 940601 Project stage: Meeting 1994-08-03
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Category:MEETING MINUTES & NOTES--CORRESPONDENCE
MONTHYEARML20211F5761999-08-26026 August 1999 Summary of 990813 Meeting with Licensee in Rockville,Md to Discuss Status & Completion Schedule of Active & Soon to Be submitted,TMI-1 Licensing Issue.List of Attendees & Meeting Handouts Encl ML20210L6541999-08-0404 August 1999 Summary of 990713 Meeting with Util in Rockville,Md Re Licensee Proposed Mods to Reactor Building Spray Sys Operation & Hpis.List of Attendees 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 ML20207B6441999-05-26026 May 1999 Summary of 990507 Meeting with Gpu Nuclear,Inc in Rockville, MD Re Status & Completion Schedule of Active & Soon to Be submitted,TMI-1 Licensing Issues.List of Attendees & Copy of Licensee Handout Used at Meeting Encl ML20154F4771998-10-0505 October 1998 Summary of 980917 Meeting W/Gpu Nuclear Inc,Amergen & NRC in Rockville,Md Re Sale & License Transfer of Three Mile Island Nuclear Genrating Station,Unit 1.List of Attendees,Copy of Licensee Handout & Copy of Meeting Transcript Encl ML20236F6671998-06-30030 June 1998 Summary of 980527 Meeting W/Util Re Control Room Habitability Evaluation Related to Control Room Operator Thyroid Dose from Fission Product Releases During Postulated Design Basis Accident at Plant Unit 1 ML20249A0561998-06-10010 June 1998 Summary of 980604 Meeting W/Gpu in TMI-1 Training Center to Discuss Status of Active & Recently Completed TMI-1 Licensing Issues ML20199J7061998-02-0202 February 1998 Summary of 971212 Meeting W/Gpu Re Control Room Habitability Evaluation Concerning CR Operator Thyroid Dose from Fission Product Release During Postulated Design Basis Accident at Plant 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 ML20217M7601997-08-21021 August 1997 Summary of 970725 Meeting W/Gpu in Rockville,Md to Discuss Licensee Plans for Inspecting SG Tubing in Upcoming Refueling Outage ML20151L8201997-08-0404 August 1997 Summary of 970715 Meeting W/Gpu Nuclear Corp in Rockville,Md Re Licensee Plans for Inspecting SG Tubing in Upcoming Refueling Outage.List of Attendees & Handouts Encl ML20148D8531997-05-28028 May 1997 Summary of 970502 Meeting W/Util to Discuss Status of Implementation Schedule for Completion of Installation of Thermo-lag at Plants.List of Attendees Encl ML20138H5581996-12-19019 December 1996 Summary of 961126 Meeting W/Util in Rockville,Md to Discuss Two Major Issues Related to SG Tube Integrity at Facility. W/List of Attendees & Viewgraphs ML20150A2351996-02-15015 February 1996 Summary of 960205 Meeting W/Gpu at TMI-1 Site to Discuss Active & Recently Completed TMI-1 Licensing Issues.List of Participants & Copy of Handouts Encl ML20149F4911994-08-0303 August 1994 Summary of 940712 Meeting W/Util at NRC Office in Rockville,Md to Discuss Results of Control Rod Drop Testing & Subsequent Control Rod Drive Mechanism Testing During Week of 940601 ML20059J3351994-01-25025 January 1994 Notification of 940202 Meeting W/R Gary in Rockville,Md to Discuss 2.206 Petition to Shut Down TMI Unit 1 ML20128P8491993-02-18018 February 1993 Summary of Operating Reactors Events Briefing 93-05 on 930210 ML20062A6511990-10-0505 October 1990 Summary of 900913 Meeting W/Util in Middletown,Pa,Re Current Licensing Issues & Insp Open Items ML20055E3181990-07-0505 July 1990 Summary of 900607 Meeting W/Gpu at TMI Site Near Middletown,Pa Re Current Licensing Issues.Attendance List Encl ML20246C3331989-06-29029 June 1989 Summary of 890614 Meeting W/Util & Commonwealth of PA in Middletown,Pa Re Status & Future Actions of All Active Licensing Issues.List of Attendees & generic/multi-plant Actions Encl ML20247K5841989-05-24024 May 1989 Summary of 890512 Meeting W/Util at Site Re Status & Future Actions of Active Licensing Issues.List of Attendees & Activities Discussed Encl ML20246F4541989-05-0202 May 1989 Summary of 890410 Meeting W/Util in Middletown,Pa Re Status & Future Actions of All Active Licensing Issues.Tmi Action Items II.K.3.31 & I.C.1 Completed Since Last Monthly Meeting & Closeout Ltrs Sent to Util on 890328 ML20235W0041989-03-0101 March 1989 Summary of 890222 Meeting Between NMSS & NRR Project Manager Re Status of Cleanup & H Thompson Concern That NRR Set Cleanup Criteria That Could Cause Problem for NRC Later on ML20235Y4221989-02-27027 February 1989 Summary of 890215 Meeting W/Util in Rockville,Md Re ATWS Implementation.List of Attendees & post-meeting Questions Encl ML20235M7051989-02-16016 February 1989 Summary of 890208 Meeting W/Bechtel & Util Re Portrayal of Bechtel & Util Auditing of Nuclear Energy Svcs in Info Notice 88-035, Inadequate Licensee Performed Vendor Audits. List of Attendees Encl ML20154F7971988-09-15015 September 1988 Summary of 880901 QA Meeting W/Util in Rockville,Md to Discuss Rev 2 of Util Operational QA Plan for Plants.Agenda & List of Participants Encl ML20207E2961988-07-28028 July 1988 Summary of 880714 Meeting W/B&W Owners Group Re Industry & NRC Actions to Resolve Issues Raised in Generic Ltr 87-12. List of Attendees,Viewgraphs & B&W Design Differences Encl ML20148S3821988-03-31031 March 1988 Summary of Operating Reactors Events Meeting 88-13 on 880329.List of Attendees,Discussion of Events & Summary of Reactor Scrams Encl ML20147J1081988-02-26026 February 1988 Summary of 880218 Meeting W/Gpu in Rockville,Md to Discuss Matters Pertaining to 7R Refueling Outage Planned to Commence on 880617.Attendance List & Viewgraphs Encl ML20238A9911987-08-27027 August 1987 Summary of 870824 Meeting W/Util in Bethesda,Md Re 870728 Proposed License Amend,Revising Radiological Effluents Tech Specs ML20237K6461987-08-0606 August 1987 Summary of 870619 Meeting W/Util in King of Prussia,Pa Re Changes to Util Emergency Plan for Plants Based on Changing Plant Status & Reclassification to Post Defueling Monitored Storage ML20214W9971987-06-10010 June 1987 Summary of 870521 Meeting W/Util in Bethesda,Md Re Results from Recent Tests of Steam Generator Tubes in TMI-1.Util Plans to Request Review of Proposed Change in Tube Plugging Criteria.Attendance List & Util Presentation Encl ML20215D0521986-12-0505 December 1986 Summary of 861113 Meeting W/Util & Gilbert Commonwealth,Inc at Site Re Status of Review Effort for App R Submittal.List of Attendees,Meeting Agenda & Licensee Handout Re Emergency Lighting Exemption Request Encl ML20207B0711986-10-30030 October 1986 Summary of 861027 Meeting W/Util & Eg&G Idaho Re Discussion of Selected Issues from Second 10-yr Interval Inservice Test Program Recently Approved by NRC .List of Attendees & Meeting Agenda Encl ML20210V1091986-09-30030 September 1986 Summary of 860916 Meeting W/Util & B&W Re Cycle 6 Reload Rept & Technical Approach Utilized by B&W & Util to Identify Problem Areas in Rept.List of Attendees & Meeting Handout Encl ML20210U0521986-09-30030 September 1986 Summary of 860922 Meeting W/Util Re once-through Steam Generator Tubes to Be Pulled During Cycle 6 Outage.Util Handouts & List of Attendees Encl ML20214L1851986-08-26026 August 1986 Summary of 860822 Meeting W/Util in Bethesda,Md to Discuss Deferral of Electrical Cable Tray & Conduit Support Mods Per App R.List of Attendees Encl ML20212J9241986-07-29029 July 1986 Summary of 860721 Meeting W/Util at Plant Site Re Mods to Fuel Handling Bldg Ventilation Sys.List Encl 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 ML20206B7861986-05-20020 May 1986 Summary of B&W Counterpart 860506-08 Meetings W/Resident Inspectors Re B&W Events,Problems & Reassessment Program. Senior Resident Inspector Comments Encl ML20155K1151986-05-19019 May 1986 Summary of 860515 Meeting W/Util in Bethesda,Md Re Steam Generator Repair Criteria as Described in Licensee Tech Spec Change Request 148.List of Attendees & Licensee Presentation Encl ML20197F1691986-05-0808 May 1986 Summary of Operating Reactors Events 860428 Meeting W/Listed Divs Re Chernobyl Nuclear Accident & Events at Us Reactors ML20203E8051986-04-18018 April 1986 Summary of Operating Reactors Events Meeting 86-12 on 860414 Re Events Since 860407.List of Attendees,Viewgraphs & Supporting Documentation 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 ML20154N8751986-03-12012 March 1986 Summary of Operating Reactor Events 860310 Meeting 86-07 W/Ornl Re Events Occurring Since 860303 Meeting.Followup Review Assignments,Status of Previous Assignments,List of Attendees & Viewgraphs Encl 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 ML20205J7411986-02-28028 February 1986 Summary of ACRS 310th Meeting on 860213-15 in Washington,Dc Re Review Studies Done & Procedures Proposed by Gpu Nuclear to Protect Against Inadvertent Criticality During Defueling of TMI-2 Core ML20154C9931986-02-24024 February 1986 Summary of Operating Reactors Event Meeting 86-04 on 860210.List of Attendees,Briefing & Reactor Scram Summaries Encl ML20141N3971986-02-24024 February 1986 Summary of Operating Reactors Events Meeting 86-03 on 860127.Attendees,events Discussed,Significant Elements of Events & Assignments Made Listed in Encls ML20154H5941986-02-15015 February 1986 Summary of ACRS Subcommittee on Core Performance 860129 Meeting W/Util & NRC in Washington,Dc to Review Potential for Recriticality at TMI-2 During Defueling Operations. Viewgraphs Encl 1999-08-04
[Table view] Category:MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
MONTHYEARML20211F5761999-08-26026 August 1999 Summary of 990813 Meeting with Licensee in Rockville,Md to Discuss Status & Completion Schedule of Active & Soon to Be submitted,TMI-1 Licensing Issue.List of Attendees & Meeting Handouts Encl ML20210L6541999-08-0404 August 1999 Summary of 990713 Meeting with Util in Rockville,Md Re Licensee Proposed Mods to Reactor Building Spray Sys Operation & Hpis.List of Attendees 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 ML20207B6441999-05-26026 May 1999 Summary of 990507 Meeting with Gpu Nuclear,Inc in Rockville, MD Re Status & Completion Schedule of Active & Soon to Be submitted,TMI-1 Licensing Issues.List of Attendees & Copy of Licensee Handout Used at Meeting Encl ML20154F4771998-10-0505 October 1998 Summary of 980917 Meeting W/Gpu Nuclear Inc,Amergen & NRC in Rockville,Md Re Sale & License Transfer of Three Mile Island Nuclear Genrating Station,Unit 1.List of Attendees,Copy of Licensee Handout & Copy of Meeting Transcript Encl ML20236F6671998-06-30030 June 1998 Summary of 980527 Meeting W/Util Re Control Room Habitability Evaluation Related to Control Room Operator Thyroid Dose from Fission Product Releases During Postulated Design Basis Accident at Plant Unit 1 ML20249A0561998-06-10010 June 1998 Summary of 980604 Meeting W/Gpu in TMI-1 Training Center to Discuss Status of Active & Recently Completed TMI-1 Licensing Issues ML20199J7061998-02-0202 February 1998 Summary of 971212 Meeting W/Gpu Re Control Room Habitability Evaluation Concerning CR Operator Thyroid Dose from Fission Product Release During Postulated Design Basis Accident at Plant 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 ML20217M7601997-08-21021 August 1997 Summary of 970725 Meeting W/Gpu in Rockville,Md to Discuss Licensee Plans for Inspecting SG Tubing in Upcoming Refueling Outage ML20151L8201997-08-0404 August 1997 Summary of 970715 Meeting W/Gpu Nuclear Corp in Rockville,Md Re Licensee Plans for Inspecting SG Tubing in Upcoming Refueling Outage.List of Attendees & Handouts Encl ML20148D8531997-05-28028 May 1997 Summary of 970502 Meeting W/Util to Discuss Status of Implementation Schedule for Completion of Installation of Thermo-lag at Plants.List of Attendees Encl ML20138H5581996-12-19019 December 1996 Summary of 961126 Meeting W/Util in Rockville,Md to Discuss Two Major Issues Related to SG Tube Integrity at Facility. W/List of Attendees & Viewgraphs ML20150A2351996-02-15015 February 1996 Summary of 960205 Meeting W/Gpu at TMI-1 Site to Discuss Active & Recently Completed TMI-1 Licensing Issues.List of Participants & Copy of Handouts Encl ML20149F4911994-08-0303 August 1994 Summary of 940712 Meeting W/Util at NRC Office in Rockville,Md to Discuss Results of Control Rod Drop Testing & Subsequent Control Rod Drive Mechanism Testing During Week of 940601 ML20059J3351994-01-25025 January 1994 Notification of 940202 Meeting W/R Gary in Rockville,Md to Discuss 2.206 Petition to Shut Down TMI Unit 1 ML20128P8491993-02-18018 February 1993 Summary of Operating Reactors Events Briefing 93-05 on 930210 ML20062A6511990-10-0505 October 1990 Summary of 900913 Meeting W/Util in Middletown,Pa,Re Current Licensing Issues & Insp Open Items ML20055E3181990-07-0505 July 1990 Summary of 900607 Meeting W/Gpu at TMI Site Near Middletown,Pa Re Current Licensing Issues.Attendance List Encl ML20246C3331989-06-29029 June 1989 Summary of 890614 Meeting W/Util & Commonwealth of PA in Middletown,Pa Re Status & Future Actions of All Active Licensing Issues.List of Attendees & generic/multi-plant Actions Encl ML20247K5841989-05-24024 May 1989 Summary of 890512 Meeting W/Util at Site Re Status & Future Actions of Active Licensing Issues.List of Attendees & Activities Discussed Encl ML20246F4541989-05-0202 May 1989 Summary of 890410 Meeting W/Util in Middletown,Pa Re Status & Future Actions of All Active Licensing Issues.Tmi Action Items II.K.3.31 & I.C.1 Completed Since Last Monthly Meeting & Closeout Ltrs Sent to Util on 890328 ML20235W0041989-03-0101 March 1989 Summary of 890222 Meeting Between NMSS & NRR Project Manager Re Status of Cleanup & H Thompson Concern That NRR Set Cleanup Criteria That Could Cause Problem for NRC Later on ML20235Y4221989-02-27027 February 1989 Summary of 890215 Meeting W/Util in Rockville,Md Re ATWS Implementation.List of Attendees & post-meeting Questions Encl ML20235M7051989-02-16016 February 1989 Summary of 890208 Meeting W/Bechtel & Util Re Portrayal of Bechtel & Util Auditing of Nuclear Energy Svcs in Info Notice 88-035, Inadequate Licensee Performed Vendor Audits. List of Attendees Encl ML20154F7971988-09-15015 September 1988 Summary of 880901 QA Meeting W/Util in Rockville,Md to Discuss Rev 2 of Util Operational QA Plan for Plants.Agenda & List of Participants Encl ML20207E2961988-07-28028 July 1988 Summary of 880714 Meeting W/B&W Owners Group Re Industry & NRC Actions to Resolve Issues Raised in Generic Ltr 87-12. List of Attendees,Viewgraphs & B&W Design Differences Encl ML20148S3821988-03-31031 March 1988 Summary of Operating Reactors Events Meeting 88-13 on 880329.List of Attendees,Discussion of Events & Summary of Reactor Scrams Encl ML20147J1081988-02-26026 February 1988 Summary of 880218 Meeting W/Gpu in Rockville,Md to Discuss Matters Pertaining to 7R Refueling Outage Planned to Commence on 880617.Attendance List & Viewgraphs Encl ML20238A9911987-08-27027 August 1987 Summary of 870824 Meeting W/Util in Bethesda,Md Re 870728 Proposed License Amend,Revising Radiological Effluents Tech Specs ML20237K6461987-08-0606 August 1987 Summary of 870619 Meeting W/Util in King of Prussia,Pa Re Changes to Util Emergency Plan for Plants Based on Changing Plant Status & Reclassification to Post Defueling Monitored Storage ML20214W9971987-06-10010 June 1987 Summary of 870521 Meeting W/Util in Bethesda,Md Re Results from Recent Tests of Steam Generator Tubes in TMI-1.Util Plans to Request Review of Proposed Change in Tube Plugging Criteria.Attendance List & Util Presentation Encl ML20215D0521986-12-0505 December 1986 Summary of 861113 Meeting W/Util & Gilbert Commonwealth,Inc at Site Re Status of Review Effort for App R Submittal.List of Attendees,Meeting Agenda & Licensee Handout Re Emergency Lighting Exemption Request Encl ML20207B0711986-10-30030 October 1986 Summary of 861027 Meeting W/Util & Eg&G Idaho Re Discussion of Selected Issues from Second 10-yr Interval Inservice Test Program Recently Approved by NRC .List of Attendees & Meeting Agenda Encl ML20210V1091986-09-30030 September 1986 Summary of 860916 Meeting W/Util & B&W Re Cycle 6 Reload Rept & Technical Approach Utilized by B&W & Util to Identify Problem Areas in Rept.List of Attendees & Meeting Handout Encl ML20210U0521986-09-30030 September 1986 Summary of 860922 Meeting W/Util Re once-through Steam Generator Tubes to Be Pulled During Cycle 6 Outage.Util Handouts & List of Attendees Encl ML20214L1851986-08-26026 August 1986 Summary of 860822 Meeting W/Util in Bethesda,Md to Discuss Deferral of Electrical Cable Tray & Conduit Support Mods Per App R.List of Attendees Encl ML20212J9241986-07-29029 July 1986 Summary of 860721 Meeting W/Util at Plant Site Re Mods to Fuel Handling Bldg Ventilation Sys.List Encl 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 ML20206B7861986-05-20020 May 1986 Summary of B&W Counterpart 860506-08 Meetings W/Resident Inspectors Re B&W Events,Problems & Reassessment Program. Senior Resident Inspector Comments Encl ML20155K1151986-05-19019 May 1986 Summary of 860515 Meeting W/Util in Bethesda,Md Re Steam Generator Repair Criteria as Described in Licensee Tech Spec Change Request 148.List of Attendees & Licensee Presentation Encl ML20197F1691986-05-0808 May 1986 Summary of Operating Reactors Events 860428 Meeting W/Listed Divs Re Chernobyl Nuclear Accident & Events at Us Reactors ML20203E8051986-04-18018 April 1986 Summary of Operating Reactors Events Meeting 86-12 on 860414 Re Events Since 860407.List of Attendees,Viewgraphs & Supporting Documentation 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 ML20154N8751986-03-12012 March 1986 Summary of Operating Reactor Events 860310 Meeting 86-07 W/Ornl Re Events Occurring Since 860303 Meeting.Followup Review Assignments,Status of Previous Assignments,List of Attendees & Viewgraphs Encl ML20205J7411986-02-28028 February 1986 Summary of ACRS 310th Meeting on 860213-15 in Washington,Dc Re Review Studies Done & Procedures Proposed by Gpu Nuclear to Protect Against Inadvertent Criticality During Defueling of TMI-2 Core ML20154C9931986-02-24024 February 1986 Summary of Operating Reactors Event Meeting 86-04 on 860210.List of Attendees,Briefing & Reactor Scram Summaries Encl ML20141N3971986-02-24024 February 1986 Summary of Operating Reactors Events Meeting 86-03 on 860127.Attendees,events Discussed,Significant Elements of Events & Assignments Made Listed in Encls ML20154H5941986-02-15015 February 1986 Summary of ACRS Subcommittee on Core Performance 860129 Meeting W/Util & NRC in Washington,Dc to Review Potential for Recriticality at TMI-2 During Defueling Operations. Viewgraphs Encl 1999-08-04
[Table view] |
Text
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[ , g ?g UNITED STATES
< E NUCLEAR REGULATORY COMMISSION 3' 4E WASHINGTON, D.C. 205S5 0001
/ August 3, 1994 Docket No. 50-289 LICENSEE: GPU Nuclear Corporation FACILITY: Three Mile Island Nuclear Station, Unit 1 (TMI-1)
SUBJECT:
SUMMARY
OF JULY 12, 1994, MEETING WITH GPU NUCLEAR CORPORATION REGARDING CONTROL R0D DROP TIME ISSUES AT THREE MILE ISLAND NUCLEAR STATION, UNIT 1 (TMI-1)(TAC N0. M89494)
On Tuesday, July 12, 1994, a public meeting was held at the U.S. Nuclear Regulatory Commission (NRC) offices located at One White Flint North, Rockville, Maryland with GPU Nuclear Corporation (GPUN), the licensee for TMI-1. The purpose of the meeting was to discuss results of the control rod drop testing and subsequent control rod drive mechanism (CRDM) testing during the week of June 1, 1994. Enclosure 1 is the list of participants at the meeting. Enclosure 2 is a copy of the handouts used during the meeting.
The first time that control rod drop times exceeded the Technical Specification (TS) limit of 1.66 seconds was October 1993, at the conclusion of the 10R refueling outage. At that time three rods exceeded the requirement and were brought back within the TS requirement by additional testing. During a scheduled outage in March 1994, surveillance testing indicated that 12 of 61 rods exceeded the TS requirement. All rods were again brought below the TS requirement by additional testing. However, following a meeting with GPUN on March 25, 1994, the staff issued a confirmatory action letter (CAL) to GPUN on March 29, 1994, requiring GPUN to establish a program of per, iodic control rod monitoring, development of evaluation criteria, a contingency plan, and a long term plan for corrective action.
THI-l was shut down on June 1, 1994, to conduct rod drop time testing. On that date, three control rods were determined to exceed the time required by the TS. GPUN removed those three CRDMs plus one other for inspection and replacement of the CRDM thermal barriers. Enclosure 2 summarizes the results of the testing and inspections. GPUN confirmed that the root cause of the lengthened control rod drop times is deposition of crud in the thermal barrier of the CRDMs. GPUN restated that the crud buildup has probably been aggravated by operating at a lower reactor coolant system (RCS) pH than normal as a result of higher boric acid concentrations required for the extended-life cores. Corrective action proposed in a March 26, 1994, letter from GPUN, and repeated in the staff's CAL, consists primarily of raising pH and lithium hydroxide levels in the RCS, and exercising control rods through 10% of their total travel on a biweekly basis. GPUN expects that these actions will result in an improvement in rod drop time. The drop times of the refurbished CRDMs were determined to be satisfactory by testing following refurbishment. p GPUN was advised in a meeting on May 3, 1994, that the staff would consider a temporary revision to the TS limit if it could ba justified by GPUN from a ( :
safety standpoint and GPUN was encouraged to submit a TS change request as j
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GPU Nuclear Corporation August 3, 1994 soon as possible so that the request could be noticed in the Federal Reaister.
Subsequently, GPUN submitted Technical Specification Change Request No. 244 on May 20, 1994, to temporarily raise the TS drop time requirement to 2.11 seconds for eight control rods. The licensee's submittal provided analysis that concluded a 3.0 second drop time for all 61 control rods would still provide adequate protection for the core in the event of an accident requiring an automatic reactor trip. The staff concluded during the July 12 meeting, however, that adequate need for a TS change had not been provided and stated that a license amendment would not be forthcoming.
GPUN discussed their plans for the remainder of the current operating cycle and tnetative plansfor additional CRDM refurbishment during the 10R refueling outage in September 1995 (see Enclosure 2). As stated in the March 1994 CAL, GPUN will submit a long-range CRDM plan to the NRC in September 1994.
This summary replaces the summary of the same meeting issued on July 14, 1994.
Original signed Ly:
Ronald W. Hernan, Senior Project Manager Project Directorate 1-4 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Enclosures:
- 1. List of Attendees
- 2. GPUN meeting handout cc w/ enclosures:
See next page Distribution w/ enclosures 1 & 2: w/ enclosure 1:
Docket File WRussell/FMiraglia MRubin NRC & Local PDRs RZimmerman LPhillips PDI-4 Memo SVarga HRichings RHernan JCalvo MVirgilio JRogge, R1 JStolz RJones OGC EJordan SNorris ACRS (10)
WDean OFFICE LA:PDI-4 PM:PDI-4 ,
A: PQl-A //_
hAME S r RHernan:cn[gkdoY[
DATE $/j/g4 h/,3/g4 [ / /94 / / / /
OFFICIAL RECORD COPY Document Name: G:\HERNAN\7-12-94. sum
1
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Three Mile Island Nuclear Station, Unit I cc w/ enclosures:
Michael Ross Michele G. Evans O&M Director, TMI-l Senior Resident Inspector (THI-1)
GPU Nuclear Corporation U.S. Nuclear Regulatory Commission Post Office Box 480 Post Office Box 311 Middletown, Pennsylvania 17057 Middletown, Pennsylvania 17057 ,
John Fornicola Regional Administrator, Region I Director, Licensing & Reg. Affairs U.S. Nuclear Regulatory Commission GPU Nuclear Corporation 475 Allendale Road i
~
100 Interpace Parkway King of Prussia, Pennsylvania 19406 Parsippany, New Jersey 07054 Robert B. Borsum Jack S. Wetmore B&W. Nuclear Technologies TMI Licensing Manager Suite 525 GPU Nuclear Corporation 1700 Rockville Pike ;
Post Office Box 480 Rockville, Maryland 20852 Middletown, Pennsylvania 17057 !
Ernest L. Blake, Jr., Esquire William Dornsife, Acting Director Shaw, Pittman, Potts & Trowbridge Bureau of Radiation Protection 2300 N Street, NW. Pennsylvania Department of ,
Washington, DC 20037 Environmental Resources Post Office Box 2063 .
Chairman Harrisburg, Pennsylvania 17120 .
Board of County Commissioners of Dauphin County Mr. T. Gary Broughton, Vice President ,
and Director - THI-1 Dauphin County Courthouse Harrisburg, Pennsylvania 17120 GPU Nuclear Corporation Post Office Box 480 Chairman Middletown, Pennsylvania 17057 Board of Supervisors of Londonderry Township !
R.D. #1, Geyers Church Road ,
Middletown, Pennsylvania 17057
-- - --,,._y--.i.
, ENCLOSURE 1 l
l LIST OF ATTENDEES ,
JULY 12, 1994 MEETING WITH GPU NUCLEAR CORPORATION REGARDING CRD RETEST PLAN TITLE AFFILIATION TITLE i Ronald W. Hernan NRC/NRR/PDI-4 Senior Project Manager Larry Phillips NRC/NRR/SRXB Section Leader Howard Richings NRC/NRR/SRXB Senior Reviewer John Stolz NRC/NRR/PDI-4 Project Directorate
- Robert Jones NRC/NRR/DSSA Acting Deputy Director, DSSA
]
Lew Miller NRC OEDO Michele Evans NRC TMI SRI Jacque Durr NRC, Region I DRP, Chief, Branch 4 l
Michael Ross GPUN O&M Director, TMI l
'l T. Gary Broughton GPUN VP and TMI Director l
Pat Walsh GPUN Manager, Plant Engineering Charles Hartman GPUN Manager, Electrical Engrg John Link GPUN Nuclear Analysis !
Jack S. Wetmore GPUN Manager, Licensing W. M. Drendall GPUN Tech Functions B. Connor GPUN Matl. Engrg., Parsippany Robert Borsum B&W Nuc. Technology Manager Stan Maingi Pennsylvania BRP L
O Enclosure 2 ;
J GPUN-NRC MEETING ACENDA JULY 12, 1994 CONTROL ROD DROP TIMES I. CONTROL ROD DROP TIME TESTING ~ JUNE 1,1994 RESULTS ,
l II. RESULTS OF THE FIELD INSPECTION OF THE FOUR CRDMS :
AND REMOVED THERMAL BARRIERS o
.a .
l III. PLANS "
l A. REMAINDER OF CYCLE 10 l B. LONGER TERM PLANS
- e. . ar ..
IV. DISCUSSION 0F TSCR FOR INCREASED ALLOWED DROP TIME
+- *;*:*'
l l
l
SUMMARY
OF JUNE 1, 1994 DROP TIME TESTING TESTED ALL 61 RODS .;
... . . . i THREE RODS EXCEEDED TECH SPECS AT L-14, GROUP 1, ROD 3 (2.07 SEC)
AT M-9, GROUP 4, ROD 5 (2.0 HSE.Cb ..
.F : - i'. ; -;-
AT P-8, GROUP 6, ROD 5,"T2.20 SEC)).c; l
i
As Found Time for 49 ' Good' Rods 1.60
~
9 e
c y1.50 s
4 a>
.E H
n '
o w
1.40 A
1.2L63 a; -
~~ _ 1,237 43 0 co k .. < ,-
1.2o5 '
< 1.30 -
/
L.251 1.152 1.151 1.15f
-di
_,,________ap-_______3,____
6R 7R 8R 9R 10R 10 U2 10 P3
Group Average Drop Times - As Found Gp1 9 1.80 -
Gn2 ,
- . 6 _.- ,
Gp3 '
- p' ,'
/
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n \ ,,
N Gg4 '
/ / ' ~s i
S 1.60 -
\ 's G G /. ,'
~3~5 ~
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\ ',
G6 E
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/
m - N,.
- , ~
/ / 9 F
u Gp7 -
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s I.40 -
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- L3 -n
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1.20 We b
e, e
e 6R 7R 8R 9R^ 10 R 10 U2 10 P3
l l
THERMAL BARRIER REPLACEMENT EFFECT ON DROP TIME t
GROUP - TIME TIME TIME NO. OF AS LEFT ROD 10R MARCH JUNE STUCK TIME COR LOC (SEC) (SEC) (SEC) BALLS (SEC)
GP 3 Ro 6 1.72 2.31 l'.'41 4~ l'.328 M3 GP 1 Ro 3 1.83 2.53 2.07 3* 1.312 L 14 GP 4 Ro 5 1.81 2.49 2.01 ""
4 '
1.320
_M 9 j GP 6 Ro 5 .l.43 2.42 2 .20. ,, . 9,33 < . 1.296 i P8 1
- THE FOURTH BALL WAS INITIALLY STUCK BUT. UNSEATED WITH A i FORCE OF APPROXIMATELY ONE POUND.
d
l CHEMISTRY CONTROL DURING JUNE SHUTDOWN AND RESTART l
e PLACED RCS ON CLEANUP TO REDUCE " CRUD" LEVELS TO LESS THAN 0.1 PPM AS AN ADDITIONAL EFFORT PRIOR TO FILLING AND VCNTING CRDMs TO REDUCE PARTICULATE CRUD. I i
1 e INSURED FILL WATER CONTAINED'<0.1 PPM " CRUD" PRIOR TO ADDING TO RCS." THIS CONTINUED A NORMAL .
EFFORT TO REDUCE PARTICULATE CRUD.
l 1
e INCREASED LITHIUM CONCENTRATION TO APPROX. 3.6 PPM PRIOR TO FILL OF RCS AND MAINTAINED LITHIUM HIGH (APPROX; 2.4 PPM)nTHROUGHOUT-THE SUBSEQUENT
. VENTING AND HEATUP.- 1 m +
1 l
o . .
l e DECREASED LITHIUM'SLIGHTLY AS-WE DE80 RATED TO GO ,
CRITICAL-AND PROCEEDED TO 100% POWER OPERATION.
MAINTAINED LITHIUM TO MAINTAIN HOT PH OF 15.9 i
l l
. I i
l
s-_.- _. -- -a,. .ua u- = -- ,=- -.u,- -~ e.- > x-- - - -.-~ -.-
+=
0 4
Y CONCLUSIONS PHYSICAL EVIDENCE OBTAINED DURING INSPECTION i SUPPORTS OUR UNDERSTANDING OF THE CAUSE OF THE SLOW ROD DROP TIMES TO BE CRUD IN THE THERMAL BARRIER CHECK VALVES AND BUSHINGS.
IMPROVEMENT FOUND IN THE AS FOUND DROP TIMES DEMONSTRATES THAT OUR CORRECTIVE ACTIONS WERE EFFECTIVE.
i t
4
-._ _ _ __ _ _ _ __ __ _ . . -- - _ - --- - , .. - . . . _ . . . _ _ , , . . . - s._-. - , ,_, , , , r- , _y- , -----
1 Nuclear TMI CHEMISTRY CONTROL FOR REMAINDER OF CYCLE 10 LITHlUM CONCEN.TRATION AS A RSCTION & BORON CONCENTRATION 4
3.5 N \ .
4 Current f3 3, m - x\ s_ '
M N , ,
, W40% %%WN/4 x s
\ Y -
3 i.,
6 \ s b\
\
i x ~ 3k N \ %
0 1000 1400 i 1230 1000 800 000 400 330 0 1800 1300 190 0 900 700 500 300 10 0 N ppm Current Data:
Boron = 1270 ppm Lithium = 2.2 ppm pH - 6.94
l $
PLANS FOR THE REMAINDER OF CYCLE 10 MAINTAIN LITHIUM /PH CONTROLS.
CONTINUE BI-WEEKLY ENHANCED ROD EXERCISING TO MAINTAIN CLEARANCES BETWEEN THE LEAD SCREW AND THERMAL BARRIER BUSHING.
MONITOR DROP TIMES IN THE EVENT OF A REACTOR TRIP PERFORM DROP TIME TESTING AT THE NEXT UNPLANNED SHUTDOWN.
PERFORM DROP TIME TESTING PRIOR TO ENTRY INTO 11R REFINE OUTAGE PLANS. .
LONGER TERM PLANS e
LONG TERM PLANS ARE INTENDED TO RETURN ALL CRDM'S TO A CONDITION THAT PROVIDES ASSURANCE THAT CONTINUED OPERATION IS WITHIN EQUIPMENT DESIGN.
e BWOG WORK IN PROGRESS e
ALTERNATE DESIGNS AND CHEMICAL CLEANING OPTIONS WITH A REPORT EXPECTED IN AUGUST.
i l
o GPUN WORK / PLANS e SUBMIT A LONG TERM PLAN IN SEPTEMBER 1994.
e PREPARED TO REPLACE 12 THERMAL BARRIERS IN 11R BASED ON o ROD DROP TIME HISTORY 1
e GASKET LEAKAGE AND PREVIOUS GASKET-WORK e ALTERNATE WORK MAY INCLUDE CHEMICAL CLEANING INSTEAD OF BARRIER REPLACEMENT. '
e OUTAGE PLAN MAY BE MODIFIED BY PRE-0UTAGE DROP l TESTING. l e
FUTURE REPLACEMENTS / REPAIRS WILL BE DETERMINED AFTER 11R.
TECH SPEC CHANGE REQUEST 244 e SUBMITTED MAY 20, 1994 e FR NOTICE COMMENT PERIOD EXPIRES JULY 13, 1994 i e WOULD INCREASE ALLOWED DROP TIME FOR 12 SELECTED RODS FROM 1.66 SECONDS TO 2.11 SECONDS e SAFETY ANALYSIS PERFORMED FOR ALL 61 RODS AT 3.0 SECONDS (WITH REDUCED OVERPOWER SETPOINT AT LOW POWER LEVELS) e REASON FOR REQUEST l
e POTENTIAL THAT SOME RODS COULD EXCEED CURRENT ;
TECH. SPEC. LIMIT BEFORE END OF CYCLE
\
o LICENSE SHOULD REFLECT THIS SITUATION AS AN ANALYZED CONDITION TO ALLEVIATE FUTURE TECH.
SPEC. VIOLATIONS l l
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t j