|
|---|
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
,,
l
- o 8[ g n NUCLEAR REGULATORY COMMISSION UNITED STATES WASHINGTON, D. C. 20555
. h
%h*****j/ hebruary 27, 1989 Docket No. 50-289 LICENSEE: GPU Nuclear Corporation FACILITY: Three Mile Island Unit 1 (TMI-1)
SUBJECT:
SUMMARY
OF FEBRUARY 15, 1989 MEETING WITH GPU NUCLEAR ON ATWS IMPLEMENTATION.
The NRC staff met with representatives of GPU Nuclear (GPUN) Corporation in Rockville, Maryland on February 15, 1989 to discuss technical issues associated with the design and installation of new systems intended to comply with the requirements of the ATWS Rule (10 CFR 50.62). Enclosure 1 is a list of attendees.
GPUN presented discussions of three technical issues in response to the staff's letter of January 3, 1989. The letter forwarded the staff's review comments on the TMI-I plant-specific preliminary design submitted on November 18, 1988. GPUN plans to submit a letter to the staff in the near future to outline the schedule and approach to ATWS implementation and to address the ',
issues discussed below. ,
'A GPUN stated that a decision has been made to provide a separate and '
independent power supply for the DSS and AMSAC logic and actuation circuits to make the design acceptable to the NRC. Therefore, Option 1 as presented in the September 7, 1988 NRC letter to the B8H Owners Group will be incorporated into the TMI-1 design.
The second issue discussed deals with the number of control rod groups required to be inserted by the ATWS mitigation system (DSS). The B&W Owners Group generic position was that only rod groups 5 through 7 needed to be inserted to achieve hot, zero-power shutdown conditions. However, because THI-1 is in a transition period to longer lived cores using more highly enriched fuel, GPUN has concluded that to assure hot, zero power conditions following a hypothesized ATWS event for all future (more reactive) core configurations all rod groups must be inserted by the DSS. GPUN reviewed the proposed circuit modifications to achieve release of all rod groups. The proposal seemed reasonable to the staff. GPUN agreed to address any concerns involving diversity in their submittal. Following the meeting, the staff further discussed this modification amongst itself and developed three questions that should be addressed in GPUN's near-term or interim submittal.
These questions are enclosed as Enclosure 2.
The third issue was the manner in which loss of main feedwater flow will be detected by the new ATWS modifications. The staff's January 3,1989 letter expressed concern that, since the initiating signal would be main feedwater pump control oil pressure, the possibility exists that a loss of feedwater flow not attributable to the pumps tripping could occur but would not be sensed by the AMSAC circuitry. To ameliorate this concern, GPUN proposed to provide additional written justification of the low probability of events other than MFW pump trip causing loss of MFW flow. As an additional measure, s90314o123 890227 PDR p
ADOCK 05000289 PDC fh!((
4 if. necessary, GPUN would consider addition of a steam generator low level-trip signal to the AMSAC which would trip the main turbine. The staff indicated that this seemed to be a reasonable approach.
The staff expressed concern that detailed engineering.for the ATWS Rule implementation. and modifications was not yet underway. It was noted that some B&W plants have essentially completed detailed engineering work on these
- modifications and have already submitted the final design to the NRC for approval. The staff plans to further discuss implementation schedules at a higher level.of management during future meetings, original signed by Ronald W. Hernan, Senior Project Manager Project Directorate I-4 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation Enclosure As Stated cc w/ enclosure:
See next page LA:PDI-4 PM:PDI-4 k P .-
SN W' RHernan:cb JSto 02/3/89 02/;/89 02Cf89 L____________ _ . _ _ _ _ _ _ . _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
Mr. Henry D. Hukill Three Mile Island Nuclear Station, GPU Nuclear Corporation Unit No. I cc:
G. Broughton Francis I. Young O&M Director, THI-1 Senior Resident Inspector (TMI-1)
GPU Nuclear Corporation U.S.N.R.C.
Post Office Box 480 Post Office Box 311
' Middletown, Pennsylvania 17057 Middletown, Pennsylvania 17057 Ricnard J. McGoey.
Manager, PWR Licensing Regional Administrator, Region I GPU Nuclear Corporation U.S. Nuclear Regulatory Commission 100 Interpace Parkway 475 Allendale Road Parsippany, New Jersey 70754 King of Prussia, Pennsylvania 19406-C. W. Smyth Robert B. Borsum THI-1 Licensing Manager Babcock & Wilcox GPU Nuclear Corporation Nuclear Power Generation Division-Port Office Box 480 Suite 525 Middletown, Pennsylvania 17057 1700 Rockville Pike Rockville, Maryland 20852 Ernest L. Blake, Jr., Esq. Governor's Office of State Planning Shaw, Pittman, Potts & Trowbridge and Development 2300 N Street, N.W. ATTN: Coordinator, Pennsylvania Washington, D.C. 20037 State Clearinghouse Post Office Box 1323 Harrisburg, Pennsylvania 17120 Sally S. Klein, Chairman Thomas M. Gerusky, Director Dauphin County Commissioner Bureau of Radiation Protection Dauphin County Courthouse Pennsylvania Department of Front and Market Streets Environmental Resources Harrisburg, Pennsylvania 17120 Post Office Box 2063 Harrisburg, Pennsylvania 17120 Kenneth E. Witmer, Chairman Board of Supervisors of Londonderry Township 25 Roslyn Road l Eilzabethtown, PA 17022 l
i i
-4 ENCLOSURE 1 ATTENDANCE LIST MEETING WITH GPU NUCLEAR ON ATWS IMPLEMENTATION NAME AFFILIATION TITLE RTE! Hernan NRC/NRR/PDI-4 Fr53!Mgr.
V.D. Thomas NRC/NRR/ DEST I&C Eng.
J.L. Mauck NRC/NRR/ DEST Section Chief G.M. Gurican GPUN - Licensing Sr. Engr.
- W.M. Drendall GPUN - 18C Sr. Engr.
J.R. Delockery GPUN - Projects Sr. Engr.
B.L.. Collins INEL/EG8G Idaho Engr. Spec. .
M.D. Lynch NRC/NRR/PDIII-3 Lead PM.
L.E. Kokasko NRC/NRR/PDIII-3 P. Engr.
l -
l l
~
. ENCLOSURE 2 Post-Meeting Questions on TMI-1 ATWS Systems
- 1. Provide information regarding the physical and operating characteristics of the Westinghouse circuit breakers being considered for use in the revised ATWS/ DSS design and the existing General Electric circuit breakers that are currently used to interrupt power to the CRDs at TMI-1. Include in this discussion information regarding the differences of the devices used to trip the circuit breakers and the type and voltage level that is used to operate these tripping devices.
- 2. Provide information on the history that TMI-I has experienced while operating the Westinghouse and General Electric circuit breakers in question. Include in this discussion information related to the preventive maintenance program that is being used to maintain these circuit breakers.
- 3. Provide general information on the cost and man power requirements if enother method of interrupting power to control rods is considered. Use the Davis Besse (All SCRs) reactor trip design or consider the use of a heavy duty line contactor as possible other design concepts to interrupt power.
l 1
u_ _ _ _ _ _ _ _ - - - - - - - - - - - - . - - - - - - _ - - - _ - - - - - - - - - - - - - - - - - - - - - _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
DISTRIBUTION tm Docket filei
- ~ NRC & Local PDRs SVarga BBoger JStolz Plant File AThadani SNewberry OGC-WF.
EJordan BGrimes ACRS(10)
HBClayton (RI)
LBettenhausen(RI)
NRC
Participants:
VThomas MDLynch JMauck LKokasko oql i \
4 t
. . . . . . _ .
