|
|---|
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
.
'## ~go UNITED STATES 8 o NUCLEAR REGULATORY COMMISSION
,1 WASHINGTON, D. C. 20656
- February 26, 1988 Docket No. 50-289 LICENSEE: GPU Nuclear Corporation FACILITY: Three Mile Island Unit 1
SUBJECT:
SUMMARY
OF FEBRUARY 18, 1088 MEETING WITH GPU NUCLEAR TO DISCUSS MATTERS RELATED TO THE 1988 REFUELING OUTAGE (7R)
The NRC staff met with representatives of GPU Nuclear on February 18, 1988 in Rockville, Maryland (One White Flint North) to discuss matters pertainino to the 7R refueling outage planned to comence on June 17, 1988. The meeting provided a forum for the licensee to discuss key aspects of the license amend-ment request to be submitted to the NRC on April 1, 1988 in support of the refueling outage and to allow the staff to identify any areas where particular information will be required for the staff to conduct its review of the amendment request.
The amendment request will include NRC approval to raise the rated power level from E 535 MWt to 2,568 MWt, a 1.3% increase in power output. The licensee pointed out that most of the safety analyses used to initially license TMI-1 were perfomed on the basis of a 2,568 MWt power level assumption so that operation at this power level is already Bounded by existing analyses. A systematic review of all implications of the higher power rating has been undertaken as outlined in Enclosure 2.
The licensee discussed TMI-1 fluence reduction program and materials surveillance progran and stated that new calculaHons using the recently issued Regulatory Guide 1.99, Revision 2 may indicate an even higher PTS margin than previous calculations yielded. Details of this topic are shown in Enclosure 2.
Commensurate with longer fuel cycles in the future, THI-1 will start loading new fuel with higher enrichment values (up to 3.63 weight percent U-235 for l cycle 7). To support the intent to use more highly enriched fuel, the i licensee has applied for an amendment request to raise the storage enrichment limits frem 3.5 to 4.3 weight percent. The staff is presently reviewing this ]
request and expects to issue an anendment before May 1, 1988.
The licensee discussed changes that will be required to the technical specifi- J cat'ons to support ster +up from this refueling nutage and requested issuance ;
of the required :niendment by July 1, 1988. Rased on the information presented !
at this meeting, the staff does not anticipate any significant technical or schedular difficulties in reviewing the amendment requests needed to support Cycle 7 of operation, l
8803090170 080226 PDR ADOCK 05000209 i P pog 1
4 The licensee questioned how the ACRS would become involved, if at all, in the request to raise the rated power level. The staff noted that ACPS will be given a copy of the incoming amendment request and the staff's safety evalua-tion thereof. ACRS will then decide if they want to review these documents on a formal basis. The staff does not foresee ACRS review of these documents as delaying issuance of the amendments required for restart.
Enclosure 1 is a list of attendees at this meeting. Enclosure 2 is a copy of the visual aids used by the licensee during the meeting.
i 4M < M ' k %h Ronald W. Hernan, Senior Project Manaaer Project Directorate I-4 Division of Reactor Projects I/II
Enclosures:
As stated cc w/ attachments:
See next page i
LA:PDI-47 PM:PDI-4 of D:PDI-SNorris N PHernan:bd .1Stol 02/)b/C 02/10/88 02/1( 8 l
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h Mr . Henry D. Hukill GPU Nuclear Corporation Three Mile Island Nuclear Station,
==
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G. Broughton Richard Conte r 0&M Director, TMI-1 Senior Resident Inspector (TM1-1)
GPU Nuclear Corporation U.S.N.R.C.
Post Office Box 480 Post Office Box 311 Middletown, Pennsylvania
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17057 Middletown, Pennsylvania 17057 Richard J. McGoey Manager, PWR Licensing Regional Administrator, Region I GPU Nuclear Corporation U.S. Nuclear Regulatory Comission 1 100 Interpace Parkway 4 -
475 Allendale Road ^ --
Parsippany, New Jersey 70754 King of Prussia, Pennsylvania 19406 h EFir- 25 i C. W. Smyth Robert B. Borsum EE0 MIN N N 5
,i TMI-1 Licensing Manager
. GPU Nuclear Corporation Babcock & Wilcox Nuclear Power Generation Division
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Shaw, Pittman, Potts & Trowbridge Governor's Office of State Planning and Development
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U.S. Nuclear Regulatory Comission H RFD!1 - Geyers Church Road Washington, D.C. T
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TMI-1 CYCLE 7 REL0AD REPORT GPUN/NRC MEETING FEBRUARY 18, 1988 AGENDA I. INTRODUCTION A. MEETING PURPOSE B. STATUS OF CYCLE 6 C. SCHEDULE FOR CYCLE 7 0UTAGE D. STATUS OF CYCLE 7 RELOAD REPORT II. RELOAD DESIGN A. 18-MONTH CYCLE B. CYCLE DESIGN C. PTS / FLUENCE REDUCTION ,
III. DIFFERENCES FROM TMI-1 CYCLE 6 A. RATED POWER UPGRADE TO 2568 MWT B. ENRICHMENT INCREASE TO 3.63 WT %
C. ZIRCALOY INTERMEDIATE GRIDS D. FUEL R0D PREPRESSURE REDUCTION E. FLECSET APPLICATION F. CONSERVATIVE DOSE EVALUATION G. TECHNICAL SPECIFICATION CURVES 8
CORE PROTECTION SAFETY LIMIT / BASES S
VARIABLE LOW PRESSURE SETP0 INT REMOVAL 0 POWER-DEPENDENT TILT LIMIT 4 ERROR ADJUSTED CURVES H. STARTUP PROGRAM IV. GPUN
SUMMARY
V. DISCUSSION
I. INTRODUCTION A. MEETING PURPOSE 4 CYCLE 7 RELOAD BRIEFING G PRESUBMITTAL DISCUSSION B. CYCLE 6 STATUS 0 100% FP OPERATION 0 CURRENT PLANNED MINI-0UTAGE (~ 4 DAYS)
O CORE AT 302 EFPD 0 EXPECTED SHUTDOWN 6/17/88 0 ABOUT 425 EFPD C. CYCLE 7 0UTAGE SCHEDULED 0 START JUNE 17TH 0 END ABOUT AUGUST 20TH 0 DURATION ~2 MONTHS S
APPROVED TECH SPEC AMENDMENT: JULY 1sT D. STATUS OF CYCLE 7 RELOAD REPORT 6 FINAL RR TO GPUN: MARCH 8TH t TSCR TO NRC: APRIL 1sT i e
i l
1 i
. . . . _ . _ _ _ _ _ _ . _ - . _ . _ . _ . , _ _ _ . . . . _ _ , , _ _ _ . _ _ _ _ _ _ _ _ . . . _ _ _ . _ . _ _ _ . - . ~ , . - . . _ , -
II. RELOAD DESIGN A. 18 MONTH CYCLE 9 LOW LEAKAGE DESIGN 8 445 +/- 15 EFPD 0 76 FRESH FUEL ASSEMBLIES B. CYCLE DESIGN 0 CORE MAP (FIGURES 3-1,3-2) e CONTROL R0D MAP (FIGURE 3-3) e BPRA MAP (FIGURE 3-4) l 4
,e , . , -, - - - - - - , , - - - - ,,---,-.-_-,-,,-----._,--.---,,n - . . - , , , , , -,,-,,------,---_-.,,,,-----,,,,,we e--,,w-- -- - , , - -
, ct anm,eiwai im, un m es n 1
it ,i ti at it OL s s 4 8 5 9 t 3 I l
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210 010 is n to y a a u a a its s (10 i t0 s te i td d
a x m x u x m x a Ed J Ile A 01g # De J 94 4 013 0
w x : x u x u x u x w 90 4 iM A 213 d 81 4 93 A 90 J 010 m x w w a w a w a w w x a '
A tlk A 18 4 913 A E3 A tit A 3e d x u n a w a w a w a w u x it to d su A 93 4 60 A 11s J !!N d 210 6e 3
a m x a w w w a w w w a x a m -
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m x u n a w m a a w a w u x m Ett (10 J SN d 39 4 64 d to J tlM J C3 11 g
'- s4 u x a w a a u u a w a x u u LA i its A 99 d 90 i tlN 4 11l 4 14 d 64 g a x u w a w a m a w a w u x a
, 40 93 J N d 51 J id A Otu A 110 4 213 60 g a m x a w w w a w w w a x e a s 910 A D e 91N 4 h i G4 s 30 i x u w a w a w a w a w u x 3 s3 s a i tu 4 m d = e su d on a m x w w a w a w a w w x e m A ste A otv e w d w d til 3
w x u x u x u x u x w til A ttu J tt3 4 tu d El g a x a x u x x x a n .On av n n ,
a a u a a i
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l alm 3 I-IW1'aoj tueabef 0 6utpeol aao) I-t aan5)3
~ ~ ~ '~ ~
Figure 3-2. Enrichment and Burnup Distribution for TMI-1 Cycle 7 8 9 to 11 12 13 14 ~15 2.85 2.95 2.85 2.85 2.85 3.63 2.85 2.85 17,558 0 13,331 0 16,507 0 15,735 17,554 2.85 2.85 2.85 2.85 2.85 3.63 2.85 K
16,000 0 11,292 0 16,347 0 16,344 2.95 2.85 2.85 3.63 2.85 2.85 L
16,817 0 16,236 0 12,711 16,695 2.85 2.85 2.85 3.63 M
13,329 0 13,746 0 2.95 3.63 2.85 16.451 0 16.035 2.95 ..
0 16,788 P
R X.XX Inttial enrichment XX,XXX BOC burnup, HWd/mtU
p -
/
/ Figure 3-3. Control Rod Locations and Group Designations for TMI-1 Cycle 7
-)
Canal A
B 1 6 1 C 3 5 5 3 D 7 8 7 8 7 E 3 5 4 4 5 3 F 1 8 6 2 6 8 1 G 5 4 2 2 4 5
-Y H W- 6 7 2 4 2 7 6 5 4 2 2 4 5 K
L 1 3 6 2 6 8 1 M , 3 5 4 4 5 3 N l 7 8 7 8 7 !
0 3 5 5 3 l l
P l l 1 6 1 R l l
Z 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 X Group Number Group No. of Rods Function 1 8 Safety .
2 8 Safety l 3 8 Safety l 4 9 Safety (
5 12 Control 6 8 Control 7 8 Control i 8 8 APSRs
/
/
Figure 3-4. L8P Enrichment and Distribution for TMI-1 Cycle 7 8 9 10 11 12 13 14 ~15 H 1.000 1.000 1.312 X
1.000 0.800 0.500 0.200 L
0.800 0.300 1.312 M 1.000 0.800 0.200 N 0.500 0.200 0.200 0 1.312 1.312 0.200 I
P 0.200 A '
No. of Concentration.
BPRAs wt% B4C 12 1.312 X.XXX 8 1.000 LBP Concentration 16 0.800 (wt% B4 C in A123 0) 8 0.500 2 0.200 Total 68 3-5
II. RELOAD DESIGN (CONT'D)
C. PTS FLUENCE REDUCTION BACKGROUND 0 JANUARY 1986 BAW-1895 0 TMI-1 MET PTS "PTS EVALUATION IN CRITERIA AT ACCORDANCE WITH CRITICAL WELD 10CFR50.61 FOR B&WOG G ASSUMED LL CY 6 REACTOR PRESSURE 7; VLL CY 8 VESSELS" 8 MARCH 1986 BAW-1901 0 SAME CYCLE SCHEME "ANALYSIS OF CAPSULE ASSUMPTIONS TMI-1C GPUN TMI-1 RV METHODS AS 4
MATERIALS SURVEILLANCE BAW-1901 PROGRAM" 9 100F PTS MARGIN 4 CYCLES 6 AND 7 LOW LEAKAGE DESIGN 0 ABOUT 30 %
FLUENCE DECREASE TWICE-BURNED ASSEMBLY 0 ADDITIONAL ON MAJOR AXIS (FIGS. FLUENCE REDUC-3-1 AND 3-2 TION AT CRITICAL WELDS CY6: 25% -
CY7: 20%
I l
l
.- ..._-,.-.. - -- - - .N
III. DIFFERENCES CY 6 TO 7 A. RATED POWER UPGRADE G 2535 MWT TO 2568 MWT (1.3% INCREASE) ,
e PLANT SYSTEM REVIEW
. BALANCE OF PLANT l
. TURBINE-GENERATOR (NAMEPLATE RATING INCREASE)
. NSSS
. RPS
. ESFAS INSTRUMENTATION
. ELECTRICAL 0 SAFETY ANALYSIS REVIEWS
. FSAR ACCIDENTS PLANT RESPONSE (M0ST AT 2568 MWT) 0FFSITE DOSE (CYCLE 7 AT 2568 MWT)
EMERGENCY PROCEDURE GUIDELINES
. ATWS STEAM GENERATOR TUBE PLUGGING EFFECTS G
6
, n_ , ,-,- - - - . . . . - _ _ . _ - . . , _ . _ _ , - _ . . . , . _ . , . . . _ , _ , , , . _
III. DIFFERENCES CY 6 TO 7 (CONT'D)
A. TMI-1 RATED POWER UPGRADE (CONT'D) 0 OPERATIONAL REVIEWS CYCLE 7 TECHNICAL SPECIFICATION LIMITS ARE FOR 2568 MWT REACTOR VESSEL FLUENCE -
CORE DESIGN (FSAR CHAPTER 3 0F 2568 MWT) :
0 ENVIRONMENTAL REVIEWS !
NORMAL RADIOLOGICAL RELEASES
. THERMAL IMPACT l
. CHEMICAL IMPACT !
. WATER USAGE FISH & ENTRAINMENT IMPINGEMENT l COOLING TOWER EFFECTS / SALT DRIFT
. METEOROLOGY LAND USE/ POPULATION /PURLIC FACILITIES 1 O
III. DIFFERENCES CY6 T0 7 (CONT'D)
A. THI-1 RATED POWER UPGRADE (CONT'D) e CONCLUSIONS
. PLANT SYSTEMS CAN BE OPERATED WITHIN THEIR DESIGN LIMITS AT 2568 MWT
. PRESENT SAFETY ANALYSIS RESULTS BOUND t
OPERATION AT 2568 MWT
. PRIMARY SYSTEM DESIGN PARAMETERS REMAIN UNCHANGED
. ENVIRONMENTAL IMPACT IS B0UNDED BY PRESENT LIMITS i
III. DIFFERENCES CY6 TO 7 (CONT'D) 1 8. ENRICHMENT INCREASE 9 3.63 WT%
4 36 0F 76 FRESH ASSEMBLIES (FIG. 3-2) 9 4 FAs 0 2.95 W/0; 36 FAs 0 2.85 W/0 0 SPENT FUEL P0OL W/0 UPGRADE
. PREVIOUS SFP LIMIT: 3.5 W/0
. NEW ANALYSIS LIMIT: 4.3 W/0
. TSCR SUBMITTED; JAN 1988
. TARGET APPROVAL: MAY 1sT
. FUEL DELIVER'/ STARTS: MAY 2ND
. NRC REVIEW STATUS 1
l i
III. DIFFERENCES (CONT'D)
C. ZIRCALOY INTERMEDIATE GRIDS 0 PREVIOUSLY USED IN: RANCHO SECO OCONEE 1, 2, 3 CRYSTAL RIVER 3 0 DESIGN APPROVED PER BAW-1781P (RANCHO SECO CY7 RELOAD REPORT, V0L 1, APRIL 1983) 0 USE OF BWC CHF CORRELATION 0 BWC 95/95 MDNBR: 1.18 0 CORE BYPASS FLOW INCREASE
. CY6: 8.4%; CY7: 8.8%
. ACTUAL BYPASS: 7.6%
_--.m_ ____,_. _ . . . - - . _ - _ _ _ . _ _ _ _ . _ - - - _ _ , -_ - - _ _ ,..___ .._... __._ ___.. _ __._ ___.- ________ .__________.._-_-..~ ____.. - _ . - - -
III. DIFFERENCES (CONT'D)
D. FUEL R0D PREPRESSURE REDUCTION O PREVIOUSLY USED IN:
OCONEE 1, 2, 3 CRYSTAL RIVER 3 ANO-1 0 HIGH BURNUP BENEFIT 9 38 0F 75 FRESH FAs l 0 LOCA KW/FT CREDIT NOT TAKEN IN CY7 l
l l
l 1
1
III. DIFFERENCES (CONT'D)
E. FLECSET APPLICATION 0 FLECSET APPROVED OCTOBER 1987 8 EM CHANGE COMPLETED 9 1/2 KW/FT BENEFIT 02-F00T LEVEL OF LOCA LIMITS F. CONSERVATIVE DOSE EVALUATION 4 CY6 TO CY7 RADIONUCLIDE INVENTORY CHANGES INSIGNIFICANT (CYCLE 7 AT 2568 MWT) 9 BOUNDING DOSE EVALUATION PERFORMED 10% INVENTORY INCREASE UPDATED PLANT PARAMETERS S RESULTS-INCREASED DOSE VALUES OVER PREVIOUS ANALYSES WELL BELOW 10CFR100 LIMITS FUTURE FSAR BASES e- - r,-,- , - --,,-----a,---.---.-,-----w---,-----e.-
, , --n,,,,e-.,,- w,,,,,,--,,,,-,_.nm.,,mre.,,-n-v.,ww-.ge------en,we~r-,mn-v w.ww--
4 III. DIFFERENCES (CONT'D)
G. TECHNICAL SPECIFICATION 8 SAFETY LIMITS CORE PROTECTION SAFETY LIMITS
. PRESSURE-TEMPERATURE 0 LYNXT CROSSFLOW ANALYSIS '
O LESS-RESTRICTIVE P-T LIMITS
. AXIAL POWER IMBALANCE CORE PROTECTION SAFETY BASES
. 4, 3, 2 PUMPS 8 LIMITING SAFETY SETTINGS P-T ENVELOP SET 0 PINTS l
. VLP TRIP REMOVAL PROTECTION BY HIGH TEMPERATURE AND LOW PRESSURE SETPOINTS AXIAL POWER IMBALANCE SETPOINTS S LIMITING CONDITIONS FOR OPERATION R0D POSITION LIMITS THREE BURNUP WINDOWS l 2 PUMP / 3 PUMP / 4 PUMP CURVES
. ERROR-ADJUSTED INDICATED % RATED POWER
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III. G. TECHNICAL SPECIFICATION CURVES (CONT'D)
OPERATIONAL IMBALANCE LIMITS 0 THREE BURNUP WINDOWS S ERROR-ADJUSTED 0 INDICATED POWER I LOCA LIMITED MAXIMUM LHR !
O NUREG-0630/FLECSET (0-1000 MWD /MTU) 1 0 TAC 02 (DENSIFICATION PERIOD) (1000-2600 .
l MWD /MTU) 0 TAC 0 2 (REMAINDER OF CYCLE) (AFTER 2600 3 MWD /MTU) l l
POWER-DEPENDENT TILT LIMIT !
e 0-50% FP l 0 AB0VE 50% FP 1 l
i l
4 e
III. DIFFERENCES (CONT'D)
H. STARTUP PROGRAM
. FLUX SYMMETRY TEST POWER DOPPLER MEASUREMENT TECHNIQUE A
e.
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son ,:-
Meeting Sumary Distribution .r' ,
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W4f14 NRC A Local PDRs S. Varga B. Boger J. Stn1z OGC-WF E. Jordan J. Partlow ACRS(10)
H8Clayton (Region I only)
R. Conte (Region I)
NRC
Participants:
M. Hodges R. Hernan W. Brooks S. Peleschak (Region I)
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