|
|---|
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
D
. SeptembLr 30, 1986 h' MEMORANDUM FOR: John -F. Stolz, Director PWR Project Directorate #6 Division of PWR Licensing-B FROM: John Thoma, Project Manager PWR Project Directorate #6 Division of PWR Licensing-B
SUBJECT:
TMI-I RELOAD MEETING SUMMARIES On Tuesday, September 16, 1986, GPUN met with the NRC staff to discuss their Cycle 6 Reload Report to be submitted by October 31, 1986. Enclosure 1 provides the list of attendees and Enclosure 2 contains the handouts provided at the meeting. The purpose of the meeting was to discuss the technical approach utilized by B&W and GPUN to identify any potential problem areas in the report.
% % 5 5 0 L M W D E f.D John Thoma, Project Manager PWR Project Directorate #6 Division of PWR Licensing-B
Enclosures:
As Stated cc w/ enclosures:
See next page p p4 fev/r6 _ f 8 0 # (,
66&;cf 7 Aos3 A.Woortl 9/p/86 d 4,( p gno??oBM$$$$i' l P
MEETING
SUMMARY
DISTRIBUTION Licensee: GPU Nuclear Corporation -
- Copies also sent to those people on service (cc) list for subject plant (s).
(DoWt].L1d NRC PDR L PDR PBD-6 Rdg JStolz JThoma
. 0GC-MNBB 9604 EJordan BGrimes ACRS-10 NRC Participants TRoss NLauben CThomas DFieno I
1
= > - - - - ~~ e-.g- - -,.4,,,
Enclosure 1 LIST OF ATTENDEES -
MEETING HELD ON SEPTEMBER 16, 1986 NAME AFFILIATION John Thoma NRC/PWR-B Thierry Ross NRC/PWR-B Norm Lauben NRC/PWR-B Cecil Thomas NRC/PWR-B Daniel Fieno NRC/PWR-B Rick McGoey GPUN Licensing Frank McPhatter B&W-Fuel Engineering Joe Randazzo TMI Licensing Scott Wilkerson TMI Nuclear Engineering Joe McCarthy GPUN TMI Fuel Projects John Luoma GPUN TMI Fuel Projects Dave Distel -
GPUN Licensing r --.. ,-- - -
TMI-1 CYCLE 6 RELOAD REPORT SUBMITTAL - GPUN/NRC PREMEETING
~
SEPTEMBER 16, 1986 I. INTRODUCTION A. GPUN Organization B. Status of Cycle 5 C. Schedule for Cycle 6 Outage D. Status of Cycle 6 Reload Report II. CYCLE DESIGN A. 18-Month Cycle B. Cycle Design C. PTS / Fluence Reduction D. Safety Analysis and Technical Specifications III. DIFFERENCES FROM TMI-1 CYCLE 5 A. Use of Cross-Flow Thermal Hydraulic Code (LYNXT)
B. . Core Bypass Flow C. TACO II -
D. Use of Gray APSRs E. Removal of Power Level Cut-Off F. Startup Program ;
G. NUREG-0630 l l
IV. OTHER )
V.
SUMMARY
l I. INTRODUCTION A. GPUN ORGANIZATION B. CYCLE 5 STATUS o ABOUT 260 EFPD o APSRs WITHDRAWN (9/13/86) o EXPECTED SHUTDOWN 11/1/86 (ABOUT 302 EFPD)
C. SCHEDULE FOR CYCLE 6 0UTAGE o START NOVEMBER 1sT o DURATION 4-TO-5 MONTHS o APPROVED TECH SPEC: MARCH 1sT I
D. STATUS OF CYCLE 6 RELOAD REPORT !
l 0 DRAFT RR TO GPUN (9/15/86) o TECH SPEC CHANGE REQUEST TO NRC (10/31/86)
f
(* GENERAL PUBLIC UTILITIES NUCLEAR CORPORATION i ~
f I
0FFICE OF THE PRESIDENT ['
I ,
P. R. CumK .
VICE PRESIDENT & VICE PRESIDENT &
DIRECTOR DIRECTOR l TECHNICAL FUNCTIONS TMI-l H. D. HUKILL R. F. WILSON I
I i DIRECTOR SYSTEMS DIRECTOR LICENSING i PLANT ENGINEERING DIRECTOR ENGINEERING & REGULATORY AFFAIRS J. J. COLITZ i
! T. G. BROUGHTON J. R. THORPE
)
NUCLEAR ANALYSIS & FUELS MANAGER PWR LICENSING LEAD NUCLEAR ENGINEER DIRECTOR R. J. MC COEY W. S. WILKERSON G. R. BOND 1
1 1 ,
MANAGER TMI FUEL MANAGER SAFETY ANAL. PWR LICENSING PROJECTS & PLANT CONTROL ENGINEER J. D. LUOMA N. TRIK0UROS D. DISTEL l FUELS ENGINEER SAFETY ANALYSIS J. D. MC CARTHY ENGINEER L. LANESE ,
i 3999f
Figure 3-1. Core Loading Diagram for THI-1, Cycle 6 7 7 6 7 7 A NO3 LO2 008 Ll4 .113 7 88 7 88 . 6 88 7 88 7 B LO1 F K01 F C11 F KIS F LIS 7 88 7 88 7 88 7 88 7 88 7 C HIS F N02 F M02 F M14 F N14 F RD8 7 88 6 8B 6 88 6 88 6 88 6 8B 7 i 0 C09 F E09 F G13 F A06 A10 F C07 F E07 F 88 7 88 6 8A 6 8B 6 8A 6 88 7 88 E F 804 F F B12 F H06 F 006 F 010 F- F08 7 7 88 6 8A 6 88 6 88 6 8A 6 88 7 7 F F H02 F G09 F B08 F G11 F A07 C04 C12 A09 F GOS 7 88 7 8B 6 8B 6 8A 6 8B 6 88 7 88 7 G F B06 B10 F B11 F F04 F F06 F F10 F F12 BOS F 6 6 88 6 88 6 8A 6 8A 6 88 6 88 6 6 H F G03 F C07 F 011 F K09 F K13 F M13 H12 H04 E03 88 7 88 6 88 6 8A 6 8B 6 88 7 8B 7 7
K LO4 F LO6 F L10 F L12 F POS F P06 PIO F P11 F 7 8B 6 8A 6 8B 6 88 6 8A 6 88 7 7 7
L F K05 F P08 F K07 F H14 F K11 F R07 004 012 R09 6 8A 6 BB 6 8A 6 88 7 8B 8B 7 88 M p p12 F N06 F N10 F H10 F PO4 F F LOB M 7 88 6 8B 6 88 6 88 6 88 6 BB 7 F K03 N07 F 007 F M09 F 009 F R06 RIO F
/ 88 7 88 7 88 7 88 7 8B 7 0 F 002 F E02 F E14 F 014 F H01 A08 7 8B 7 8B 6 88 7 8B. 7 P
F01 F G01 F 005 F GIS F FIS 7 7 6 7 7 003 F02 N08 F14 013 12 13 14 15 8 9 10 11 1 2 3 4 5 6 7 C Ba tch ,
===== Previous Cycle Location; F = Fresh Fuel Assembly 3-3 N&Miceps a McDermott compenn
,n ,---- ,- - - - , , , - - - - , -
- - - , ----.-m, -- - - - - , , ,
Figure 3-2. Enrichment and 8urnup Distribution for TMI-1, Cycle 6 8 9 10 11 12 13 14 15 2.85 2.95 2.85 2.85 2.85 2.85 2.85' 2.85 H 19,779 18,934 17,249 19,745 0 0 0 20.033 2.85 2.85 2.85 2.85 2.85 2.85 2.85 19,167 0 15,739 0 9,411 0 10,550
. 2.85 2.95 2.85 2.85 2.85 2.85 19,155 0 16,987 0 7,596 10,330 2.85 2.85 2.85 2.85 M
17,883 0 6,772 0 2.85 2.85 2.85 N
17,249 0 6,513 2.85 0
7,844 P
R X.XX Initial enrichment .
XX,XXX BOC burnup, mwd /mtU l Babcock & WHcom 3-4 , , ,, y s.
Figure 3-3. Control Rod Locations and Group '
Designations for TMI-1. Cycle 6 ,
Fuel Transfer 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 H W- 6 7 2 4 2 7 6 -Y K 5 4 2 2 4 5 L 1 8 6 2 6 8 1 il i 3 5 4 4 5 3 N l 7 8 7 8 7 O 3 5 5 3 l
P l l 1 6 1 R i i 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 3 8 Safety 4 9 Safety 5 12 Control 6 8 Control 7 8 Control ,
8 8 APSRs 3-5 NAMb8 a McDermott com
Figure 3-4. LBP Enrichment and Distribution for THI-1 Cycle 6 8 9 10 11 12 13 14 15 H 1.03 1.03 0.80 K 1.03 1.03 1.03 0.20 L 1.03 1.03 0.80 M 1.03 1.03 0.80 N 1.03 0.80 0.20 0 0.80 0.80 0.20 l
p 0.20 I
R l
" Concentration, No. of BPRAs wt % B 4C X.XX LEP Concentration (wt % B4 C in Al230) 20 0l80' 16 0.20 l
Total 3E _
l Babcock &WHcom
, 3-6 aucce m ic e r s l
II. CYCLE DESIGN A. 18 MONTH CYCLE o LOW LEAKAGE DESIGN o 425 +/- 15 EFPD o 76 FRESH FUEL ASSEMBLIES o 68 BPRAs B. CYCLE DESIGN o CORE MAP (FIGURES 3-1, 3-1) l o CONTROL ROD MAP (FIGURE 3-3) o BPRA MAP (FIGURE 3-4;)
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C. PTS / FLUENCE REDUCTION BACKGROUND o JANUARY 1986 BAW-1895 o TMI-1 MET PTS
" PTS EVALUATION IN CRITERIA AT ACCORDANCE WITH CRITICAL WELD 10CFR50.61 FOR B&WOG o ASSUMED LL CY 6,
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REACTOR PRESSURE VESSELS" 7; VLL CY 8 o MARCH 1986 BAW-1901 o SAME CYCLE SCHEME
" ANALYSIS OF CAPSULE ASSUMPTIONS AND THI-1C GPUN TMI-1 RV METHODS AS MATERIALS SURVEILLANCE BAW-1901 PROGRAM" o 100 PTS MARGIN CYCLE 6 l
o LOW-LEAKAGE DESIGN o ABOUT 30% PERCENT FLUENCE DECREASE o TWICE-BURNED ASSEMBLY o ADDITIONAL FLUENCE OR MAJOR AXIS (FIGURE REDUCTION AT 3-1 AND 3-2) CRITICAL WELD y - - = - . - . - - - - - . , , . - - - . -
D. SAFETY ANALYSIS AND TECHNICAL SPECIFICATIONS :
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LIMITING SAFETY SETTINGS o CORE PROTECTION SAFETY LIMITS o FLUX / FLOW / IMBALANCE SETPOINTS LIMITING CONDITIONS FOR OPERATION o ROD POSITION LIMITS THREE BURNUP WINDOWS 2 PUMP /3 PUMP /4 PUMP CURVES
% RATED POWER VS % ALLOWABLE POWER o OPERATIONAL IMBALANCE LIMITS THREE BURNUP WINDOWS o LOCA LIMITED MAXIMUM LHR NUREG-0630 TACO 2 (DENSIFICATION PERIOD) ,
TACO 2 (REMAINDER OF CYCLE) o APSR TECHNICAL SPECIFICATIONS NONE REQUIRED FOR GRAY APSR o POWER LEVEL CUTOFF CYCLE SPECIFIC ANALYSIS
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III. DIFFERENCES FROM THI-1 CYCLE 5 A. CROSS-FLOW T-H CODE O PROVIDES ADDITIONAL DNBR MARGIN o MASS TRANSFER BETWEEN FLOW CELLS o USED FOR ANO-1 AND CR-3 o APPRdVED NRC CODE 1
l
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l B. CORE BYPASS FLOW o 2% DECREASE FROM CYCLE 5 BYPASS (8.4% COMPARED TO 10.4%)
o CONSERVATIVE VS. ACTUAL. BYPASS WITH LBPs INSERTED
+
1 C. TACO 2 o STANDARD IN ALL B&W RELOAD FUEL DESIGNS o PROVIDES MECHANISTIC DENSIFICATION MODEL o USED FOR CURRENT LOCA LIMITS o EFFECTS SHOWN IN BOC ALLOWABLE PEAK LHRs l
l l
1
1 D. GRAY AXIAL POWER SHAPING RODS .
APSE DESIGN o 63 INCH INCONEL POISON o INCREASED CLAD THICKNESS o BETTER OVERALL QUALITY APSR BENEFIT i o REDUCED CORE PEAKING o LOWER KW/FT WITH MOVEMENT o IMPROVED FUEL RELIABILITY o LOWER FUEL ENRICHMENTS APSR TECHNICAL SPECIFICATIONS o NONE REQUIRED
. o MINOR PEAKING PENALTY APPLIED. TO OTHER CURVES -
PREVIOUS EXPERIENCE o SMUD (RANCHO SECO) o FPC (CRYSTAL RIVER) o DUKE (OCONEE)
'l
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E. POWER LEVEL CUTOFF CYCLE 5 ANALYSIS o GENERIC XENON PENALTY IN ANALYSIS o TECHNICAL SPECIFICATION PEAKING ENSURED WITHIN GENERIC ASSUMPTIONS CYCLE 6 ANALYSIS -
o CYCLE SPECIFIC XENON PEAKING UTILIZED o PEAKING PENALTY APPLIED IN LCO CURVES PREVIOUS EXPERIENCE o DUKE (OCONEE) -
0 ARKANSAS POWER & LIGHT (ANO-1)
--~w w v . ,-w ,w n
I F. STARTUP TESTING .
ZERO POWER TESTING o CONTROL ROD TRIP TESTING o ALL RODS OUT CRITICAL BORON o ISOTHERMAL TEMPERATURE COEFFICIENT o CONTROL ROD WORTH o BORON WORTH POWER ESCALATION TESTING o CORE POWER DISTRIBUTION INTERMEDIATE POWER LEVEL (40% - 75%)
FULL POWER (100%)
o INCORE/EXCORE DETECTOR CORRELATION (0 INTERMEDIATE POWER)
REVISED SLOPE CRITERION o POWER COEFFICIENTS (O FULL POWER)
DOPPLER COEFFICIENT TEMPERATURE COEFFICIENT
_. h
o O
G. NUREG-0630 o REVISED CLADDING RUPTURE / BALLOONING MODELS o INCLUDED IN CYCLE 6 LOCA LIMITS o PENALTIES AT BOC o EFFECTS INCLUDED IN OTHER TECH SPECS I
l
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