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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 MINUTES-INTERNAL (NON-TRANSCRIPT) MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
MONTHYEARML20069M7991979-12-10010 December 1979
Summary of 791207 Meeting Re Basic Concepts for Startup & Test Program
ML20085A4071979-08-0303 August 1979
Summary of 781204 Telephone Conference W/B&W Re ECCS Small Break Analysis N4M-2-14 - Response to K-5020
ML20085A4011979-08-0303 August 1979
Summary of 781204 Telephone Conference W/B&W Re Small Break Analysis - Response to K-5020
ML20085A9581979-07-30030 July 1979
Summary of 790723 Meeting W/Duke Power Co Re B&W NSSS, Including Nuclear & Fossil Operations,Integrated Control Sys,Feedwater Sys & once-through Steam Generators
ML20136A9251979-04-0505 April 1979
Summary of 790405 Meeting of Util Industry Committee on Reactor Core Condition Working Group Re Zircaloy-water Reaction & Hydrogen Inventory in Lynchburg,Va
ML20136A9161979-04-0505 April 1979
Summary of 790405 Meeting of Util-Industry Committee on Reactor Core Condition Working Group Re Pellet Conditions in Lynchburg,Va
ML20085A4811977-09-28028 September 1977
Summary of 770928 Meeting W/Bechtel,B&W & NRC at Davis- Besse Site Re 770924 Accident
1979-08-03
[Table view] |
Text
, =
(r i TELECON: ECCS - SMALL BREAK LOCA ANALYSIS N4M-2-14 12-4-78 REF LTR K-5020 gg gg g g W10C144 C-K Regr.ested by Carl Michelson jff/fl_.3, A, E;2;U 2:00 / '
8-671-1060 x2707 LHC Carl Michelson Lee Haack B&W: Bob Lightle Bob Jones' TVA: RIS Stu Thickman Harry O'Brien Jim McF.t.l Lou Cartin Dennis Renner Henry Daily Carl: What co - nts does B&W have on K-5020 and where do we go from here.
Bob L: Very detailed study - hard to respond w/o equally detailed study -
are trying to get problem in perspective.
Carl: Question of vapor formation - Temp at t pt = temp at core exit (steam in U-bend)
Bob J: Steam bubble does form - natural cir.culation does cease ..
Carl: What is heat removal mechanism when natural circulation ceases.
Bob J: Pool boiling. When accident starts - lose offsite power get natural cire mode thru system. At this time, bubbles form in core region and are carried throughout RCS. Steam pocken forms .
O t P
XC405?4
= -
.?
in upper portion of RV. Press of RV supports hydrostatic head in ,
hot leg (?) - vent valves open - liquid depletes to cold leg elev and steam escapes thru the break.
Carl: Break isn't big annf to take all heat out'.
. Bob J: Removal of all hest is not controlling factor in small break analysis. Trying to remove certain volume of steam. Some steam quenched by HPI.
Carl: We factored this into our analysis. Your predictions are based on larger breaks - small breaks don't behave the same way.
Bob J: You probably don't have any natural circulation for'small break case.
1 Carl: Do you keep the core covered - If so, how do you know.
l Bob J: Because of vent valve, will deplete system inventory - level will drop below secondary side of SG. At thi. time, will still have water in RV - if you have inventory in system, you have water -
. in RV.
Carl: Do you disagree with my Figures 2 and 37
. e Bob J: Haven't checked your numbers. ,
I -
XC40575
Carl: Have to calculate to determine if core stays covered for breaks under
.05 ft - This is really all we're asking.
Bob J: We've looked at .05 break, in extrapolated to smaller breaks and concluded that covering the core is not a problem. NRC has accepted this, verbally, that smaller breaks are not a problem.
Carl: Need B&W to point out where your results differ from ours - your calculations are more sophisticated than ours so we want B&W to tell us where we're wrong.
\
Bob L: To give the answers you want will require a detailed calculation from B&W.
Bob J: We don't feel this effort is warranted.
Carl: Just reply to our K-5020 describing how you replied to NRC for breaks
(.05Ft.2 . Not asking B&W to do a new analysis.
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