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Category:MEETING MINUTES & NOTES--CORRESPONDENCE
MONTHYEARML20207L7711999-03-11011 March 1999 Summary of 990223 Meeting with NSP to Discuss Potential NRC Review Process for New Core & Thermal Hydraulic Computer Modeling Methods Currently Under Evaluation by NSP ML20207L7611999-03-0909 March 1999 Summary of 990224 Meeting with NSP Re Implications of NSP Recently Extended Commitment for Monticello ITS Submittal, Implications of NRC Initiative Toward risk-informed TSs & Interfacing ITS Conversion ML20196F6101998-12-0101 December 1998 Summary of 981029 Meeting with Northern States Power, Wisconsin Electric,Wisconsin Public Service & Alliant-IES in Rockville,Md Re Various Aspects of Potential Regulatory Issues Associated with Ongoing Cooperative Efforts ML20206S6301998-06-17017 June 1998 Summary of 980602 ACRS Thermal Hydraulic & Severe Accident Phenomena Subcommitteemeeting in Rockville,Md Re GE Extended Power Uprate Program for Operating BWRs & NSP lead-plant Application for Power Uprate ML20198Q5881997-10-31031 October 1997 Summary of 970910 Meeting W/Util in Rockville,Md Re Status of BWR Power Uprate Program.List of Attendees,Agenda & Handouts Encl ML20211F8071997-09-22022 September 1997 Summary of 970911 Meeting W/Northern States Power Co in Rockville,Md Re Equipment Environ Qualification Program. List of Attendees Encl ML20132D1331996-12-13013 December 1996 Summary of 961105 Meeting W/Northern States Power & GE to Discuss Contents of 960726 License Amend Request,Pertaining to Monticello Extended Power Uprate Program & Supporting Activities ML20057F2811993-10-12012 October 1993 Summary of 930929 Meeting W/Util Re Installation of Water Level Monitoring Instrumentation at Plant.List of Attendees & Presentation Slides Encl ML20149D6051993-09-15015 September 1993 Summary of 930708 Region III Annual Training Managers Conference in Glen Ellyn,Il.Purpose of Meeting to Provide Forum for Discussion on Rev 7 of Operator Licensing Examiner Stds & to Discuss Operator Licensing Issues ML20056F8171993-08-0909 August 1993 Summary of Operating Reactors Events Meeting 93-29 on 930804.List of Attendees & Viewgraphs Encl ML20217C5121991-07-0303 July 1991 Summary of Operating Reactors Events Meeting 91-12 on 910626 ML20215C8721987-06-0808 June 1987 Summary of Operating Reactors Events Meeting 87-10 on 870406 Re Events Which Occurred Since 870330 Meeting.List of Attendees,Events Discussed & Significant Elements of Events & Summary of Reactor Scrams & Significant Events Encl ML20213F0641986-11-10010 November 1986 Summary of Operating Reactors Events Meeting 86-36 on 861020.List of Attendees,Events Discussed,Significant Events Data Sheet,Summary of Scrams W/Complications & Status of Previous & New Assignments Encl ML20215G0561986-10-0707 October 1986 Summary of 860911 Meeting W/Bwr Owners Group in Bethesda,Md Re Strawman Generic Requirements for Enhancing BWR Containment Performance in Severe Accident Conditions.Second Technical Exchange Meeting in mid-Nov 1986 Proposed ML20199L6471986-06-26026 June 1986 Summary of Operating Reactors Events Meeting 86-21 on 860623.Attendance List & Viewgraphs Encl ML20125A4201978-09-11011 September 1978 Summary of 780824 NRC Meeting Held W/Ge,Tva,Nsp, & B & P Representatives to Discuss Swelling in Four GE High Density Spent Fuel Storage Racks in Monticello Spent Fuel Pool. (Encl to 7809210158) ML20125C5621978-05-0101 May 1978 Summary of 780309-10 Meeting W/Mark I Owners Group in Bethesda,Md Re Changes in Long Term Program as Reflected in Rev 3 to Mark I Owners Group Program Action Plan ML20125B9641978-03-20020 March 1978 Summary of 771027 Meeting W/Ge & Mark I Owners Group Re multiple-subsequent Actuations of Safety/Relief Valves Following Isolation Event ML20127A4681978-03-0101 March 1978 Summary of 771129 Meeting W/Mark I Owners Group & GE in San Franciso,Ca Re Listed Topics,Including Results & Bases for long-term Program Decision Point 3.List of Attendees & Viewgraphs Encl ML20140G4971978-02-0909 February 1978 Summary of 780119 Meeting W/Mark II Owners Group,Ge & BNL Re Status of safety-relief Valve Related Loads on Mark II Containment.Meeting Agenda,Attendee List & Presentation Matls Encl ML20125C5681978-02-0303 February 1978 Summary of 780126 Meeting W/Nsp & GE Re Proposed Plant Spent Fuel Pool Expansion ML20125B9961977-12-29029 December 1977 Summary of 771215 Meeting W/Util Re Fall 1977 Facility Feedwater Nozzle & Control Rod Drive Return Line Nozzle Mods ML20127H6141977-11-11011 November 1977 Trip Rept of 771007 Visit to Facility to Observe Licensees Effort to Maintain Occupational Radiation Exposures ALARA During Repair of Feedwater Nozzles ML20127K1931977-11-11011 November 1977 Trip Rept of 771007 Visit to Monticello Nuclear Plant Re Licensee'S Effort to Maintain Occupational Radiation Exposures ALARA ML20127H6361977-11-0101 November 1977 Summary of 771020 Meeting W/Util & Nuclear Associates International Re Discussions on Proposed Submittal of Topical Rept,Documenting Core Analysis Sys Used at Plant. List of Attendees & Presentation Slides Encl ML20127H3801977-09-15015 September 1977 Summary of 770824 & 25 Meeting W/Representatives of Mark I Owners Group in Bethesda,Maryland Re Results & Bases for Decision Point 2 in Mark I Owners LTP & Proposed Changes in Scope of LTP Due to Results of Decision Point 2 ML20127H3951977-09-14014 September 1977 Summary of 770808 Meeting W/Representatives of Mark I Owners Group in Bethesda,Maryland Re Structural Acceptance Criteria for Mark I Containment LTP ML20127H2771977-09-13013 September 1977 Summary of 770617 Meeting W/Representatives of Mark I Owners Group & GE in Bethesda,Md Re Discussions on Structural Acceptance Criteria for Mark I Containment Long Term Program.List of Attendees & Meeting Agenda Encl ML20141N3471977-05-20020 May 1977 Summary of 770411 Meeting W/Mark I Owners Group & GE to Discuss Structural Acceptance Criteria for Mark I Containment long-term Program.List of Attendees Encl ML20128F4251977-03-10010 March 1977 Summary of 770301 Meeting W/Util Re Proposed QA Program for Plants.Attendance List & Agenda Encl ML20214G7031977-03-0303 March 1977 Summary of 770216-17 Meetings W/Mark II Owners Group,Ge & BNL in San Jose,Ca Re Monticello Test Results & Analytical Model Verification.Attendance List Encl ML20127H4311977-02-18018 February 1977 Summary of 770202-04 Meeting W/Representatives of Mark I Owners Group in San Jose,Ca Re Discussions on Proposed Revs to Mark I Containment Long Term Program Action Plan & Review of Status of Ongoing Testing & Analytical Efforts ML20125B9891976-11-12012 November 1976 Summary of 761028 Meeting W/Util & Consultant,Bechtel Power Corp Re Plant 10CFR50 App J Exemption Request.List of Attendees & Document from Util Encl ML20140G2641976-10-0404 October 1976 Summary of 760921 Meeting W/Ge & Inel in Bethesda,Md Re Areas of Concern Developed During Review of Safety Relief Analytical Model Described in NEDE-20942-P.Attendance List Encl ML20125C5711976-09-0909 September 1976 Summary of 760812 Meeting W/Mark I Owners Group,Ge,Epri & Techncial Consultants Re Listed Long Term Program Tasks ML20125C5721976-09-0909 September 1976 Summary of 760819 Meeting W/Mark I Owners Group,(Ge) in Bethesda,Md Re Discussions on Mark I Containment Ltp.List of Attendees Encl ML20125D6581976-08-18018 August 1976 Summary of 760717-08 Meeting W/Representatives of Mark I Owners Group in Bethesda,Md Re Discussions on Reassessed Content of Mark I Containment LTP & Recently Submitted Responses to Questions on STP Final Rept ML20140G2531976-06-28028 June 1976 Trip Rept of 760614-17 Site Visits Re Relief Valve Test Sequence.Test Results Encl ML20128C3711976-06-16016 June 1976 Summary of 760602 Meeting W/Mark I Owners Group in San Jose, CA Re General Guidelines for Defining Failure for Each Structural Failure Mode Being Considered in plant-unique Structural Analyses ML20140G2591976-06-15015 June 1976 Trip Rept of 760529 Site Visit Re Witness of Safety/Relief Valve Tests.List of Attendees Encl ML20127N9961976-05-24024 May 1976 Summary of 760513 Meeting W/Mark I Owners Group (GE) in Bethesda,Md Re Discussions on Program for plant-unique Torus Support Sys Analyses Presented in Ltr from GE to NRC .List of Meeting Attendees Encl ML20127P0271976-05-0606 May 1976 Summary of 760408 Meeting W/Mark I Owners Group (GE) in Bethesda,Md Re Discussions on Plant Specific Analyses of Mark I Torus Support Structure.List of Attendees Encl ML20126C2391976-04-19019 April 1976 Summary of 760401 Meeting W/Representatives of Mark I OG & GE in Bethesda,Md Re Revised Mark I OG Organization & Mark I Containment Reevaluation Schedule.List of Attendees Encl ML20126C1851976-03-24024 March 1976 Summary of 760318 Meeting W/Util Re App I Requirements.List of Attendees & Agenda Encl ML20126C2031976-03-0505 March 1976 Summary of 760226 Meeting W/Representatives of Mark I OG in Bethesda,Md Re BWR Mark I Containment Evaluation ML20128D8921975-11-28028 November 1975 Summary of 751031 Meeting W/Util to Discuss Monticello Reactor Vessel Feedwater Nozzle Cladding Cracks.List of Attendees Encl ML20235E9641975-08-0606 August 1975 Summary of 750717 Meeting W/Mark I Owners Group Re Role of Mark I Owners Group Program & Schedule for Determining Mark I Safety/Relief Valve & LOCA Dynamic Loads & Impact of Loads on Operating Mark I Plants.List of Attendees Encl ML20128C7861974-10-0303 October 1974 Summary of 740919 Meeting W/Util in Bethesda,Md Re Reg Guides 1.3 & 1.7 Relative to post-accident Combustible Gas Control Requirements for Plant Containment ML20128D9481974-04-0202 April 1974 Summary of 740322 Meeting W/Util in Bethesda,Md Re Plant Prompt Relief Trip Electrical Connections & Containment Penetrations ML20127G6091974-03-14014 March 1974 Summary of 740220 & 21 Meeting W/Util,Bechtel & GE in Bethesda,Md Re Prompt Relief Trip & Stated Valves 1999-03-09
[Table view] Category:MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
MONTHYEARML20207L7711999-03-11011 March 1999 Summary of 990223 Meeting with NSP to Discuss Potential NRC Review Process for New Core & Thermal Hydraulic Computer Modeling Methods Currently Under Evaluation by NSP ML20207L7611999-03-0909 March 1999 Summary of 990224 Meeting with NSP Re Implications of NSP Recently Extended Commitment for Monticello ITS Submittal, Implications of NRC Initiative Toward risk-informed TSs & Interfacing ITS Conversion ML20196F6101998-12-0101 December 1998 Summary of 981029 Meeting with Northern States Power, Wisconsin Electric,Wisconsin Public Service & Alliant-IES in Rockville,Md Re Various Aspects of Potential Regulatory Issues Associated with Ongoing Cooperative Efforts ML20206S6301998-06-17017 June 1998 Summary of 980602 ACRS Thermal Hydraulic & Severe Accident Phenomena Subcommitteemeeting in Rockville,Md Re GE Extended Power Uprate Program for Operating BWRs & NSP lead-plant Application for Power Uprate ML20198Q5881997-10-31031 October 1997 Summary of 970910 Meeting W/Util in Rockville,Md Re Status of BWR Power Uprate Program.List of Attendees,Agenda & Handouts Encl ML20211F8071997-09-22022 September 1997 Summary of 970911 Meeting W/Northern States Power Co in Rockville,Md Re Equipment Environ Qualification Program. List of Attendees Encl ML20132D1331996-12-13013 December 1996 Summary of 961105 Meeting W/Northern States Power & GE to Discuss Contents of 960726 License Amend Request,Pertaining to Monticello Extended Power Uprate Program & Supporting Activities ML20057F2811993-10-12012 October 1993 Summary of 930929 Meeting W/Util Re Installation of Water Level Monitoring Instrumentation at Plant.List of Attendees & Presentation Slides Encl ML20149D6051993-09-15015 September 1993 Summary of 930708 Region III Annual Training Managers Conference in Glen Ellyn,Il.Purpose of Meeting to Provide Forum for Discussion on Rev 7 of Operator Licensing Examiner Stds & to Discuss Operator Licensing Issues ML20056F8171993-08-0909 August 1993 Summary of Operating Reactors Events Meeting 93-29 on 930804.List of Attendees & Viewgraphs Encl ML20217C5121991-07-0303 July 1991 Summary of Operating Reactors Events Meeting 91-12 on 910626 ML20215C8721987-06-0808 June 1987 Summary of Operating Reactors Events Meeting 87-10 on 870406 Re Events Which Occurred Since 870330 Meeting.List of Attendees,Events Discussed & Significant Elements of Events & Summary of Reactor Scrams & Significant Events Encl ML20213F0641986-11-10010 November 1986 Summary of Operating Reactors Events Meeting 86-36 on 861020.List of Attendees,Events Discussed,Significant Events Data Sheet,Summary of Scrams W/Complications & Status of Previous & New Assignments Encl ML20215G0561986-10-0707 October 1986 Summary of 860911 Meeting W/Bwr Owners Group in Bethesda,Md Re Strawman Generic Requirements for Enhancing BWR Containment Performance in Severe Accident Conditions.Second Technical Exchange Meeting in mid-Nov 1986 Proposed ML20199L6471986-06-26026 June 1986 Summary of Operating Reactors Events Meeting 86-21 on 860623.Attendance List & Viewgraphs Encl ML20125A4201978-09-11011 September 1978 Summary of 780824 NRC Meeting Held W/Ge,Tva,Nsp, & B & P Representatives to Discuss Swelling in Four GE High Density Spent Fuel Storage Racks in Monticello Spent Fuel Pool. (Encl to 7809210158) ML20125C5621978-05-0101 May 1978 Summary of 780309-10 Meeting W/Mark I Owners Group in Bethesda,Md Re Changes in Long Term Program as Reflected in Rev 3 to Mark I Owners Group Program Action Plan ML20125B9641978-03-20020 March 1978 Summary of 771027 Meeting W/Ge & Mark I Owners Group Re multiple-subsequent Actuations of Safety/Relief Valves Following Isolation Event ML20127A4681978-03-0101 March 1978 Summary of 771129 Meeting W/Mark I Owners Group & GE in San Franciso,Ca Re Listed Topics,Including Results & Bases for long-term Program Decision Point 3.List of Attendees & Viewgraphs Encl ML20140G4971978-02-0909 February 1978 Summary of 780119 Meeting W/Mark II Owners Group,Ge & BNL Re Status of safety-relief Valve Related Loads on Mark II Containment.Meeting Agenda,Attendee List & Presentation Matls Encl ML20125C5681978-02-0303 February 1978 Summary of 780126 Meeting W/Nsp & GE Re Proposed Plant Spent Fuel Pool Expansion ML20125B9961977-12-29029 December 1977 Summary of 771215 Meeting W/Util Re Fall 1977 Facility Feedwater Nozzle & Control Rod Drive Return Line Nozzle Mods ML20127H6361977-11-0101 November 1977 Summary of 771020 Meeting W/Util & Nuclear Associates International Re Discussions on Proposed Submittal of Topical Rept,Documenting Core Analysis Sys Used at Plant. List of Attendees & Presentation Slides Encl ML20127H3801977-09-15015 September 1977 Summary of 770824 & 25 Meeting W/Representatives of Mark I Owners Group in Bethesda,Maryland Re Results & Bases for Decision Point 2 in Mark I Owners LTP & Proposed Changes in Scope of LTP Due to Results of Decision Point 2 ML20127H3951977-09-14014 September 1977 Summary of 770808 Meeting W/Representatives of Mark I Owners Group in Bethesda,Maryland Re Structural Acceptance Criteria for Mark I Containment LTP ML20127H2771977-09-13013 September 1977 Summary of 770617 Meeting W/Representatives of Mark I Owners Group & GE in Bethesda,Md Re Discussions on Structural Acceptance Criteria for Mark I Containment Long Term Program.List of Attendees & Meeting Agenda Encl ML20141N3471977-05-20020 May 1977 Summary of 770411 Meeting W/Mark I Owners Group & GE to Discuss Structural Acceptance Criteria for Mark I Containment long-term Program.List of Attendees Encl ML20128F4251977-03-10010 March 1977 Summary of 770301 Meeting W/Util Re Proposed QA Program for Plants.Attendance List & Agenda Encl ML20214G7031977-03-0303 March 1977 Summary of 770216-17 Meetings W/Mark II Owners Group,Ge & BNL in San Jose,Ca Re Monticello Test Results & Analytical Model Verification.Attendance List Encl ML20127H4311977-02-18018 February 1977 Summary of 770202-04 Meeting W/Representatives of Mark I Owners Group in San Jose,Ca Re Discussions on Proposed Revs to Mark I Containment Long Term Program Action Plan & Review of Status of Ongoing Testing & Analytical Efforts ML20125B9891976-11-12012 November 1976 Summary of 761028 Meeting W/Util & Consultant,Bechtel Power Corp Re Plant 10CFR50 App J Exemption Request.List of Attendees & Document from Util Encl ML20140G2641976-10-0404 October 1976 Summary of 760921 Meeting W/Ge & Inel in Bethesda,Md Re Areas of Concern Developed During Review of Safety Relief Analytical Model Described in NEDE-20942-P.Attendance List Encl ML20125C5711976-09-0909 September 1976 Summary of 760812 Meeting W/Mark I Owners Group,Ge,Epri & Techncial Consultants Re Listed Long Term Program Tasks ML20125C5721976-09-0909 September 1976 Summary of 760819 Meeting W/Mark I Owners Group,(Ge) in Bethesda,Md Re Discussions on Mark I Containment Ltp.List of Attendees Encl ML20125D6581976-08-18018 August 1976 Summary of 760717-08 Meeting W/Representatives of Mark I Owners Group in Bethesda,Md Re Discussions on Reassessed Content of Mark I Containment LTP & Recently Submitted Responses to Questions on STP Final Rept ML20128C3711976-06-16016 June 1976 Summary of 760602 Meeting W/Mark I Owners Group in San Jose, CA Re General Guidelines for Defining Failure for Each Structural Failure Mode Being Considered in plant-unique Structural Analyses ML20127N9961976-05-24024 May 1976 Summary of 760513 Meeting W/Mark I Owners Group (GE) in Bethesda,Md Re Discussions on Program for plant-unique Torus Support Sys Analyses Presented in Ltr from GE to NRC .List of Meeting Attendees Encl ML20127P0271976-05-0606 May 1976 Summary of 760408 Meeting W/Mark I Owners Group (GE) in Bethesda,Md Re Discussions on Plant Specific Analyses of Mark I Torus Support Structure.List of Attendees Encl ML20126C2391976-04-19019 April 1976 Summary of 760401 Meeting W/Representatives of Mark I OG & GE in Bethesda,Md Re Revised Mark I OG Organization & Mark I Containment Reevaluation Schedule.List of Attendees Encl ML20126C1851976-03-24024 March 1976 Summary of 760318 Meeting W/Util Re App I Requirements.List of Attendees & Agenda Encl ML20126C2031976-03-0505 March 1976 Summary of 760226 Meeting W/Representatives of Mark I OG in Bethesda,Md Re BWR Mark I Containment Evaluation ML20128D8921975-11-28028 November 1975 Summary of 751031 Meeting W/Util to Discuss Monticello Reactor Vessel Feedwater Nozzle Cladding Cracks.List of Attendees Encl ML20235E9641975-08-0606 August 1975 Summary of 750717 Meeting W/Mark I Owners Group Re Role of Mark I Owners Group Program & Schedule for Determining Mark I Safety/Relief Valve & LOCA Dynamic Loads & Impact of Loads on Operating Mark I Plants.List of Attendees Encl ML20128C7861974-10-0303 October 1974 Summary of 740919 Meeting W/Util in Bethesda,Md Re Reg Guides 1.3 & 1.7 Relative to post-accident Combustible Gas Control Requirements for Plant Containment ML20128D9481974-04-0202 April 1974 Summary of 740322 Meeting W/Util in Bethesda,Md Re Plant Prompt Relief Trip Electrical Connections & Containment Penetrations ML20127G6091974-03-14014 March 1974 Summary of 740220 & 21 Meeting W/Util,Bechtel & GE in Bethesda,Md Re Prompt Relief Trip & Stated Valves ML20126B1771973-10-0909 October 1973 Summary of 730927 Meeting W/Util in Bethesda,Md to Discuss Util Plans to Replace Four Existing spring-loaded Safety Valves on Plant Steam Lines W/Four Addl Target Rock Relief/ Safety Valves ML20128E0871973-09-11011 September 1973 Summary of 730906 Meeting W/Util in Bethesda,Md Re drywell- Torus Vacuum Breaker,Valve Position Indicators & Alarm Circuits to Assure Valve Closure & Changes to TS to Include Specific Vacuum Breaker Leak Test Requirements ML20128D1981973-06-15015 June 1973 Summarizes 730517 Meeting W/Util in Bethesda,Md to Discuss Basis for Proposed Rev to Tech Specs Re Control Rod Reactivity Worth Limits ML20125B3361972-10-30030 October 1972 Summary of 720930 ACRS Meeting W/Licensees in Washington DC Re Safety Review Monticello Full Term Operating License 1999-03-09
[Table view] |
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l 3' k. NUCLE AR REGULATORY COMMissl0N wAswiwoToN,0, C. 20606
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)' February 18, 1977 DOCKETS NOS.: 50-219, 50-2 50-237, 50-245, 50-249, 50-254, 50 259, 50-260, 50 63 50-265, 50-271, 50-277, 50-278, 50-293, 50-296, 50-298, 50-321, 50-324, 50-325, 50-331, 50-333, 50-341, 50-354, 50-355, and 50-366.
LICENSEES:
Boston Edison Company, Carolina Power & Light Company, Commonwealth Edison Company, Detroit Edison Company, Georgia Power Company, Iowa Electric Light & Power Company, Jersey Central Power & Light Company, Nebraska Public Power District, Niagara Mohawk Power Corporation, Northeast Nuclear Energy Company, Northern States Power Company, Philadelphia Electric Company, Power Authority of the State of New York, Public Service Electric and Gas,_ Tennessee Valley Authority, Vermont Yankee Nuclear Power Corporation.
FACILITIES: Oyster Creek Nuclear Generating Station, Nine Mile Point Unit No.1, Pilgrim Unit No.1, Dresden Units Nos. 2 and 3, Millstone Unit No.1. Quad Cities Units Nos.1 and 2, Monticello, Peach Bottom Units Nos. 2 and 3. Browns Ferry Units Nos.1, 2 and 3. Vermont Yankee, Hatch Units Nos.1 and 2, Brunswick Units Nos.1 and 2. Duane Arnold Energy Center, Cooper, Fitzpatrick, Enrico Fenni Unit No. 2, and Hope Creek Units Nos. 1 and 2.
SUMMARY
OF MEETINGS HELD ON FEBRUARY 2, 3, and 4, 1977 WITH REPRESENTATIVES OF THE MARK I OWNER'S GROUP On February 2, 3, and 4,1977, meetings were held in San Jose, California with representatives of the Mark I Owner's Group, General Electric Company (GE), and their technical consultants. The purposes of the meetings were to (1) discuss proposed revisions to the Mark I Containment Long Term Program (LTP) Action Plan, (2) review the status of ongoing LTP testing and analytical efforts, (3) establish procedures for Mark I Owner's Group - NRC staff interfacing during the conduct of the LTP, and (4) visit the GE 1/4 scale two-dimensional pool swell testing facility and the EPRI 1/12 scale three-dimensional pool swell testing facility.
Enclosures 1 and 2 are lists of the meeting attendees, e
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9211100511 770218 DH ADOCKODOOg3
Hecting Sumary Sumary February 2,1977 Meeting R. Buchholz provided an overview of the material which the Owners Group would present to the NRC staff during the course of the meetings, including a brief discussion of the revised integrated LTP schedule.
Copies of the draft version of Revision 1 to the LTP Action Plan were distributed to NRC staff members present to serve as a reference during the presentations.
D. Galle. Connonwealth Edison Company, informed the NRC staff that he was stepping down from his position as Chairman of the Mark I Owner's Group due to a change in his responsibilities within Connonwealth Edison Company and that R. Logue, Philadelphia Electric Company, is the new Chai man.
W. Cooper, Teledyne, described the program and schedule for development of the LTP Structural Acceptance Criteria (Task 3.1). The intent of this effort is to establish criteria which comply with Section !!! of the ASME Code, including the Sumer 1977 Addenda, to the maximum extent practical.
A limited number of justifiable exceptions to the Code criteria may be identified (e.g., column buckling criteria). A test program (Task 3.2) related to column buckling is currently in progress. The initial plant unique analysis structural guide is targeted for March 1977. Cooper stated that this would be a " discussion" document and that it is anticipated that a series of workinq meetings would be held between the NRC staff and the representatives of the Mark I Owners Group leading to a final NRC-approved version by October 1978. The first such meeting is tentatively scheduled for April 1977.
Hal Townshend, GE, described the three dimensional multivent full Scale Testing Facility (FSTF) program (Task 5.11) for defining steam flow induced chugging loads on the torus shell and vent system downcomers.
Enclosure 3 provides a detailed description of the FSTF. Construction of this facility is targeted for completion in November 1977 and comencement of the testing program is targeted for February 1978. A test report is schedulsifor September 1978 with the submission of a final plant application report targeted for early 1979. The Mark 1 Owners stated that the objectives of this testing program are limited to the definition of steam chugging loads and testing of potential steam chugging load mitigating devices. There was some discussion regarding the capability for extracting the forcing
~
function (in addition to measuring the structural response) from testing in
._ - - - . - . ~. ~ ..a ....-.:..u..w. m .c.:.= ..,. ::- - - -
I '
Meeting, Summary !
I a facility with flexible walls. GE stated that the design was equivalent to the worst hydrodynamic conditions (Monticello) of all operating Mark I facilities.
W.Bilanin,GE,describedtheintegrateuLTPtasks(Tasks 5.11, 5.13, 5.15,5.16) related to steam chugging loads. An interim predictive model, based on existing data and an analytical model, is scheduled to be available in mid-1977. This analytical model will be refined based on data from additional small scale test facilities and ultimately by the FSTF test results. It is anticipated that this model will be used to define plant-unique steam chugging loads.
Ed Kyss, GE, described the LTP task (5.15) related to determining hydraulic /
structural interaction effects on the Mark I containment system. These efforts are aimed at the development of an analytical model which could be verified by the FSTF test results and which would then be used for plant-unique applications. At the present time this program is primarily designed to predict hydraulic / structural interaction associated with steam chugging; however, GE is hopeful that the model application could be expanded to other sources of hydraulic / structural interaction.- The NRC staff inquired about this program's capability to decouple the steam chugging forcing function from the feedback effects of the hydraulic / structural '
interaction.
S. Lui GE, described the LTp task (5.14) related to the definition of loads on submerged structures in the torus. (This is a program suppression pool containment systems, applyingIIto andMark III I, generic for a designs).
H. Townsend, GE, reviewed the status and described the objectives of the 1/12 scale two-dimensional pool swell testing program (Task 5.8). Based on the testing to date it is clear that the measured downward force is very sensitive to the structural stiffness of the test bed. A sub-task has been added to this testing program with an objective to study further the effects of test bed structural flexibility on the measured torus pressure forces.
S. Stark, GE, reviewed the status and described the objectives of the 1/4 scale two-dimensional testing program (Task 5.5). Based on the data obtained to date, the scaling laws nave been confirmed for all parameters except the downward load for an initial condition of 0 psid drywell to wetwell differential pressure; the scaling laws have been confirmed for all parameters for an initial condition of maximum drywell to wetwell differential pressure.
Heeting, Summary 4 Enclosure 4 contains the slides used in the presentations made during this meeting.
February 3,1977 C. Sullivan, EPRI, discussed the 1/12 scale three-dimensional testing
.. program (Task 5.6). He stated that the facility was in the final stages of construction and that shakedown testing was scheduled to commence this month. He indicated that the test scope had been expanded to include investigation of the effects of asymmetric ness distribution. R. Kiang, SRI, discussed the efforts which have been directed at minimizing the effects of instrument error on the results of the test program, in particular for the load measurements. The NRC staff expressed a concern that wave interference effects should be considered.
R. Chan, JAYCOR, discussed the progress of the pool swell analytical model development program (Task 5.9). The model will be 21/2 dimensional and ,
is designed to simulate the non-uniform hydrodynamic response in the torus beginning with initial drywell pressurization and ending just prior to bubble breakthrough. The model will be validated using the 1/12 scale three-dimensional test data. The Mark I Owners do not intend to use the Lawrence Livermore Laboratory (LLL) test data to validate the model.
Progress to date indicates that the model requires additional refinement to better predict peak downward loads.
G. Sliter and J. Carey, EPRI, discussed the programs (Task 5.3), both analytical and testing, which are designed to investigate fluid-structure effects associated with vent header impact loads. Comparison of the results of the analytical and testing programs is scheduled for August 1977.
GE will conduct additional 1/4 scale tests using both rigid and flexible .
vent sections.
S. Arain, GE, discussed the program (Task 5.4), for developing plant-unique seismic slosh loads. .
J. Humphrey, GE, discussed the program (Task 6.3) for investigation and testing of potential pool swell load mitigating devices. The objective of the program is to identify a single device with attractive pool swell and steam chugging mitigation performance. Preliminary screening tests have identified several designs which offer attractive mitigation potential; additional testing is scheduled through September 1977.
~ ~ ' H. Townsend, GE, discussed the program (Task 6.1) for identifying a potential steam chugging load mitigation device. Preliminary screening tests are currently in progress. Additional testing is scheduled through August 1977.
p
1 Heeting Summary M. Tanner, GE, discussed the program (Task 6.2) for identifying a potential safety-relief valve load mitigatino device. Initial screening of potential devices is in progress, based r:n i review of existing test data. A large scale testing program of potin,tial devices will be included in the LTP.
S. Stark and L. Stark (GE) discussed the preliminary results of the Monticello in-plant safety-relief valve testing program (Task 5.1). Further data reduction is necessary to correct strain gage measurement errors. The identification of asymmetric loading conditions in the torus shell was of particular interest. A final report is scheduled to be issued in July 1977.
Enclosure 5 contains the slides used in the presentations made during this meeting.
Februsry 4, i,/7 Meeting P. lanni, GE, provided a general overview of the LTP content and schedule.
He stated that the Mark I Owners and GE believe that the revised LTP is responsive to all NRC requirements. He requested acknowledgement of this from the NRC staff. The NRC staff stated that, based on the infonnation presented at the meetings of the two previous days, we are in general agreement with that belief, but that we would like to review the submitted version of Revision 1 of the LTP Action Plan before making a firm statement. B. Sobon, GE, stated that the final version of Revision 1 would be submitted to NRC on February 11, 1977. The NRC staff stated that further discussion regarding the use of test data from the LLL 1/5 scale facility would be necessary. The NRC staff further stated that we were confident that the Short Tenn Program Safety Evaluation Report would be issued in the very near future.
A general discussion took place regarding the philosophy for future interfacing between the Mark I Owners Group and the NRC staff during the conduct of the LTP. The following general guidelines were agreed to:
- a. Major meetings should take place at 3 to 4 month intervals, primarily at major decision points in the LTP. The next major meeting would most likely be scheduled for July 1977.
- b. Single purpose meetings should be called as appropriate, but that these would be " working" meetings limited to smaller groups.
- c. A periodic (monthly) information report on the program status would be submitted to the NRC. Enclosure 6 is a sample of such a report.
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Meeting Sumary ,
- d. Preliminary information reports on testing and analytical program results would be sub itted to the NRC when available (see Enclosure 7).
At the request of the NRC staff, the Mark I Owners and GE described the Quality Assurance procedures which are being utilized during the conduct.
of the testing and analytical programs.
NRC personnel were taken on a tour of the GE 1/4 scale two-dimensional testing facility and the EPRI 1/12 scale three-dimensional testing facility.
Y, NGl John C. Guibert Operating Reactors Branch #3 Division of Operating Reactors
Enclosures:
- 1. Attendance List - February 2, 1977 meeting
- 2. Attendance List - February 3, 1977 meeting
- 3. Full Scale Test Facility Program Description
- 4. Slides used in presentation of February 2,1977 meeting
- 5. Slides used in presentation of February 3,1977 meeting
- 6. Mark I containment Program Activity Review Report -
November 1976 Proposed Mark I Long Term 7.
Program Documentation
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NUCLEAR REGULATORY CO.'. MIS $10N - l E 9 WASHINGTON. D. c. 20565 {
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--- Lvd e t Files [o 943- NRC. Participants ,
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- B. C. Rusche W.'Paulson d
- E. G. Case J. Shea~ , , r
_ ,V. Stello-P. O'Connor
- i T. J. Carter R. Snaider
- D. Ziemann P..DIDenedetto 4
- R. Reid M. Fletcher W.-Butler M.'Fairtile-- i
- L. C. Shao- 'P. Riehm' ' '
- with enclosure *J. Knight
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