|
|---|
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] |
Text
..~.
. V ,. ,.
(M UNITE 3 STATES - .
p* . .Ne\ NUCLEAR REGULATORY COMMIS$10N WASHINGTON, D. C. 2065S i
e ]
3 )ki k.o / ....
May 24, 1976 1
George Lear, Chief. Operating Reac' tors Branch (3, DOR DOCKETS NOS.: ~ 50-219, 50-220, 50-237..,50-245, 50-249, 50-254, 50-259, ,
50-260, # 263 50-265, 50-271, 50-277, 50-278, 50-293, 50-296, 50-298, 50-321,:50-324 325, 50-331, 50-333, 50-341, 50-354, 50-355, and 50-366.
i LICENSEESt Boston Edison Company, Carolina Power & Light Company,- '
Commonwealth Edison Company, Detroit Edison Company, Georgia-Power Company, Iowa Electric Light & Power . company 7 Jersey Central Power & Light Company,-Nebraska Public Power-District,_
J Niagara Mohawk Power Company, Northcast Nuc1 car Energy Company, ;
Northern States Power Company,-Philadciphia. Electric Company, i
Power Authority State of_New York, Public Service Electric- i and Gas, Tennessee Valley _ Authority', -Vermont = Yankee Nuclear -
Power Corporation.-
FACILITIES: . Oyster Creek Nuclear Generating Station, Nine Mile Point Unit 1. Pilgrim l', Dresden Units-2 and 3 Millstone. Unit-1.-- .
Quad Cities Units 1 and"2, Monticello, Peach Bottom Units
!. 2 and 3, Browns Terry Unit -1, 2 and. 3. Vermont 1 Yankee, l Hatch Units 1 and 2, Brunswick Units:1-and 2,;Duane Arnold l Energy Center, Cooper, Fitzpatrick, Enrico Fermi Unit.-2, -
and Hope Creek Units 1 and 2.
SU' MARY _0F !!EETING HELD ON MAY 13, 1976 WITil' REPRESENTATIVES OF THE: MARK I OWERS CROUP ,
on May 13, 1976 a meeting was held in Bethesda-with representatives of.the-Mark I Owners Groap, General Electric Company- (CE), =and their: technical
-consultants. The purpose of the meeting was-(1) to discuss. the- program for the plant-unique torus support-system analyses presented in a letter from GE to the.NRC staff dated April 26,;1976, and (2) to discuss'the 1/4 scalet pool swell test: program objectives.- Enclosure 1-is a list _of, meeting. attendees.
SLMMARY' 1-l- N. Edwards, NUTECH,~ described the program for'the plant-unique analyses of l torus support systems and!.the piping ati: ached to the torus. Enclosure 2-l contains the slides-used.in this presentation. General discussion between the NRC staff and representatives of.the Mark I Owners Group resulted;in o
g 9212010474 760524 PDR ADOCK 05000263?
P pon
the identification of several outstanding areas of concern:
- a. The criteria which will be utilized to evaluate the plant unique analysis results include specified "stlength ratios" (SR), where the SR for an '
elcecnt is defined as the stress (or strain) in the element for a given applied load divided by a lower bound of the value of the stress (or strain) in that element at which one would predict failure of the element.
The NRC staf f stated that general guidelines for defining "f ailure" for each failure mode being considered should be developed. A meeting j
between representatives of the Mark I owners group and the NRC staff l
w311 take place in early June 1976 to develop such guidelines.
- b. Uith respect to the plant unique sensitivity analysis for upward loads, the NRC staff requested that GE investigate the effects of applying the load factor (LF) to the entire pressure-time history curve (i.e., to both the downward and the upward segments of the curve) in addition to applying the LF to the upward force segment of the curve alone,
- c. The NRC staff requested information which supports the use of a static analysis (rather than a dynamic analysis) of piping systems attached to the torus to predict stresses due to a postulated torus uplif t.
- d. The NRC staff stated that, in the application of the seceptance criteria for the attached piping, se should not be increased because of the dynamic strain rate effect.
- c. The NRC staff stated that the following information should also be included in the plant unique analyses:
- 1. A description.of the procedures utilized in calculating the " total"
- dynamic parameters (such as mass, stiffness, damping values, and I forcing functions) for the single degree of freedom equivalent model in terms of the actual system parameters.
- 2. A discussion of the effects of calculated torus uplift on the vent pipes and vent pipe bellows.
- 3. A discussion of the effects of calculated torus uplif t on the operability of active pumps and valves on piping lines attached to the torus.
l Representatives of the Mark I Owners Group stated that _ the reassessment of the Long Term Program Tasks has been delayed and that the Owners Group will not be prepared to discuss this reassessmen.t with the NRC staff until the l
first week in July 1976. ,
I G
t \
The NRC staf f stated that, based ~ upon the information which has been presented, application of a correction factor of 0.8 to the Most Probable Loads of January 28, 1976 is acceptable.
S. Stark, CE, described the preliminary design and test objectives of the 1/4 scale Mark I Containment testing facility. Enclosure 3 contains the slides used in this presentation. The NRC staff requested information related to future plans for thrco dimensional (3D) testing. R. Fernandez, EPRI, stated that ne;;otiations were in progress for developing a 3D testing program which would consist of a 1/12 scale test facility with multiple downcomers.
Representatives of the Ouners Group stated that they would keep the NRC staff advised of any future plans for additional testing.
/ ll 'l
- r s C.2.(Ja ..s.'.. f" John Guibert Operating Reactors Branch #3 Division of Operating -
Enclosures:
- 1. Attendance List
- 2. Slides
- 3. Slides t
l 9
ENCLOSLTRE 1 ATTENDANCE LIST MEETING ECTUEEN MARK 1 OUNERS CROUP AND NRC STATT MAY 13, 1976
_NNIE ORGANIZATIOJ John Gulbert NRC George !. car NRC
- h. D. Lim
- NRC/EB G. ilagchi NRC/EB Ricnard J. Stuart NRC/ DOR /ENG. BR.
Jack Kodrich NRC C. C. Laina.e NRC C. J. Andetson - NRC C. I. CrJmes NRC
- k. Tedesco NRC No r nan U. l'.chiard s NUTECll l R. E. Keever NUTECil ,
R. F. Petrokas NUTECil N. 7.. Macters GE S. J. Stark GC R.11. Buchholz GE L. V. Sobon GE U. E. Cooper Tcledyne Mat'l. Res.
J . A. llayward Teledyne flat 'l. Res.
C. W. Volf Jersey Central Power & Light B. Biava Jersey Central Power & Light T. T. Robin Southern Services K. R. Iy-Engar Southern Services G. Maisc Brookhaven Lab G.11. Neils Northern States Power D. Lynn Uhitt CB1 R. 11. Logue Philadelphia Electric Co.
R. F. Reedy Chicago Bridge & Iron W. F. Bauer Public Service E & G Co.
D. P. Galle Commonwealth Edison P. Kennedy Tokyo Elec. Power Co.
R. N. Smart NUS Co.
R. T. Fernandez EPRI F. E.'Gregor Detroit Edison Co.
l
NL1- 0 %.e; p DESCRIPTION OF SIIORT TERM PROGRAM PLANT UNIQUE TORUS SUPPORT SYSTEMS AND ATTACllED PIPING ANALYSIS Prepared for:
l Mark I Containmc t Owners Group 9
April 23, 1976 nutech
~
DESCRIt' TION OF Sfl0RT TERbl PROGRAb1 .
PLANT llNIQUE TORUS SUPPORT SYSTEh!S AND ATTACilED PIPING ANALYSIS TABLE OF_ CONTENTS Lags LIST OF PIGURES iii j
1.0 INTRODUCTION
1.1
- 2. 0 11ETil0D OF ANALYSIS 2.1 2.1 Downward Loads 2.1 2.2 Upward Loads 2.2 2.2.1 Torus Support Systems 2.2 2.2.2 Piping Attached to Torus 2.3 3.0 LOA 111NGS 3.1 4.0 CRITERIA 4.1 4.1 Base Caso Analysis 4.2 4.1.1 Torus Support System 4.2 4.1.2 Attached Piping 4.2 4.2 Load Sensitivity Analysis 4.3 4.2.1 Torus Support System 4.4 4.2.2 Attached Piping 4.4 4.3 Plant Unique Action Plan 4.5
- 5. 0 CONCLUSION 5.1
6.0 REFERENCES
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