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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] |
Text
_ _ _ _ - _ _ _ _ _ _ _ _ _ _
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[ e UNITED STATES j ,, ,
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ATOMIC ENERGY COMMISSION
- "# , W ASHINGloN. D C. 20%4%
l % ,, / Oct 301m ,
4 Files (Docket No. 50-263)
TilRU upann, Chief, ORB #2, L
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- SAFETY R VIEW OF !ONTICELLO FULL-TERM OPERATING LICENSE - SECOND ACRS SUDCOMMITTEE HEETING Representatives of Northern States Power Company (WSP) and of the ;
Directorate of Licensing (see Attachment 1) met in Washington, D. C. , !
on September 30, 1972, with ACRS Subcommittee members Mr. H. Etherington (Chairman), Dr.11. Isbin, and Professor W. Kerr to review the Monticello Nuc1 car Generating Station Unit No.1 in consideration of issining a full-term operating license (FTOL) for the facility.
AEC staf f met with the ACRS Subcommittee f or approximately 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> prior to the meeting with NSP to review in detail selected items of '
the AEC Saf ety Evaluation Report for the Monticello FTOL. Copies of the 4 separate petitions for 1 cave to intervene, all received within the last three days, were provided to each of the subcommittee members.
Dr. 1sbin noted that a draf t copy of a report prepared by the Directorato ;
of Regulatory Operations, " Evaluation of Incidents of Primary Coolant Release f rom Operating Reactors", has been inade available to the
' intervenors and suggested that NSP cotmnents on the draf t be solicited.
He was advised by the Licensing staf f that the report is a draf t under--
going review by regulatory management and a decision regarding.its release is not yet available.
Dr. Isbin referred to Neil Thompson's paper delivered at the recent Air Cleaning Conf erence and asked if we have reviewed it. He was inf ormed that we were f amiliar with the contents.
Dr. Isbin requested clarification of the inf ant doce values discussed on page 6 of our Saf ety Evaluation, lie was advised that the calculations for the Final Environmental Statement, f rom which the numbers in our report were taken, have been revised; therefore, this portion of our Saf ety Evaluation will be revised before it is released : to the public.
)'
The staf f review of the Backfit Supplement to Saf ety Guide No. 11 was discussed emphasizing that additional flow restrictors and check valve position indicators in the 60 instrument line containment penetrations connected to the core coolant system are not required because open ended failure of one of the lines without closure of the check valve nr isolation valve does not result in excessive releases of radioactivity in relation to 10 CFR 100 limits.
1 i
9212090317 721030 d i
PDR ADOCK 05000263 0 PDR y y-- % 7 y - p t--y-
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-3 Files OCT 3 0 IBM i
The Subcommittee noted that the depleted fuel shipping cask must be
. Iowered 150 feet for transportation to offolte facilities for fuel recovery and asked for details of this operation. We replied that we did not review fuel handling accidents in our current evaluation I because we were not aware of any new concern that had arisen in this l area since the AEC Safety Evaluation for the POL was issued in 1 March 1970. We agreed to look into the subject and to advise the i SubcommitLee of our findings. ]
The meeting with NSP was opened with remarks by W. W. Larkin, Vice .
President of NSP, who declared that NSP is dedicated to protecting
- the health and safety of the public while providing reliable-electric '
power for the customers. The meeting proceeded according to the agenda-i (Attachment 2) previously agreed upon by the ACRS Subcommittee and NSP.
Zero release of liquid ef fluents for the past-six months, as reported-in the January June 1972 semiannual report by NSP and in oral discussion during the meeting, led to questions relative. to the tritium buildup in primary coolant. NSP representatives stated that during this period of time when no radioactive liquid was released into the ;
Mississippi River, it was necessary to add 20 - 30,000 gallons of makeup water per month. NSP indicated that this amount of water is -
lost in the evaporative process and will. limit the tritium concentration in the primary coolant to levels well below the tritium concentrations observed in PWRs, although they (NSP) have not projected to the future or attempted to observe the tritium buildup in the coolant as the effects of zero release of liquid effluents become more evident. It also was admitted by NSP that the new gaseous waste cleanup system to be placed in operation early in 1973 could significantly reduce the evaporative release route for tritium, assuming that zero release of liquid effluents is maintained and that, in time, the tritium concentration could be of some concern but not at the same icvel as PWRs because of the lower rate of producing tritiun in BWRs.
The Subcommittee commented that the 0.75 Ci/yr iodine release is excessive since it results in 67 mR thyroid dose to a child due to milk ingestion. NSP replied that a release of this magnitude would require continuous steam leaks in the turbine building in excess of 2400 lbs/hr,'a value that they believe is excessive. (2400 lbs/hr corresponds-to $7.500 lbs/ day, 1,73 x 10 6 lbs/mo or 210,000 gals /mo' . .
our' observation .that 210,000 gals /mo is far in excess of the evaporative losses that, as NSP noted earlier, have been measured over the last 6-month period with zero liquid effluent release - this rationale was not part of the dialogue _ between the Subcommittee and NSP1
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- i Files Oct 3 0 W2 ,
The Subcommittee was informed by the GE representative that one second
- closure of all MSIVs will result in a 37 psi pressure peak, a value ;
that is 54 psi below the overpressure setting of the first safety. i valve. The transient does not cause heat flux to exceed 100%. The turbine stop valves, however, can close fast enough to cause heat flux in excess of 100% because the reactivity insertion due to pressurization exceeds the negative reactivity due to reactor. scram.
- Discussion of containment pressurization incidents revealed that ;
pressure switches have been added to the safety valves to more accurately- i determine which valves open in containment pressurization incidents.
Steam lines are to be instrumented to measure vibration and record events that may activate overpressure safety valves. This program is a f ollowup to incidents. that have already occurred and will. enable a +
more accurate determination of the cause of premature safety-valve i actuation, delayed operation of relief valves, or valves that stick open.
i Meteorology tower ef fectiveness during emergencies is being reevaluated.
The height of towers may be increased frum 140 f t to the height of the of f-gas stack (vm300 feet).
It was noted that the prairie Island Nuclear Power plant will monitor for primary system cracks using acoustic ; triangulation. Verification that the vent line vacuum breakers are closed and also containment .s inerting in relation to post-accident hydrogen generation due to radiolysis was discussed briefly. The Subcommittee restated their belief that Icak detection and location equipment can be improved.
Af ter a caucus, the Subcommittee Chairman announced that he would recommend a full ACRS committee review of the NSP application for a FIOL, but he stated that the date for such a meeting was not certain.
The licensee was advised that he need not preparc. formal presentations '
on any subjects for the full Committee meeting; .however, .it was noted that the ACRS may have questions in all the areas reviewed by the '
Subcommittee, but very likely on the following topics:
J ECCS State responsibility f or emergency procedures
-; i
. Coolant Icakage-Post-accident hydrogen control i
t- i
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, Files -
4- Oct 3 0 IN2 The written material assembled for the ACRS Subcommittee meeting van distributed as a visual aid prior to the meeting and is availab.te
- for reference in the project work file.
k\s - e ~
l J ames J. Shea Operating Reactors Branch #2 Directorate of Licensing-
Enclosures:
- 1. List of attendees
- 2. Agenda cc w/encle:
A. Giambusso, L:RP M. Rosen, L RP ,
D. J. Skovholt, L:0R T. J. Carter, L:0R D. L. Ziemann, L 0RB #2 J. J. Shea, L 0RB #2 R. H. Diggs, L:0R3 #2 <
J. Gallo, OGC PDR Local PDR t
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4 Attendece - ACRS Subcommittee meeting on September 30, 1972 Northern States Power Company a
Elmont Charles Ward Leon Roy Eliason Dwayne Glenn Fitzgerald Marion Jonn Robinson '
Marcus Henry Voth
- Morgan lienry Clarity Cerald llugo Neils Charles Edward Larson Martin Francis Dinville Gordon Herbert Jacobson Douglas Dean Antony Willard Enos Anderson James Robert Pasch Melford Thomas Opstad Jay Eliott Silberg Wade Wadsworth Larkin Peter Dean Arrowsmith GE - San Jose ,
John Lannean Benson Lowell Herman Frauenholz
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. 4 ATTACli!!ENT 3 <
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i AGENDA MONTICELLO ACRS SUBCOMMITTEE MEETING (second day) a1P Street Offices - Saturday, September 30
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- 30 AM Convene - 5:00 PM Caucus - 5:30 PM Adjourn
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2.
Management report of Monticello operations - Vade Larkin Monticello's ability to comply with State requirements - Wade Larkin
- 3. Operating experience at Monticello - Chuck Larson
- 4. Operating experience at other BWR's that will be applicable to Monticello - Morgan Clarity and Gerry Neils
- 5. Expected performance of improved radvaste system compared to proposed Appendix I - Mel Opstad
- 6. Main steam line isolation valve system - Chuck Larson and Marc Voth
- 7. Instrumentation and control systems performance - Chuck Larson and Gordy Jacobson
- 8. Provision to follow the course of an accident - Chuck Larson and Leon Diason
- 9. E::ergency plans and State participation - Al Ward and Leon Biason ,
- 10. In-service inspection results - Gerry Neils L1. Continuing Q. A. program and specific methods for ruhi4m .naintenance - Gerry Neil 1.2. Leak detection effectiveness - Chuck Larson and Jim Pasch
- 13. Protection against turbine generated missiles - Jack Benson
- 14. Vibration and loose parts monitoring - Gerry Neils
- 15. Compliance with AEC Safety Guide - Duane Fitzgerald and Paro Voth
- 16. Pipe whip protection - Jack Benson
- 17. Anticipated transients without scram - Marc Voth
- 18. Instrumentation to detect fuel failures - Gerry Neils & Leon Hiason
- 19. ECCS evaluation and observe performance - Parc Voth j 20. Calculated consequences of a rod drop accident - Maro Voth and Jack Benson
- 21. Discussion items 4
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MONTICELLO ACRS SUB00MMITTEE VIETING !
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- September 30, 1972 l
Applicant Attendees ;
W V Larkin, Group Vice President - Power Supply E C (A1) Vard, Director, Engineering Vice Presidential Staff Gerry Neils, General Superintendent - Nuclear Power Plant Operation Chuck Larcon, Monticollo Plant Manager Morgan Clarity, Superintendent - Monticello Plant Enginoering & Radiation Protection Leon Eliason, Monticello Radiation Protection Engineer ,
Marty Dinville, Monticello Plant Engineer - Operations Gordy Jacobson, Plant Engineer - Technical Doug Antony, Engineer - Operations Villard Anderson, Plant Superintendent - Operations & Faintenance Jim Pasch, Engineer - Operations Karc Voth, Administrator - Nuclear Support Services Mol Opstad, Nuclear Engineer IEGAL COUNSEL Jay Silberg, Shaw, Pittman, Potts, Trowbridge & Madden i GNERAL ELECTRIC Jack Benson, Manager of Safety and Licensing Operational Plants Frit Prauenholz, Specialist - Safety. and Licensing CONSULTANTS-Dr Duane Fitzgerald, Senior Staff Consultant - NUS Corporation 4 Dr John Robinson, Nuclear Engineering - Black & Veatch' Pete Arrowsmith, President - Suntac Nuclear Corporation 1 >
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