|
|---|
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
{{#Wiki_filter:. . .
g) %,
umToo suTos ATOMIC ENERGY COMMISSION k
q , ,
us,u ~m e,~ o c ems m
W - } #g SEP 2 7 mz Files (Docket No. 50-263)
THRU: I L .3 Z mann, Chief, ORB #2, L ax MONTICELLO - AC
'UBCOMMITTEE REVIEW FOR FULL-TEPJ! OPERATING LICENSE llembers of the t!onticello ACRS Subcommittee, H. Etherington and H. S. Isbin, met in Washington D. C. , on September 11, 1972, with Nortnern States Power Company (NSP) and AEC Directorate of Regulation (DR) representatives to review the NSP application for a full-term operating license (FIDL) dated June 15, 1972, and the AEC Directorate of Licensing (DL) Saf ety Evaluation dated August 25, 1972. DL was questioned about General Electric report NEDO 10299 (January 1971),
Flow Distribution Measurements in Monticello Core, specifically whether or not we had considered this report in the Monticello Safety Evaluation for a FTOL. We responded that the repor t had nut been evaluated as part of the DL Safety Evaluation.
Mr. E. C. (A1) Ward was the spokesman for the NSP representatives when they joined the meeting and began their formal presentation. -An agenda for the meeting and a list of NSP attendees was distributed while Mr. Etaerington, Chairman of the Subcommittee, made his opening remarks which included plans f or a second Subcoamittce meeting prior to the full ACRS meeting which, at the conclusion of the meeting, was tentatively scheduled for October 5 or 5, 1972.
NSP f ollowed the attached agenda with f requent references to their FTOL application. Dana Ditmore of General Electric (GE) presented -
the f ollowing comparative fuel information (not previously presented) as a oasis f or the conclusion that GE fuel clad creepdown is negligible and that, in accordance with GE NEDO 1050, " Fuel Irradiation Experience",
supported by extensive visual, neutronic and gacma graph examination of GE irradiated fuel, there is no evidence of fuel clad collapse and none is expected.
Clad creepdown is an important clad collapse consideration, as GE sees it, based on the limited nonproprietary information on Ginna fuel clad collapse made available to them by the AEC.
1 9212090345 720927 PDR ADOCK 05000263 O PDR
.______JL_______-__________ _ _ _ _ _ ___________ __ _
Files SEP 2 71972 COMPARISON O_F GE AND_WESTINGH0_USE FUEL Fbnticello - Ginna Fuel- UO 2
UO 2
Density (percent of theoretical) 95 90-92 & 94 Fuel diameter - inches 0.487 0.367 Gap - inches 0.012 0.0065 Clad Zircaloy Zircaloy Clad diameter - inches 0.531 0.396 Clad thickness 0.032 0.024 Coolant pressure - psig 1015 2250 Mean clad temperatu+ e *F for top 1/3 core 585 660 Clad primary membrane stress psi 8600 18,500 GE representatives reported that 280 TIP scans wera part of more than 7500 TIP scans reviewed by GE f or evidence of nuclear signal perturbation that might be indicative of enlarged f uel pellet spacing gap or clad collapse. No such indications were expected or discovered. He also noted that total length of fuel columns had not changed by more than 0.5% and that this value may be lower because good preirradiation ref erence measurements were not made.
The Subcommittee requested:
- 1. NSP to furnish copies of all agreements with the State of Minnesota or other state agencies.
- 2. NSP to provide isotope release limits permitted by the State compared with proposed Appendix I to 10 CFR Part 50.
- 3. A point by point review of the P. A. Morris October 1971 letter to USP.
4 e
Files -
3- ;
r r
- 4. Reconsideration of the significance of the grinder caused ,
torus damage.
~
- 5. Reevalnation of the effect on fuel life of transients such as pribary u stem / blawdowns. [CE had indicated that fuel rous with hydride blisters could pop earlier but that net (end of core life) fuci rod douage would not be increased by such blowdown incidents.)
- 6. A reanalysis by General-Electric of the consequences of '
I uccond, or the f astest possible, isolation valve closure instead of the minimum c) sure time of 3 seconds as currently required by the Technical Specifications.
- 7. An evaluation by DR of comparative isolation valve closure and Icak rateo for operating BWRs.
- 8. An evaluation by DR of of f-gas release experience as f uel depletes at other BWRs, and modifications that have been made at other operating LWRs.
- 9. An analysis of the effects of transient iodine releases during power level changes or blowdowns.
At the conclusion of the meeting, the Chairman- confirmed the necessity ,
for another Subcommittee meeting prior to the full ACRS meeting early in October to review in detail (2-3 hours) with the DL staf f the DL Safety Evaluation for Monticello', to consider NSp evaluation of a number of significant abnormalities such as those revealed by NSP in Attachment 7, and other generic items to be identified by Dr.1sbin and made available to NSP through the DL staff. Dr. Isbin was to 4
consult with tne full ACRS committee with regard to desirability for the -
DL staf f or the ACRS to meet with state officials to review arrange-ments aud agreements between NSP and State of Minnesota agencies as related to accidents at Monticello that could affect the health and -
safety of the public, and advise us of the outcome.
~
'i
. - ~
ames J hea
.bperating Reactors Branch #2 Directorate of Licensing
Enclosures:
- 1. Agenda
- 2. List of significant abnormalities cc: See attached list
- _n_ _ _ _ . _ _ _ ,- -__ --__u..- - . . , _ - -
4 .. . , . . . - . _ _ _ . . -
- _ _ _ _ . _ _ . _ . _ . , _ . _ . _ _ . _ _ _ . - ~ . _ . _ _ - . . - _ . _ . _ . _ _ _ . _ . _ .
ec w/enclosuress AGiambusso, L
- . DJSkovholt, L TJCarter, L
, DLZiemann, L i JJShea, L 2 RMDiggs, L -{
l, 4
1 i
t e
i i
r I
't b
5 I e
t l r s
P b
I 3
. i d
5 I
1<
i
+
?
v
,B
'l'
- h r
e i-
' I
-T P
, ' - i
.*; Attachment #1 >
s 'I i
t
.i
{
MON"'ICELI4 ACRS SUBCOMMITTEE IG:ETING.
September 11, 1972 Ar,ENDA 1 IntYoductiOD ............................................... Al Vard i 2 Statue of Stato Agencies ................................... Al Ward 3 Statun of Intervenors ...................................... Gerald Charnoff- l 4: General Office Management and Plant Organizatic ........... Ice Mayor ti 5 ?hysical Changea to th+ Plant .............................. Marc Voth j 6 significant Operating Abnormalities or Deficiencies ........ Morgan Clarity 7 Other Plant Incidente Related to Montice.llo ................ Morgan Clarity i
8 helear Fuel - Generic Status .............................. Dana Ditmore 9 holonr Fuel - Monticellok................................... Maro Voth ;
10 Post-Accident-l!ydrogen Control ...............................
Duano Fitzgere AP 11 January 10, 1970 ACRS Letter Iter.o - S tatus Report . . . . . . . . . . . Duano Fitzgerald.
Discussion Items h
r e, _ I b
5
.-~....;,.. , . __, , - ,_ . , _ ,. . 4. , . . _ .
,.. _ , ,.-. , a. i
c u ,. -
. . a sma- = - u- -+<a s.. a-er--u - >w.. + -. - . - - . - . -.-. - -- .a,u... a .a. a. .xa ~ a.asu - . - > . --
l
)
I MONTICELIO ACRS SUBCOMMITTEE MEETING September 11, 1972- l Appliennt Attendees {
NSP --
E O (A1) Ward, Director, Engineering Vice Presidential Start- i Lee Mayer, Director - Nuclear Support Services , -;
4 i
Gorry Neils, conorni Superintendent - Nuclear Power Plant Operation ,
Chuck Laroon, Monticollo Plant Manager l Morgan Clarity, Superintendent Monticello Plant Engineering & Radiation Protectiot :
Leon Eliacon, Monticello Radiation Protection Engineer !
a Marty Dinville, Monticello Plant Engineer - Operations
=i Marc Vgth, Administrator - Nuclear Support Services :
Don Bohn, Supervising Environmental Engineer. ,
LEGAL COUNSEL Gerald Charnoff, Shaw, Pittman, Potto,. Trowbridge & Madden GENERAL ELECTRIC Jack Benson, Manager of Safety and Licensing Operrator 1 Plstnts Fritz Frauenholm, Specialist - Safety and Licensing Dana Ditmoro, Manager of NPD Fuel Applications 00MSULTANTS Dr Duane Fitzgerald, ~ Senior Staff Consultant - NUS Corporation
'Dr John Robinson Nuclear' Engineering - Black & Ventch
.)
9 6
. - - - ' w.- e,, .-e<.-.c+. -*r ,~-+,v-v-ec--w- m- ,, 1-,5= --- +- e- y e ----r-+-y -ne 2
.-+-4a 9 4 g--d ,t , -w++! 4- v= - y
i
, , .o
. J tr f,UllCO.'Mlli t I, r,7 [ T l fn %) 1 *, . .
-t
. )
S rne..a r y 0011 I r < r, f .v t4. v f nvni v i,g;
- . slP hifIe htik Ittit't.1klfn1 h!'rg y tei ,] { { j p r; nrpj [)# f j p { , qc l p r; I
/- ,
/
- 1. TW fiystren and pianp prtibinne. I i
P. lA> i n t ur e r. p. ira t or lovel probimer..
i
- 3. HPCI cyntun, including oP, problonn.
3 4 Recire ptrnp and pterp teal probluns. !
v
- 5. Rolinf and safety valve problunn.g
- 6. Air ejector water loop seal problems. , -f 4
~
- 7. RHR eervice water cycten problens.
- 8. Core reactivity problen.
.p i
- 9. MS flow restrictor problems. i
- 10. MSIV probluns. ,
F 4
L P
i, .
p l ~.
L l, *
.?
?
g' >
l1 l
, . , , ._ , - . . . . - + - ; -- - -4 ,,~~--r r r- -+ ~ -------tm-*~D*"-
' ' * ' + - ~ ' ' ' " ~ ' ' *}}
