Semantic search
Jump to navigation
Jump to search
Issue date | Title | Topic | |
---|---|---|---|
ML20206G515 | 30 April 1999 | Summary of 990421 Meeting with Util Re Error Involving Recent ATWS Analyses Using GE Odyn Code.List of Attendees Encl | Reactor Vessel Water Level |
ML20207L771 | 11 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 | |
ML20207L761 | 9 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 | |
ML20202J203 | 28 January 1999 | Summary of 990107 Meeting with NSP Re Recent License Amend Request for PINGP Ts.List of Meeting Participants & NSP Meeting Presentation Slides Encl | Boric Acid |
ML20196F610 | 1 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 | |
ML20249C471 | 24 June 1998 | Summary of 980611 Meeting W/Wog in Rockville,Md Re Part Length CRDM Issues.List of Attendees & Matl Presented at Meeting Encl | Probabilistic Risk Assessment |
ML20206S630 | 17 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 | |
ML20198Q588 | 31 October 1997 | Summary of 970910 Meeting W/Util in Rockville,Md Re Status of BWR Power Uprate Program.List of Attendees,Agenda & Handouts Encl | |
ML20217E123 | 25 September 1997 | Summary of 970826 Meeting W/Nsp Re Plant Revised MSLB Containment Pressure Response in Anticipation for License Amend Request to Reduce Boron Concentration in Boric Acid Storage Tanks.List of Attendees & Handouts Encl | Boric Acid |
ML20211F807 | 22 September 1997 | Summary of 970911 Meeting W/Northern States Power Co in Rockville,Md Re Equipment Environ Qualification Program. List of Attendees Encl | |
ML20140H918 | 9 May 1997 | Trip Rept of 970410-11 Visit to Ul to Observe full-scale Fire Endurance Test of 1 & 3 Hour Versawrap Fire Barrier Sys.List of Participants Encl | Fire Barrier |
ML20137W331 | 17 April 1997 | Summary of 970407 Meeting W/Util & Transco Products,Inc Re Versawrap,New Electrical Raceway Firewrap Sys.Attachment 1 Describes Components of Typical Veraswrap Barrier & Attachment 2 Re Transco Products,Inc Test Procedure Encl | Fire Barrier |
ML20132D133 | 13 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 | |
ML20057F281 | 12 October 1993 | Summary of 930929 Meeting W/Util Re Installation of Water Level Monitoring Instrumentation at Plant.List of Attendees & Presentation Slides Encl | |
ML20149D605 | 15 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 | Generic Fundamentals Examination License Renewal Inattentive |
ML20056F817 | 9 August 1993 | Summary of Operating Reactors Events Meeting 93-29 on 930804.List of Attendees & Viewgraphs Encl | |
ML20128H958 | 10 February 1993 | Summary of 930202 Meeting W/Util Re Proposed Amend Requests Currently Under Review.Amends Included,Refueling & Fuel Handling Spec Changes,Containment Penetration List Removal & Instrumentation Spec Changes | |
ML20217C512 | 3 July 1991 | Summary of Operating Reactors Events Meeting 91-12 on 910626 | |
ML20151Q813 | 3 August 1988 | Summary of Operating Reactors Events Meeting 88-031 on 880802.Viewgraphs & List of Attendees Encl | |
ML20154A899 | 4 May 1988 | Summary of Operating Reactors Events 88-18 Meeting on 880503 Re Events Which Occurred Since 880426 Meeting.List of Attendees & Viewgraphs Encl | |
ML20237G389 | 27 August 1987 | Summary of Operating Reactors Events Meeting 87-25 on 870804 Re Events That Occurred Since 870728 Meeting.List of Attendees,Viewgraphs & Summary of Reactor Scrams Encl | |
ML20236K670 | 13 July 1987 | Summary of 870713 Public Hearing on Northern States Power Co Fuel Rod Consolidation Pilot Project in St Paul,Mn | Chernobyl |
ML20215C872 | 8 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 | |
ML20213F064 | 10 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 | Reactor Vessel Water Level Ultimate heat sink |
ML20215G056 | 7 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 | Backfit |
ML20199L647 | 26 June 1986 | Summary of Operating Reactors Events Meeting 86-21 on 860623.Attendance List & Viewgraphs Encl | Anchor Darling |
ML20138N984 | 19 December 1985 | Summary of 851122 Meeting W/Licensees & Westinghouse to Present Status of Program for Developing New Upper Plenum Injection Evaluation Model.Nonproprietary Viewgraphs,List of Attendees & Agenda Encl | Fuel cladding |
ML20137Y664 | 25 November 1985 | Summary of 851106 Meeting W/Util & B&W Re Reliability of Auxiliary Feedwater Sys.List of Attendees Encl | Weak link |
ML20237B067 | 25 November 1985 | Summary of 851106 Meeting W/Util Re Reliability of Auxiliary Feedwater Sys.List of Attendees & Licensee Viewgraphs Encl | Weak link |
ML20209G211 | 23 August 1985 | Trip Rept of 850715 Site Visit to Participate in INPO Training Accreditation Site Team Activities.Weaknesses Included Lack of Accreditation for Mgt Training & Evaluation Criterion | |
ML20133F753 | 31 July 1985 | Summary of 850626 Meeting W/Util & Westinghouse Re Upcoming Changes to Reactor Internals & Impact on Tech Specs.Licensee Plans to Change from Exxon Fuel to Westinghouse Fuel.Agenda & Attendance List Encl | |
ML20133E066 | 25 July 1985 | Summary of 850628 Meeting W/Utils & Westinghouse Re Status of Development of New Upper Plenum Injection Evaluation Model.List of Attendees & Agenda Encl | |
ML20126L233 | 1 May 1981 | Summary of 810429 Meeting W/Pwr Owners Group Re Thermal Shock to Reactor Pressure Vessels.All Parties Agree That Thermal Shock W/Subsequent Repressurization Is Safety Concern Needing Prompt Evaluation | |
ML20062H356 | 12 December 1979 | Summary of 791126 Meeting W/Westinghouse & Util Re Base Metal Cracking in Reactor Vessel Nozzles Under Stainless Steel Cladding | |
ML20062F559 | 12 December 1978 | Summary of 781026 Meeting to Discuss Tech Specs for Secondary Water Chem,Reactor Coolant Activity & Secondary Coolant Activity | |
ML20125A420 | 11 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) | Hydrostatic |
ML20196H398 | 5 July 1978 | Summary of 780622 Meeting W/Westinghouse Owners Group to Discuss Results of Phase a of three-phase Plan & Current Schedule for Resolution of Asymmetric LOCA Loads Isssue.List of Attendees Encl | |
ML20125C562 | 1 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 | |
ML20125B964 | 20 March 1978 | Summary of 771027 Meeting W/Ge & Mark I Owners Group Re multiple-subsequent Actuations of Safety/Relief Valves Following Isolation Event | |
ML20127A468 | 1 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 | |
ML20140G497 | 9 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 | |
ML20125C568 | 3 February 1978 | Summary of 780126 Meeting W/Nsp & GE Re Proposed Plant Spent Fuel Pool Expansion | |
ML20125B996 | 29 December 1977 | Summary of 771215 Meeting W/Util Re Fall 1977 Facility Feedwater Nozzle & Control Rod Drive Return Line Nozzle Mods | |
ML20127K193 | 11 November 1977 | Trip Rept of 771007 Visit to Monticello Nuclear Plant Re Licensee'S Effort to Maintain Occupational Radiation Exposures ALARA | High Radiation Area |
ML20127H614 | 11 November 1977 | Trip Rept of 771007 Visit to Facility to Observe Licensees Effort to Maintain Occupational Radiation Exposures ALARA During Repair of Feedwater Nozzles | High Radiation Area |
ML20127H636 | 1 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 | |
ML20127H380 | 15 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 | |
ML20127H395 | 14 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 | Earthquake |
ML20127H277 | 13 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 | |
ML20245C321 | 11 July 1977 | Summary of 770525 Meeting W/Westinghouse & Util Group Members Re Efforts to Prevent Reactor Vessel Overpressurization.W/O Encls |