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Administration
- Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting
Results
Other: ML20076E880, ML20079M106, ML20080E109, ML20100G880, ML20100G888, ML20100H212, ML20112G667, ML20127J807, ML20135B301, ML20135D754, ML20137H372, ML20137S741, ML20141P181, ML20154K144, ML20197C598, ML20197G513, ML20205C845, ML20206B459, ML20207K470, ML20211P495, ML20215E408, ML20215G100, ML20235G758
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MONTHYEARML20076E8801983-05-17017 May 1983 Responds to NRC 830413 Order Re Environ Qualification of safety-related Electrical Equipment,Per 10CFR50.49.Environ Qualification Records Audit Will Be Completed by 831231 Project stage: Other ML20080E1091983-08-15015 August 1983 Provides Followup to Util Re Environ Qualification of safety-related Electrical Equipment. Justification for Continued Operation W/Components Not Fully Qualified Provided Project stage: Other ML20079M1061984-01-0909 January 1984 Advises NRC Re Status of Three Commitments Made in Util Concerning Environ Qualification of safety-related Electrical Equipment.Valve Actuators Tested & Successfully Passed HELB Tests Project stage: Other ML20100G8881984-09-11011 September 1984 Four-Minute Isolation of Postulated Steam Line Breaks at Fort St Vrain Nuclear Generating Station Project stage: Other ML20112G6671984-12-27027 December 1984 Informs of Efforts to Environmentally Qualify Certain post-accident Monitoring Equipment Per 10CFR50.49.Equipment Identified in Reg Guide 1.97 & Existing in Harsh Environ Will Be Qualified by 850331 Project stage: Other ML20108A2121985-02-0404 February 1985 Informs of Receipt of Generic Ltr 84-24 on 850121 & Request for Addl Info on Environ Qualification of Electrical Equipment on 850128.Responses to Both Ltrs Will Be Provided by 850328 Project stage: Request ML20100H2121985-03-25025 March 1985 Forwards Response to NRC 841227 Order Re Certification of Compliance w/10CFR50.49 (Generic Ltr 84-24).Util Previously Submitted Ltrs Re Environ Qualification of safety-related Equipment in Response to IE Bulletin 79-01B Project stage: Other ML20100G8801985-03-28028 March 1985 Forwards Addl Info Re Environ Qualification Program. Response to NRC 850128 Concerns & Summary of Completion Schedule for Outstanding Items Encl Project stage: Other ML20237L1731985-03-29029 March 1985 Notification of 850403 Meeting W/Util in Bethesda,Md to Discuss Equipment Qualification Project stage: Meeting ML20127J8071985-06-11011 June 1985 Maintains Util Position of Full Compliance w/10CFR50.49 in Response to Eh Johnson 850611 Inquiry Re Environ Qualifications of Electrical Equipment Important to Safety. Responses to Each Concern Presented in Encl Project stage: Other ML20237L1551985-06-25025 June 1985 Submits Daily Highlight.Notifies of 850702 Meeting W/Util in Bethesda,Md to Discuss State of Compliance of Plant W/ Equipment Qualification Rule 10CFR50.49 Project stage: Meeting ML20132B9171985-07-11011 July 1985 Discusses Resolution of Technical Issues of Aging & Operability Times Per 850702 Meeting Re Environ Qualification Program.Hold on Reactor Power to 15% Proposed as Initial Limitation Project stage: Meeting ML20132F0721985-07-19019 July 1985 Safety Evaluation Documenting Deficiencies in Licensee Program for Environ Qualification of Electric Equipment Important to Safety.Licensee Response to Generic Ltr 84-24 Inadequate.However,Operation at 15% Power Authorized Project stage: Approval ML20132F0231985-07-19019 July 1985 Forwards Safety Evaluation Re Environ Qualification of Electric Equipment Important to Safety & Authorizes Interim Operation in dry-out Mode at Max 15% of Rated Power,Based on Listed Conditions,Until Technical Review Completed Project stage: Approval ML20134M0161985-08-20020 August 1985 Submits Discussion of Technical Issues Re Environ Qualification Program Raised During Meetings W/Nrc.Aging & Operability Time Program Operator Response Time,Temp Profiles & Shutdown Cooling Paths & Equipment Evaluated Project stage: Meeting ML20135B3011985-08-30030 August 1985 Forwards Justification to Operate Facility at Reduced Power Level.Requests That NRC Provide Concurrence for Facility to Be Operated at 8% Power Level for Period of Time Not to Exceed 45 Days.Operation Does Not Pose Undue Safety Risk Project stage: Other ML20135D7541985-08-30030 August 1985 Advises That Rev of Emergency Procedures Committed to in Deferred to Coincide W/Final Environ Qualification Program Documentation.Procedure Revs at This Time Will Cause More Confusion than Clarity for Operators Project stage: Other ML20205C8451985-09-10010 September 1985 Forwards Info Supporting 850830 Request to Operate at 8% Power to Facilitate Core Dryout for 45 Days,Per 850826,0903 & 04 Telcons.Moisture Removal Needed to Maintain Conditions Prescribed in FSAR & Tech Specs Project stage: Other ML20205C4811985-09-11011 September 1985 Provides Commitment That Operating Procedures & Operator Training Described in Providing Addl Info in Support of Request to Operate at Up to 8% Power Will Be Complete Prior to Withdrawal of Control Rods Project stage: Withdrawal ML20137S7411985-09-23023 September 1985 Forwards Addl Calculations,Clarifying Util Re Predicted Fuel/Pcrv Liner Temps Resulting from Design Basis Event from 8% Power & Subsequent Reactor Cooling Utilizing Liner Cooling Sys.Calculations Confirm Original Position Project stage: Other ML20137H3721985-11-26026 November 1985 Memorandum & Order Granting Extension of 851130 Deadline for Environ Qualification of Electrical Equipment to 860531 & Approving Proposal to Allow Operation w/35% Reactor Power Limit During Interim.Served on 851127 Project stage: Other ML20151N7211985-12-27027 December 1985 Forwards Response to 851105 Request for Addl Info Needed to Determine If Environ Qualification Program Complies W/ Requirements of 10CFR50.49.Sys Description & Temp Profiles Used in Environ Qualification Program Also Encl Project stage: Request ML20141P1811986-01-29029 January 1986 Rev 00 to Justification/Analysis:Environ Qualification of Square D Pressure & Temp Switches Project stage: Other ML20141M8081986-02-14014 February 1986 Advises That DBAs Re Permanent Loss of Forced Circulation & Rapid Depressurization of Reactor Vessel Must Be Addressed in Equipment Qualification Program.Util Cooperation W/Program Mods Confirmed During 851029 Meeting Project stage: Meeting ML20154K1441986-02-28028 February 1986 Forwards Addl Info Re Environ Qualification,Per 851105 Request.Encl Info for Three Line Break Scenarios in Reactor Bldg Will Allow Independent Verification of Temp Profiles Obtained from Ga Technologies Using Computer Programs Project stage: Other ML20142A0441986-03-12012 March 1986 Summary of 860221 Onsite Meeting W/Util,Inel,D Benedetto Assoc,S&W,Tenera,Ned & NPD Re Equipment Qualification Program & Steam Line Rupture Detection & Isolation Sys Project stage: Meeting ML20141P1771986-03-14014 March 1986 Summary of 860130 Meeting W/Util,Inel,Tenera & Sargent & Lundy Re Equipment Qualification (EQ) Program.List of Attendees,Test Profiles & Review of Sample EQ Package Encl Project stage: Meeting ML20205S2591986-04-10010 April 1986 Summary of 860326 Site Meeting W/Util,Dibenedetto Assoc,Inc, Sandia & Sargent & Lundy Re Status of Qualifications of 10CFR50.49 Cables & Maint Records History Review.Viewgraphs & Attendees List Encl Project stage: Meeting ML20204A3181986-05-0101 May 1986 Provides Status Summary of Environ Qualification Program. Addl Details on Program Contained in 860501 Draft Environ Qualification Submittal.Major Equipment Replacements Listed Project stage: Draft Other ML20197G5131986-05-12012 May 1986 Requests Concurrence Re Inclusion of DBA in Environ Qualification Program Per Berkow .Util Will Not Environmentally Qualify Electric Equipment to Mitigate DBA-1 & DBA-2 Since Equipment Not Exposed to Harsh Environ Project stage: Other ML20198H4561986-05-27027 May 1986 Summary of 860505 Meeting W/Util Re Status of Equipment Qualification Program.Considerable Work Remains Before Approval of Full Power Operation Can Be Granted.Staff Recommended Util Continue to Complete Program Project stage: Meeting ML20205S2341986-06-0101 June 1986 Summary of 860502 Meeting W/Util & Inel in Bethesda,Md Re Equipment Qualification Program Problem Areas.Attendees List & Supporting Documentation Encl Project stage: Meeting ML20206R6241986-06-20020 June 1986 Forwards Environ Qualification Submittal Re Activities to Assure Compliance w/10CFR50.49 & Incorporating Comments on Draft 860502 Submittal.Evaluations Will Be Available for Review Before Request for Release to Full Power Project stage: Draft Request ML20203B6181986-07-15015 July 1986 Summary of 860613 Meeting W/Util in Bethesda,Md Re Status of Plant Equipment Qualification Program.List of Attendees, Environ Qualification of Plant Safe Shutdown Cable & Cable Qualification Binders Encl Project stage: Meeting ML20204H6531986-07-31031 July 1986 Responds to 860724 Request for Documentation Re Use of Thermal Lag Analysis in Environ Qualification of Electrical Equipment in Plant.Thermal Analysis Will Be Performed Per Rev 3 to CENPD-255-A Project stage: Request ML20206P5971986-08-15015 August 1986 Summary of 860724 Meeting W/Util,Inel,Wyle Labs,Sargent & Lundy & Tenera in Bethesda,Md Re Util Draft Documentation to Justify Qualification of safety-related Cabling at Plant. List of Attendees Encl ML20197C5631986-10-30030 October 1986 Forwards Draft FATE-86-117, Review of Convection Heat Transfer Coefficients Utilized in Fort St Vrain Main Steam Line Break Analyses, Technical Evaluation Rept (Ter).Ter Addresses Details Used in Temp Profile Calculations Project stage: Draft Approval IR 05000267/19860251986-10-30030 October 1986 Insp Rept 50-267/86-25 on 860816-0930.Violations Noted: Failure to Follow Procedures,To Review Mod Control Procedures & to Sufficiently Document Design Verification Project stage: Request ML20197C5981986-10-31031 October 1986 Review of Convection Heat Transfer Coefficients Utilized in Fort St Vrain Main Steam Line Break Analyses, Technical Evaluation Rept Project stage: Other ML20214Q0951986-11-25025 November 1986 Summary of 861027 Meeting W/Util to Discuss Schedule for Ie/Nrr Insp of Equipment Qualification Program.Attendance List & Viewgraphs Encl Project stage: Meeting ML20214U7071986-12-0202 December 1986 Summary of 861120 Meeting W/Util,Ornl,Ga Technologies & Eg&G Re Temp Profiles for Equipment Qualification.List of Attendees & Viewgraphs Encl Project stage: Meeting ML20215E4081986-12-12012 December 1986 Forwards Analyses of Three Steam Line Break Scenarios for Reactor Bldg & Three Scenarios for Turbine Bldg Using Convective Heat Transfer Coefficient of 1.0,per NRC 861120 Request Project stage: Other ML20215G1001986-12-19019 December 1986 Forwards Second Formal Submittal Re Turbine Bldg Temp Profiles Resulting from Steam Line Breaks,Per 861120 Request.Composite Temp Profile Curves Originally Submitted as Basis for Environ Qualification Program Appropriate Project stage: Other ML20207K4701986-12-31031 December 1986 Final Review of Convection Heat Transfer Coefficients Utilized in Fort St Vrain Main Steam Line Break Analysis, Technical Evaluation Rept Project stage: Other ML20207K4021987-01-0202 January 1987 Forwards Final FATE-86-117, Review of Convection Heat Transfer Coefficient Utilized in Fort St Vrain Main Steam Line Break Analysis, Technical Evaluation Rept,For Info Project stage: Approval ML20207Q4431987-01-16016 January 1987 Confirms 870126-30 Equipment Qualification Insp,Per 870113 Meeting at Region IV Ofcs.Mgt Entrance Meeting Scheduled for 870126 at Site Visitors Ctr & Exit Meeting Tentatively Scheduled for 870130 at Plant Site Project stage: Meeting ML20210P5241987-01-29029 January 1987 Forwards Draft Evaluation of Confinement Environ Temps Following High Energy Line Breaks Proposed for Fort St Vrain Environ Qualification Program, Technical Evaluation Rept,In Response to Util 861212 & 19 Submittals Project stage: Draft Other ML20210P6451987-01-31031 January 1987 Draft Evaluation of Confinement Environ Temps Following High Energy Line Breaks Proposed for Fort St Vrain Environ Qualification Program, Technical Evaluation Rept Project stage: Draft Other ML20211P4951987-02-25025 February 1987 Informs of Present Status & Plans Re Completion of Environ Qualification Program,Per Open Items Identified During 870130 Site Insp.Program & Implementing Procedures to Assure Environ Qualification in Place.Status of Open Items Encl Project stage: Other ML20212J2931987-02-26026 February 1987 Forwards Amend 50 to License DPR-34 & Safety Evaluation. Amend Changes Tech Specs Re Steam Line Rupture Detection/ Isolation Sys Project stage: Approval 1986-11-25
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Category:MEETING MINUTES & NOTES--CORRESPONDENCE
MONTHYEARML20138G7291996-12-0303 December 1996 Summary of 961203 Meeting W/Psc in Plattville Co Re Decommissioning & License Termination of Fsv.Slides,Encl ML20137H2471995-04-12012 April 1995 Summary of 950405-06 Meeting W/Utility at Fort St Vrain Re Stier,Anderson & Malone Rept.Attendees Listed ML20128G1851993-01-29029 January 1993 Summary of 930128 Meeting W/Psc in Rockville,Md Re Briefing of NRC Staff on Status of Fsv Decommissioning Activities. Meeting Agenda & Summary of PSCs Briefing Encl ML20055J3931990-07-31031 July 1990 Summary of 900725 Meeting W/Util in Rockville,Md Re Defueling & Decommissioning of Facility.Attendees List Encl ML20246D9231989-08-18018 August 1989 Summary of 890718 Meeting W/Util to Discuss Defueling of Plant.List of Attendees,Agenda & Viewgraphs Encl ML20236C9921989-03-13013 March 1989 Summary of 890307 Meeting W/Util & Ga Technologies Re Plant Coastdown & Defueling.Attendance List,Agenda & Viewgraphs Encl ML20195D5591988-10-26026 October 1988 Summary of 881013 & 14 Meeting W/Util to Discuss Potential Decommissioning of Facility.W/O Stated Encl ML20154E4031988-09-0909 September 1988 Summary of 880831 Meeting W/Util Re Fire Protection Issues at Plant.Meeting Attendees Encl ML20151K6901988-07-18018 July 1988 Summary of Operating Reactors Events Meeting 88-28 on 880712.Viewgraphs & List of Attendees Encl ML20151K7361988-04-15015 April 1988 Summary of Operating Reactors Events Meeting 88-15 on 880412.List of Attendees & Viewgraphs Encl ML20153A8551988-03-0909 March 1988 Summary of 880304 Meeting W/Util to Discuss 880122 Submittal Re Helium Circulator Failure & Recovery.Attendee List & Viewgraphs Encl ML20149L4981988-02-12012 February 1988 Summary of 871207 Meeting W/Utils in Bethesda,Md Re Licensees Revised Proposal to Comply W/Nrc Requirement for Simulation Facilities Under 10CFR55.45(b).List of Attendees & Util Simulation Facility Group Guideline Encl ML20147D8901988-01-12012 January 1988 Summary of 881202-03 Meeting W/Util,Inel & ORNL Re Status of Tech Spec Upgrade Program.Meeting Attendees & Listed Ref Encl ML20237D6921987-12-15015 December 1987 Summary of 871203 Meeting W/Util & Inel Re Protective Sys Setpoints in Tech Specs.List of Meeting Attendees Encl ML20237D2251987-12-15015 December 1987 Summary of 871204 Meeting W/Util Re Licensee Latest Proposals for Licensing Actions Concerning CRD Mechanism Temp Requalification & Position Instrumentation.List of Attendees & Related Info Encl ML20236B9121987-10-20020 October 1987 Summary of 871002 Meeting W/Util Re Specific Aspects of Util Approach to Conform w/10CFR55 for Facility.List of Attendees & Util Presentation Matl Encl ML20236A9731987-10-13013 October 1987 Summary of 870915-16 Meetings W/Four Facility Licensees in Bethesda,Md Re Proposal to Apply for NRC Approval for Simulation Facilities.Viewgraphs & Related Documents Encl ML20235Z5891987-10-0808 October 1987 Summary of 871006 Operating Reactor Events Meeting 87-34 Re Events Occurring Since 870929 Meeting.List of Attendees & Presentation Matl Encl ML20235H4401987-09-21021 September 1987 Summary of 870911 Meeting W/Util in Arlington,Tx Re Failure of Plant Circulator S/N C-2101 & Licensee Program to Recover from Failure.Licensee Rept, Preliminary Rept of Helium Circulator S/N C-2101 Damage & Justification... Encl ML20207S6271987-03-12012 March 1987 Summary of 870210 Meeting W/Util Re Emergency Diesel Generator Electrical Independence.List of Attendees Encl ML20210P0191987-02-0505 February 1987 Summary of 870113 Meeting W/Util Re Completion of Equipment Qualification Program & Program & Approvals Required for Plant Restart ML20212D8641986-12-24024 December 1986 Summary of 861209 Meeting W/Util Re Plant Emergency Electrical Power Sys.Fsar Commitment Re Emergency Diesel Generators revised.Marked-up Draft Rept Re Ac Standby Power Sys Encl ML20207B9781986-12-15015 December 1986 Summary of 861027-30 Meetings W/Util,Eg&G Idaho,Inc & ORNL at Site Re Tech Spec Upgrade Program.List of Attendees & NRC Comment Resolution Encl ML20214U7071986-12-0202 December 1986 Summary of 861120 Meeting W/Util,Ornl,Ga Technologies & Eg&G Re Temp Profiles for Equipment Qualification.List of Attendees & Viewgraphs Encl ML20214P8511986-11-25025 November 1986 Summary of 861105 Meeting W/Lasl Re Technical Evaluation Rept on Prestressed Concrete Reactor Vessel Tendons.Staff Requires Determination Re Listed Items.List of Attendees Encl ML20214Q0951986-11-25025 November 1986 Summary of 861027 Meeting W/Util to Discuss Schedule for Ie/Nrr Insp of Equipment Qualification Program.Attendance List & Viewgraphs Encl ML20197B8651986-10-28028 October 1986 Summary of 861001-02 Meetings W/Util,Inel & ORNL Re Staff Comments on Plant Tech Spec Upgrade Program.Nrc Comments Not Intended to Require Plant Mod or Changes to Licensing Basis of Plant ML20215L2101986-09-12012 September 1986 Summary of ACRS Subcommittee on Gas-Cooled Reactor Plants 860626 Public Meeting W/Nrc & Util in Washington,Dc Re Bases Used to Impose Requirements on Facility & Possibility of Severe Accidents.Attendance List & Viewgraphs Encl ML20215L2001986-09-12012 September 1986 Summary of ACRS Subcommittee on Fort St Vrain 860402 Public Meeting W/Nrc & Util at Facility Re Technical Problems Addressed During Recent Extended Outage & Mgt Charges. Attendance List & Viewgraphs Encl ML20206P5971986-08-15015 August 1986 Summary of 860724 Meeting W/Util,Inel,Wyle Labs,Sargent & Lundy & Tenera in Bethesda,Md Re Util Draft Documentation to Justify Qualification of safety-related Cabling at Plant. List of Attendees Encl ML20211Q6161986-07-23023 July 1986 Summary of Operating Reactor Events Meeting 86-25 on 860721 Re Events Since 860714 Meeting.List of Attendees,Discussion of Events & Status of Assignments Encl.Response Requested for Incomplete Assignments ML20207H0281986-07-21021 July 1986 Summary of 860627 Meeting W/Util Re Status of Tech Spec Upgrade Program.List of Attendees Encl ML20207H1211986-07-18018 July 1986 Trip Rept of 860625-27 Site Visit to Review QA Program, Observe Equipment Qualification Mods & Obtain Unescorted Access Status ML20203B6181986-07-15015 July 1986 Summary of 860613 Meeting W/Util in Bethesda,Md Re Status of Plant Equipment Qualification Program.List of Attendees, Environ Qualification of Plant Safe Shutdown Cable & Cable Qualification Binders Encl ML20199K4911986-06-27027 June 1986 Summary of 860604 Meeting W/Util Re Status of Licensing Actions.List of Attendees,Summary of NRC Responses to Actions & Summary of Actions Encl ML20205S2341986-06-0101 June 1986 Summary of 860502 Meeting W/Util & Inel in Bethesda,Md Re Equipment Qualification Program Problem Areas.Attendees List & Supporting Documentation Encl ML20198H4561986-05-27027 May 1986 Summary of 860505 Meeting W/Util Re Status of Equipment Qualification Program.Considerable Work Remains Before Approval of Full Power Operation Can Be Granted.Staff Recommended Util Continue to Complete Program ML20197F1691986-05-0808 May 1986 Summary of Operating Reactors Events 860428 Meeting W/Listed Divs Re Chernobyl Nuclear Accident & Events at Us Reactors ML20197F6541986-05-0707 May 1986 Summary of 860423-24 Meetings W/Util,Ga Technologies & S&W at Site Re Fuel Block Cracking,Bldg 10 Const,Seismic Instrumentation,Pcrv Tendons & Integrated Leak Rate Testing. Attendance List & Viewgraphs Encl ML20203E8051986-04-18018 April 1986 Summary of Operating Reactors Events Meeting 86-12 on 860414 Re Events Since 860407.List of Attendees,Viewgraphs & Supporting Documentation Encl ML20205J9221986-04-18018 April 1986 Summary of ACRS 312th Meeting on 860410-12 in Washington,Dc Re Proposed NRC Safety Goal Policy Statement & Need for Guidance in Environ & PRA for Quantification of Public Health Risks to Nearby Populations ML20205S2591986-04-10010 April 1986 Summary of 860326 Site Meeting W/Util,Dibenedetto Assoc,Inc, Sandia & Sargent & Lundy Re Status of Qualifications of 10CFR50.49 Cables & Maint Records History Review.Viewgraphs & Attendees List Encl ML20141B7451986-03-28028 March 1986 Summary of 860313 Meeting W/Util in Arlington,Tx Re Tech Spec Limiting Condition for Operation 4.1.9 Covering Frequency of Manipulation of Reactor Controls.Supporting Documentation Encl ML20142A0661986-03-14014 March 1986 Summary of 860116 Meeting W/Util,Training Co,Inc & SM Stoller Corp Re Performance Enhancement Program. Viewgraphs Encl ML20141P1771986-03-14014 March 1986 Summary of 860130 Meeting W/Util,Inel,Tenera & Sargent & Lundy Re Equipment Qualification (EQ) Program.List of Attendees,Test Profiles & Review of Sample EQ Package Encl ML20142A0441986-03-12012 March 1986 Summary of 860221 Onsite Meeting W/Util,Inel,D Benedetto Assoc,S&W,Tenera,Ned & NPD Re Equipment Qualification Program & Steam Line Rupture Detection & Isolation Sys ML20138R7331985-10-31031 October 1985 Summary of 851029 Meeting W/Util & ORNL Re Schedule Extension to Equipment Qualification Rule.List of Attendees, Agenda & Matls Presented by Util Encl ML20138P0081985-10-21021 October 1985 Summary of Operating Reactors Events Meeting 85-19 on 851007 W/Ofc Directors,Div Directors & Representatives on Events Which Occurred Since Last Meeting on 851007 ML20134F3081985-08-15015 August 1985 Summary of 850722-26 Meetings W/Util & Ga Technologies Re Tech Spec Upgrade.List of Attendees Encl ML20129E6721985-05-28028 May 1985 Summary of 850803 Meeting W/Util & Ga Technologies Re CRD Mechanism Tech Spec Problem.List of Attendees Encl 1996-12-03
[Table view] Category:MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
MONTHYEARML20138G7291996-12-0303 December 1996 Summary of 961203 Meeting W/Psc in Plattville Co Re Decommissioning & License Termination of Fsv.Slides,Encl ML20137H2471995-04-12012 April 1995 Summary of 950405-06 Meeting W/Utility at Fort St Vrain Re Stier,Anderson & Malone Rept.Attendees Listed ML20128G1851993-01-29029 January 1993 Summary of 930128 Meeting W/Psc in Rockville,Md Re Briefing of NRC Staff on Status of Fsv Decommissioning Activities. Meeting Agenda & Summary of PSCs Briefing Encl ML20055J3931990-07-31031 July 1990 Summary of 900725 Meeting W/Util in Rockville,Md Re Defueling & Decommissioning of Facility.Attendees List Encl ML20246D9231989-08-18018 August 1989 Summary of 890718 Meeting W/Util to Discuss Defueling of Plant.List of Attendees,Agenda & Viewgraphs Encl ML20236C9921989-03-13013 March 1989 Summary of 890307 Meeting W/Util & Ga Technologies Re Plant Coastdown & Defueling.Attendance List,Agenda & Viewgraphs Encl ML20195D5591988-10-26026 October 1988 Summary of 881013 & 14 Meeting W/Util to Discuss Potential Decommissioning of Facility.W/O Stated Encl ML20154E4031988-09-0909 September 1988 Summary of 880831 Meeting W/Util Re Fire Protection Issues at Plant.Meeting Attendees Encl ML20151K6901988-07-18018 July 1988 Summary of Operating Reactors Events Meeting 88-28 on 880712.Viewgraphs & List of Attendees Encl ML20151K7361988-04-15015 April 1988 Summary of Operating Reactors Events Meeting 88-15 on 880412.List of Attendees & Viewgraphs Encl ML20153A8551988-03-0909 March 1988 Summary of 880304 Meeting W/Util to Discuss 880122 Submittal Re Helium Circulator Failure & Recovery.Attendee List & Viewgraphs Encl ML20149L4981988-02-12012 February 1988 Summary of 871207 Meeting W/Utils in Bethesda,Md Re Licensees Revised Proposal to Comply W/Nrc Requirement for Simulation Facilities Under 10CFR55.45(b).List of Attendees & Util Simulation Facility Group Guideline Encl ML20147D8901988-01-12012 January 1988 Summary of 881202-03 Meeting W/Util,Inel & ORNL Re Status of Tech Spec Upgrade Program.Meeting Attendees & Listed Ref Encl ML20237D6921987-12-15015 December 1987 Summary of 871203 Meeting W/Util & Inel Re Protective Sys Setpoints in Tech Specs.List of Meeting Attendees Encl ML20237D2251987-12-15015 December 1987 Summary of 871204 Meeting W/Util Re Licensee Latest Proposals for Licensing Actions Concerning CRD Mechanism Temp Requalification & Position Instrumentation.List of Attendees & Related Info Encl ML20236B9121987-10-20020 October 1987 Summary of 871002 Meeting W/Util Re Specific Aspects of Util Approach to Conform w/10CFR55 for Facility.List of Attendees & Util Presentation Matl Encl ML20236A9731987-10-13013 October 1987 Summary of 870915-16 Meetings W/Four Facility Licensees in Bethesda,Md Re Proposal to Apply for NRC Approval for Simulation Facilities.Viewgraphs & Related Documents Encl ML20235Z5891987-10-0808 October 1987 Summary of 871006 Operating Reactor Events Meeting 87-34 Re Events Occurring Since 870929 Meeting.List of Attendees & Presentation Matl Encl ML20235H4401987-09-21021 September 1987 Summary of 870911 Meeting W/Util in Arlington,Tx Re Failure of Plant Circulator S/N C-2101 & Licensee Program to Recover from Failure.Licensee Rept, Preliminary Rept of Helium Circulator S/N C-2101 Damage & Justification... Encl ML20207S6271987-03-12012 March 1987 Summary of 870210 Meeting W/Util Re Emergency Diesel Generator Electrical Independence.List of Attendees Encl ML20210P0191987-02-0505 February 1987 Summary of 870113 Meeting W/Util Re Completion of Equipment Qualification Program & Program & Approvals Required for Plant Restart ML20212D8641986-12-24024 December 1986 Summary of 861209 Meeting W/Util Re Plant Emergency Electrical Power Sys.Fsar Commitment Re Emergency Diesel Generators revised.Marked-up Draft Rept Re Ac Standby Power Sys Encl ML20207B9781986-12-15015 December 1986 Summary of 861027-30 Meetings W/Util,Eg&G Idaho,Inc & ORNL at Site Re Tech Spec Upgrade Program.List of Attendees & NRC Comment Resolution Encl ML20214U7071986-12-0202 December 1986 Summary of 861120 Meeting W/Util,Ornl,Ga Technologies & Eg&G Re Temp Profiles for Equipment Qualification.List of Attendees & Viewgraphs Encl ML20214P8511986-11-25025 November 1986 Summary of 861105 Meeting W/Lasl Re Technical Evaluation Rept on Prestressed Concrete Reactor Vessel Tendons.Staff Requires Determination Re Listed Items.List of Attendees Encl ML20214Q0951986-11-25025 November 1986 Summary of 861027 Meeting W/Util to Discuss Schedule for Ie/Nrr Insp of Equipment Qualification Program.Attendance List & Viewgraphs Encl ML20197B8651986-10-28028 October 1986 Summary of 861001-02 Meetings W/Util,Inel & ORNL Re Staff Comments on Plant Tech Spec Upgrade Program.Nrc Comments Not Intended to Require Plant Mod or Changes to Licensing Basis of Plant ML20215L2101986-09-12012 September 1986 Summary of ACRS Subcommittee on Gas-Cooled Reactor Plants 860626 Public Meeting W/Nrc & Util in Washington,Dc Re Bases Used to Impose Requirements on Facility & Possibility of Severe Accidents.Attendance List & Viewgraphs Encl ML20215L2001986-09-12012 September 1986 Summary of ACRS Subcommittee on Fort St Vrain 860402 Public Meeting W/Nrc & Util at Facility Re Technical Problems Addressed During Recent Extended Outage & Mgt Charges. Attendance List & Viewgraphs Encl ML20206P5971986-08-15015 August 1986 Summary of 860724 Meeting W/Util,Inel,Wyle Labs,Sargent & Lundy & Tenera in Bethesda,Md Re Util Draft Documentation to Justify Qualification of safety-related Cabling at Plant. List of Attendees Encl ML20211Q6161986-07-23023 July 1986 Summary of Operating Reactor Events Meeting 86-25 on 860721 Re Events Since 860714 Meeting.List of Attendees,Discussion of Events & Status of Assignments Encl.Response Requested for Incomplete Assignments ML20207H0281986-07-21021 July 1986 Summary of 860627 Meeting W/Util Re Status of Tech Spec Upgrade Program.List of Attendees Encl ML20203B6181986-07-15015 July 1986 Summary of 860613 Meeting W/Util in Bethesda,Md Re Status of Plant Equipment Qualification Program.List of Attendees, Environ Qualification of Plant Safe Shutdown Cable & Cable Qualification Binders Encl ML20199K4911986-06-27027 June 1986 Summary of 860604 Meeting W/Util Re Status of Licensing Actions.List of Attendees,Summary of NRC Responses to Actions & Summary of Actions Encl ML20205S2341986-06-0101 June 1986 Summary of 860502 Meeting W/Util & Inel in Bethesda,Md Re Equipment Qualification Program Problem Areas.Attendees List & Supporting Documentation Encl ML20198H4561986-05-27027 May 1986 Summary of 860505 Meeting W/Util Re Status of Equipment Qualification Program.Considerable Work Remains Before Approval of Full Power Operation Can Be Granted.Staff Recommended Util Continue to Complete Program ML20197F1691986-05-0808 May 1986 Summary of Operating Reactors Events 860428 Meeting W/Listed Divs Re Chernobyl Nuclear Accident & Events at Us Reactors ML20197F6541986-05-0707 May 1986 Summary of 860423-24 Meetings W/Util,Ga Technologies & S&W at Site Re Fuel Block Cracking,Bldg 10 Const,Seismic Instrumentation,Pcrv Tendons & Integrated Leak Rate Testing. Attendance List & Viewgraphs Encl ML20203E8051986-04-18018 April 1986 Summary of Operating Reactors Events Meeting 86-12 on 860414 Re Events Since 860407.List of Attendees,Viewgraphs & Supporting Documentation Encl ML20205J9221986-04-18018 April 1986 Summary of ACRS 312th Meeting on 860410-12 in Washington,Dc Re Proposed NRC Safety Goal Policy Statement & Need for Guidance in Environ & PRA for Quantification of Public Health Risks to Nearby Populations ML20205S2591986-04-10010 April 1986 Summary of 860326 Site Meeting W/Util,Dibenedetto Assoc,Inc, Sandia & Sargent & Lundy Re Status of Qualifications of 10CFR50.49 Cables & Maint Records History Review.Viewgraphs & Attendees List Encl ML20141B7451986-03-28028 March 1986 Summary of 860313 Meeting W/Util in Arlington,Tx Re Tech Spec Limiting Condition for Operation 4.1.9 Covering Frequency of Manipulation of Reactor Controls.Supporting Documentation Encl ML20142A0661986-03-14014 March 1986 Summary of 860116 Meeting W/Util,Training Co,Inc & SM Stoller Corp Re Performance Enhancement Program. Viewgraphs Encl ML20141P1771986-03-14014 March 1986 Summary of 860130 Meeting W/Util,Inel,Tenera & Sargent & Lundy Re Equipment Qualification (EQ) Program.List of Attendees,Test Profiles & Review of Sample EQ Package Encl ML20142A0441986-03-12012 March 1986 Summary of 860221 Onsite Meeting W/Util,Inel,D Benedetto Assoc,S&W,Tenera,Ned & NPD Re Equipment Qualification Program & Steam Line Rupture Detection & Isolation Sys ML20138R7331985-10-31031 October 1985 Summary of 851029 Meeting W/Util & ORNL Re Schedule Extension to Equipment Qualification Rule.List of Attendees, Agenda & Matls Presented by Util Encl ML20138P0081985-10-21021 October 1985 Summary of Operating Reactors Events Meeting 85-19 on 851007 W/Ofc Directors,Div Directors & Representatives on Events Which Occurred Since Last Meeting on 851007 ML20134F3081985-08-15015 August 1985 Summary of 850722-26 Meetings W/Util & Ga Technologies Re Tech Spec Upgrade.List of Attendees Encl ML20129E6721985-05-28028 May 1985 Summary of 850803 Meeting W/Util & Ga Technologies Re CRD Mechanism Tech Spec Problem.List of Attendees Encl ML20128P6271985-05-23023 May 1985 Summary of 850516 Meeting W/Util Re Emergency Electrical Power Sys Concerns Resulting from Staff Evaluation of Problems from Testing Emergency Diesel Generators on 841218. Justification for Continued Operation Requested 1996-12-03
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. - - -- . - - -. -- . ..
p ara i
%, UNITED STATES
- y g NUCLEAR REGULATORY COMMISSION O j WASHINGTON, D. C. 20555 .
~%%,.. / August 15, 1986 Dccket No. 50-267 MEMORANDUM FOR: Herbert N. Berkow, Director Standardization and Special ,
I
! Projects Directorate Division of PWR Licensing-B -
- 0. D. T. Lynch, Jr. , Section Le 1 THRU:
Standardization and Special h Projects Directorate Division of PWR Licensing-B FROM: Kenneth L. Heitner, Project Manager <
Standardization and Special Projects Directorate Division of PWR Licensing-B
SUBJECT:
SUMARY OF JULY 24, 1986 MEETING WITH PUBLIC SERVICE COMPANY OF COLORADO (PSC) TO DISCUSS CABLE QUALIFICATION This meeting was held at the Nuclear Regulatory Commission's offices, Room
. P-422, Bethesda, Maryland at 9:00 a.m. on July 24, 1986. The purpose of this l meeting was to discuss, in detail, the draft documentation prepared by PSC to justify qualification of safety related cabling at the Fort St. Vrain Nuclear GeneratingStation(FSV). Meeting attendees are listed in the enclosure.
PSC's staff and consultants briefly reviewed three licensee-selected sample cable qualification packages for the staff. Typically, the qualification packages used a thermal lag analy.;is to demonstrate that the actual environ-ment which could be experienced by the cable during an accident was within
, the envelope of available qualification test data. This is because the
- . predicted FSV environment typically exceeded this envelope for less than a i minute, and only for very severe pipe breaks. Where test data and reports were not available for the specific cable in question, PSC used qualification data for similar cables made by another manufacturer. Similarity arguments were based on the fact that the cables were all fabricated from polyvinylchloride materials. PSC stated that similarity analyses of this type had been previously accepted by the NRC.
Of particular interest were details of the cable qualification process for i cables which could not be specifically identified by manufacturer's type.
Certain " generic" cables at FSV were' originally purchased by Eastern Cable, one of the contractors during the construction of FSV. The specific manufacturer for these cables.is not known. However, short duration high temperature test results were available to demonstrate the qualification for these cables during high temperature transients. Long-tem operability for these cables was demonstratec by a comparison of the manufacturing standards for these cable types. The minimum acceptance levels of the manufacturing standards for these cables are adequate to assure long-term operability.
$N 7
$[
P
t The thermal lag analysis used in demonstrating qualification utilized aThe consulta "
specific thermal model for each cable type.
heat transfer to the cable by PSC radiation, convection also noted that thermal lag and cond to model cable internal f. eat generation. These included:
analysis had been used to qualify certain other components.
l a
- Terminal Blocks,
- Cable Splices, and
- Switchgear at Motor Control Centers. -
The staff commented that PSC's general approach to cable However, qualification, the as indicated by the sample packages, appeared to be acceptable.
staff noted several areas for potential improvements of the cable qualification packages. These included:
(The
- - Clarifying the qualification goals of each qualification pa and difficult to meet than for lower category packages.)
- Including a signoff sheet indicating review and acceptance by etch qualification package.
ptckage should also be noted.
- Having qualified FSV Quality Assurance personnel review each package upon receipt from the contractor.
- Evaluating the role of the end devices in assessing potential leakage currents for instrumentation cables. The need for
- Eliminating inconsistencies in qualification packages.
quality control in the development process of these packages should be emphasized.
The staff requested that PSC provide specific reference to their thermal lag methodology. PSC agreed to add this to the forthcoming update of the equipment list (MEL).
as fieldwork continued.
PSC stated that their current projections indicated that the fielfork would However, be complete and the plant ready to operate by about O program could take two to four weeks longer.
@ M b. b Kenneth L. Heitner, Project Manager Standardization and Special Projects Directorate Division of PWR Licensing-B
Enclosure:
As stated cc w/ enclosure:
See next page
Mr. R. O. Williams Public Service Company of Colorado Fort St. Vrain _
cc:
Mr. D. W. Warembourg, Manager Albert J. Hazle, Director Nuclear Engineering Division Radiation Control Division Public Service Company Department of Health of Colorado 4210 East lith Avenue P. O. Box 840 Denver, Colorado 80220 Denver, Colorado 80201 Mr. David Alberstein, 14/159A Mr. J. W. Gahm, Manager GA Technologies, Inc. Nuclear Production Division Post Office Box 85608 Public Service Company of Colorado San Diego, California 92138 16805 Weld County Road 19-1/2 Platteville, Colorado 80651 Mr. H. L. Brey, Manager
? Nuclear Licensing and Fuel Division Mr. L. W. Singleton, Manager
- Public Service Company of Colorado Quality Assurance Division P. O. Box 840 Fort St. Vrain Nuclear Station Denver, Colorado 80201 16805 Weld County Road 19-1/2 Platteville, Colorado 80651 Senior Resident Inspector U.S. Nuclear Regulatory Commission P. 0. Box 640 Platteville, Colorado 80651 Kelley, Stansfield & 0'Donnell Public Service Company Building Room 900 550 15th Street Denver, Colorado 80202 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000
. Arlington, Texas 76011 Chairman, Board of County Commissioners of Weld County, Colorado Greeley, Colorado 80631 Regional Representative Radiation Programs Environmental Protection Agency 1800 Lincoln Street Denver, Colcrado 80203 l
t l
6 Enclosure NRC - PSC Meeting: July 24, 1986 (Cable qualification)
Name Organization K. L. Heitner NRR/DPWRL-B/SSPD Paul Shemanski NRR/PWR-B/PEICSB John M. Fehringer INEL/NRC Contractor
, R. E. Ireland NRC - RIV G. T. Hubbard NRC - IE/VPB Rob Burg Tenera Phil DiBenedetto DBA Inc.
- Sam Marquez PSC Mike Niehoff PSC Jim Anderson WYLE LABS James Selan PSC Jim Gleason WYLE William H. Schwartz DBA Inc.
i James Grossman SN Labs Charles Hinson NRR/DPWRL-B/SSPD John C. McKinley NRC/ACRS Staff J. Sinnappan S&L Bill Adams Sargent & Lundy
)
l _ --
August 15, 1986 0<AWA 3, g p g AccAt PDR The thermal lag analysis used in demonstrating qualification utilized a specific thermal model for each cable type. The consultant's model considered heat transfer to the cable by radiation, convection and condensation.
Consistent assumptions were used to model flow parameters around the cable and to model cable internal heat generation. PSC also noted that thermal lag analysis had been used to qualify certain other components. These included:
- Terminal Blocks,
- Cable Splices, and
- Switchgear at Motor Control Centers.
The staff comented that PSC's general approach to cable qualification, as indicated by the sample packages, appeared to be acceptable. However, the staff noted several areas for potential improvements of the cable qualification packages. These included:
- Clarifying the qualification goals of each qualification package. (The staff noted the requirements for Category 1 packages were more extensive and difficult to meet than for lower category packages.)
- Including a signoff sheet indicating review and acceptance by PSC in each qualification package. Open items relevant to that qualification package should also be noted.
- Having qualified FSV Quality Assurance personnel review each package upon receipt from the contractor.
- Evaluating the role of the end devices in assessing potential leakage currents for instrumentation cables.
- Eliminating inconsistencies in qualification packages. The need for quality control in the development process of these packages should be emphasized.
The staff requested that PSC provide specific reference to their ther;ral lag methodology. PSC agreed to add this to the forthcoming update of the master equipment list (MEL). However, PSC noted that further MEL updates were likely as fieldwork continued.
PSC stated that their current projections indicated that the fieldwork would j be complete and the plant ready to operate by about October 1,1986. However, completion of the files required to support the equipment qualification program could take two to four weeks longer.
Original signed by Kenneth L. Heitner, Project Manager Standardization and Special Projects Directorate Division of PWR Licensing-B
Enclosure:
As stated cc w/ enclosure:
See next page
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Ogg.-B:SSPD DPWRL-B:SSPD :SSPD DP 'SSPD pscohan KHeitner:cw HBerk O g /86 08/15~/86 08 /86 08//f/86