Letter Sequence Meeting |
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Results
Other: ML20096C267, ML20154M436, ML20154N901, ML20206A268, ML20236C636, ML20236Q429, ML20237C032, ML20245E654, ML20245E660, ML20247F625, ML20247G557
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MONTHYEARML20096C2671984-08-17017 August 1984 Forwards Revised Schedule for App R Review,Submittals,Plant Mods & Fire Protection Safe Reactor Shutdown/Cooldown Capability Incorporating NRC Concerns & Comments Project stage: Other ML20236C6161987-10-15015 October 1987 Forwards Application for Amend to License DPR-34,deleting Fire Protection Limiting Conditions of Operations & Surveillance Requirements from Tech Specs.Fee Paid Project stage: Request ML20236C6271987-10-15015 October 1987 Application for Amend to License DPR-34,deleting Fire Protection Limiting Conditions for Operation & Surveillance Requirements from Tech Specs Project stage: Request ML20236C6361987-10-15015 October 1987 Proposed Tech Specs,Deleting Fire Protection Limiting Conditions for Operation & Surveillance Requirements Project stage: Other ML20236Q4291987-11-12012 November 1987 Advises That Util 871015 Request to Delete Fire Protection Tech Specs Premature.Util Must Have Approved Fire Protection Program & Request Amend to License Containing License Condition Per Encl 3 to Generic Ltr 86-10 Project stage: Other ML20237C0321987-12-15015 December 1987 Forwards Fort St Vrain Nuclear Generating Station Fire Protection Plan, for Approval,Per Generic Ltr 86-10. Review of Util & NRC Correspondence Re Fire Protection Provided Project stage: Other ML20153F4951988-04-29029 April 1988 Requests Addl Info to Continue Review of Util 871215 Submittal Re Fire Protection Plan within 45 Days of Ltr Date Project stage: Approval ML20195H9451988-06-13013 June 1988 Forwards Response to NRC 880429 Request for Addl Info Re Facility Fire Protection Program Plan.W/Three Oversize Drawings Project stage: Request ML20151V7281988-08-18018 August 1988 Notification of 880831 Meeting W/Util in Rockville MD to Discuss Fire Protection at Facility Project stage: Meeting ML20154M4361988-09-0909 September 1988 Rev a to EE-FP-0005, Evaluation of Cable Trays Outside of Congested Cable Area Project stage: Other ML20154E4031988-09-0909 September 1988 Summary of 880831 Meeting W/Util Re Fire Protection Issues at Plant.Meeting Attendees Encl Project stage: Meeting ML20154M3991988-09-20020 September 1988 Documents & Summarizes Actions & Commitments Resulting from 880831 Meeting Re NRC Review of Fire Protection Plan. Verification Testing Results of Emergency Lighting Addressed in Followup Ltr.W/Three Oversize Proprietary Drawings Project stage: Meeting ML20154N9011988-09-22022 September 1988 Advises That Details to Specific Emergency Lighting Mods Will Be Provided by 881121 Due to Util Test Results Indicating Inadequate Lighting,Per 10CFR50,App R,Section Iii.J Project stage: Other ML20206A2681988-10-28028 October 1988 Advises That Listed Emergency Lighting Mods Will Be Installed & Functional by Startup at End of Fourth Refueling Project stage: Other ML20245E6601989-01-0606 January 1989 Independent Review of Fire Protection Program Plan,Public Svc Co of Co,Fort St Vrain Nuclear Generating Station Project stage: Other ML20245E6541989-01-0606 January 1989 Forwards Technical Evaluation Rept SAIC-88/1822, Independent Review of Fire Protection Plan,Public Svc Co of Co,Fort St Vrain Nuclear Generating Plant Project stage: Other ML20246N4691989-03-16016 March 1989 Provides Comments on Draft Science Applications Intl Corp Technical Evaluation Rept SAIC-88/1822 Re Fire Protection Program Project stage: Draft Other IR 05000267/19890041989-03-16016 March 1989 Insp Rept 50-267/89-04 on 880227-0303.No Violations or Deviations Noted.Major Areas Inspected:Licensed Operator Training Project stage: Request ML20247F6251989-03-27027 March 1989 Forwards Issue 3 of Fire Protection Operability Requirements 13 & 15 Re Insp of Both Sides of Penetration & Functional Testing of Fusible Link Dampers,Respectively,Per Generic Ltr 86-10 Project stage: Other ML20247G5571989-05-18018 May 1989 Advises That 880722 Rev 1 to Fire Protection Program Plan Acceptable.Approved Plan Should Be Incorporated in Updated FSAR Per Generic Ltr 86-10 Project stage: Other 1988-08-18
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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 ML19327C1731989-11-13013 November 1989 Summary of 891025 Meeting W/Util Re Issues Connected W/Plant Reactor Defueling.List of Attendees,Presentation Matl & Rev B to EE-DEC-0022, Fort St Vrain Neutron Source Analysis Using DIF3D, Encl ML19327B8071989-11-0707 November 1989 Summary of 891026 Meeting W/Doe & Util Re Utilization of Data from Facility to Support Review of Matl Htgr.List of Attendees & Handouts Encl ML19324B4651989-10-26026 October 1989 Summary of 891013 Meeting w/util,GECA-ESL & Foster Wheeler to Discuss Facility & Potential Const of ISFSI 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 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 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 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 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 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 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 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 ML19327C1731989-11-13013 November 1989 Summary of 891025 Meeting W/Util Re Issues Connected W/Plant Reactor Defueling.List of Attendees,Presentation Matl & Rev B to EE-DEC-0022, Fort St Vrain Neutron Source Analysis Using DIF3D, Encl ML19327B8071989-11-0707 November 1989 Summary of 891026 Meeting W/Doe & Util Re Utilization of Data from Facility to Support Review of Matl Htgr.List of Attendees & Handouts Encl ML19324B4651989-10-26026 October 1989 Summary of 891013 Meeting w/util,GECA-ESL & Foster Wheeler to Discuss Facility & Potential Const of ISFSI 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 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 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 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 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 ML20142A0661986-03-14014 March 1986 Summary of 860116 Meeting W/Util,Training Co,Inc & SM Stoller Corp Re Performance Enhancement Program. Viewgraphs 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 1996-12-03
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_ - _.
o UNITED 8TATES g
NUCLEAR REGULATORY COMMISSION n
r.
a WASHINGTON, D C. 20655
%,*...)
September 9,1988 Docket No.: 50-267 MEMORANDUM FOR:
Jose A. Calvo, Director Project Directorate IV Division of Reactor Projects - III.
IV, Y and Special Projects FROM:
Kenneth L. Heitner, Project Manager Project Directorate IV Division of Reactor Projects - III.
IV, V and Specail Projects
SUBJECT:
SU WARY OF AUGUST 31, 1988 MEETING WITH PUBLIC SERVICE COMPANY OF COLORADO (PSC) TO DISC'.!SS FIRE PROTECTION AT FORT St. VRAIN (TAC NO. 66508)
A reeting was held at PSC's request to discuss fire protection issues at Fort St. Vrain (FSV). The attendees at the meeting are listed in.
PSC stated that they are working towards completing all fire protection related modifications. The PSC target date for completing these actions remains the fourth refueling outage. PSC is also contemplating rodifications to the ACM system. This would be discussed at a future meeting.
During the meeting, PSC discussed several topics as follows:
1.
Fire Protection - PSC stated that an independent audit by Garewell (Enclosure 2) indicated gaps in fire detection coverage, PSC would add new detectors to mitigate this problem.
2.
Concentrated Cable locations - PSC had evaluated other potential concentrated cable locations in the plant. No new concentrated cable locations were found.
3.
Emergency Lighting Test - PSC noted that they had not conducted the emergency lighting "T" test as of this date. However, they were still planning to conduct the test during this outage.
0 g1ma age P
Jose A. Calvo
-2 PSC also, briefly reviewed a sunmary of the fire protection licensing basis for FSV. This is included in Enclosure 3.
t
\\b Kenneth L. Heitner, Project Manager Project Directorate IV Division of Reactor Projects - III, IV, V and Special Projects
Enclosures:
As stated cc:
Service List 01 IBUTION vloclet FTTe-NRC & Local PCRs PDIV R/F JCalvo KHeitner OGC.Rockville EJordan EGrines NRC Participants ACRS (10)
THartin Reg. IV cc:
Service List OFC'^iPHiPDlV gG.}.~s:
.....:......... ):............:............:............:............:............:...........
HAME :KHeitner:jc :
DA(E :09/_9/p_8 ___:
pp g g g.... ~.... _ _ - -_ -
Jose A. Calvo PSC also, briefly reviewed a sumary of the fire protection licensing basis for FSV. This is included in Enclosure 3.
li Kenneth L. Heitner, Project Manager Project Directorate IV Division of Reactor Projects - III, IV Y and Special Projects
Enclosures:
-l As stated t
cc: Service List r
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--.-._...___._....,_-..--m_.
Mr. R. O. Williams, Jr.
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 80201-0840 Mr. David Alberstein, 14/159A Mr. R. O. Williams, Jr., Acting 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. P. F. Tomlinson, Manager Public Service Company of Colorade Quality Assurance Division P. O. Box S40 Public Service Company of Colorado Denver, Colorado 80201-0840 16805 Weld County Road 19-1/2 Platteville, Colorado 80651 Senior Resident Inspector U.S. Nuclear Regulatory Comission Mr. R. F. Walker P. O. Box 640 Pubite Service Company of Colorado Platteville, Colorado 80651 Post Office Box 840 Denver, Colorado 80201-08/.0 Kelley, Stansfield & 0'Donnell Public Service Company Building Comitment Control Program Room 900 Coordinator 550 15th Street Public Service Company of Colorado Denver, Colorado 80202 2420 W. 26th Ave. Suite 100-0 Denver, Colorado 80211 Regional Administrator, Region IV U.S. Nuclear Regulatory Comission 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 Chairman, Board of County Comissioners of Weld County, Colorado Greeley, Colorado 80631 Regional Representative Radiation Programs Environmental Protection Agency 1 Denver Place 999 ISth Street, Suite 1300 Denver, Colorado 80202-2413
t ENCLOSURE 1 NRC PSC MEETING AUGUST 31, 1988 FIRE PROTECTION i
NAME ORGANIZATION I
K. L. Heitner NRC M. M. Holmes PSC G. S. Bates PSC G. D. Schmalz PSC M. E. Deniston PSC H. George TENERA i
D. G. Seymour PSC T. F. Westerman NRC 1
M. E. Murphy NRC T. A. Storey NRC l
D. Kubicki NRC j
E. Tomlinson NRC l
i l
1 1
i 1
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Il l
I 5
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i
ENCLOSURE 2 L'
Gamewell8 MEMBER OF THE CERBERUS G ACUP h August 1G,1988 l
l Public Service Company of Colorado 2420 West 26th Avenue l
Suite 1000 Oenver, CO 80211 Attn Greg Bates RF Automatic Fire Ootection at the Fort St. Vrain Nuclev* Generating Station Page 1 OF 4 j
Gr eg Here is an account of our meeting on Hondny afternoon, August 1,
1988, in your office, with yourself at.1 Weyne Kendall representing Public Service Co., and Rob Wagner and mysoif'. epresenting F. A.
Systema Inc.
1)
Public Service Company of Colorado in the "Authority having jurisdiction" as defined in NFPA, and pertaining to the Fort Saint Vrain Nucioar generating Station.
2)
Reference modo 2) Plan E-20SO, sheet 1 of 1,
initial issue CN-2003, Elevatsen 4791'-O A)
No added detection required for area betwoon gr id lines H-J, and 2-3.3 0)
No added detection required for mri e.on restrooms located between grid lines H-J, una C)
No added detection required at the Herin Entry or Security room located between grid linee G-H, and 1-2 0)
No added detection required by Northwest stairs located between grid lines G.S-H, and 1.8-3 E)
Open grid ceiling located between grid lines 0-H, and 2.9-4.8 is pr otected by detection on elevation 4811'-O" F)
No added detection required for area between grid lines E.S-F.S.
and 2.3-3.2 Fire Alarm S, stems. Inc.P 0 Box 957. Avon.Colorade 81620.(303@9 53M.In Colorado 1 SCG233 7590
(S) 1 Attn Greg Bates Fablic Service Company of Colorado August 16, 1988 Page 2 of 4 G)
No edded decoction required for area between grid lines A1.9-C, and 1-2 H)
Opea area between grid lines E-F, and 5-5b.1 is protected by detection on elevation 4811'-U" I)
No addta detect'*an required for arer between grid linse 0.7-F, and 5b.1-3 The following area's need to be re-surveyed to determine if added de'cection lo er 'uired by the Authority having jurisdiction.
8)
Re-suryzy ures in Maintenance shop between grid '4ne E-F, and 1-2 to dete mine if added detection is aequired.
K)
R.-survey area o*
added on Wald Shop located on West side of Maintent -ce shop to determine IF e,dded d',',ection !,e required.
L)
Pe-survey area tetween grid line C 4-0.5, and 2.8-3.2 to ootermine if added dstection is required.
The following area's are to receive added detection.
M)
Instoll one R902 smoke detector in top of elevator shaft, that will allow elevator to recall to Level 5 when activated, and have an emergency over ride switch located in the elevator car for Fire Origade and Security use.
N)
Install one R7 smoke dutector to asen between gr id lines a
C.P-0.5, and 4.2-4.8 0)
Install one R7 mmoke detector to area between grid lines C-C.G, and 1.9-3 P)
Install one R7 smoke detector to area betwee grid lines u-C, and 5-7 Q)
Inc. tall one R7 smoke detector to e-em netween grid lines F-G, and Sb. V8 3)
References b
Plai E-205*, sheet 1 of 1,
initial issue CN-2003, E.. e v = : - n 4811 A)
No adds!
. ed for area between grid lines A-A1.6 a
8)
No addtd -
Ared for area between grid lines F.G and 5.2-L...
t
m
.I
..l'
( 3)
I Attn Greg Bates Public service company of Colorado I
August 16, 1983 i
Page 3 of 4 r
C)
No added detection required in area betwen geld lines C-E.2, and 3-4.5 The following area's need to be re-surveyed to determine if added detection is required by the Authority having jurisdiction.
O)
Re-survey area between grid lines B-C, and 2-3a to determine if added detection is required.
The following area's are to receive added detection.
1 E)
Install one R7 smoke detector in are between grid lines G-H, I
and 4-5 t
L l
F)
Install one R7 mmake detector in area betweela grid lines G-H, ar.d 2.2-3.G G)
Install one Linser Beam detector to area between grid lines A-8, and 1-4,5 7
s H)
Install one Linear Beam detector to area between grid lines A-0, and 1-2 j
I)
Install one R7 smoke detector in area between c"id lines j
B-B.6, and 7-8 i
l 4)
No added protection required on Plan E-2C52, sheet 1 of 1, i
i initial issu CN-2OO3, Elevation 4846'-0"
[
h 5)
Referenew made to Plan E-2053, sheet 1 of 1,
initial issue l
CN-2003, Elevation 4758'-0" and 4759'-0"
)
A)
No added detection required to area between grid lines L-M.
]
and da-5.5 8)
Ret,-ences made to Plan E-2053, sheet 1 of 1,
initial issue CN-2003, Elevation 4740'-8" l
h j.
A)
No Wed detection required in area etween grid lines L-Mg
]
and 4c-7 7)
References made to plane E-RO54, sheet 1 of 1, initial issue l'
CN-2003, Elevation 4816'-O" j
A)
Re-survey area between grid lines J-J.5, and 4-da to determine if added detection is required.
i l
8)
References made to Plan E-2054, sheet 1 of 1, initial issue CN-2003, Elevation 4884'-0" i
l l
\\
(4)
Attn Greg Setes Public service Company of' Colorado August is, 1988 l
Page 4 of 4 A)
No udded detection required in area between grid lines J.2-L.5, and do.5-7 8)
Me-survey area between grid lines J-J.3 and 4-4e to determine if added detection le required C)
Install one Linear Beam detector to area between grid lines J.5-L.2, and 4e-5 9)
References made to Plan E-2054, eheet i rF 1,
initial issue CN-2OO3, Elevation 4781'-0" A)
No added detection required to area between grid lines J.1-M, l
and 4m-5.8 l
B)
Me-survey area between grid lines K-M, and 5.8-7, if detection is required install one Linear Scam detector.
10)
No added protection required on Plan E-1951, sheet 1 of 1, initial issue CN-1482C, Building 10 oli elevations.
Greg, if you have any questions, revisions, or alterations to these minutes please contact me.
Thank you,
$Y AfY$
(
Edson L. (lower Jr.
l
4 ENCLOSURE 3 U)
O PUBLIC SERVICE COMPANY OF COLORADO NUCLEAR REGULATORY COMMISSION AUGUST 31, 1988 I.
STATUS OF HRC OPEN ITEMS ASSOCIATED WITH THE FSV FPPP 1
l 1.
FIRE DETECTION 2.
CONCENTRATED CABLE LOCATIONS OUTSIDE THE CCA l
3.
VERIFICATION TEST OF EMERGENCY LIGHTING l
II.
UPCOMING NRC APPENDIX R\\FPPP AUDIT
- 1. CONFIRMATION OF GROUND RULES & METHODOLOGY
- 2. NRC COMMENTS
(A s
o FSV APPENDIX R METHODOLOGY i
A.
CONGESTED CABLE AREAS 1.
CONGESTED CABLES AREAS (CCA) DEFINED AS CONTROL ROOM, 480V SWITCHGEAR ROOM, AUX ELECTRIC ROOM,
& CONGESTED CABLES AREAS ALONG J & G WALLS t
2.
LIMITING CONSEQUENCES OF CCA TIRE:
MEANS SHALL BE AVAILABLE TO SHUTDOWN \\COOLDOWN REACTOR SUCH THAT THE CO!1 SEQUENCES OF DBA 1 ARE NOT EXCEEDED j
t 3.
PERFORMANCE GOALS:
a.
ACHIEVING & MAINTAINING A SUBCRITICAL REACTIVITY CONDITION b.
ACHIEVING DEPRESSURIZATION THROUGH THE 1
HELIUM PURIFICATION SYSTEM c.
PCRV LINER COOLING FUNCTION d.
PROCESS MONITORING TUNCTION e.
SUPPORTING TUNCTIONS SUCH AS COOLING, LUBRICATION, ETC. REQUIRED TO SUPPORT CHUTDOWN\\COOLDOWN TUNCTIONS t
i' s
I I
i
f.
B.
NON-CONGESTED CABLE AREAS 1.
LIMITING CONSEQUENCES OF A NON-CCA FIRE:
MEANS SHALL BE AVAILABLE TO SHUTDOWN \\COOLDOWN THE THE REACTOR SUCH THAT NO FUEL DAMAGE OCCURS (<2900 F).
NO SIMULTANEOUS RUPTURE OF BOTH PRIMARY COOLANT BOUNDARY & SECONDARY CONTAINMENT BOUNDARY SUCH THAT NC UNMONITORED RADIOLOGICAL RELEASES OCCURS.
2.
PERFORMANCE GOALS:
a.
ACHIEVING & MAINTAINING SUBCRITICAL REACTIVITY CONDITIONS b.
MAINTAINING PCRV LINER INTEGRITY & PCRV STRUCTURAL AND PRESSURE CONTAINMENT INTEGRITY c.
REACTOR HEAT REMOVAL FUNCTION d.
PROCESS MONITORING FUNCTION e.
SUPPORTING FUNCTIONS l
___]
(W)
I C.
SPECIFIC CRITERIA 1.
G & J WALLS AUTOMATIC SPRINKLERS IN COMPLY WITH EITHER NFPA 13 OR NFPA 15 l
2.
REDUNDANT OR ALTERNATE EMUTDOWN\\COOLDOWN CAPABILITY SHALL BE PHYSICALLY & ELECTRICALLY INDEPENDENT OF SPECIFIC FIRE LOCATION i
3.
REDUNDANT OR ALTERNATE SHUTDOWN \\COOLDOWN CAPAB'ILITY SHALL ACCOMMODATE POST FIRE CONDITIONS WHERE OFFSITE POWER IS AVAILABLE AND WHERE OFFSITE POWER IS NOT t
AVAILABLE FOR 72 HOURS 4.
EQUIPMENTS & SYSTEMS, PRIOR TO CONSIDERING ANY POSTULATED FIRE DAMAGE, SHALL BE CAPABLE OF BEING POWERED EITHER BY AN OFFSITE & AN ONSITE POWER SOURCE, OR BY TWO INDEPENDENT ONSITE POWER SOURCES 5.
SHUTDOWN \\COOLDOWN PROCEDURES IN EFFECT IN EVENT OF ANY SINGLE FIRE 6.
NUMBER OF OPERATING SHIFT PERSONNEL, EXCLUSIVE OF FIRE BRIGADE, REQUIRED TO OPERATE SHUTDOWN \\COOLDOWN EQUIPMENT SMALL BE ONSITE AT ALL TIMES THE REACTOR IS NOT SHUTDOWN 7.
SHUTDOWN \\COOLDOWN SYSTEMS & EQUIPMENT NEED NOT BE DESIGNED TO MEET SEISMIC CATEGORY I, SINGLE FAILURE CRITERIA, OR OTHER DESIGN BASIS ACCIDENT CRITERIA
( EXCEPT WHERE REQUIRED FOR OTHER REASONS, E.G.
BECAUSE OF INTERFACE WITH OR IMPACT ON EXISTING SAFETY SYSTEMS, OR BECAUSE OF ADVERSE VALVE ACTIONS DUE TO FIRE DAMAGE 8.
SHUTDOWN \\COOLDOWN EQUIPMENT FOR EACH LOCATIONS SHALL BE KNOWN TO BE ISOLATED FROM ASSOCIATED CIRCUITS SO TO PREVENT OPERATION j
9.
WATER-FILLED MECHANICAL COMPONENTS SHALL NOT BE CON-I SIDERED DAMAGED BY THE FIRE. WATER-FILLED VALVES &
MECHANICAL COMPONENTS WITH MANUAL OPERATORS IN THE FIRE AREA SMALL BE CONSIDERED TO BE MANUALLY OPERABLE WITHIN 1 HOUR AFTER THE START OF THE FIRE t
--