Letter Sequence Meeting |
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MONTHYEARML20074A7561983-04-27027 April 1983 Clarifies Proposed Changes in Undervoltage Protection & Reiterates Schedule for Implementation of Design Changes & Mods.Existing non-Class IE Undervoltage Relays Will Be Retained as Protection for 4,160-volt Buses Project stage: Request ML20135H5631985-08-31031 August 1985 Truth-Analysis/Action-Reaction Review of 480-Volt Essential Bus Tie Breaker Control Scheme, Final Rept Project stage: Other ML20212N6621985-08-31031 August 1985 Technical Evaluation Rept for Proposed Change to Operation of Ginna Fuel Pool Charcoal Filter Sys, Informal Rept Project stage: Request ML20137S3631985-09-13013 September 1985 Corrected Page 1 to Responding to 850614 Commitment to Perform Evaluation of Emergency Diesel Generator Control Logic Circuitry.Ltr Number Changed Project stage: Other IR 05000267/19850171985-09-13013 September 1985 Insp Rept 50-267/85-17 on 850617-0816.Violation Noted: Failure to Rept Nine Circulator Trips in 1984 & Seven Trips in 1985 & No Differential Helium Pressure Maintained When Pcrv Pressure Above 100 Psia Project stage: Request ML20135H5591985-09-13013 September 1985 Forwards Truth-Analysis/Action-Reaction Review of 480-Volt Essential Bus Tie Breaker Control Scheme, Final Rept & Provides Evaluation of Control Logic Design Project stage: Other ML20134A3651985-10-23023 October 1985 Amends Correction Portion of Item 2 (286G1A & 286G1B) in Util Re Results of Proto-Power Corp Analysis Concerning Emergency Electrical Power Sys Independence Project stage: Other ML20137B3561986-01-0303 January 1986 Informs That Design Changes Involving Emergency Diesel Generator (EDG) Control Logic Circuitry Implemented.No Single Failure Will Interfere W/Proper Operation of Redundant EDG Project stage: Other ML20137K9991986-01-14014 January 1986 Notifies That Design Changes in Emergency Diesel Generator Control Logic Circuitry Implemented,Per 850913 Commitment. Changes Assure That Failure Will Not Interfere W/Operation of Redundant Generator.Ltr Supersedes Project stage: Other ML20140H1101986-03-31031 March 1986 Submits Info Re Startup Check List for Automatic Operation of Emergency Diesel Generators,Sys Operating Procedure 92-04,in Response to NRC .Numbers Will Be Assigned to All Valves in Emergency Diesel Generator Rooms Project stage: Other ML17251A7911986-03-31031 March 1986 Reactor Containment Bldg Integrated Leakage Rate Test. Project stage: Request ML20206T7341986-07-0101 July 1986 Submits Summary & Schedule of Mods to Be Performed on Emergency Diesel Generator Control Circuitry in Response to 860515 & 21 Telcons.Mods Will Be Completed Prior to Startup from Current Equipment Qualification Outage Project stage: Other ML20213G5811986-08-0707 August 1986 Draft Review of Fort St Vrain Onsite AC 'Standby' Power Sys W/Regards to Compliance to Single Failure Criterion & Ser Project stage: Draft Other ML20213G5641986-11-12012 November 1986 Forwards Onsite Class 1E Power Sys Design Features Review Status Rept Based on FSAR & NRC 860814 Meeting W/Licensee & Inel Draft Review of Fort St Vrain Onsite AC 'Standby' Power.... Resolution to Problems Requested Before 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 ML20212G8671987-01-0909 January 1987 Forwards Rev a to EE-92-0008, Engineering Evaluation of Load Shedding,Load Auto Start Prohibit,Load Sequencing,Bus Tie Breaker Alignment & Generator Breaker Closing Portions of Emergency Diesel Generator Control Circuitry Project stage: Other ML20207R9471987-03-0606 March 1987 Rev 1 to Review of Fort St Vrain Onsite AC `Standby' Power Sys Re Compliance to Single Failure Criterion & Ser Project stage: Other ML20207R9381987-03-0606 March 1987 Forwards Rev 1 to EGG-NTA-7456, Review of Fort St Vrain Onsite AC `Standby' Power Sys Re Compliance to Single Failure Criterion & Ser Project stage: Approval ML20207S6271987-03-12012 March 1987 Summary of 870210 Meeting W/Util Re Emergency Diesel Generator Electrical Independence.List of Attendees Encl Project stage: Meeting ML20237G2051987-08-0606 August 1987 Concurs w/870601 Proposed Mods Re Adequacy of 1C Battery to Supply Dc Control Power to 480 Volt Ac Essential Bus 2. Submittal of Application for Amend to License Recommended Project stage: Other ML20237J2271987-08-10010 August 1987 Submits Application Fee for Re Proposed Design Changes to Supply Dc Control Power to 480 Volt Ac Essential Bus 2 & Associated Undervoltage Relays.Encl Fee Will Cover Upcoming Tech Spec Amend for Proposed Electrical Changes Project stage: Other 1986-12-24
[Table View] |
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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
[Table view] |
Text
. . . . = . . -. . - _ . . .
3 j % UNITED STATES 4 3 -k NUCLEAR REGULATORY COMMlSSION l
3,'#' } W ASHINGTON. D. C. 20555 i
'*A , , , , , /
Docket No. 50-267 MEMORANDUM FOR: Herbert N. Berkow,' Director Standardization and Special Projects Directorate Division of PWR Licensing-P THRU: 0. D. T. Lynch, Jr., Section Leader
. Standardization and Special Projects Directorate Division of PWR Licensing-B l
FROM: Kenneth L. Heitner, Project Manager Standardization and Special 1 Projects Directorate E Division of PWR Licensing-B
SUBJECT:
SUMMARY
OF FEBRUARY 10, 1987 MEETING WITH PUBLIC SERVICE COMPANY OF COLORADO (PSC).TO DISCUSS FORT ST. VRAIN EMERGENCY DIESEL GENERATOR (EDG) ELECTRICAL INDEPENDENCE Introduction The purpose of this meeting was to discuss in detail the PSC submittal, dated January 9,1987 (P-87008),on EDG electrical independence. The staff's
- objective during this meeting was to establish that no single failure of the
- automatic control system would
!= - Lead to accidental paralleling of the EDGs, or j
- Prevent manual operation of the EDGs.
In addition, the staff wished to discuss PSC's program for testing the circuit breakers (CBs) which protected the circuits containing the automatic throwover i (ATO) for the 480 volt switchgear de control power supplies. Attendees at this meeting are listed in the enclosure.
At the onset of the meeting, PSC stated that each of the three switchgear sets discussed'during the meeting is designed to have its control power provided from either of the two redundant de buses through an ATO scheme.
PSC stated that there were four levels of automatic undervoltage protection provided on each of the three 480 volt ac emergency buses. These were:
- 1) Loss of primary power source on any one of the three buses -
Automatic throwover of the affected bus to the alternate off-site
! power source.
- 2) Degraded voltage for 120 seconds on any two of the three buses -
Trip all three off-site source CEs, start both EDGs, and load shed.
i
[2gg{ f5 7 P
N-
w l-
- 3) Loss of voltage on any two of the three buses - Start EDGs and Icad shed.
- 4) Loss of voltage for 30 seconds on any one of three buses - Scrarr the reactor.
EDG Operation The staff and PSC personnel reviewed the operation of the EDGs in detail, including the steps required for the EDGs to energize their respective buses.
Separate examinations were made for:
- EDG output CBs,
- Emergency bus off-site pcwer source CBs, and
- Emergency bus tie CBs.
0>eration of the CBs Tie EDG output CBs can be closed ranually from the control room or locally at the EDGs. Synchronizing equipment is at both locations. There are protective circuits for over-current and reverse power associated with the CB. The local panels also have controls for the individual engines. If both engines associated with an EDG do not start, the output CB will not close automatically and can be manually closed.
The bus tie CBs have protective circuitry to prevent them f:om closing on a faulted bus. Additional contacts were being utilized to assure the EDGs could not accidentally be paralleled through the bus ties, even if a single failure occurred. In a loss-of-bus-voltage, the ccnnection preference for the swing-bus (No. 2) was preselected. Powever, when the EDGs were called to start, the swing-bus will be tied to the first bus energized by its associated EDG.
Operation of the off-site power source CBs was also examined.
The staff concluded from their examination of the CBs that manual capability )
of the EDG CBs has civisional independence, and was not affected by any identified single failure. Furthermore, there was no possibility cf accidentally paralleling the EDGs as a result of a single failure.
CB Testing PSC stated that to assure that the ATO for the 480 volt switchgear control power supply would not lead to the loss of all de power, the ATO CBs, along with the ATO contractors, would be tested before plant restart from the present outage.
The staff stated that this would be acceptable. However, it was agreed that the CB testino will be an interim measure to avoid a single fault causing loss of both sources of de control power due to the ATO scheme. A permanent solution of the problems associated with the existing ATO scheme is to adc a third dc source of power. PSC is actively evaluating this modification and will submit their proposal to the NRC by June 1, 1987, per the commitment in Attachment 3 of the PSC submittal of January 9,1987, noted above.
(
I
0 l
v 3-Automatic Controls Staff review of the autorietic control of the EDG output CBs, the off-site power source CBs, and the bus tie CBs led to the conclusion that this syster' was also acceptable. That is, the automatic centrol system met the single failure criteria, and the PSC separation criteria for divisicnal independence appeared to be adequate. However, the staff stated thst they would reouest a confirmatory review of the separation criteria by Region IV inspection personnel. Reference would also be made to the staff's acceptance of the Alternate Cooling Method diesel as the power source should a single fire damage the 480 volt switchgear.
Based on the above findings, the staff cencludes that all majcr concerns abcut the electrical independence of the EDG's and their manual and automatic control systems have been resolved. The staff concludes that the licensee's actions to resolve these issues to date fom an adecuate basis for safe plert operation.
7 - : i .
5 4 .wwN r-- ,
fMd.3 Kenneth L. Heitner, Project Manager -
Standardization and Special Projects Directorate Division of PWP. Licensing-B
Enclosure:
As stated cc w/ enclosure:
See next page
Mr. R. O. Williams 4- 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 Conpany 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 65608 Public Service Company of Colerado 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 Colorado Quality Assurance Division P. O. Box 840 Public Service Company of Colorado Denver, Colorado 80201 16805 Weld County Road 19-1/2 Platteville, Colorado 80651 Senior Resident Inspector U.S. Nuclear Regulatory Commission Mr. R. F. Walker P. 0. Box 840 Public Service Company of Colorado Platteville, Colorado 80651 Post Office Ecx 840 Denver, Colorado 80201-0840 Kelley, Stansfield ti O'Donnell Public Service Company Building Commitment Control Program Room 900 Coordinator 550 15th Street Public Service Company of Colorado Denver, Colorado 80202 2420 W. 26th Ave. Suite 100-D Denver, Colorado 80211 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000
-Arlington, Texas 76011 i
Chairman, Board of County Commissioners of Weld County, Colorado Greeley, Colorado 80631 Regional Representative
- Radiation Programs Environmental Protection Agency 1 Denver Place 999 18th Street, Suite 1300 Denver. Colorado 80202-2413 1
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Enclosure 1
t Attendees at PSC - NPC Meetino February 10', 1987 Name Oroanization Ken Feitner NRC/NRR/DPWRL-B J. R. Reesy Public Service Company of Colorado J. R. Johns Public Service Company of Colorado Howard Parkhunst Proto Power Corp.
Robert A. Schenderlein Public Service Company of Colorado James Selan PSC/ Licensing Paul Michaud NRC/ Resident Inspector Charles Miller NRC/NRR/PEICSB-SL
- 1. Ahmed NRC/NRR/PEICSB J. Calvo NRC/NRR/PEICSB l
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.- T March'12, 1987 Automatic Controls Staff review of the automatic control of the EDG output CBs, the off-site power source CBs, and the bus tie CBs led to the conclusion that this system was also acceptable. That is, the automatic control system met the single
-failure criteria, and the PSC separation criteria for divisional independence appeared to be adequate. However, the staff stated that they would request a confirmatory review of the separation criteria by Region IV inspection personnel. Reference would also be made to the staff's acceptance of the Alternate Cooling Method diesel as the power source should a single fire damage the 480 volt switchgear.
Based on the above findings, the staff concludes that all major concerns about the electrical independence of the EDG's and their manual and automatic control systems'have been resolved. The staff concludes that the licensee's actions to' resolve these issues to date fonn an adequate basis for safe plant operation.
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 D.lSTRLBUTION:
45 2ReUjJej RIreland, RIV NRC PDR JGagliardo, RIV Local PDR JJaudon,- RIV PBSS Reading DCrutchfield FMiraglia KHeitner 0GC-Bethesda 0 Lynch EJordan HBerkow
, BGrimes IAhmed l JPartlow CMiller l HThompson JCalvo ACRS (10) PNoonan
- See Previous Concurrence Pli PBSS PifsS PR$S S
n XHeitner:cw OL'ydch HBerlkbw 3/n /87 03/12/87 03T4/87 03/lk/87
- PEICSB* PEICSB* PEICSB* PBAD*
[
IAhmed CMiller JCalvo DCrutchfield l 03/03/87 03/03/87 03/05/87 03/10/87
\
r Automatic Controls Staff review of the automatic control of the EDG output CBs, the off-site power source CBs, and the bus tie CBs led to the conclusion that this system was also acceptable. That is, the automatic control system met the single
- failure criteria and that the PSC separation criteria for divisional 7 independence = appeared- to be adequate.
However, the staff stated that they would request a confirmatory review of I the separation criteria by Region IV inspection personnel. Reference would l .also be made to the staff's acceptance of the Alternate Cooling Method diesel as the power source should a single fire damage the 480 volt switchgear.
Based on the above findings, the staff concludes that all major concerns about
.the electrical independence of the EDG's and their manual and automatic control systems have been resolved. The staff concludes that the licensee's
-actions to resolve these issues to date form an adequate basis for safe plant operation.
Kenneth L. Heitner, Project Manager Standardization and Special Projects Directorate Division of PWR Licensing-B
Enclosure:
As stated cc w/ enclosure:
, See next page DISTRIBUTION:
Docket File RIreland, RIV NRC PDR JGagliardo, RIV Local PDR JJaudon, RIV PBSS Reading DCrutchfield FMiraglia KHeitner 0GC-Bethesda Olynch EJordan HBerkow BGrimes- IAhmed JPartlow CMiller HThompson JCalvo ACRS (10) PNoonan
- See Previous Concurrence (P3 PBSS PBSS PBSS PNoonan KHeitner:cw Olynch HBerkow 03/cl/87 03/3 /87 03/ /87 ,03/ /87 PEICSB* PEICSB* PEICSB* P p IAhmed CMiller JCalvo DC field 03/03/87 03/03/87 03/05/87 03//o /87 ,
, '1
'e c:
s However, the staff stated that they would request a confirmatory review of the separation criteria by Region IV inspection personnel. Reference would also be made to the staff's acceptance of the Alternate Cooling Method diesel as the power source should a single fire damage the 480 volt switchgear. '
Basedontheabovefindings,thestaffconcludesthfallmajorconcernsabout the electrical independence of the EDG's and their manual and automatic control systems have been resolved. The staff concludes that the licensee's actions to resolve these issues to date form an adequate basis for safe plant operation.
Kenneth L. Heitner, Project Manager Standardization and Special Projects Directorate Division of PWR Licensing-B
Enclosure:
As stated cc w/ enclosure:
See next page DISTRIBUTION:
Docket File RIreland, RIV NRC PDR JGagliardo, RIV Local PDR JJaudon, RIV PBSS Reading DCrutchfield FMiraglia 0GC-Bethesda EJordan BGrimes JPartlow
, HThompson l ACRS(10)
PNoonan KHeitner Olynch HBerkow IAhmed CMiller j JCalvo PBSS PBSS PBSf, N onan KHeitner:cw Olynch HBe"kow 03/')./87 03/2/87 03/ /87 03/ /87 PEICSB PEICSB G m PEICSB 77 g, Pr;AD IAhmed CMiller JCalvo DCrutchfield 03/3 /87 03/3 /87 03/r/87 03/ /87
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