PNO-IV-84-014, on 840623,reactor Tripped on High Pressure Signal & 6 of 7 Control Rod Pairs Failed to Drop.Cause Unknown.Drive Mechanisms Will Be Removed for Exam
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Other: ML20087D526, ML20091E427, ML20091E667, ML20096C267, ML20101P455, ML20101T673, ML20128N324, ML20128Q523, ML20132D461, ML20133E065, ML20133G264, ML20134E393, ML20135B283, ML20137G089, ML20137M414, ML20138M184, ML20141G663, ML20141P193, ML20148G166, ML20149E148, ML20155G379, ML20197B758, ML20198D937, ML20202F052, ML20204G480, ML20205D265, ML20206B182, ML20207E030, ML20207Q913, ML20209C232, ML20211G583, ML20214P255, ML20214P273, ML20214U381, ML20214U731, ML20214X272, ML20235F214, ML20235G486, ML20236C261, ML20236G303, ML20236H463 | |
MONTHYEARML20087D5261984-03-0202 March 1984
[Table View]Requests Exemption from Requirements of Sections Iii.G,J,L & O to 10CFR50,App R.Fire Protection Provisions Believed Adequate to Protect Health & Safety of Public in Event of Accidents Involving Fires.Affidavit Encl Project stage: Other ML20091E6671984-05-10010 May 1984 Forwards List of Correspondence on Fire Protection,Per 840427 Request.List Identifies Ltrs Originated from NRC & Util Relevant to Fire protection,10CFR50,App R,Branch Technical Position 9.5-1,cable Separation & Plant Issues Project stage: Other ML20091E4271984-05-11011 May 1984 Forwards Summary of Fire Protection Review to Determine Conformance of Facility to Section Iii.G of 10CFR50,App R, Per 840427 Commitment.Fire Protection Provisions Adequate Project stage: Other ML20092M5471984-06-22022 June 1984 Responds to 840608 Meeting Re Application of 10CFR50,App R Fire Protection Requirements to Facility.Schedule for App R Review & Submittal & Proposed Fire Protection Regulatory Guidance Resolving HTGR Issues Encl Project stage: Meeting PNO-IV-84-014, on 840623,reactor Tripped on High Pressure Signal & 6 of 7 Control Rod Pairs Failed to Drop.Cause Unknown.Drive Mechanisms Will Be Removed for Exam1984-06-25025 June 1984 PNO-IV-84-014:on 840623,reactor Tripped on High Pressure Signal & 6 of 7 Control Rod Pairs Failed to Drop.Cause Unknown.Drive Mechanisms Will Be Removed for Exam Project stage: Request ML20090C5261984-07-0606 July 1984 Responds to NRC Concerns Re Fire Protection Review,Bldg 10 Licensing Requirements,Control Rod Failure to Scram, Documentation of Disciplinary Actions,Clearance Tags & Radiological Emergency Exercise Scenario,Per 840625 Meeting Project stage: Meeting ML20096C2671984-08-17017 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 ML20101P4551984-12-14014 December 1984 Advises That Final Installation of Oil Mist Detection Sys Completed Wk of 841105,per 840625 Commitment.Sys Inoperable During Initial Checkout.Manufacturer Repaired & Balanced Entire Sys on 841115,however,on 841121 Sys Inoperable Again Project stage: Other ML20101T6731985-01-25025 January 1985 Forwards Table 5.0.1,omitted from Rept 3 of App R Fire Protection Evaluation,Originally Submitted by Project stage: Other ML20128Q5231985-05-15015 May 1985 Responds to Re Contradictory Statements Submitted in Three Util Ltrs.Circulator Speed Instruments Not Relied Upon in 10CFR50,App R,Re Fire Protection Evaluation Because of Close Proximity Between Loops Project stage: Other ML20128N3241985-05-17017 May 1985 Informs of Completion of Mod Work to Automate G&J Wall Sprinkler Sys,Per 840817 App R Commitment Project stage: Other ML20132D4611985-07-11011 July 1985 Documents 850708 Telcon Re Interim Fire Protection Measures Committed to in or Lee .Fire Watch Frequency Increased.Personnel Will Carry Flashlights at All Times Per Operating Order 85-11,prior to Plant Startup Project stage: Other ML20133G2641985-07-16016 July 1985 Documents 850715 Telcon Re App R Fire Protection Evaluation Schedule.Util Will Complete Mod Item 4.2 Re Penetration Seals by 850717.Revised Completion Date Allows for Installation of Final Seal,Surveillance Testing & Sign Offs Project stage: Other 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 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 ML20133H5331985-08-0202 August 1985 Requests Assessment of Consequences of Loss of Shutdown Sys Due to Fire in Bldg 10,as Part of Review of Fire Protection Features at Plant.Evaluation Requested within 30 Days of Ltr Date Project stage: Approval ML20134E3931985-08-0505 August 1985 Submits Info on Status of Mods Proposed in 850401 Rept 4 Re Exemptions & Mods to App R Fire Protection Evaluation.Listed Mods Complete Project stage: Other ML20137G0891985-08-0808 August 1985 Notifies of Delay in Obtaining All Replacement Fire Door Matls,Per ,Due to Door to Hardware Compatibility Problems W/Facility Security Sys.Matls Will Be Delivered by 851015 Project stage: Other ML20135B2831985-08-30030 August 1985 Provides Info to Resolve Questions & Concerns Identified in Review of Repts 1-4 for App R Evaluation & Rept 5 for Branch Technical Position 9.5-1,App a Evaluation of Bldg 10.Page Changes for Repts 1-5,incorporating Resolutions,Encl Project stage: Other ML20205D2651985-09-0303 September 1985 Informs of Fire Detection Sys Design Status.Initial Change Notice Providing Detection Device Design & Location Issued on 850901,per 850401 Commitment.Installation Expected by 860201 Project stage: Other ML20133E0651985-09-10010 September 1985 Responds to NRC Re Violations Noted in Insp Rept 50-267/85-16.Corrective Actions:Design for New Storage Ctr Initiated Project stage: Other ML20138M1841985-10-14014 October 1985 Clarifies Commitment Dates in Util Re Proposed Mods Per 10CFR50,App R Fire Protection Evaluation.Remaining Mods Expected to Be Completed During Refueling Outage Project stage: Other ML20136J3161985-11-0101 November 1985 Forwards Questions Re Manual Operations & Instrumentation Based on Review of 841116-1217 & 850117 & 0401 Submittals of App R Safe Shutdown Models.Addl Info Requested within 30 Days of Ltr Receipt Project stage: Approval ML20138P3311985-12-20020 December 1985 Forwards Response to 851101 Request for Addl Info Re App R Safe Shutdown Model.Steps Included in Fire Protection Shutdown Procedure for Operators to Properly Position motor- Operated Valves Project stage: Request ML20137M4141986-01-21021 January 1986 Informs of Updated Efforts to Implement Fire Detection Sys. Completion Anticipated by 860601.As Result of extension,24 H Fire Watch Will Continue as Stated in Interim Measures of Rept 4 Project stage: Other ML20141P1931986-03-14014 March 1986 Forwards Info/Clarification for Open Items & Revised App R Fire Protection Evaluations (Repts 1-4) & Fire Hazards Analysis & Evaluation of Bldg 10 (Rept 5) Project stage: Other ML20202F0521986-04-0404 April 1986 Forwards Valve Position & Alignment Justification & Revs to App R Repts 1 & 3 Incorporating Manual Pressurization Sys for Helium Circulator Brake & Seal Sys Into Shutdown Model, Per 860314 Commitment Project stage: Other ML20141G6631986-04-17017 April 1986 Requests Util Evaluate Encl NRC 851222 Press Release Re New Criteria for Granting Exemptions from 10CFR50 to Determine If Exemptions from App R Fire Protection Requirements Still Required.Info Requested within 60 Days Project stage: Other ML20155G3791986-04-28028 April 1986 Requests That 850401 Exemption from Sections Iii.G & Iii.J of App R & 10CFR50.12(a) Re Fire Protection Be Granted.List of Exemptions Encl Project stage: Other ML20198D9371986-05-15015 May 1986 Forwards App R Evaluation Re Valve Position & Alignment,As Encl to Walker ,Per Request Project stage: Other ML20202G6441986-07-10010 July 1986 Informs of Plans to Submit Documentation Re Results of CRD Improvements Integrated Sys Study by 860815.Requests NRC Confirmation of Submittal Date Project stage: Request ML20207F3771986-07-15015 July 1986 Forwards Supplemental Info to 860314 & 0404 Submittals Re Local Manual Operations Required for Fire in Each Area & Assessment of Adequacy of Present Staffing Levels to Accomplish Fire Protection Shutdown Project stage: Supplement ML20204C1671986-07-22022 July 1986 Responds to 860428 Request for Exemption from Fire Protection Requirements,Per 10CFR50.12.Although Technical Review Not Completed,Submittals Adequately Address Criteria. Request for Relief from 10CFR50.48 Cannot Be Acted Upon Project stage: Approval ML20204G4801986-07-31031 July 1986 Informs That 860710 Request for Delay of Submittal of Integrated Sys Study Until 860815 Acceptable.Revised Listing of Commitments,Updated to Reflect Completion of Items 11 & 16b,encl Project stage: Other ML0311502641986-08-20020 August 1986 Withdrawn NRC Generic Letter 1986-014: Operator Licensing Examinations Project stage: Request ML20212N4761986-08-26026 August 1986 Safety Evaluation Approving Licensee 850401 Exemption Request from Requirements in 10CFR50,App R,Section Iii.J Re Emergency Lighting Project stage: Approval ML20212N4711986-08-26026 August 1986 Forwards Safety Evaluation Approving Util 850401 Exemption Requests from Requirements in 10CFR50.40 & 10CFR50,App R, Section Iii.J Re Emergency Lighting Project stage: Approval ML20197B7581986-10-16016 October 1986 Notifies of Development of Fire Protection Program Plan at Plant in Accordance W/Requirements of 10CFR50.48(a),per 860314 Commitment.Plan Includes Updated Fire Hazards Analysis for Each Plant Fire Area Project stage: Other ML20211G5831986-10-22022 October 1986 Anticipates Completion of Steam Generator Analysis & App R Modeling Reanalysis Work by Feb 1987,per 860918 Telcon W/Nrc Re Steam Generator Cool Down Studies for App R Project stage: Other ML20214G1091986-11-18018 November 1986 Forwards Draft Fire Protection Safety Evaluation Supporting Util 850401 Request for Exemption from 10CFR50,App R Requirements & Proposed Safe Shutdown Sys.Status Rept on Listed Items & Comments Re Draft Evaluation Requested Project stage: Draft Approval ML20214G1411986-11-18018 November 1986 Draft Safety Evaluation Supporting Util 850401 Request for Exemption from 10CFR50,App R Requirements Re Fire Protection & Proposed Safe Shutdown Sys.Related Info Encl Project stage: Draft Approval ML20214P2551986-11-20020 November 1986 Forwards Updated & Condensed Version of Const Schedule for Proposed App R Mods,Per Request Project stage: Other ML20207E0301986-12-29029 December 1986 Forwards Corrected Schedule of Proposed App R Mods Noted in .Mod Re Emergency Lighting Will Be Completed,As Discussed in 860826 Ser,Within 12 Months Following NRC Approval Project stage: Other ML20235J4001987-01-16016 January 1987 Forwards Comments on Draft Fire Protection SER Project stage: Draft Other ML20209C2321987-01-23023 January 1987 Advises Util to Complete App R Mods to Facility Expeditiously.Staff Considers Dates in 861120 & 1229 Ltrs as Commitments.Nrc Considering Rev to Listing of Util Commitments Re Operation of Facility Project stage: Other IR 05000267/19870011987-02-27027 February 1987 Insp Rept 50-267/87-01 on 870202-06.No Violations or Deviations Identified.Major Areas Inspected:Fire Protection/Prevention Program & Implementation Project stage: Request ML20207Q9131987-02-27027 February 1987 Requests Concurrence to Reduce Roving Fire Watch,Committed to in Util ,To Hourly Fire Watch for Turbine Water Removal Pumps Effective on 870325.New Fire Detection Sys Described in Util Installed Project stage: Other ML20206B1821987-04-0202 April 1987 Advises That Util 870227 Request to Reduce Level of Roving Fire Watches,Acceptable.Maintain Hourly Fire Watch in Current Turbine Water Removal Pumps.Change May Be Implemented Upon Completion of New Fire Protection Sys Project stage: Other ML20214P2731987-05-15015 May 1987 Forwards Revs to App R Evaluations for Shutdown Model, Electrical Reviews, Fire Protection Reviews & Exemptions & Mods, to Show Consistency W/Safe Shutdown Trains Project stage: Other ML20214U7311987-06-0101 June 1987 Requests Exemption from 10CFR50,App R Requirements,Except Sections Iii.G & Iii.J Under 10CFR50.12,establishing Unambiguous Regulatory Criteria for High Temp Gas Cooled Reactor.History of Correspondence on Issue Encl Project stage: Other 1985-09-03 |
| ML20198T499 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 06/25/1984 |
| From: | Ireland R, Johnson E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| References | |
| PNO-IV-84-014-0, PNO-IV-84-14, NUDOCS 9711170011 | |
| Download: ML20198T499 (1) | |
Similar Documents at Fort Saint Vrain | |
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Category:PRELIMINARY NOTIFICATION OF EVENT OR OCCURRENCE (PNO
MONTHYEARPNO-IV-89-055, on 890829,Board of Directors Directed Termination of Nuclear Operations at Facility for 100-day Cooldown Period in Preparation for 30-month Reactor Defueling.Nrc Currently Reviewing Defueling Safety Analysis1989-08-29029 August 1989
[Table view]PNO-IV-89-055:on 890829,Board of Directors Directed Termination of Nuclear Operations at Facility for 100-day Cooldown Period in Preparation for 30-month Reactor Defueling.Nrc Currently Reviewing Defueling Safety Analysis PNO-IV-89-052C, updates 890818,21 & 23 Unplanned Reactor Shutdowns Due to Inoperable Control Rod.Control Rod Assembly Will Be Removed Using Bldg Crane.Aluminum Shutter Will Be Remotely Placed on Bottom of Canister1989-08-25025 August 1989 PNO-IV-89-052C:updates 890818,21 & 23 Unplanned Reactor Shutdowns Due to Inoperable Control Rod.Control Rod Assembly Will Be Removed Using Bldg Crane.Aluminum Shutter Will Be Remotely Placed on Bottom of Canister PNO-IV-89-052B, on 890823,unplanned Reactor Shutdown Due to Inoperable Control Rod.Licensee Plans to Remove Control Rod Pair W/Bldg Crane in Unshielded Configuration to Shielded, Contained Evolution1989-08-23023 August 1989 PNO-IV-89-052B:on 890823,unplanned Reactor Shutdown Due to Inoperable Control Rod.Licensee Plans to Remove Control Rod Pair W/Bldg Crane in Unshielded Configuration to Shielded, Contained Evolution PNO-IV-89-052A, on 890818,after Attempting to Withdraw & Insert Control Rod Pair from Region 19,control Rod Motor Stopped Drawing Current & Indicated Open Conductor or Thermal Overload.Pair Will Be Withdrawn Using Bldg Crane1989-08-21021 August 1989 PNO-IV-89-052A:on 890818,after Attempting to Withdraw & Insert Control Rod Pair from Region 19,control Rod Motor Stopped Drawing Current & Indicated Open Conductor or Thermal Overload.Pair Will Be Withdrawn Using Bldg Crane PNO-IV-89-052, on 890817,unplanned Reactor Shutdown Due to Inoperable Control Rod Drive Occurred.Attempts to Clear Cause of Slack Cable Light Failed.Loop 2 Shutdown Due to Upset in Bearing Water Sys Occurred During Plant Shutdown1989-08-18018 August 1989 PNO-IV-89-052:on 890817,unplanned Reactor Shutdown Due to Inoperable Control Rod Drive Occurred.Attempts to Clear Cause of Slack Cable Light Failed.Loop 2 Shutdown Due to Upset in Bearing Water Sys Occurred During Plant Shutdown PNO-IV-89-044, on 890628,pressure in Waste Gas Receiver a Decreased from 250 Psig & Pressure in Receiver a Decreased from 60 to 50 Psig.Caused by Erroneous Valve Lineup.Plant Stack Monitors Did Not Alarm1989-06-28028 June 1989 PNO-IV-89-044:on 890628,pressure in Waste Gas Receiver a Decreased from 250 Psig & Pressure in Receiver a Decreased from 60 to 50 Psig.Caused by Erroneous Valve Lineup.Plant Stack Monitors Did Not Alarm PNO-IV-89-040, from 890622-23,power Exceeded 82% & Secondary Heat Balance Indication in Control Room Read Approx 79.2%.On 890623,discovered Incorrect Input Into Secondary Heat Balance Calculation.Power Reduced to 65% Pending Evaluation1989-06-23023 June 1989 PNO-IV-89-040:from 890622-23,power Exceeded 82% & Secondary Heat Balance Indication in Control Room Read Approx 79.2%.On 890623,discovered Incorrect Input Into Secondary Heat Balance Calculation.Power Reduced to 65% Pending Evaluation PNO-IV-89-036, on 890529,two Teenagers Shot by off-duty Security Guard Following Confrontation Re Assault.Guard Arrested & Being Held for Murder.Licensee Plans to Issue Press Release.State of Co Will Be Informed.Record Copy1989-05-30030 May 1989 PNO-IV-89-036:on 890529,two Teenagers Shot by off-duty Security Guard Following Confrontation Re Assault.Guard Arrested & Being Held for Murder.Licensee Plans to Issue Press Release.State of Co Will Be Informed.Record Copy PNO-IV-89-031, on 890427,CRD 3 Failed to Insert on Scram During Performance of Weekly Partial Insertion Scram Tests. Troubleshooting Confirmed That CRD Brake Deenergized & That Rod Out Limit Cleared.Licensee Plans to Replace CRDs 3 & 71989-04-28028 April 1989 PNO-IV-89-031:on 890427,CRD 3 Failed to Insert on Scram During Performance of Weekly Partial Insertion Scram Tests. Troubleshooting Confirmed That CRD Brake Deenergized & That Rod Out Limit Cleared.Licensee Plans to Replace CRDs 3 & 7 PNO-IV-88-054, on 880705,reactor Shut Down to Commence 99-day Planned Outage to Replace Fasteners Associated W/Helium Circulators.Licensee Schedule Calls for Return to Operations on 881007.Region IV Prepared to Respond to Media Inquiries1988-07-0606 July 1988 PNO-IV-88-054:on 880705,reactor Shut Down to Commence 99-day Planned Outage to Replace Fasteners Associated W/Helium Circulators.Licensee Schedule Calls for Return to Operations on 881007.Region IV Prepared to Respond to Media Inquiries PNO-IV-88-025, on 880404,following Manual Reactor Scram, Unplanned Release of Noble Gas Occurred When Relief Valve Opened to Relieve Pressure in Vent Line Between the Core Support Floor & Waste Gas Sys1988-04-0505 April 1988 PNO-IV-88-025:on 880404,following Manual Reactor Scram, Unplanned Release of Noble Gas Occurred When Relief Valve Opened to Relieve Pressure in Vent Line Between the Core Support Floor & Waste Gas Sys PNO-IV-88-011, on 880210,helium Circulator Tripped Due to Erroneous Low Speed Signal W/Reactor at 75% Power.Reactor Operators Manually Srammed Reactor from 25% Power W/One Helium Circulator Running.State of Co Informed1988-02-11011 February 1988 PNO-IV-88-011:on 880210,helium Circulator Tripped Due to Erroneous Low Speed Signal W/Reactor at 75% Power.Reactor Operators Manually Srammed Reactor from 25% Power W/One Helium Circulator Running.State of Co Informed PNO-IV-87-052, on 871002,reactor Tripped Due to Loss of Both Reactor Coolant Flow Loops Due to Fire in Turbine Bldg. Caused by Failure of Hydraulic Sys Filter.Reactor Manually Tripped,Alert Declared & Fire Extinguished1987-10-0505 October 1987 PNO-IV-87-052:on 871002,reactor Tripped Due to Loss of Both Reactor Coolant Flow Loops Due to Fire in Turbine Bldg. Caused by Failure of Hydraulic Sys Filter.Reactor Manually Tripped,Alert Declared & Fire Extinguished PNO-IV-87-035, licensee Initiated Plant Shutdown,Estimated to Last Approx 35 Days,To Replace Helium Coolant Circulation 1D.Circulation Developed Wobble & Penetration Interspace Seal Leak of Purified Helium.State of Co Will Be Informed1987-07-29029 July 1987 PNO-IV-87-035:licensee Initiated Plant Shutdown,Estimated to Last Approx 35 Days,To Replace Helium Coolant Circulation 1D.Circulation Developed Wobble & Penetration Interspace Seal Leak of Purified Helium.State of Co Will Be Informed PNO-IV-87-025, on 870427,received Permission to Take Reactor at Power Levels Above 10%.On 870430,generator Synchronized W/Grid.Licensee Will Conduct Operations at Less than 35% Power Until Certain Technical Issues Resolved1987-05-0101 May 1987 PNO-IV-87-025:on 870427,received Permission to Take Reactor at Power Levels Above 10%.On 870430,generator Synchronized W/Grid.Licensee Will Conduct Operations at Less than 35% Power Until Certain Technical Issues Resolved PNO-IV-87-020, augmented Insp of Low Power Operations Led Region to Conclude That Plant Being Operated in Prof & Conservative Manner.Licensee Conducting Surveillance Testing1987-04-24024 April 1987 PNO-IV-87-020:augmented Insp of Low Power Operations Led Region to Conclude That Plant Being Operated in Prof & Conservative Manner.Licensee Conducting Surveillance Testing PNO-IV-87-018, on 870417,reactor Taken Critical.First Criticality Since Reactor Shut Down on 860531 for Outage to Make Mods.Plant Under 10% Power Restriction for Operator Effectiveness Evaluation & Drying Out of Reactor Core1987-04-17017 April 1987 PNO-IV-87-018:on 870417,reactor Taken Critical.First Criticality Since Reactor Shut Down on 860531 for Outage to Make Mods.Plant Under 10% Power Restriction for Operator Effectiveness Evaluation & Drying Out of Reactor Core PNO-IV-87-019, former Manager of Nuclear Production Convicted & Sentenced to 3 Yrs.Conviction Resulted from Guilty Plea & Plea Bargaining.Three Others Indicted at Same Time for Related Offences Have Not Yet Come to Trial1987-04-17017 April 1987 PNO-IV-87-019:former Manager of Nuclear Production Convicted & Sentenced to 3 Yrs.Conviction Resulted from Guilty Plea & Plea Bargaining.Three Others Indicted at Same Time for Related Offences Have Not Yet Come to Trial PNO-IV-86-029, util Announced Expense Write Down of Company Assets in Amount of $75-100 Million,Study of Alternatives Re Future Operations & Approval of Settlement Agreement W/ Litigating Parties in Suits Before State of Co1986-09-24024 September 1986 PNO-IV-86-029:util Announced Expense Write Down of Company Assets in Amount of $75-100 Million,Study of Alternatives Re Future Operations & Approval of Settlement Agreement W/ Litigating Parties in Suits Before State of Co ML20212P0011986-08-25025 August 1986 PNS-IV-86-002:on 860822,determined That During June 1986 Security Watchman Entered & Exited Site w/22-caliber Handgun Hidden in Boot.Site Access of Individual Terminated & Investigation Underway.Personnel Being Hand Searched PNO-IV-86-012, on 860411,turbine Trip Occurred Due to Faulty electro-hydraulic Control (EHC) Card Following Synchronization W/Grid for First Time Since June 1984.EHC Card Repaired & Plant Returned to Grid on 8604121986-04-14014 April 1986 PNO-IV-86-012:on 860411,turbine Trip Occurred Due to Faulty electro-hydraulic Control (EHC) Card Following Synchronization W/Grid for First Time Since June 1984.EHC Card Repaired & Plant Returned to Grid on 860412 PNO-IV-85-010, on 860403,noble Gas Release of 96 Mci Over 1 H Period Occurred.Caused by Helium Circulators & Purification Sys Loss Due to Partial Loss of Offsite Power During Blizzard.Power Restored1986-04-0303 April 1986 PNO-IV-85-010:on 860403,noble Gas Release of 96 Mci Over 1 H Period Occurred.Caused by Helium Circulators & Purification Sys Loss Due to Partial Loss of Offsite Power During Blizzard.Power Restored PNO-IV-85-037A, on 850721,criticality Achieved.Crd Assemblies Refurbished & Bolting in All Four Circulators & Reserve Shutdown Hopper Matl Replaced During Prolonged Shutdown Since 8406231985-07-22022 July 1985 PNO-IV-85-037A:on 850721,criticality Achieved.Crd Assemblies Refurbished & Bolting in All Four Circulators & Reserve Shutdown Hopper Matl Replaced During Prolonged Shutdown Since 840623 PNO-IV-85-037, on 850719,confirmation of Action Ltr Issued Permitting Reactor to Return to Operation at Power Levels Not to Exceed 15% of Rated Power,Pending Resolution of Questions Re Equipment Qualification1985-07-19019 July 1985 PNO-IV-85-037:on 850719,confirmation of Action Ltr Issued Permitting Reactor to Return to Operation at Power Levels Not to Exceed 15% of Rated Power,Pending Resolution of Questions Re Equipment Qualification PNO-IV-84-014A, on 840626,licensee Committed to Maintain Fort St Vrain in Shutdown Condition Until Cause of Failure of Six Rod Pairs to Drop on Reactor Trip Identified,Corrective Measures Taken & NRC Authorizes Return to Operations1984-06-27027 June 1984 PNO-IV-84-014A:on 840626,licensee Committed to Maintain Fort St Vrain in Shutdown Condition Until Cause of Failure of Six Rod Pairs to Drop on Reactor Trip Identified,Corrective Measures Taken & NRC Authorizes Return to Operations PNO-IV-84-014, on 840623,reactor Tripped on High Pressure Signal & 6 of 7 Control Rod Pairs Failed to Drop.Cause Unknown.Drive Mechanisms Will Be Removed for Exam1984-06-25025 June 1984 PNO-IV-84-014:on 840623,reactor Tripped on High Pressure Signal & 6 of 7 Control Rod Pairs Failed to Drop.Cause Unknown.Drive Mechanisms Will Be Removed for Exam PNO-IV-80-010, on 800304,hydraulic Oil Fire Occurred in Turbine Bay.Caused by Hydraulic Oil Leakage from Valve Flange on to Hot Steam Traps.Fire Extinguished Immediately by Security Guard.Platteville Fire Dept Notified1980-03-0505 March 1980 PNO-IV-80-010:on 800304,hydraulic Oil Fire Occurred in Turbine Bay.Caused by Hydraulic Oil Leakage from Valve Flange on to Hot Steam Traps.Fire Extinguished Immediately by Security Guard.Platteville Fire Dept Notified PNO-IV-80-009, on 800228,State of Co Will Conduct Emergency Response Exercise to Test State & Local Emergency Plans. Members of Interagency Regional Advisory Committee & Region 4 Will Observe & Critique Exercise1980-02-25025 February 1980 PNO-IV-80-009:on 800228,State of Co Will Conduct Emergency Response Exercise to Test State & Local Emergency Plans. Members of Interagency Regional Advisory Committee & Region 4 Will Observe & Critique Exercise ML20213C9261979-04-13013 April 1979 Correction to PNO-79-67T.Radiation Activity for Soil & Vegetation Samples on Page 2 Corrected ML20217A3311978-12-0101 December 1978 PNO-78-200:on 781129,plant Encountered Helium Circulator Auxiliary,Buffer-Mid-Buffer Mismatch.Cause by Opening of Low Pressure Separator Safety Relief Valve Which Released Quantity of Reactor Coolant ML20249A7461978-04-26026 April 1978 PNS-78-018:on 780429-0501,according to Media Accounts & Other Info Received by Nrc,Antinuclear Demonstrations May Occur at Fort St Vrain in Colorado.Protestors Intend to Plant Spiderwort Flowers Adjacent to Nuclear Site ML20248J8841978-03-29029 March 1978 PNO-78-067:on 780123,util Authorized to Operate Fort St Vrain Station at Power Levels Up to 70% of Design Rating ML20248L0671978-02-0909 February 1978 PNO-78-026,util Public Svc Co of Co Authorized by NRC to Operate Fort St Vrain Plant Up to Power Level of 2% of Rated Power to Dry Reactor Core & Stabilize Primary System Chemistry ML20249A0821978-01-24024 January 1978 PNO-78-011A:on 780123,NRC Inspectors Verified Total Radioactivity Release to Environs Was Approx 4 Curies, Primarily Consisting of Noble Gases.Plant Remains in Normal Shutdown Condition ML20249A0891978-01-23023 January 1978 PNO-78-011:on 780123,release of Gaseous Radioactive Matl Offsite from Ft St Vrain NPP Near Platteville,Co.Cause of Release Reported to Be Failure of Buffer Seal in Helium Circulation Sys ML20207G4051977-12-12012 December 1977 PNO-77-215:on 771130,St Vrain Facility Shutdown Due to High Moisture in Primary Sys.Evaluations Prior to Shutdown, Indicated Leakage Associated with Loop 1 of Primary Sys. Steam Generator Leak Suspected ML20249A8701977-04-20020 April 1977 PNS-77-018:on 770419,Region IV Insp & Enforcement Inspector Gained Entry Into Reactor Bldg W/O Security Challenge & Contrary to Facility Existing Security Program.Licensee Does Not Plan to Issue Press Release ML20249B4921976-07-0202 July 1976 PNO-76-109:on 760701,Fort St Vrain Facility Was Taken Critical.Facility Had Been in Shutdown Condition Since May 1975 for Corrective Actions for Electrical Cable Routing Deficiencies ML20236V3591975-08-28028 August 1975 PN-75-077:on 750826,intentional Unauthorized Interchange of Electrical Cables Was Identified.Recorder Inputs for Ph/ Conductivity for SG Feedwater Was Found Reversed 1989-08-29 Category:TEXT-INSPECTION & AUDIT & I&E CIRCULARS MONTHYEARIR 05000267/19970011997-04-0707 April 1997
[Table view]Insp Rept 50-267/97-01 on 970310-11.No Violations Noted. Major Areas Inspected:Reviews of Status of Radiation Protection,Environ Monitoring & Radwaste Mgt Programs IR 05000267/19960051996-12-23023 December 1996 Insp Rept 50-267/96-05 on 961203-05.No Violations Noted. Major Areas Inspected:Access Licensees Implementation of Radiation Protection Program & Decommissioning Plan & Included Reviews of Status of Radiation Protection IR 05000267/19940031996-04-0202 April 1996 Revised NOV from Insp Rept 50-267/94-03.Violation Noted: Contractor to Licensee Submitted Inaccurate Radiation Surveys ML20136B3051996-04-0202 April 1996 Revised NOV from Insp Rept 50-267/94-03.Violation Noted: Numerous Required Records of Radiation Surveys Were Created Which Were Not Complete & Accurate ML20137H1731995-08-17017 August 1995 Investigation Rept 4-95-015.Noncompliance Noted.Major Areas Investigated:Alleged Deliberate Failure of Contract Employee to Perform Daily Response Checks on Portable Contamination Monitor ML20137K0551995-05-26026 May 1995 Investigation Rept 4-94-010 on 950526.No Noncompliance Noted.Major Areas Investigated:Allegations Re Falsification of Radiation Survey Records ML20058P5931993-10-12012 October 1993 EN-93-101:on 931012,notice of Proposed Imposition of Civil Penalty in Amount of $80,000 Issued to Licensee.Action Discussed in SECY-93-263 & Approved by Commission on 931007 ML20062H8191990-11-29029 November 1990 Notice of Violation from Insp on 901022-26.Violation Noted: Test of Protected Area Intrusion Detection Zones Defeated by Testing Personnel Jumping Over Zone IR 05000267/19900171990-11-29029 November 1990 Insp Rept 50-267/90-17 on 901001-1109.No Violations or Deviations Noted.Major Areas Inspected:Operational Safety, Monthly Surveillance & Maint Observation IR 05000267/19900181990-11-20020 November 1990 Partially Withheld Insp Rept 50-267/90-18 on 901022-26. Violation Noted.Major Areas Inspected:Physical Security Program,Including Protected & Vital Area Barriers,Detection & Assessment Aidscommunications,Testing,Packages & Maint IR 05000267/19900191990-11-16016 November 1990 Insp Rept 50-267/90-19 on 901015-19.No Violations or Deviations Noted.Areas Inspected:Stated Radiological Controls IR 05000267/19900201990-11-14014 November 1990 Insp Rept 50-267/90-20 on 901029-1102.Noncitable Violation Noted.Major Areas Inspected:Insp of Fire Protection/ Prevention Program ML20058E4951990-10-30030 October 1990 Notice of Violation from Insp on 900928.Violation Noted: Licensee Did Not Perform Radiation & Airborne Surveys Before Allowing Special Svcs Licensed Operator to Enter Hot Svc Facility to Remove Five Unshielded Radioactive Samples IR 05000267/19900141990-10-11011 October 1990 Insp Rept 50-267/90-14 on 900801-0930.No Violations or Deviations Noted IR 05000267/19900111990-08-15015 August 1990 Insp Rept 50-267/90-11 on 900601-0728.No Violations Noted. Major Areas Inspected:Onsite Followup of Ler,Operational Safety Verification,Monthly Maint Observation & Monthly Surveillance Observation IR 05000267/19900131990-08-0303 August 1990 Insp Rept 50-267/90-13 on 900709-13.No Violations or Deviations Noted.Major Areas Inspected:Emergency Preparedness Program Including Emergency Detection & Classification,Knowledge & Performance of Duties IR 05000267/19900101990-07-25025 July 1990 Insp Rept 50-267/90-10 on 900611-15.No Violations or Deviations Noted.Major Areas Inspected:Radioactive Matl Transportation Program,Liquid & Gaseous Radwaste Mgt Programs,Including Radiological Effluent Releases IR 05000267/19890191989-10-0202 October 1989 Insp Rept 50-267/89-19 on 890821-26 & 29-30.No Violations or Deviations Noted.Major Areas Inspected:Region 19 CRD Assembly Recovery Activities,Followup on Region 19 CRD Clevis Bolt Failures & Steam Generator Ring Header Problems ML20248B3051989-09-26026 September 1989 Notice of Violation from Insp on 890716-0831.Violation Noted:Four Reactor Engineers Worked on safety-related Test of Reactor Core Beyond Tech Specs Limit W/O Documented Authorization IR 05000267/19890161989-09-26026 September 1989 Insp Rept 50-267/89-16 on 890716-0831.Violation Noted.Major Areas Inspected:Onsite Followup of Ler,Followup on Violations,Followup of Open Item,Review of Part 21 Repts & Review of Licensee Action of Events PNO-IV-89-055, on 890829,Board of Directors Directed Termination of Nuclear Operations at Facility for 100-day Cooldown Period in Preparation for 30-month Reactor Defueling.Nrc Currently Reviewing Defueling Safety Analysis1989-08-29029 August 1989 PNO-IV-89-055:on 890829,Board of Directors Directed Termination of Nuclear Operations at Facility for 100-day Cooldown Period in Preparation for 30-month Reactor Defueling.Nrc Currently Reviewing Defueling Safety Analysis PNO-IV-89-052C, updates 890818,21 & 23 Unplanned Reactor Shutdowns Due to Inoperable Control Rod.Control Rod Assembly Will Be Removed Using Bldg Crane.Aluminum Shutter Will Be Remotely Placed on Bottom of Canister1989-08-25025 August 1989 PNO-IV-89-052C:updates 890818,21 & 23 Unplanned Reactor Shutdowns Due to Inoperable Control Rod.Control Rod Assembly Will Be Removed Using Bldg Crane.Aluminum Shutter Will Be Remotely Placed on Bottom of Canister PNO-IV-89-052B, on 890823,unplanned Reactor Shutdown Due to Inoperable Control Rod.Licensee Plans to Remove Control Rod Pair W/Bldg Crane in Unshielded Configuration to Shielded, Contained Evolution1989-08-23023 August 1989 PNO-IV-89-052B:on 890823,unplanned Reactor Shutdown Due to Inoperable Control Rod.Licensee Plans to Remove Control Rod Pair W/Bldg Crane in Unshielded Configuration to Shielded, Contained Evolution PNO-IV-89-052A, on 890818,after Attempting to Withdraw & Insert Control Rod Pair from Region 19,control Rod Motor Stopped Drawing Current & Indicated Open Conductor or Thermal Overload.Pair Will Be Withdrawn Using Bldg Crane1989-08-21021 August 1989 PNO-IV-89-052A:on 890818,after Attempting to Withdraw & Insert Control Rod Pair from Region 19,control Rod Motor Stopped Drawing Current & Indicated Open Conductor or Thermal Overload.Pair Will Be Withdrawn Using Bldg Crane ML20246E6011989-08-21021 August 1989 Notice of Violation from Insp on 890710-14.Violation Noted:From 890101-0712,only Three of Seven Shipments of Nonexempt Radioactive Matls Had Current License on File PNO-IV-89-052, on 890817,unplanned Reactor Shutdown Due to Inoperable Control Rod Drive Occurred.Attempts to Clear Cause of Slack Cable Light Failed.Loop 2 Shutdown Due to Upset in Bearing Water Sys Occurred During Plant Shutdown1989-08-18018 August 1989 PNO-IV-89-052:on 890817,unplanned Reactor Shutdown Due to Inoperable Control Rod Drive Occurred.Attempts to Clear Cause of Slack Cable Light Failed.Loop 2 Shutdown Due to Upset in Bearing Water Sys Occurred During Plant Shutdown IR 05000267/19890131989-08-16016 August 1989 Insp Rept 50-267/89-13 on 890626-30.Violation Noted.No Deviations Noted.Major Areas Inspected:Radwaste Sys IR 05000267/19890141989-08-15015 August 1989 Insp Rept 50-267/89-14 on 890710-14.Violation Noted.Major Areas Inspected:Radiation Protection Program ML20245J5721989-08-10010 August 1989 Notice of Violation from Insp on 890717-21.Violation Noted: Procedures Covering Timely Testing of Reactor Protection Sys Startup Channel & Periodic Test & Calibr of Diesel Engine Overspeed Trip for diesel-driven Fire Pump Not Established ML20245J5791989-08-10010 August 1989 Insp Rept 50-267/89-17 on 890717-21.Violations Noted.Major Areas Inspected:Licensee Programs for Instrument Calibr & Functional Testing of Diesel Fuel Oil Quality & Storage & Actions on Previously Identified Insp Findings ML20246A7061989-08-0909 August 1989 Exam Rept 50-267/OL 89-02 During Wk of 890710.Exam Results: Three of Four Limited Senior Reactor Operator Applicants Passed Exam.Answer Key Encl ML20245H3971989-08-0808 August 1989 Insp Rept 50-267/89-12 on 890601-0715.Violation Noted.Major Areas Inspected:Onsite Followup of Lers,Operational Safety Verification & Monthly Surveillance & Maint Observations ML20245H3941989-08-0808 August 1989 Notice of Violation from Insp on 890628.Violation Noted:On 890625,util Failed to Verify Positioning of HS-6335 to Tank 1 B,Resulting in Unanalyzed Gaseous Waste Release ML20248E0101989-08-0303 August 1989 Notice of Violation from Insp on 880522-26.Violations Noted: Inadequate Testing of cross-connect Valves Per Tech Spec SR 5.3.4 & Failure to Test High Flow Alarms Per Tech Spec SR 5.4.5 ML20248E0261989-08-0101 August 1989 Team Insp Rept 50-267/89-08 on 890522-26.Violations Noted. Major Areas Inspected:Maint Activities Re Reactor Water Cooling Sys (Sys 46) ML20247L6141989-07-14014 July 1989 Notice of Violation from Insp on 890623-27.Violation Noted: Failure to Provide Adequate Administrative Control of Plant Changes That Affect safety-related Plant Procedures IR 05000267/19890151989-07-11011 July 1989 Insp Rept 50-267/89-15 on 890623-27.Violation Noted.Major Areas Inspected:Circumstances & Events Associated W/ Operation of Facility Above Authorized Max Power Level of 82% of Full Power PNO-IV-89-044, on 890628,pressure in Waste Gas Receiver a Decreased from 250 Psig & Pressure in Receiver a Decreased from 60 to 50 Psig.Caused by Erroneous Valve Lineup.Plant Stack Monitors Did Not Alarm1989-06-28028 June 1989 PNO-IV-89-044:on 890628,pressure in Waste Gas Receiver a Decreased from 250 Psig & Pressure in Receiver a Decreased from 60 to 50 Psig.Caused by Erroneous Valve Lineup.Plant Stack Monitors Did Not Alarm PNO-IV-89-040, from 890622-23,power Exceeded 82% & Secondary Heat Balance Indication in Control Room Read Approx 79.2%.On 890623,discovered Incorrect Input Into Secondary Heat Balance Calculation.Power Reduced to 65% Pending Evaluation1989-06-23023 June 1989 PNO-IV-89-040:from 890622-23,power Exceeded 82% & Secondary Heat Balance Indication in Control Room Read Approx 79.2%.On 890623,discovered Incorrect Input Into Secondary Heat Balance Calculation.Power Reduced to 65% Pending Evaluation ML20245G4781989-06-22022 June 1989 Exam Rept 50-267/OL-9-01 on 890523-25.Exam Results:Two Senior Reactor Operator & Three Reactor Operator Candidates Passed All Portions of Exams & Issued Appropriate Licenses. One Reactor Operator Failed Written Exam IR 05000267/19890101989-06-15015 June 1989 Insp Rept 50-267/89-10 on 890501-31.No Violations Noted. Major Areas inspected:follow-up of Ler,Licensee Action on Previously Identified Insp Findings,Operational Safety Verification & Monthly Surveillance Observation ML20244C1271989-06-0808 June 1989 Notice of Violation from Insp on 890324-0430.Violations Noted:Two Examples of Failing to Comply W/Tech Spec Requirements & Inadequate Control of Replacement Parts for safety-related Equipment ML20244C1301989-06-0101 June 1989 Insp Rept 50-267/89-07 on 890319-0430.Violations Noted.Major Areas Inspected:Previously Identified Insp Findings, Operational Safety Verification,Monthly Surveillance Observation & Monthly Maint Observation PNO-IV-89-036, on 890529,two Teenagers Shot by off-duty Security Guard Following Confrontation Re Assault.Guard Arrested & Being Held for Murder.Licensee Plans to Issue Press Release.State of Co Will Be Informed.Record Copy1989-05-30030 May 1989 PNO-IV-89-036:on 890529,two Teenagers Shot by off-duty Security Guard Following Confrontation Re Assault.Guard Arrested & Being Held for Murder.Licensee Plans to Issue Press Release.State of Co Will Be Informed.Record Copy PNO-IV-89-031, on 890427,CRD 3 Failed to Insert on Scram During Performance of Weekly Partial Insertion Scram Tests. Troubleshooting Confirmed That CRD Brake Deenergized & That Rod Out Limit Cleared.Licensee Plans to Replace CRDs 3 & 71989-04-28028 April 1989 PNO-IV-89-031:on 890427,CRD 3 Failed to Insert on Scram During Performance of Weekly Partial Insertion Scram Tests. Troubleshooting Confirmed That CRD Brake Deenergized & That Rod Out Limit Cleared.Licensee Plans to Replace CRDs 3 & 7 IR 05000267/19890061989-04-24024 April 1989 Partially Withheld Insp Rept 50-267/89-06 on 890313-17 (Ref 10CFR73.21).Violation Noted.Major Areas Inspected:Physical Security Program,Including Mgt Support & Security Program Plan & Protected & Vital Area Barriers ML20245C8311989-04-14014 April 1989 Notice of Violation from Insp on 890217.Violation Noted: Stairway of Reactor Bldg Utilized by Potentially Contaminated Individuals Prior to Performing Whole Body Frisk & by Individuals Exiting Area After Frisking ML20245C8341989-04-13013 April 1989 Insp Rept 50-267/89-03 on 890201-0318.Violations Noted. Major Areas Inspected:Lers,Reserve Shutdown Matl Removal, Operational Safety Verification,Radiological Controls, Monthly Surveillance Observation & Maint Observation IR 05000267/19890051989-04-12012 April 1989 Insp Rept 50-267/89-05 on 890306-10 & 13-17.No Violations Noted.Major Areas Inspected:Previously Identified Insp Items,Surveillance Procedures & Records,Allegation Followup & Preparations for Refueling IR 05000267/19870351989-04-0707 April 1989 Final SALP Rept 50-267/87-35 for May 1987 - Aug 1988. Category 1 Assigned in Areas of Maint,Fire Protection & Radiological Controls 1997-04-07 |
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t PRELIMINARY
. ._ m _ NDTIFICATION Or EVENT OR UNUSUAL OCCURRENCE -- PNO-IV-44-14
, C OF] ,
This preliminary" notification constitutes EARLY notice of events of P05518LE t
safety or public interest significance. The information is as initially received without verification or ovaluation, and is basically all thalis known by MRC staff on this date. !
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FACILITY: Public Sert *1ce Company of Licensee Eme mency Class icatf4;n: . '
- Colorado .
,,,,_, Motification of
- c r. - '
1 EvRit Fort St. Vrain Nuclear Fower . ,,,,,,_ Al ert i
~
Stetton '
,,,_ Site Area Emergency @
Platteville, Colorado g i
, Docket 50-267 General Emergency X Not Applicable I o 3 . 5
SUBJECT:
- FAILUAE OF CONTNOL 2005 70 IMEERT -
S 3
During 'the efternoon and evening of June 22, 1984, the reactor was being shutdown in a controlled menner because of a problem with high moisture in the f f.el ius ' coolant. Secause of moisture freeze-up in the operating train of the helium purification system 1st-down of helium via that system was temperectly i
halted while normal helium purge ficw into the reactor vessel continued. At about 12:30 a.m. OCT) June 23, 1964, the reactor tripped on a high pressure signal resulting from a combination of increased heliue inventory and '
Programming down of the high pressure trip point as reactor power was reduced .- ,- , -
The lice' nsee reported this reactor trip to the headquarters duty officer et 1:07 a.m. (MDT).
At abb 9:02 a.m. (MDT) on June 23, the licensee-informed the duty officer that, h$sen the reertor trip occurred, 6 out of the 37 control rod pairs had failed to drop. It was reported that the shif t supervisor, after verifying adequate shutdown margin through power recorder traces, and in accordance with procedures, p911ed fuses to the drive mechanisms but the rod pairs failed te drop. He then replaced the fuses and successfully lowered all 6 rod pairs to I their full-in position by running the drive motors (drum and cable drives). ;
All rods were inserted within 20 minutes of the reactor trip.
The liconeee made an oral coomitment on June 23 to stay shutdown at least 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />' while evaluation proceeds. The cause of failure is nog kr.own.
- The licensee the hot: service now plans to remove one or more drive mechanisms pr diinmination in facility, d t n en <_ a ,
l T5e Commissioner's technical assistants who were ava14bidiWerefbriefed at 12:0
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p.a. OCT) . ,~..hyo telernn
..... t.n June 23. Neither the r{icoge je the NRC plan )(t'/
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