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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20205G8771999-03-26026 March 1999 Forwards Copy of Cover Page from Fort St-Vrain Welding Manual,Which Had Been Listed as Encl on Page 4 of 990325 Reply to EA 98-081.Cover Page Had Been Inadvertently Left Out with Original Reply ML20197H8811998-12-0101 December 1998 Forwards Proposed Change to Fsv ISFSI Physical Protection Plan in Which Commitment Is Made to Provide Feature to Security Posture for Facility ML20236R9191998-07-20020 July 1998 Ltr Contract:Mod 4 to Task Order 27, Task Area No 4 of Basic Contract - Fort St Vrain Insp Under Contract NRC-02-95-003 ML20199H8141997-11-21021 November 1997 Responds to Requesting Clarification as to Whether Increase in Tritium & Iron-55 Contamination Limits That Were Approved for Plant Apply to All Licensees ML20198K1931997-10-10010 October 1997 Provides Supplemental Info in Support of Util Proposed Rev to Physical Security Plan for Plant Plant Isfsi.Plan Withheld,Per 10CFR2.790(d) & 10CFR73.21 ML20198H5601997-09-16016 September 1997 Final Response to FOIA Request for Documents.Documents Listed in App a Being Released in Entirety ML20141F3521997-05-14014 May 1997 Forwards Proposed Issue 4 of Physical Security Plan for Fort St Vrain ISFSI for Review & Approval.Encl Withheld,Per 10CFR2.790(d) ML20141C8611997-05-0909 May 1997 Informs of Approval of Fsv Final Survey Rept & Effluent Pathway Survey Plan & Supporting Analysis ML20141K9881997-05-0505 May 1997 Forwards Amend 89 to License DPR-34 & Supporting Safety Evaluation.Amend Designates All Elements of Approved Decommissioning Plan as License Termination Plan ML20138G2701997-04-28028 April 1997 Provides Response to NRC Comments Re Proposed Sampling & Survey Plan for Fsv Effluent Pathway.Response Documents Fsv Liquid Effluent Discharge Pathway Areas Are Acceptable for Release for Unrestricted Use IAW Draft NUREG/CR-5849 ML20148D4651997-04-24024 April 1997 Forwards Revised Interim Ltr Rept Which Describes Procedures & Results of Confirmatory Survey of Group E Effluent Discharge Pathway Areas at Fsv Station ML20138B0511997-04-22022 April 1997 Forwards Copy of Proposed Amend to Fsv NPDES Permit, Wastewater Discharge Permit CO-0001121 Requested to Support Repowering Activities,Iaw Section 3.2.d of Fsv Non-Radiological Ts,App B to License DPR-34 ML20140E1061997-04-10010 April 1997 Forwards Confirmatory Survey of Group Effluent Discharge Pathway Areas for Fsv Nuclear Station,Platteville,Co ML20137S4481997-04-0808 April 1997 Informs That Decommissioning Activities at Fsv Are Complete & NRC Issued Exemption from Requirements of 10CFR50.54(w) in .Property Damage Insurance Policy Is Maintaned to Protect Fsv balance-of-plant Assets ML20137S0821997-04-0707 April 1997 Forwards Insp Rept 50-267/97-01 on 970310-11.No Violations Noted ML20137S1691997-04-0707 April 1997 Fifth Partial Response to FOIA Request for Documents. Forwards Documents Listed in App K ML20137S5421997-04-0707 April 1997 Forwards Final Quarterly 10CFR50.59 Rept of Changes,Tests & Experiments Affecting Decommissioning of Fort St Vrain Nuclear Station ML20137R6921997-04-0404 April 1997 Informs of Approval for Request for Addl 45 Days to Remedy Deficiencies Identified in NRC Re Financial Assurance Mechanism for Fsv Decommissioning Costs ML20148D5951997-04-0404 April 1997 Forwards Confirmatory Survey for Fsv Nuclear Station, Psc,Platteville,Co, Final Rept ML20137J8051997-03-31031 March 1997 Third Partial Response to FOIA Request for Documents.Records in App F Encl & Will Be Available in Pdr.App G & H Records Withheld in Part (Ref FOIA Exemptions 5 & 7) ML20148D5811997-03-26026 March 1997 Forwards Confirmatory Survey Plan for Group E Effluent Discharge Pathway Areas at Fsv Nuclear Station, Covered in Final Survey Rept,Vol 6 ML20137G7361997-03-25025 March 1997 Requests Addl Time for Util to Respond to NRC Comments in Re Financial Assurance Mechanism for Fort St Vrain Decommissioning Costs ML20137G9521997-03-24024 March 1997 Forwards Quarterly 10CFR50.59 Rept for Period 961201-970228 Re Changes,Tests & Experiments for Fort St Vrain Decommissioning ML20137H1131997-03-24024 March 1997 Second Partial Response to FOIA Request for Documents. Forwards Documents Listed in App D.Documents Also Available in Pdr.Documents Listed in App E Withheld in Part (Ref FOIA Exemption 6) ML20137C0061997-03-18018 March 1997 Documents That There Have Been No Activities Involving Release of Radioactive Matls from Fsv Nuclear Station That Potentially Could Have Affected Environ,Subsequent to Previous Radiological Envion Operating Rept ML20137C0181997-03-18018 March 1997 Documents That No Personnel Has Received Radiation Exposure at Fsv in 1997 or at Any Time Subsequent to ML20136G1201997-03-11011 March 1997 Forwards Annual Radioactive Effluent Release Rept for Jan- Dec 1996 & Jan-Mar 1997. All Effluent Releases Completed as of 960703.Repts on Activities After 960703 Reflect Disposal of Solid Waste ML20136B1331997-02-28028 February 1997 First Partial Response to FOIA Request for Documents. Documents Listed in App a Already Available in Pdr.Forwards App B Documents.App C Documents Being Withheld in Entirety (Ref FOIA Exemption 5) ML20135D7891997-02-27027 February 1997 Forwards Responses to Comments Re Fort St Vrain Final Survey Rept ML20135D9531997-02-27027 February 1997 Forwards Copy of Amend to Util Npdes,Wastewater Discharge Permit CO-0001121,which Clarifies That Monitoring of Farm Pond Outlet Required When Industrial Wastewater Being Discharged Through Upstream Goosequill Ditch ML20135A8711997-02-14014 February 1997 Requests That Encl Deficiencies Identified in Financial Assurance Mechanism for Fort St Vrain Decommissioning Cost Be Addressed within 45 Days ML20134D1551997-01-31031 January 1997 Forwards Util Responses to NRC Comments Provided in NRC Ltr Re Sampling & Survey Plan Used for Final Radiological Survey of Liquid Effluent Pathway at Ft St Vrain ML20134C8481997-01-30030 January 1997 Forwards Draft Confirmatory Survey Rept for Fsv Nuclear Station,Psc,Platteville,Co Providing Info on Essap Activities on 960930-1003 ML20133L4961997-01-0707 January 1997 Forwards Comments That Need to Be Resolved Before Final Approval of Util Submittal Entitled, Proposed Sampling & Survey Plan for Effluent Pathway,Ft St Vrain Final Survey Program ML20133E0481997-01-0202 January 1997 Forwards Comments to Fsv Nuclear Station, Decommissioning Project Final Survey Rept (Volumes 4-11), for Consideration ML20132G0421996-12-23023 December 1996 Forwards Insp Rept 50-267/96-05 on 961203-05.No Violations Noted ML20132F2841996-12-19019 December 1996 Forwards Quarterly 10CFR50.59 Rept of Changes,Tests & Experiments Affecting Decommissioning of Plant,Covering Period of 960901-1130 ML20133A8591996-12-16016 December 1996 Forwards Original & Copy Transcripts of Public Hearing,Held on 961203 in Platteville,Co Re Decommissioning & License Termination of Util Ft Saint Vrain Nuclear Generating Station ML20133N0011996-12-0404 December 1996 Recommends That NRC Require License to Modify Submission of Unexecuted Draft Trust Agreement Remaining Decommissioning Costs for Ft St Vrain Nuclear Generating Station in Listed Ways ML20135A5861996-11-25025 November 1996 Submits Suppl Info Re Annual Environ Rept for 1995 Operation of Fsv ISFSI ML20135B3861996-11-25025 November 1996 Informs That NRC Reviewed Util 961114 Submittal (P-96096) Entitled, Fort St Vrain Final Emergency Response Plan, & Meets Requirements of 10CFR50.54(q) ML20135A6361996-11-20020 November 1996 Submits Copy of Describing Discharge Practices for Groundwater Seeping Into Fsvs Reactor Building Sump ML20134L4721996-11-14014 November 1996 Notifies NRC That Util Adopted Fsv ISFSI Emergency Response Plan to Direct Emergency Response for Radiological Accidents Occuring at Site,Until 10CFR50 License Is Terminated ML20134G5991996-10-30030 October 1996 Forwards Volumes 1-12 to Final Survey Rept for Groups A,B,C Rev 1,D Rev 1,E,F Rev 1 & G-J for NRC Approval in Support of Forthcoming Request for Termination of Fsv 10CFR50 License ML20134F4351996-10-30030 October 1996 Forwards Sections 1,2,6 & 8 from Survey Packages F0015, F0039 & F0126 & Sections 1,2 & 6 from Survey Package F0115 to Support on-site NRC Insp ML20133D7691996-10-22022 October 1996 Forwards Preliminary Rept Re Orise Support of NRC License Insp at Fsv on 960930-1003 ML20136B1411996-10-15015 October 1996 FOIA Request for Documents Re NOV Addressed to Scientific Ecology Group Re NRC Insp Rept 50-267/94-03 & OI Investigation Repts 4-94-010 & 4-95-015 ML20128M6181996-10-0404 October 1996 Forwards Ltr from PSC to Co Dept of Public Health & Environ Describing Monitoring Practices at Plant ML20128G8041996-10-0101 October 1996 Forwards Fsv Decommissioning Fire Protection Plan Update ML20128G0481996-09-30030 September 1996 Submits Rev to Psco Definitions of Contents of Documentation Packages Re Fsv Final Survey Project 1999-03-26
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20205G8771999-03-26026 March 1999 Forwards Copy of Cover Page from Fort St-Vrain Welding Manual,Which Had Been Listed as Encl on Page 4 of 990325 Reply to EA 98-081.Cover Page Had Been Inadvertently Left Out with Original Reply ML20197H8811998-12-0101 December 1998 Forwards Proposed Change to Fsv ISFSI Physical Protection Plan in Which Commitment Is Made to Provide Feature to Security Posture for Facility ML20198K1931997-10-10010 October 1997 Provides Supplemental Info in Support of Util Proposed Rev to Physical Security Plan for Plant Plant Isfsi.Plan Withheld,Per 10CFR2.790(d) & 10CFR73.21 ML20141F3521997-05-14014 May 1997 Forwards Proposed Issue 4 of Physical Security Plan for Fort St Vrain ISFSI for Review & Approval.Encl Withheld,Per 10CFR2.790(d) ML20138G2701997-04-28028 April 1997 Provides Response to NRC Comments Re Proposed Sampling & Survey Plan for Fsv Effluent Pathway.Response Documents Fsv Liquid Effluent Discharge Pathway Areas Are Acceptable for Release for Unrestricted Use IAW Draft NUREG/CR-5849 ML20148D4651997-04-24024 April 1997 Forwards Revised Interim Ltr Rept Which Describes Procedures & Results of Confirmatory Survey of Group E Effluent Discharge Pathway Areas at Fsv Station ML20138B0511997-04-22022 April 1997 Forwards Copy of Proposed Amend to Fsv NPDES Permit, Wastewater Discharge Permit CO-0001121 Requested to Support Repowering Activities,Iaw Section 3.2.d of Fsv Non-Radiological Ts,App B to License DPR-34 ML20140E1061997-04-10010 April 1997 Forwards Confirmatory Survey of Group Effluent Discharge Pathway Areas for Fsv Nuclear Station,Platteville,Co ML20137S4481997-04-0808 April 1997 Informs That Decommissioning Activities at Fsv Are Complete & NRC Issued Exemption from Requirements of 10CFR50.54(w) in .Property Damage Insurance Policy Is Maintaned to Protect Fsv balance-of-plant Assets ML20137S5421997-04-0707 April 1997 Forwards Final Quarterly 10CFR50.59 Rept of Changes,Tests & Experiments Affecting Decommissioning of Fort St Vrain Nuclear Station ML20148D5951997-04-0404 April 1997 Forwards Confirmatory Survey for Fsv Nuclear Station, Psc,Platteville,Co, Final Rept ML20148D5811997-03-26026 March 1997 Forwards Confirmatory Survey Plan for Group E Effluent Discharge Pathway Areas at Fsv Nuclear Station, Covered in Final Survey Rept,Vol 6 ML20137G7361997-03-25025 March 1997 Requests Addl Time for Util to Respond to NRC Comments in Re Financial Assurance Mechanism for Fort St Vrain Decommissioning Costs ML20137G9521997-03-24024 March 1997 Forwards Quarterly 10CFR50.59 Rept for Period 961201-970228 Re Changes,Tests & Experiments for Fort St Vrain Decommissioning ML20137C0061997-03-18018 March 1997 Documents That There Have Been No Activities Involving Release of Radioactive Matls from Fsv Nuclear Station That Potentially Could Have Affected Environ,Subsequent to Previous Radiological Envion Operating Rept ML20137C0181997-03-18018 March 1997 Documents That No Personnel Has Received Radiation Exposure at Fsv in 1997 or at Any Time Subsequent to ML20136G1201997-03-11011 March 1997 Forwards Annual Radioactive Effluent Release Rept for Jan- Dec 1996 & Jan-Mar 1997. All Effluent Releases Completed as of 960703.Repts on Activities After 960703 Reflect Disposal of Solid Waste ML20135D9531997-02-27027 February 1997 Forwards Copy of Amend to Util Npdes,Wastewater Discharge Permit CO-0001121,which Clarifies That Monitoring of Farm Pond Outlet Required When Industrial Wastewater Being Discharged Through Upstream Goosequill Ditch ML20135D7891997-02-27027 February 1997 Forwards Responses to Comments Re Fort St Vrain Final Survey Rept ML20134D1551997-01-31031 January 1997 Forwards Util Responses to NRC Comments Provided in NRC Ltr Re Sampling & Survey Plan Used for Final Radiological Survey of Liquid Effluent Pathway at Ft St Vrain ML20134C8481997-01-30030 January 1997 Forwards Draft Confirmatory Survey Rept for Fsv Nuclear Station,Psc,Platteville,Co Providing Info on Essap Activities on 960930-1003 ML20133E0481997-01-0202 January 1997 Forwards Comments to Fsv Nuclear Station, Decommissioning Project Final Survey Rept (Volumes 4-11), for Consideration ML20132F2841996-12-19019 December 1996 Forwards Quarterly 10CFR50.59 Rept of Changes,Tests & Experiments Affecting Decommissioning of Plant,Covering Period of 960901-1130 ML20133A8591996-12-16016 December 1996 Forwards Original & Copy Transcripts of Public Hearing,Held on 961203 in Platteville,Co Re Decommissioning & License Termination of Util Ft Saint Vrain Nuclear Generating Station ML20133N0011996-12-0404 December 1996 Recommends That NRC Require License to Modify Submission of Unexecuted Draft Trust Agreement Remaining Decommissioning Costs for Ft St Vrain Nuclear Generating Station in Listed Ways ML20135A5861996-11-25025 November 1996 Submits Suppl Info Re Annual Environ Rept for 1995 Operation of Fsv ISFSI ML20135A6361996-11-20020 November 1996 Submits Copy of Describing Discharge Practices for Groundwater Seeping Into Fsvs Reactor Building Sump ML20134L4721996-11-14014 November 1996 Notifies NRC That Util Adopted Fsv ISFSI Emergency Response Plan to Direct Emergency Response for Radiological Accidents Occuring at Site,Until 10CFR50 License Is Terminated ML20134G5991996-10-30030 October 1996 Forwards Volumes 1-12 to Final Survey Rept for Groups A,B,C Rev 1,D Rev 1,E,F Rev 1 & G-J for NRC Approval in Support of Forthcoming Request for Termination of Fsv 10CFR50 License ML20134F4351996-10-30030 October 1996 Forwards Sections 1,2,6 & 8 from Survey Packages F0015, F0039 & F0126 & Sections 1,2 & 6 from Survey Package F0115 to Support on-site NRC Insp ML20133D7691996-10-22022 October 1996 Forwards Preliminary Rept Re Orise Support of NRC License Insp at Fsv on 960930-1003 ML20136B1411996-10-15015 October 1996 FOIA Request for Documents Re NOV Addressed to Scientific Ecology Group Re NRC Insp Rept 50-267/94-03 & OI Investigation Repts 4-94-010 & 4-95-015 ML20128M6181996-10-0404 October 1996 Forwards Ltr from PSC to Co Dept of Public Health & Environ Describing Monitoring Practices at Plant ML20128G8041996-10-0101 October 1996 Forwards Fsv Decommissioning Fire Protection Plan Update ML20128G0481996-09-30030 September 1996 Submits Rev to Psco Definitions of Contents of Documentation Packages Re Fsv Final Survey Project ML20129C0421996-09-20020 September 1996 Forwards Quarterly Submittal of 10CFR50.59 Rept of Changes, Tests & Experiments for Facility Decommissioning,Covering Period of 960601-0831 ML20133D7601996-09-16016 September 1996 Forwards Confirmatory Survey Plan for Fsv Nuclear Station Decommissioning Project,First Final Survey Rept Submittal- Vols 1-5.NRC Comments Incorporated.Spending Plan Attached ML20117P0711996-09-13013 September 1996 Describes Util Plans to Remove Bldg 28 from Plant Facility ML20129A4431996-09-11011 September 1996 Describes Util Plans for Demonstrating That Liquid Effluent Pathway & Surrounding Open Land Areas Satisfy 10 Mrem/Yr Criteria Provided in Plant Final Survey Plan ML20117K5291996-09-0404 September 1996 Provides Notification That Util Will Be Revising Financial Assurance Mechanism That Will Be Used to Cover Remaining Costs of Decommissioning Plant ML20117C7281996-08-22022 August 1996 Discusses Impact of Final Decommissioning Rule & Requests NRC Concurrence That Requirements to Submit & Obtain Approval of License Termination Plan Have Been Satisfied ML20116P3431996-08-16016 August 1996 Describes Actions to Remove Structures & Equipment Items from Fort St Vrain Facility for NRC Info.Requests That NRC Advise Util of Wishes to Perform Confirmatory Survey of Any Parts of New Fuel Storage Building Before 960903 ML20133D7551996-08-14014 August 1996 Provides Environ Survey & Site Assessment Program'S (Essap) Comments Re Review of Fsv Nuclear Station Decommissioning Project Final Survey Rept ML20116M0771996-08-14014 August 1996 Provides Suppl Response to Re Insp Rept 50-267/96-01 in Jan 1996 Re NRC Concerns About Fsv Final Survey Program.Specifically,Bias in Instrumentation Response Overestimating Amount of Contamination Present ML20116M1841996-08-13013 August 1996 Forwards Util Responses to NRC Comments in Re Use of in-situ Gamma Spectroscopy to Measure Exposure Rates During Plant Final Survey.Approval to Use in-situ Gamma Spectroscopic instrument,Microspec-2,requested ML20116K0061996-08-0909 August 1996 Submits Fort St Vrain Nuclear Station Decommissioning Project Final Survey Rept ML20116M1241996-08-0808 August 1996 Responds to NRC Bulletin 96-004, Chemical,Galvanic,Or Other Reactions in Spent Fuel Storage & Transportation. Informs That Modular Vault Dry Storage Sys Is Not Susceptible to Problems Addressed in Bulletin ML20116F8141996-08-0202 August 1996 Informs of Util Intent to Modify Fort St Vrain Control Room,Which Will Make Certain Final Survey Locations Unavailable for Further Review.Final Survey Efforts Are Complete ML20116F3611996-08-0202 August 1996 Submits Revised Documentation for Fort St Vrain Final Survey Program ML20116A4511996-07-19019 July 1996 Requests NRC Approval of Proposed Method to Fsv Final Survey Plan to Determine Exposure Rates in Prestressed Concrete Reactor Vessel 1999-03-26
[Table view] Category:UTILITY TO NRC
MONTHYEARML20059K2091990-09-14014 September 1990 Requests That Dj Trumblee Reactor Operator License Be Terminated,Effective 900912 ML20059L5831990-09-14014 September 1990 Forwards Application for Amend to License DPR-34,changing Tech Spec Design Features Section to Remove CRD & Orifice Assemblies from Core Regions Defueled in Support of Plant Closure Activities ML20059H9471990-09-14014 September 1990 Forwards Rev to Proposed Physical Security Plan,Per .Encl Withheld (Ref 10CFR73.21) ML20064A6841990-09-14014 September 1990 Notifies That Ms Frazier License OP-5608-1 Terminated Effective 900906,per 10CFR50.74 ML20059D3231990-08-15015 August 1990 Forwards fitness-for-duty Performance Data Rept for Plant ML20058N5661990-08-0808 August 1990 Requests Exemption from 10CFR50.54(w)(1) Requirements for Min Property Insurance Coverage ML20058L8031990-08-0303 August 1990 Forwards GA-C18103, Fort St Vrain Cycle 3 Core Performance, Per Request for Addl Info Re Proposed Amend to Tech Spec Which Would Allow Util to Complete Defueling of Facility ML20058M1931990-07-31031 July 1990 Advises of Termination of Kj Einig Reactor Operator License, Effective 900727 ML20056A1791990-07-30030 July 1990 Responds to NRC Re Violations Noted in Insp Rept 50-267/90-07.Corrective Actions:Electrical & Mechanical Craft Personnel Assigned to Planning & Scheduling Organization ML20055H8091990-07-23023 July 1990 Forwards Addl Info in Support of 900622 SAR for Isfsi. Proprietary SAR Withheld (Ref 10CFR2.790) ML20058P6891990-07-20020 July 1990 Forwards Security Plan for Proposed ISFSI for NRC Review,Per 900622 & 0412 Ltrs.Plan Withheld (Ref 10CFR73.21) ML20056A1711990-07-20020 July 1990 Discusses Decommissioning Funding for Plant.Util Revised Decommissioning Financial Plan,Based on Safstor,Currently in Effect & Funds Will Be Accumulated Per Plan Provisions ML20055G7061990-07-20020 July 1990 Forwards Application for Amend to License DPR-34,revising Tech Spec 6.1 to Remove Equipment to Support Plant Closure ML20055G8601990-07-20020 July 1990 Responds to NRC Re Violations Noted in Insp Rept 50-267/90-07.Corrective Actions:Site Mgt Recognized Applicability of 10CFR50.72(b)(2)(vi) Re Previous Day Notification & Immediately Notified NRC ML20055H2811990-07-20020 July 1990 Forwards Rev 4 to Updated Fire Protection Plan ML20055H6571990-07-20020 July 1990 Responds to NRC Bulletin 90-001, Loss of Fill Oil in Transmitters Mfg by Rosemount. No Rosemount Model 1153 or 1154 Transmitters Presently in Use at Plant ML20059D1361990-07-13013 July 1990 Applies for Exemption from Payment of Annual Fees for FY90, Per 10CFR171 ML20055E0401990-07-0303 July 1990 Forwards Issue 3 to FPOR-18, Fire Protection Operability Requirements, as Result of Rev 3 to Facility Fire Protection Plan ML20055E0331990-07-0202 July 1990 Informs of Plans to Remove B Helium Circulator from Plant Prestressed Concrete Reactor Vessel in Mannner Similar to Previous Circulator Maint Outages.Requests Timely Ack of NRC Concurrence W/Undertaking ML20055D3931990-06-29029 June 1990 Forwards Response to Generic Ltr 90-04,requesting Info on Status of Generic Safety Issues.W/O Encl ML20055E9171990-06-29029 June 1990 Resubmits Semiannual Radioactive Effluent Release Rept Jul-Dec 1989, as Result of Omitted Tables ML20044A8281990-06-29029 June 1990 Notifies of Termination of Wj Ashmore,License SOP-43244 & Requests That Reactor Operator License Be Terminated Effective 900620,per 10CFR50.74 ML20055D1591990-06-22022 June 1990 Forwards Proposed Change to Updated Fsar,App B Re Use of Controls Other than Change Notice Sys to Implement Mods Such as Cutting & Capping of Piping,In Order to Obtain Positive Equipment Isolation ML20043J0581990-06-15015 June 1990 Forwards Proposed Issue 5 to Fort St Vrain Nuclear Generating Station Defueling Emergency Response Plan, Deleting Offsite Emergency Response Capabilities,Per Util 890816 Defueling SAR & NUREG-0654 ML20043D3291990-05-25025 May 1990 Forwards Response to NRC 900330 Ltr Re Violations Noted in Insp Rept 50-267/90-04.Encl Withheld (Ref 10CFR73.21) ML20043C8981990-05-25025 May 1990 Responds to NRC Re Violations Noted in Insp Rept 50-267/90-05.Corrective Actions:Mgt Will Continue to Stress Requirement for Procedural Compliance on Ongoing Basis ML20055D2051990-05-25025 May 1990 Responds to Violations Noted in Insp Rept 50-267/90-06. Corrective Actions:Extensive Training on Radiological Emergency Response Plan Implementing Procedures Will Be Provided to Operating Crews Beginning in May 1990 ML20043B3691990-05-22022 May 1990 Describes Util Current Plans for Removal of Certain Plant Equipment Items.Components to Be Removed Have No Required Nor Useful Function During Planned or Postulated Remaining Defueling or Shutdown Conditions ML20043A9491990-05-11011 May 1990 Forwards Issue 59 to AOP-K-1, Environ Disturbances - Earthquake ML20042F9771990-05-0404 May 1990 Forwards Assessment of Possible Sources of Water in Plant Core,Means of Detecting Water in Pcrv & Effects of Water Ingress on Reactivity,For Info ML20042F9011990-05-0101 May 1990 Forwards Conceptual Plan & Cost Estimates for Early Dismantlement of Fort St Vrain Pcrv, Per NRC 900315 Request ML20034C0911990-04-27027 April 1990 Forwards Revised Abnormal & Emergency Operating Procedures, Including Issue 57 to AOP-A,AOP-B,AOP-H-1,AOP-H-2 & AOP-H-3 ML20042E8911990-04-27027 April 1990 Requests 30-day Extension to 900529 to Submit Response to Violations Noted in Insp Rept 50-267/90-04 ML20042F3111990-04-26026 April 1990 Forwards Application to Amend License DPR-34,providing Tech Spec Changes Needed to Complete Defueling ML20034B3151990-04-18018 April 1990 Forwards Response to Request for Addl Info on Exercise Weakness Noted in Insp Rept 50-267/89-22.Actions Taken by Directing Reactor Operator During Accident Scenario Appropriate & Licensee Notification Process Adequate ML20042G0061990-04-12012 April 1990 Forwards Draft Physical Security Plan for Proposed ISFSI to Store Spent Fuel Onsite.Plan Withheld (Ref 10CFR73.21) ML20033G6571990-04-0202 April 1990 Forwards Issue 9 to Fire Protection Operability Requirements & Revised Table of Contents.Revs Not safety- Related Nor Significant & Do Not Require Changes to Tech Specs ML20033G6611990-03-30030 March 1990 Provides Summary of Level & Sources of Nuclear Property Insurance for Plant,Per 10CFR50.54(w)(2) ML20012D4711990-03-19019 March 1990 Requests Approval of Encl Exemption Request Allowing Util to Accumulate Decommissioning Funds Beyond Termination of Operations ML20033F1711990-03-0707 March 1990 Advises That Fee for Invoice I0546 Remitted on 900307 ML20012B7541990-03-0707 March 1990 Informs of Electronic Transfer of Fees on 900307 for Invoice IO547 ML20033E1241990-02-23023 February 1990 Provides Enhancement to 891122 Response to Violations Noted in Insp Rept 50-267/89-20.Corrective Action:Operations Shift Personnel Dispatched to Blow Down Svc Air & Instrument Air Lines in Turbine & Reactor Bldgs ML20011F4691990-02-22022 February 1990 Responds to NRC Re Violations Noted in Insp Rept 50-267/89-23.Violation Re Fire Doors 13 & 9 Between 480-volt Ac Switchgear Room & Bldg 10 Propped Open on 891129 Disputed.Improved Communications Underway ML20006E7821990-02-15015 February 1990 Forwards Responses to 891004 Questions Re Decommissioning Financial Plan ML20011E7861990-02-0707 February 1990 Forwards Overview of Evaluation on Compliance W/Environ Qualification Regulation (10CFR50.49) During Defueling of Facility.During Defueling,Pcrv Will Be Maintained at Nearly Atmospheric Pressures & Rapid Depressurization Not Possible ML20011E8941990-02-0707 February 1990 Responds to 890719 NRC Bulletin 89-002 Re safety-related Anchor/Darling Model S350W Swing Check Valves.Licensee Reviewed Plant Data Base & Design Documents & Concludes That No Anchor/Darling Model S350W Valves Installed at Plant ML20006D6621990-02-0606 February 1990 Responds to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Currently Established Preventive Maint & Tech Spec Surveillance Activities on HXs Remaining in Svc Will Continue ML20011E5031990-02-0606 February 1990 Notifies of Termination of Ma Rhoton Employment W/Util, Effective 900206 ML20006B2091990-01-26026 January 1990 Forwards Fire Operability Requirements 3 & 14,Issues 3 & 4, Respectively,To Fire Protection Program Plan,Section FP.6.1. Changes Cover Halon Sys & Basis & Records Ctr Halon Sys ML20006B7791990-01-25025 January 1990 Forwards Application for Amend to License DPR-34,changing Section 7.1 of Tech Specs.Specifically,Senior Vice President,Nuclear Operations Revised to Vice President, Nuclear Operations & Nuclear Training Manager Revised 1990-09-14
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- - N' pubne service companylatteville, Colorado oe cenomde 16805 Weld County Road 191/2, 80651
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November 7,1979 Fort St. Vrain Unit No. 1 P-79266 Mr. Karl V. Seyfrit, Director Nuclear Regulatory Cor: mission Region IV Office of Inspection and Enforcement 611 Ryan Plaza Drive Suite 1000 Arlington, Texas 76012 REF:
Facility Operating License No. DPR-34 Docket No. 50-267
Dear Mr. Seyfrit:
Enclosed please find a copy of Reportable Occurrence Report No. 50-267/79-45/03-L-0, Final, submitted per the requirements of Technical Specification AC 7.5.2(b)2.
Also, please find ' inclosed one copy of the Licensee Event Report for Reportable Occurrence Report No. 50-26 7/79-45/0} L-0.
Very truly yours, bW Don Warembourg Manager, Nuclear roduction DW/alk cc: Director, MIPC
,.7,,9 2, /. 1 y
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REPORT DATE:
November 7,1979 REPORTABLE OCCURRENCE 79-45 I
ISSUE O OCCURRENCE DATE:
October 8,1979 Page 1 of 5 FORT ST. VRAIN NUCLEAR GENERATING STATION PUBLIC SERVICE COMPANY OF COLORADO 16805 WELD COUNTY ROAD 19 1/2 PLAITEVILLE, COLORADO 80651 REPORT No. 50-267/ 79-45/03-L-0 Final IDENTIFICATION OF OCCURRENCE:
On four occasions between October 8,1979, and October 15, 1979, total primary coolant oxidants (the sum of water, carbon monoxide, and carbon dioxide) ex-ceeded 10 parts per million with average core outlet temperature greater than 1,200*F.
These occurrences constitute operation in a degraded mode permitted by LCO 4.2.10, and are reportable per Fort S t. Vrain Technical Specification AC 7.5.2(b)2.
EVENT
DESCRIPTION
At 1400 hours0.0162 days <br />0.389 hours <br />0.00231 weeks <br />5.327e-4 months <br /> on October 8,1979, the plant was operating at approximately 38* ther=al power and 120 MWe with an average core outlet temperature less than 1,200*F and total primary coolant oxidants greater than 10 ppm. A de-cision was made to increase reactor power in an attempt to facilitate mois-ture removal and between October 8,1979, and October 15, 1979, degraded mode operations allowed by LCO 4.2.10 occurred on four occasions, as described be-low.
1.
At approximately 1430 hours0.0166 days <br />0.397 hours <br />0.00236 weeks <br />5.44115e-4 months <br /> on October 8,1979, average core outlet tem-perature exceeded 1,200*F for the first time sin e return to power on September 15, 1979. Reference Figure 1, point 1 At that time, the total primary coolant oxidant level was approximately 15.7 ppm. As reac-ter power and core outlet temperature were increased to facilitate mois-ture removal, primary coolant oxidant levels increased as moisture was allowed to outgas from the graphite in the core. A maximum primary coolant oxidant level of 24.0 ppm was reached at 0000 hourt on October 9,1979, with corres onding core outlet temperature of 1,320*F (reference Figure 1, point
).
Total oxidant levels began a decreasing trend, with aver-age core let temperature holding steady.
At 0800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> on October 9,1979, it was decided to decrease reactor power to hold average core outlet temperature below 1,200*F until oxidant levels reachedavaluelessthan10 ppm (referenceFigure1, point (3)).
9 272 f9 hho W e/
REPORTABLE OCCURRENCE 79-45 ISSUE O Page 2 of 5 EVENT DESCRIPTION (continued):
2.
Because total oxidants had been less than 10 ppm since approximately 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br /> October 9,1979, reactor power was increased at 1340 hours0.0155 days <br />0.372 hours <br />0.00222 weeks <br />5.0987e-4 months <br /> on Octo-b er 10, 19 79. By 1400 hours0.0162 days <br />0.389 hours <br />0.00231 weeks <br />5.327e-4 months <br />, average core outlet temperature was greater than 1,200*F.
As core outlet temperature was increased, the small amount of moisture remaining in the core was allowed to react with the graphite, resulting in increased primary coolant oxidant levels. At approximately 1700 hours0.0197 days <br />0.472 hours <br />0.00281 weeks <br />6.4685e-4 months <br /> on October 10, 1979, the plant again entered o ration under a degraded mode of LCO 4.2.10 (reference Figure 1, point 4 ).
Following an initial increase due to the rise in core outlet temperature, oxidant levels decreased to less th 10 ppm at 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br /> on October 11, 1979 (reference Figure 1, point
).
3.
A small increase in moisture resulted in total primary coolant oxidants again exceeding 10 ppe at 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> on October 11, 1979, (reference Figure 1, point (})).
Af ter degraded mode operation of approximately 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, sufficient mois-ture cleanup occurred that total pr mary coolant oxidants dropped below 10 ppm (reference Figure 1, point 7 ).
4 Total primary coolant oxidants remained at less than 10 ppm until 1400 hours0.0162 days <br />0.389 hours <br />0.00231 weeks <br />5.327e-4 months <br /> on October 13, 1979. Beginning at 0000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> on October 13, 1979, carbon monoxide began increasing, and this eventually brought the total of primary coolant oxidants to greater than 10 ppm. Followin short period of degraded mode operation (reference Figure 1, point S
), total oxidants dropped below 10 ppm and no further degraded mode operation was observed.
CAUSE
DESCRIPTION:
'leasons for the LCO 4.2.10 degraded mode operation referenced in this report are as follows:
1.
At approximately 0400 hours0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br /> on October 8,1979, a temporary loss of liquid nitrogen to the low temperature absorber resulted in an increase in total oxidants due primarily to carbon monoxide.
Following a peak at approxi-mately 0800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> carbon monoxide levels decreased. At 1345 hours0.0156 days <br />0.374 hours <br />0.00222 weeks <br />5.117725e-4 months <br />, a de-cision was made to increase reactor power to facilitate removal of mois-ture remaining in the core following a dryer bypass due to cross tower leakage on October 5,1979. This increase in temperature resulted in increased oxidant levels.
2.
The degraded mode operation referenced in item 2 of the event description was the result of an increase in core outlet temperature which allowed moisture to react with the core graphite, resulting in increased carbon monoxide and carbon dioxide values.
3.
Degraded mode operation described in item nu=ber 3 was a result of a small increase in moisture level.
'7'9 273
REPORTABLE OCCURRENCE 79-45 I
ISSUE O Page 3 of 5
CAUSE
DESCRIPTION (continued):
/
4.
The degraded mode operation noted in item 4 of the event description was due to a small, gradual increase in carbon monoxide. Ne explanation trace-able to plant operation is available for this brief period of degraded mode op era tion.
CORRECTIVE ACTION:
Corrective action for the occurrences noted in this report is as follows:
1.
Reactor power was reduced on October 9,1979, to achieve an average core outlet temperature less than 1,200*F until pri=ary coolant oxidants were brought within the limits of LCO 4.2.10.
2, 3, and 4.
No specific corrective action was taken for the degraded mode operation referenced in itecs 2, 3, and 4.
Sufficient pri=ary coolant cleanup occurred in each case to return pri=ary coolant oxidants to less
. than 10 ppm.
No further corrective action is anticipated or required.
9 274
lu. YUK 1ABLt ULGUKKENCE /9-4)
FIGURE 1 ISSUE O Page 4 ef 5 AVERAGE CORE OUILET TEMPERATURE VERSUS PRIFARY COOLANT OXIDANTS 1350 -
O-
- - 24 AVERAGE CORE OLT-LET TE!!PERATURE
_ 22
=!
E
'+
z
- - b 1300 20 1
- - 18 9
=
- - 16 mt E.
1250 -
d 14 i-TOTAL OXIDANTS 16 i
E 2=;
1200
?;@
~'
t'
-- 10
.m
- - 8 D
's Al T
6 1150 0000 0000 0000 0000 0000 0000 0000 0000 10/8 10/9 10/10 10/11 10/12 10/13 10/14 10/ 15 DATE/ TIME
REPORTABLE OCCURRENCE 79-45 I
ISStE o Page 5 of 5
, b]No>d Prepared by:
o-Cathy C./ Collard Technical Services Technician Reviewed by:
./
p a Services Supervisor g
Reviewed by:
Frank M. Mathie Operations Manager Approved by:
Md Manager, Nuclear Product [ ion Don Warembourg
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05000267/LER-1979-001, Forwards LER 79-001/03L-0 | Forwards LER 79-001/03L-0 | | 05000267/LER-1979-001-03, /03L-0 on 790102:total Primary Coolant Oxidant Concentration Exceeded 10 Vol Ppm While Core Average Outlet Temp Was Greater than 1200 F.Caused by Low Temp Absorber Heatup,Releasing Oxidant to Primary Coolant | /03L-0 on 790102:total Primary Coolant Oxidant Concentration Exceeded 10 Vol Ppm While Core Average Outlet Temp Was Greater than 1200 F.Caused by Low Temp Absorber Heatup,Releasing Oxidant to Primary Coolant | | 05000267/LER-1979-002-03, /03L-0 on 790127:operation in Degraded Mode Resulted from Repairs to Seat of Buffer Helium Purge Valve. Bypass of Buffer Helium Dryer Caused by Leakage Past Valve Seat Insert of Velan Model P-33876-N/78R Valve | /03L-0 on 790127:operation in Degraded Mode Resulted from Repairs to Seat of Buffer Helium Purge Valve. Bypass of Buffer Helium Dryer Caused by Leakage Past Valve Seat Insert of Velan Model P-33876-N/78R Valve | | 05000267/LER-1979-002, Forwards LER 79-002/03L-0 | Forwards LER 79-002/03L-0 | | 05000267/LER-1979-004-03, /03L-0 on 790203:during Normal Operation,Cooling Tower Blowdown Exceeded Limit But Was Not Reported.Caused by Incorrect Completion of Surveillance Forms.Forms Changed & Personnel Instructed | /03L-0 on 790203:during Normal Operation,Cooling Tower Blowdown Exceeded Limit But Was Not Reported.Caused by Incorrect Completion of Surveillance Forms.Forms Changed & Personnel Instructed | | 05000267/LER-1979-004, Forwards LER 79-004/03L-0 | Forwards LER 79-004/03L-0 | | 05000267/LER-1979-005-03, /03L-0 on 790209:during Semiannual Loss of Outside Electrical Power Test,Output Circuit Breaker Did Not Close.Cause Unknown.Breaker Replaced W/Equivalent Spare | /03L-0 on 790209:during Semiannual Loss of Outside Electrical Power Test,Output Circuit Breaker Did Not Close.Cause Unknown.Breaker Replaced W/Equivalent Spare | | 05000267/LER-1979-005, Forwards LER 79-005/03L-0 | Forwards LER 79-005/03L-0 | | 05000267/LER-1979-013-03, /03L-0 on 790412:during Test of Snubbers Many Found Inoperable Due to Unacceptable Lockup & Bleed Characteristics.Caused by Setpoint Drift,Dirty Oil & Clogged Valves.All Snubbers Repaired & Adjusted | /03L-0 on 790412:during Test of Snubbers Many Found Inoperable Due to Unacceptable Lockup & Bleed Characteristics.Caused by Setpoint Drift,Dirty Oil & Clogged Valves.All Snubbers Repaired & Adjusted | | 05000267/LER-1979-013, Forwards RO 50-267/79-13/03-L-O & LER 79-013/03L-0 | Forwards RO 50-267/79-13/03-L-O & LER 79-013/03L-0 | | 05000267/LER-1979-015-03, /03L-0 on 790507:during Routine Surveillance Testing,Setpoint of Pcrv Rupture Disc M-11702 Found to Be 826 Psig.Caused by Calibr Drift.Disc Recalbr | /03L-0 on 790507:during Routine Surveillance Testing,Setpoint of Pcrv Rupture Disc M-11702 Found to Be 826 Psig.Caused by Calibr Drift.Disc Recalbr | | 05000267/LER-1979-015, Forwards LER 79-015/03L-0 | Forwards LER 79-015/03L-0 | | 05000267/LER-1979-016, Forwards LER 79-016/01T-0 | Forwards LER 79-016/01T-0 | | 05000267/LER-1979-016-01, /01T-0 on 790521:punch Gap of Pcrv Rupture Disc M-11702 Found Out of Tolerance W/Vendor Specs.Caused by Undocumented Change of Punch Gap Specs.Tolerances Returned to Original Specs | /01T-0 on 790521:punch Gap of Pcrv Rupture Disc M-11702 Found Out of Tolerance W/Vendor Specs.Caused by Undocumented Change of Punch Gap Specs.Tolerances Returned to Original Specs | | 05000267/LER-1979-017-01, /01T-0 on 790626:fault Current Trip Occurred, Causing Reactor Scram & Interrupted Reactor Cooling.Caused by Water Spray in Switchgear,Resulting in Short Circuit Due to Voltage Perturbation | /01T-0 on 790626:fault Current Trip Occurred, Causing Reactor Scram & Interrupted Reactor Cooling.Caused by Water Spray in Switchgear,Resulting in Short Circuit Due to Voltage Perturbation | | 05000267/LER-1979-017, Forwards LER 79-017/01T-0 | Forwards LER 79-017/01T-0 | | 05000267/LER-1979-018, Forwards LER 79-018/03L-0 | Forwards LER 79-018/03L-0 | | 05000267/LER-1979-018-03, /03L-0 on 790630:one motor-operated Butterfly Valve Found Inoperable by Remote Manual Control.Cause Is Unknown.Cause & Corrective Action to Be Reported in Future Suppl | /03L-0 on 790630:one motor-operated Butterfly Valve Found Inoperable by Remote Manual Control.Cause Is Unknown.Cause & Corrective Action to Be Reported in Future Suppl | | 05000267/LER-1979-019-03, /03L-0 on 790711:during Normal Operation,Weekly Functional Test of Area Radiation Monitors Not Performed for 1 Wk.Caused by Misfiling of Card for Surveillance Test. Computer Readout Will Be Used as Cross Check on Card Sys | /03L-0 on 790711:during Normal Operation,Weekly Functional Test of Area Radiation Monitors Not Performed for 1 Wk.Caused by Misfiling of Card for Surveillance Test. Computer Readout Will Be Used as Cross Check on Card Sys | | 05000267/LER-1979-020-03, /03L-0 on 790717:during Normal Plant Operation, Engine Failed to Start.Caused by Failure of Emergency Diesel Temp Switch C.Switch Replaced | /03L-0 on 790717:during Normal Plant Operation, Engine Failed to Start.Caused by Failure of Emergency Diesel Temp Switch C.Switch Replaced | | 05000267/LER-1979-021-03, /03L-1 on 790720:during Review of Surveillance Tests,Discovered That Halon Fire Suppression Sys Surveillance Test for Second Quarter Not Performed.Caused by Inadequate Control & Direction Re Refueling Work Load | /03L-1 on 790720:during Review of Surveillance Tests,Discovered That Halon Fire Suppression Sys Surveillance Test for Second Quarter Not Performed.Caused by Inadequate Control & Direction Re Refueling Work Load | | 05000267/LER-1979-021, Forwards LER 79-021/03L-0 | Forwards LER 79-021/03L-0 | | 05000267/LER-1979-022-03, /03L-0 on 790720:lack of Aquatic Macroinvertebrate Sample Collection.Caused by Oversight of Field Sampling Personnel Employed by Contract Agent.Agent Indicated Program Was Resumed & Will Continue Biweekly | /03L-0 on 790720:lack of Aquatic Macroinvertebrate Sample Collection.Caused by Oversight of Field Sampling Personnel Employed by Contract Agent.Agent Indicated Program Was Resumed & Will Continue Biweekly | | 05000267/LER-1979-023-03, /03L-0 on 790727:while Performing Normal Surveillance,Fixed Feedwater Low Flow Switch Found Inoperable. Caused by Component Failure from Normal Wear. Module Was Repaired,Reinstalled & Retested Satisfactorily | /03L-0 on 790727:while Performing Normal Surveillance,Fixed Feedwater Low Flow Switch Found Inoperable. Caused by Component Failure from Normal Wear. Module Was Repaired,Reinstalled & Retested Satisfactorily | | 05000267/LER-1979-024-03, /03L-0:on 790804,on Three Occasions Between 790804-16,total Primary Coolant Oxidants Exceeded 10 Ppm W/Core Average Outlet Temp Greater than 1,200 F.Caused by Dryer Bypass Resulting in Water Ingress to Core | /03L-0:on 790804,on Three Occasions Between 790804-16,total Primary Coolant Oxidants Exceeded 10 Ppm W/Core Average Outlet Temp Greater than 1,200 F.Caused by Dryer Bypass Resulting in Water Ingress to Core | | 05000267/LER-1979-024, Forwards LER 79-024/03L-0 | Forwards LER 79-024/03L-0 | | 05000267/LER-1979-025-03, /03X-0:on 790806,during Steady State Operation at 45% Thermal Power,Emergency Diesel Generator a Found in Degraded Mode, & B Engine Also Declutched.Caused by Relay Failure Due to Normal End of Life.Relay Replaced | /03X-0:on 790806,during Steady State Operation at 45% Thermal Power,Emergency Diesel Generator a Found in Degraded Mode, & B Engine Also Declutched.Caused by Relay Failure Due to Normal End of Life.Relay Replaced | | 05000267/LER-1979-026-03, /03L-0:on 790807,bearing Water Makeup Pump P-2105 Removed from Svc to Perform Line Repair W/Reactor at 65% Power.Caused by Hole in Recirculation Line of Pump,Requiring Removal from Svc.Line Repaired.Pump Returned to Svc | /03L-0:on 790807,bearing Water Makeup Pump P-2105 Removed from Svc to Perform Line Repair W/Reactor at 65% Power.Caused by Hole in Recirculation Line of Pump,Requiring Removal from Svc.Line Repaired.Pump Returned to Svc | | 05000267/LER-1979-027-01, /01T-0:on 790817,noted That Recent Pipe Hanger Installation Power Operated Relief Valve Cooling Water Lines Would Have Prevented Proper Installation of Pipe Spools. Caused by Pipe Ends Changing Alignment | /01T-0:on 790817,noted That Recent Pipe Hanger Installation Power Operated Relief Valve Cooling Water Lines Would Have Prevented Proper Installation of Pipe Spools. Caused by Pipe Ends Changing Alignment | | 05000267/LER-1979-028-01, /01T-0:on 790817,personnel Grounded Instrument Panel,Blowing Fuses & Causing Voltage Perturbation on Instrument Bus 2.Caused by Error by Nonlicensed Maint Personnel.Ground Corrected & Power Restored | /01T-0:on 790817,personnel Grounded Instrument Panel,Blowing Fuses & Causing Voltage Perturbation on Instrument Bus 2.Caused by Error by Nonlicensed Maint Personnel.Ground Corrected & Power Restored | | 05000267/LER-1979-029, Forwards LER 79-029/03L-0 | Forwards LER 79-029/03L-0 | | 05000267/LER-1979-029-03, /03L-0:on 790819,during Plant Startup,B Instrument Air Compressor Became Inoperable.Caused by Failure of Discharge Feather Valve.All Discharge Valves on Compressor Replaced & C Air Compressor Returned to Svc | /03L-0:on 790819,during Plant Startup,B Instrument Air Compressor Became Inoperable.Caused by Failure of Discharge Feather Valve.All Discharge Valves on Compressor Replaced & C Air Compressor Returned to Svc | | 05000267/LER-1979-030, Forwards LER 79-030/03L-0 | Forwards LER 79-030/03L-0 | | 05000267/LER-1979-030-03, /03L-0:on 790821,primary Coolant Oxidants Exceeded Limiting Condition for Operation.Caused by Offline Helium Dryer Drying Out Operations & Extended Regeneration Period. Core Outlet Temps Reduced Whenever Oxidant Limits Excee | /03L-0:on 790821,primary Coolant Oxidants Exceeded Limiting Condition for Operation.Caused by Offline Helium Dryer Drying Out Operations & Extended Regeneration Period. Core Outlet Temps Reduced Whenever Oxidant Limits Exceeded | | 05000267/LER-1979-031, Forwards LER 79-031/03L-0 | Forwards LER 79-031/03L-0 | | 05000267/LER-1979-031-03, /03L-0:on 790821 & 0830,plant Operated W/Reactor Dewpoint Outside Tech Spec Limits.Caused by Helium Dryer Bypass,Due to Faulty Time Delay Relay.No Cause for 790821 Event.Relay Replaced & Tested | /03L-0:on 790821 & 0830,plant Operated W/Reactor Dewpoint Outside Tech Spec Limits.Caused by Helium Dryer Bypass,Due to Faulty Time Delay Relay.No Cause for 790821 Event.Relay Replaced & Tested | | 05000267/LER-1979-032, Forwards LER 79-032/03X-1 | Forwards LER 79-032/03X-1 | | 05000267/LER-1979-032-03, /03X-1:on 790913,during Testing,Four Helium Circulator Seal Malfunction Pressure Differential Switch Units Would Not Trip or Tripped Outside Limits.Caused by Dirt Accumulation in Electrical Switches | /03X-1:on 790913,during Testing,Four Helium Circulator Seal Malfunction Pressure Differential Switch Units Would Not Trip or Tripped Outside Limits.Caused by Dirt Accumulation in Electrical Switches | | 05000267/LER-1979-033, Forwards LER 79-033/03L-0 | Forwards LER 79-033/03L-0 | | 05000267/LER-1979-033-03, /03L-0:on 790828,unauthorized Release Made from 1A Gas Waste Surge Tank.Caused by Wrong Valve Lineup.Valve Checkoff Sheets Revised to Require Operator Initials for Each Valve.Personnel Admonished | /03L-0:on 790828,unauthorized Release Made from 1A Gas Waste Surge Tank.Caused by Wrong Valve Lineup.Valve Checkoff Sheets Revised to Require Operator Initials for Each Valve.Personnel Admonished | | 05000267/LER-1979-034-03, /03L-0:on 790830,while Operating at 36% Thermal Power,Emergency Diesel Generator Day Tanks Did Not Have 500 Gallons of Fuel Oil as Required Per Tech Specs.Caused by Inoperable High Level Switch Which Controls Pump Operations | /03L-0:on 790830,while Operating at 36% Thermal Power,Emergency Diesel Generator Day Tanks Did Not Have 500 Gallons of Fuel Oil as Required Per Tech Specs.Caused by Inoperable High Level Switch Which Controls Pump Operations | | 05000267/LER-1979-034, Forwards LER 79-034/03L-0 | Forwards LER 79-034/03L-0 | | 05000267/LER-1979-035-01, /01T-0:on 790831,field Audit Analysis Indicated Inconsistencies in Hangers of as-built safety-related Piping.Caused by Design & Installation Inconsistencies. Remaining Hangers Being Analyzed | /01T-0:on 790831,field Audit Analysis Indicated Inconsistencies in Hangers of as-built safety-related Piping.Caused by Design & Installation Inconsistencies. Remaining Hangers Being Analyzed | | 05000267/LER-1979-036-03, /03L-0:on 790910,cold Reheat Snubber CRS-262 Inoperable W/Reactor in Shutdown Condition.Caused by Missing Pin That Kept Snubber from Being Properly Attached to Pipe. New Pin Fabricated & Installed.Snubber Returned to Svc | /03L-0:on 790910,cold Reheat Snubber CRS-262 Inoperable W/Reactor in Shutdown Condition.Caused by Missing Pin That Kept Snubber from Being Properly Attached to Pipe. New Pin Fabricated & Installed.Snubber Returned to Svc | | 05000267/LER-1979-037-03, /03L-0:on 790919,during Normal Operation,Liquid Radwaste Release Was Made in Noncompliance W/Limiting Conditions for Operation.Caused by Operator Failure to Reset Flow Switch to New Required Flow Rate.Operators Admonished | /03L-0:on 790919,during Normal Operation,Liquid Radwaste Release Was Made in Noncompliance W/Limiting Conditions for Operation.Caused by Operator Failure to Reset Flow Switch to New Required Flow Rate.Operators Admonished | | 05000267/LER-1979-037, Forwards LER 79-037/03L-0 | Forwards LER 79-037/03L-0 | | 05000267/LER-1979-038, Forwards LER 79-038/03L-0 | Forwards LER 79-038/03L-0 | | 05000267/LER-1979-038-03, /03L-0:on 790921,analytical Sys Primary Coolant Moisture Monitor ME-9307 Became Inoperable W/Reactor at Less than 2% Power.Caused by Burned Out Thermal Electric Heater/Cooler & Two Faulty Relays.Head & Relays Replaced | /03L-0:on 790921,analytical Sys Primary Coolant Moisture Monitor ME-9307 Became Inoperable W/Reactor at Less than 2% Power.Caused by Burned Out Thermal Electric Heater/Cooler & Two Faulty Relays.Head & Relays Replaced | | 05000267/LER-1979-039-03, /03L-0:on 790924,authorized Liquid Waste Release Was Made,Requiring Raising Setpoints on Liquid Waste Activity Monitors Above Normal.Caused by Failure to Return Monitors to Normal Setpoints Prior to Starting Release | /03L-0:on 790924,authorized Liquid Waste Release Was Made,Requiring Raising Setpoints on Liquid Waste Activity Monitors Above Normal.Caused by Failure to Return Monitors to Normal Setpoints Prior to Starting Release | | 05000267/LER-1979-040, Forwards LER 79-040/03L-0 | Forwards LER 79-040/03L-0 | |
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