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Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML18017A9181999-10-0808 October 1999 LER 99-008-00:on 991008,CR Emergency Filtration Sys Tech Specs Occurred.Caused by Site Personnel Failed to Recognize That Blocking Open CR Emergency Filtration Sys.Procedures Revised.With 991008 Ltr ML18017A8671999-09-10010 September 1999 LER 99-007-00:on 990811,determined That Cvis ARMs High Alarm Setpoints Were Not within TS Limit.Caused by Not Having Procedure to Verify If Cvis ARM High Alarm Setpoints Were within TS Requirements.Revised Procedures.With 990910 Ltr ML18016B0481999-08-0404 August 1999 LER 99-006-01:on 981124,noted Failure to Comply with TS 4.0.4 & TS 3/4.6.3, Civs. Caused by post-maint Testing That Did Not Adequately Test Control Circuitry & Verify Isolation Time Following Maint.Procedure Was Revised ML18016A9801999-06-0404 June 1999 LER 99-006-00:on 981124,failed to Comply with TS 4.0.4 & TS 3/4.6.3, Civ. Caused by post-maint Testing That Did Not Adequately Test Control Circuitry & Verify Isolation Time Following Maint.Procedure Will Be Revised.With 990604 Ltr ML18016A9111999-04-12012 April 1999 LER 99-005-00:on 990313,plant Exceeded ESFAS TS 3.3.2,Action 21.Caused by Inadequate Procedure Rev Preparation.Licensee Revised Applicable Maint Surveillance Test Procedure (MST-10072) to Identify TS Required Actions.With 990412 Ltr ML18016A8971999-04-0808 April 1999 LER 99-004-00:on 990312,unit Trip Was Noted.Caused by Degraded Condition of SG Water Level Flow Control Valve. Replaced Positioners on All Three FW Regulating Valves.With 990408 Ltr ML18016A8261999-02-22022 February 1999 LER 99-003-00:on 990123,noted That Plant Was Outside Design Basis Due to Isolation of Fire Protection Containment Sprinkler Sys.Caused by Human Error.Restored Containment Sprinkler Sys to Operable Status.With 990222 Ltr ML18016A8111999-02-12012 February 1999 LER 99-002-00:on 990114,RT Due to Not Removing Temporary Device from Relay Following Calibration Was Noted.Caused by Human Error.Counseled Personnel Involved in Event.With 990212 Ltr ML18016A7971999-02-0505 February 1999 LER 99-001-00:on 990106,SF Pool Water Level Was Not Maintained Greater than 23 Feet Above Stored BWR Fuel Assemblies.Caused by Fasteners Bending Under Specific Circumstances.Increased Water Level.With 990205 Ltr ML18016A7941999-01-29029 January 1999 LER 98-004-01:on 980313,identified Design Deficiency Re Potential Runout of Tdafwp.Caused by Inadequate Original AFW Sys Design.Operability Evaluation Was Completed on 980313 & Addl Engineering Analysis Was Performed by Vendor ML18016A7211998-11-17017 November 1998 LER 98-007-00:on 981023,turbine Control Anomaly Caused Manual Rt.Caused by Failure to Incorporate Verbal Vendor Guidance in Operating Procedures.Addl Vendor Guidance Will Be Verified & Added to Procedures.With 981117 Ltr ML18016A4841998-07-0707 July 1998 LER 97-002-01:on 970207,determined That Cold Weather Conditions Resulted in Mfiv Being Potentially Inoperable During Period 970117-20.Caused by Inadequate Design of HVAC Sys.Implemented Mods to Steam Tunnel HVAC Sys ML18016A4701998-06-30030 June 1998 LER 97-021-03:on 980210,discovered That SFP Water Level Had Not Been Verified Greater than 23 Feet Above BWR Fuel Assemblies.Caused by Misinterpretation of TS Requirements. Will Submit TS Change Request to Revise TS 3.9.1.11 ML18016A4491998-06-0808 June 1998 LER 98-006-00:on 980508,failure to Perform Insp & Preventive Maint on MCCB as Required by TS Was Noted.Caused by Inadequate Sps.Tested 9 Pressurizer Heater Bank Breakers by Cycling each.W/980608 Ltr ML18022B0551998-05-20020 May 1998 LER 98-005-00:on 980420,TS Verbatim non-compliance Was Determined.Caused by Misinterpretation of TS Requirements. Issued Memo to Reemphasize Need to Comply W/Literal Meaning of TS Requirements in Verbatim manner.W/980520 Ltr ML18016A4061998-04-30030 April 1998 LER 98-002-01:on 980121,determined Ssps (P-11 Permissive) Testing Deficiency.Caused by Inadequate Review of Initial Ts.Will Revise & Perform Surveillance Test Procedures to Verify Operability of P-11 Permissive ML18016A3841998-04-13013 April 1998 LER 98-004-00:on 980313,design Deficiency Related to Indequate Runout Protection for Turbine Driven AFW Pump Was Identified.Caused by Inadequate Original AFW Sys Design. Evaluation (ESR 98-00100) Will Be completed.W/980409 Ltr ML18016A3441998-03-12012 March 1998 LER 97-021-02:on 980210,identified Failure to Properly Test non-safety Related Pressurizer Porv.Caused by Inadequate Surveillance Test Procedures.Revised Operations Surveillance Test OST-1117 to Include Testing of Subject PORV ML18016A3291998-02-27027 February 1998 LER 98-003-00:on 980129,failure to Perform Shutdown Margin Calculation Required by TS Surveillance Requirements Occurred.Caused by Ambiguity in TS 3.1.3.1.c.Procedures revised.W/980227 Ltr ML18016A3211998-02-20020 February 1998 LER 98-002-00:on 980121,solid State Protection Sys Testing Deficiency Occurred.Caused by Inadequate Review of Initial Tech Specs.Ts Testing Frequency for P-11 Permissive Revised. W/980217 Ltr ML18016A3131998-02-0909 February 1998 LER 98-001-00:on 980109,potential Condition Outside Design Basis Related to Instrument Air Sys Leak Causing SG pre- Heater Bypass Isolation Valves to Be Inoperable Was Noted. Caused by Inadequate Design Control.Generated Jco 98-01 ML18016A2641997-12-18018 December 1997 LER 97-024-00:on 971118,SSPS Testing Deficiency Was Noted. Caused by Inadequate Testing Scheme Provided by Ssps Vendor. Revised procedure.W/971218 Ltr ML18016A2501997-11-24024 November 1997 LER 97-023-00:on 920721,RCS PIV Testing Deficiency Was Noted.Caused by Failure to Consider All Testing Variables During Initial Sp Development.Surveillance Tp OST-1506 Was Revised to Incorporate Correction factor.W/971124 Ltr ML18016A2201997-10-22022 October 1997 LER 97-021-01:on 970922,discovered That Spent Fuel Pool Water Level Was Not Maintained Greater than 23 Feet Above Stored BWR Fuel Assemblies.Caused by Misinterpretation of TS Requirements.Revised Daily Surveillance Procedures ML18016A2081997-10-14014 October 1997 LER 97-016-01:on 970608,reactor Trip Occurred,Due to Personnel Error While Attempting to Adjust Power Range Nuclear Instrumentation Channel Following Performance of Calorimetric.Procedures revised.W/971014 Ltr ML18016A2111997-10-14014 October 1997 LER 96-008-02:on 960425,turbine Trip/Reactor Trip Occurred. Caused by High Resistance Connection Resulting from a Phase Switch Jaw & Blade Contacts.Failed a Phase Disconnect Switch on Breaker 52-7 Replaced ML18016A1931997-09-29029 September 1997 LER 97-022-00:on 970829,TS Required Shutdown Due to Expiration of AFW Lco.Caused by Personnel Error.Completed Repairs TDAFW Pump & Returned Plant to Svc on 970831. W/970926 Ltr ML18016A1891997-09-12012 September 1997 LER 97-020-00:on 970814,inadequate Fire Protection Provided for safety-related EDG Fuel Oil Transfer Pump Cables Resulted in Operation Outside Design Basis.Caused by Engineering Oversight.Established Fire watches.W/970912 Ltr ML18016A1881997-09-12012 September 1997 LER 97-021-00:on 970814,spent Fuel Pool Water Level Was Not Maintained Greater than 23 Feet Above Stored BWR Fuel Assemblies.Caused by Misinterpretation of Ts.Directions Provided to Operations.W/970912 Ltr ML18012A8641997-08-18018 August 1997 LER 97-019-00:on 970720,turbine Trip/Reactor Trip Occurred. Caused by Three Phase Fault That Collapsed Excitation Field in Main Generator,Resulting in Generator Lockout.Exciter Rotor Assembly Was replaced.W/970818 Ltr ML18012A8581997-08-0808 August 1997 LER 96-018-01:on 960903,manual Reactor Trip Occurred Due to Loss of Normal Sw.Caused by Mechanical Failure of B Water Pump & a Normal SW to Remain Running Once Manually Started.Restored a Normal SW Pump to Svc ML18012A8551997-08-0808 August 1997 LER 96-013-02:on 961028,condition Outside of Design Basis Where RWST Had Been Aligned w/non-seismically Qualified Sys Was Identified.Caused by Failure to Reconcile Operating Procedure Lineups.Established Administrative Controls ML18012A8471997-07-31031 July 1997 LER 97-018-00:on 970701,determined That Plant Procedures Had Not Received Proper Reviews & Approvals.Caused by Failure to Comply W/Plant Administrative Procedure AP-006.Counseled Involved individuals.W/970731 Ltr ML18012A8371997-07-24024 July 1997 LER 97-S01-00:on 970405,unescorted Access Inappropriately Granted to Contract Outage Workers Was Determined.Caused by Personnel Error.Access Files for Individuals Inappropriately Granted Unescorted Access Were Placed on Access Hold ML18012A8291997-07-11011 July 1997 LER 97-017-00:on 970612,failed to Recognize Inoperable Reactor Afd Monitor.Caused by Personnel Error.Operators Involved in Event Will Be Counseled Prior to Assuming Shift duties.W/970711 Ltr ML18012A8301997-07-0808 July 1997 LER 97-016-00:on 970608,reactor Trip Occurred Due to Personnel Error in Adjusting Power Range (Pr) Nuclear Instrumentation (Ni).Issued Night Order Prohibiting Pr Ni Adjustment When Redundant Channel inoperable.W/970708 Ltr ML18012A8241997-07-0202 July 1997 LER 97-015-00:on 970602,inadequate Auxiliary Feedwater Sys Flow Control Valve Surveillance Testing Deficiency Was Identified.Caused by Failure to Recognize Impact on TS 4.7.1.2.1.Readjusted AFW FCV Actuator spring.W/970702 Ltr ML18022B0181997-06-13013 June 1997 LER 97-014-00:on 970514,SI Occurred During Ssps Surveillance Testing.Caused by Inattention to Detail During Recent Rev to Surveillance Test Procedure Being Used.Revised Deficient Surveillance procedures.W/970613 Ltr ML18012A8081997-06-0909 June 1997 LER 97-013-00:on 970508,entry Into Mode-6 Without Operable Components,Resulting in TS 3.0.4 Violation Occurred.Caused by Personnel Error.Personnel Involved counseled.W/970609 Ltr ML18012A8021997-06-0606 June 1997 LER 97-023-02:on 961114,design Deficiency Was Identified in Emergency DG Protection Circuitry.Caused by Inadequate Plant Design.Revised Surveillance Test Procedures OST-1013 & OST-1073.W/970606 Ltr ML18012A8011997-06-0404 June 1997 LER 97-012-00:on 970505,determined That Previous Auxiliary Control Panel Had Not Verified Operability of Interposing Relays.Caused by Misinterpretation of Tss.Reviewed Other Remote Shutdown Panel Transfer circuitry.W/970604 Ltr ML18012A7951997-05-29029 May 1997 LER 96-023-01:on 961114,design Deficiency in EDG Protection Circuitry Was Identified.Caused by Inadequate Original Plant Design.Surveillance Test Procedures OST-1013 & OST-1073 revised.W/970529 Ltr ML18012A7891997-05-22022 May 1997 LER 97-011-00:on 970422,inappropriate TS Interpretation Resulted in Violations of ECCS Accumulator TS & Entry Into TS 3.0.3.Caused by Procedural Inadequacy.Tsi 88-001 Cancelled 970508 & Procedures revised.W/970522 Ltr ML18012A7871997-05-19019 May 1997 LER 97-010-00:on 970418,design Deficiency Determined Re Reactor Coolant Pump Motor Oil Collection Sys.Caused by RCP Ocs Design Detail.Rcp Ocs Enclosures for Each of Three Installed RCP Motors Have Been modified.W/970519 Ltr ML18012A7761997-05-0707 May 1997 LER 97-009-00:on 970407,fuse Was Removed from CR Ventilation Isolation Signal Power Supply Circuitry Due to Personnel Error.Individuals Involved Were counseled.W/970507 Ltr ML18012A7751997-05-0505 May 1997 LER 97-008-00:on 970404,safety-related AHU Not Declared Inoperable During Maintenance on Associated Temperature Switches Resulting in Violation of Ts.Caused by Incorrect Interpretation.Operations Night Order issued.W/970505 Ltr ML18012A6291997-04-24024 April 1997 LER 97-007-00:on 970325,inoperable CCW Sys TS 3.0.3 Entry Made.Caused by Combination of Procedural Inadequacies, Improper Use of Procedure Guidance & Poor Communication. Applicable Individuals counseled.W/970423 Ltr ML18022B0151997-04-17017 April 1997 LER 97-006-00:on 970318,breach Was Identified in Thermo-Lag Fire Barrier Wall Due to Inadequate Initial Design,Poor Construction Methods & Incomplete as-built Design.Visual Insp of Thermo-Lag Barrier Walls performed.W/970417 Ltr ML18012A6041997-04-0303 April 1997 LER 97-004-00:on 970304,in-plant Spent Fuel Cask Handling Activities Conducted Outside Design Basis.Caused by Lack of Understanding of Requirements.Operations Placed on Hold Pending NRC Review & Approval of procedures.W/970331 Ltr ML18012A6031997-03-31031 March 1997 LER 97-003-00:on 970227,steam Generator Low Level Protection Circuitry Outside Design Basis Occurred.Caused by Inadequate Failure Modes & Effects Analysis Performed as-built Piping Configuration for S/G Level.Review performed.W/970331 Ltr 1999-09-10
[Table view] Category:RO)
MONTHYEARML18017A9181999-10-0808 October 1999 LER 99-008-00:on 991008,CR Emergency Filtration Sys Tech Specs Occurred.Caused by Site Personnel Failed to Recognize That Blocking Open CR Emergency Filtration Sys.Procedures Revised.With 991008 Ltr ML18017A8671999-09-10010 September 1999 LER 99-007-00:on 990811,determined That Cvis ARMs High Alarm Setpoints Were Not within TS Limit.Caused by Not Having Procedure to Verify If Cvis ARM High Alarm Setpoints Were within TS Requirements.Revised Procedures.With 990910 Ltr ML18016B0481999-08-0404 August 1999 LER 99-006-01:on 981124,noted Failure to Comply with TS 4.0.4 & TS 3/4.6.3, Civs. Caused by post-maint Testing That Did Not Adequately Test Control Circuitry & Verify Isolation Time Following Maint.Procedure Was Revised ML18016A9801999-06-0404 June 1999 LER 99-006-00:on 981124,failed to Comply with TS 4.0.4 & TS 3/4.6.3, Civ. Caused by post-maint Testing That Did Not Adequately Test Control Circuitry & Verify Isolation Time Following Maint.Procedure Will Be Revised.With 990604 Ltr ML18016A9111999-04-12012 April 1999 LER 99-005-00:on 990313,plant Exceeded ESFAS TS 3.3.2,Action 21.Caused by Inadequate Procedure Rev Preparation.Licensee Revised Applicable Maint Surveillance Test Procedure (MST-10072) to Identify TS Required Actions.With 990412 Ltr ML18016A8971999-04-0808 April 1999 LER 99-004-00:on 990312,unit Trip Was Noted.Caused by Degraded Condition of SG Water Level Flow Control Valve. Replaced Positioners on All Three FW Regulating Valves.With 990408 Ltr ML18016A8261999-02-22022 February 1999 LER 99-003-00:on 990123,noted That Plant Was Outside Design Basis Due to Isolation of Fire Protection Containment Sprinkler Sys.Caused by Human Error.Restored Containment Sprinkler Sys to Operable Status.With 990222 Ltr ML18016A8111999-02-12012 February 1999 LER 99-002-00:on 990114,RT Due to Not Removing Temporary Device from Relay Following Calibration Was Noted.Caused by Human Error.Counseled Personnel Involved in Event.With 990212 Ltr ML18016A7971999-02-0505 February 1999 LER 99-001-00:on 990106,SF Pool Water Level Was Not Maintained Greater than 23 Feet Above Stored BWR Fuel Assemblies.Caused by Fasteners Bending Under Specific Circumstances.Increased Water Level.With 990205 Ltr ML18016A7941999-01-29029 January 1999 LER 98-004-01:on 980313,identified Design Deficiency Re Potential Runout of Tdafwp.Caused by Inadequate Original AFW Sys Design.Operability Evaluation Was Completed on 980313 & Addl Engineering Analysis Was Performed by Vendor ML18016A7211998-11-17017 November 1998 LER 98-007-00:on 981023,turbine Control Anomaly Caused Manual Rt.Caused by Failure to Incorporate Verbal Vendor Guidance in Operating Procedures.Addl Vendor Guidance Will Be Verified & Added to Procedures.With 981117 Ltr ML18016A4841998-07-0707 July 1998 LER 97-002-01:on 970207,determined That Cold Weather Conditions Resulted in Mfiv Being Potentially Inoperable During Period 970117-20.Caused by Inadequate Design of HVAC Sys.Implemented Mods to Steam Tunnel HVAC Sys ML18016A4701998-06-30030 June 1998 LER 97-021-03:on 980210,discovered That SFP Water Level Had Not Been Verified Greater than 23 Feet Above BWR Fuel Assemblies.Caused by Misinterpretation of TS Requirements. Will Submit TS Change Request to Revise TS 3.9.1.11 ML18016A4491998-06-0808 June 1998 LER 98-006-00:on 980508,failure to Perform Insp & Preventive Maint on MCCB as Required by TS Was Noted.Caused by Inadequate Sps.Tested 9 Pressurizer Heater Bank Breakers by Cycling each.W/980608 Ltr ML18022B0551998-05-20020 May 1998 LER 98-005-00:on 980420,TS Verbatim non-compliance Was Determined.Caused by Misinterpretation of TS Requirements. Issued Memo to Reemphasize Need to Comply W/Literal Meaning of TS Requirements in Verbatim manner.W/980520 Ltr ML18016A4061998-04-30030 April 1998 LER 98-002-01:on 980121,determined Ssps (P-11 Permissive) Testing Deficiency.Caused by Inadequate Review of Initial Ts.Will Revise & Perform Surveillance Test Procedures to Verify Operability of P-11 Permissive ML18016A3841998-04-13013 April 1998 LER 98-004-00:on 980313,design Deficiency Related to Indequate Runout Protection for Turbine Driven AFW Pump Was Identified.Caused by Inadequate Original AFW Sys Design. Evaluation (ESR 98-00100) Will Be completed.W/980409 Ltr ML18016A3441998-03-12012 March 1998 LER 97-021-02:on 980210,identified Failure to Properly Test non-safety Related Pressurizer Porv.Caused by Inadequate Surveillance Test Procedures.Revised Operations Surveillance Test OST-1117 to Include Testing of Subject PORV ML18016A3291998-02-27027 February 1998 LER 98-003-00:on 980129,failure to Perform Shutdown Margin Calculation Required by TS Surveillance Requirements Occurred.Caused by Ambiguity in TS 3.1.3.1.c.Procedures revised.W/980227 Ltr ML18016A3211998-02-20020 February 1998 LER 98-002-00:on 980121,solid State Protection Sys Testing Deficiency Occurred.Caused by Inadequate Review of Initial Tech Specs.Ts Testing Frequency for P-11 Permissive Revised. W/980217 Ltr ML18016A3131998-02-0909 February 1998 LER 98-001-00:on 980109,potential Condition Outside Design Basis Related to Instrument Air Sys Leak Causing SG pre- Heater Bypass Isolation Valves to Be Inoperable Was Noted. Caused by Inadequate Design Control.Generated Jco 98-01 ML18016A2641997-12-18018 December 1997 LER 97-024-00:on 971118,SSPS Testing Deficiency Was Noted. Caused by Inadequate Testing Scheme Provided by Ssps Vendor. Revised procedure.W/971218 Ltr ML18016A2501997-11-24024 November 1997 LER 97-023-00:on 920721,RCS PIV Testing Deficiency Was Noted.Caused by Failure to Consider All Testing Variables During Initial Sp Development.Surveillance Tp OST-1506 Was Revised to Incorporate Correction factor.W/971124 Ltr ML18016A2201997-10-22022 October 1997 LER 97-021-01:on 970922,discovered That Spent Fuel Pool Water Level Was Not Maintained Greater than 23 Feet Above Stored BWR Fuel Assemblies.Caused by Misinterpretation of TS Requirements.Revised Daily Surveillance Procedures ML18016A2081997-10-14014 October 1997 LER 97-016-01:on 970608,reactor Trip Occurred,Due to Personnel Error While Attempting to Adjust Power Range Nuclear Instrumentation Channel Following Performance of Calorimetric.Procedures revised.W/971014 Ltr ML18016A2111997-10-14014 October 1997 LER 96-008-02:on 960425,turbine Trip/Reactor Trip Occurred. Caused by High Resistance Connection Resulting from a Phase Switch Jaw & Blade Contacts.Failed a Phase Disconnect Switch on Breaker 52-7 Replaced ML18016A1931997-09-29029 September 1997 LER 97-022-00:on 970829,TS Required Shutdown Due to Expiration of AFW Lco.Caused by Personnel Error.Completed Repairs TDAFW Pump & Returned Plant to Svc on 970831. W/970926 Ltr ML18016A1891997-09-12012 September 1997 LER 97-020-00:on 970814,inadequate Fire Protection Provided for safety-related EDG Fuel Oil Transfer Pump Cables Resulted in Operation Outside Design Basis.Caused by Engineering Oversight.Established Fire watches.W/970912 Ltr ML18016A1881997-09-12012 September 1997 LER 97-021-00:on 970814,spent Fuel Pool Water Level Was Not Maintained Greater than 23 Feet Above Stored BWR Fuel Assemblies.Caused by Misinterpretation of Ts.Directions Provided to Operations.W/970912 Ltr ML18012A8641997-08-18018 August 1997 LER 97-019-00:on 970720,turbine Trip/Reactor Trip Occurred. Caused by Three Phase Fault That Collapsed Excitation Field in Main Generator,Resulting in Generator Lockout.Exciter Rotor Assembly Was replaced.W/970818 Ltr ML18012A8581997-08-0808 August 1997 LER 96-018-01:on 960903,manual Reactor Trip Occurred Due to Loss of Normal Sw.Caused by Mechanical Failure of B Water Pump & a Normal SW to Remain Running Once Manually Started.Restored a Normal SW Pump to Svc ML18012A8551997-08-0808 August 1997 LER 96-013-02:on 961028,condition Outside of Design Basis Where RWST Had Been Aligned w/non-seismically Qualified Sys Was Identified.Caused by Failure to Reconcile Operating Procedure Lineups.Established Administrative Controls ML18012A8471997-07-31031 July 1997 LER 97-018-00:on 970701,determined That Plant Procedures Had Not Received Proper Reviews & Approvals.Caused by Failure to Comply W/Plant Administrative Procedure AP-006.Counseled Involved individuals.W/970731 Ltr ML18012A8371997-07-24024 July 1997 LER 97-S01-00:on 970405,unescorted Access Inappropriately Granted to Contract Outage Workers Was Determined.Caused by Personnel Error.Access Files for Individuals Inappropriately Granted Unescorted Access Were Placed on Access Hold ML18012A8291997-07-11011 July 1997 LER 97-017-00:on 970612,failed to Recognize Inoperable Reactor Afd Monitor.Caused by Personnel Error.Operators Involved in Event Will Be Counseled Prior to Assuming Shift duties.W/970711 Ltr ML18012A8301997-07-0808 July 1997 LER 97-016-00:on 970608,reactor Trip Occurred Due to Personnel Error in Adjusting Power Range (Pr) Nuclear Instrumentation (Ni).Issued Night Order Prohibiting Pr Ni Adjustment When Redundant Channel inoperable.W/970708 Ltr ML18012A8241997-07-0202 July 1997 LER 97-015-00:on 970602,inadequate Auxiliary Feedwater Sys Flow Control Valve Surveillance Testing Deficiency Was Identified.Caused by Failure to Recognize Impact on TS 4.7.1.2.1.Readjusted AFW FCV Actuator spring.W/970702 Ltr ML18022B0181997-06-13013 June 1997 LER 97-014-00:on 970514,SI Occurred During Ssps Surveillance Testing.Caused by Inattention to Detail During Recent Rev to Surveillance Test Procedure Being Used.Revised Deficient Surveillance procedures.W/970613 Ltr ML18012A8081997-06-0909 June 1997 LER 97-013-00:on 970508,entry Into Mode-6 Without Operable Components,Resulting in TS 3.0.4 Violation Occurred.Caused by Personnel Error.Personnel Involved counseled.W/970609 Ltr ML18012A8021997-06-0606 June 1997 LER 97-023-02:on 961114,design Deficiency Was Identified in Emergency DG Protection Circuitry.Caused by Inadequate Plant Design.Revised Surveillance Test Procedures OST-1013 & OST-1073.W/970606 Ltr ML18012A8011997-06-0404 June 1997 LER 97-012-00:on 970505,determined That Previous Auxiliary Control Panel Had Not Verified Operability of Interposing Relays.Caused by Misinterpretation of Tss.Reviewed Other Remote Shutdown Panel Transfer circuitry.W/970604 Ltr ML18012A7951997-05-29029 May 1997 LER 96-023-01:on 961114,design Deficiency in EDG Protection Circuitry Was Identified.Caused by Inadequate Original Plant Design.Surveillance Test Procedures OST-1013 & OST-1073 revised.W/970529 Ltr ML18012A7891997-05-22022 May 1997 LER 97-011-00:on 970422,inappropriate TS Interpretation Resulted in Violations of ECCS Accumulator TS & Entry Into TS 3.0.3.Caused by Procedural Inadequacy.Tsi 88-001 Cancelled 970508 & Procedures revised.W/970522 Ltr ML18012A7871997-05-19019 May 1997 LER 97-010-00:on 970418,design Deficiency Determined Re Reactor Coolant Pump Motor Oil Collection Sys.Caused by RCP Ocs Design Detail.Rcp Ocs Enclosures for Each of Three Installed RCP Motors Have Been modified.W/970519 Ltr ML18012A7761997-05-0707 May 1997 LER 97-009-00:on 970407,fuse Was Removed from CR Ventilation Isolation Signal Power Supply Circuitry Due to Personnel Error.Individuals Involved Were counseled.W/970507 Ltr ML18012A7751997-05-0505 May 1997 LER 97-008-00:on 970404,safety-related AHU Not Declared Inoperable During Maintenance on Associated Temperature Switches Resulting in Violation of Ts.Caused by Incorrect Interpretation.Operations Night Order issued.W/970505 Ltr ML18012A6291997-04-24024 April 1997 LER 97-007-00:on 970325,inoperable CCW Sys TS 3.0.3 Entry Made.Caused by Combination of Procedural Inadequacies, Improper Use of Procedure Guidance & Poor Communication. Applicable Individuals counseled.W/970423 Ltr ML18022B0151997-04-17017 April 1997 LER 97-006-00:on 970318,breach Was Identified in Thermo-Lag Fire Barrier Wall Due to Inadequate Initial Design,Poor Construction Methods & Incomplete as-built Design.Visual Insp of Thermo-Lag Barrier Walls performed.W/970417 Ltr ML18012A6041997-04-0303 April 1997 LER 97-004-00:on 970304,in-plant Spent Fuel Cask Handling Activities Conducted Outside Design Basis.Caused by Lack of Understanding of Requirements.Operations Placed on Hold Pending NRC Review & Approval of procedures.W/970331 Ltr ML18012A6031997-03-31031 March 1997 LER 97-003-00:on 970227,steam Generator Low Level Protection Circuitry Outside Design Basis Occurred.Caused by Inadequate Failure Modes & Effects Analysis Performed as-built Piping Configuration for S/G Level.Review performed.W/970331 Ltr 1999-09-10
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML18017A9181999-10-0808 October 1999 LER 99-008-00:on 991008,CR Emergency Filtration Sys Tech Specs Occurred.Caused by Site Personnel Failed to Recognize That Blocking Open CR Emergency Filtration Sys.Procedures Revised.With 991008 Ltr ML18017A9151999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Shearon Harris Npp. with 991012 Ltr ML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data ML18017A8671999-09-10010 September 1999 LER 99-007-00:on 990811,determined That Cvis ARMs High Alarm Setpoints Were Not within TS Limit.Caused by Not Having Procedure to Verify If Cvis ARM High Alarm Setpoints Were within TS Requirements.Revised Procedures.With 990910 Ltr ML18017A8621999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Harris Nuclear Plant.With 990908 Ltr ML18016B0481999-08-0404 August 1999 LER 99-006-01:on 981124,noted Failure to Comply with TS 4.0.4 & TS 3/4.6.3, Civs. Caused by post-maint Testing That Did Not Adequately Test Control Circuitry & Verify Isolation Time Following Maint.Procedure Was Revised ML18017A8361999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Shearon Harris Nuclear Power Plant.With 990811 Ltr ML18016B0151999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Shearon Harris Npp. with 990713 Ltr ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML18016A9801999-06-0404 June 1999 LER 99-006-00:on 981124,failed to Comply with TS 4.0.4 & TS 3/4.6.3, Civ. Caused by post-maint Testing That Did Not Adequately Test Control Circuitry & Verify Isolation Time Following Maint.Procedure Will Be Revised.With 990604 Ltr ML18016A9851999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Shearon Harris Nuclear Plant,Unit 1.With 990614 Ltr ML18017A8981999-05-12012 May 1999 Technical Rept Entitled, Harris Nuclear Plant-Bacteria Detection in Water from C&D Spent Fuel Pool Cooling Lines. ML18016A9581999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Shearon Harris Nuclear Plant,Unit 1.With 990513 Ltr ML18016A9011999-04-12012 April 1999 Part 21 Rept Re Defect in Component of DSRV-16-4,Enterprise DG Sys.Caused by Potential Problem with Connecting Rod Assemblies Built Since 1986,that Have Been Converted to Use Prestressed Fasteners.Affected Rods Should Be Inspected ML18016A9111999-04-12012 April 1999 LER 99-005-00:on 990313,plant Exceeded ESFAS TS 3.3.2,Action 21.Caused by Inadequate Procedure Rev Preparation.Licensee Revised Applicable Maint Surveillance Test Procedure (MST-10072) to Identify TS Required Actions.With 990412 Ltr ML18016A8971999-04-0808 April 1999 LER 99-004-00:on 990312,unit Trip Was Noted.Caused by Degraded Condition of SG Water Level Flow Control Valve. Replaced Positioners on All Three FW Regulating Valves.With 990408 Ltr ML18016A8941999-04-0505 April 1999 Revised Pages 20-25 to App 4A of non-proprietary Version of Rev 3 to HI-971760 ML18016A9101999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Shearon Harris Nuclear Power Plant.With 990413 Ltr ML18016A8661999-03-31031 March 1999 Shnpp Operator Training Simulator,Simulator Certification Quadrennial Rept. ML18017A8931999-02-28028 February 1999 Risks & Alternative Options Associated with Spent Fuel Storage at Shearon Harris Nuclear Power Plant. ML18016A8551999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Shearon Harris Npp. with 990312 Ltr ML18016A8261999-02-22022 February 1999 LER 99-003-00:on 990123,noted That Plant Was Outside Design Basis Due to Isolation of Fire Protection Containment Sprinkler Sys.Caused by Human Error.Restored Containment Sprinkler Sys to Operable Status.With 990222 Ltr ML18016A8531999-02-18018 February 1999 Non-proprietary Rev 3 to HI-971760, Licensing Rept for Expanding Storage Capacity in Harris SFP 'C' & 'D'. ML18016A8111999-02-12012 February 1999 LER 99-002-00:on 990114,RT Due to Not Removing Temporary Device from Relay Following Calibration Was Noted.Caused by Human Error.Counseled Personnel Involved in Event.With 990212 Ltr ML18016A7971999-02-0505 February 1999 LER 99-001-00:on 990106,SF Pool Water Level Was Not Maintained Greater than 23 Feet Above Stored BWR Fuel Assemblies.Caused by Fasteners Bending Under Specific Circumstances.Increased Water Level.With 990205 Ltr ML18022B0631999-02-0404 February 1999 Rev 0 to Nuclear NDE Manual. with 28 Oversize Uncodable Drawings of Alternative Plan Scope & 4 Oversize Codable Drawings ML20202J1161999-02-0101 February 1999 SER Accepting Relief Requests Associated with Second 10-year Interval Inservice Testing Program ML18016A8041999-01-31031 January 1999 Monthly Operating Rept for Jan 1999 for Shearon Harris Nuclear Power Plant.With 990211 Ltr ML18016A7941999-01-29029 January 1999 LER 98-004-01:on 980313,identified Design Deficiency Re Potential Runout of Tdafwp.Caused by Inadequate Original AFW Sys Design.Operability Evaluation Was Completed on 980313 & Addl Engineering Analysis Was Performed by Vendor ML18016A7801998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Shearon Harris Npp. with 990113 Ltr ML18016A7671998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Shnpp,Unit 1.With 981215 Ltr ML18016A9731998-11-28028 November 1998 Changes,Tests & Experiments, for Harris Nuclear Plant.Rept Provides Brief Description of Changes to Facility & Summary & of SE for Each Item That Was Implemented Under 10CFR50.59 Between 970608-981128.With 990527 Ltr ML18016A8351998-11-28028 November 1998 ISI Summary 8th Refueling Outage for Shearon Harris Power Plant,Unit 1. ML18016A7411998-11-25025 November 1998 Rev 1 to Shnpp Cycle 9 Colr. ML18016A7211998-11-17017 November 1998 LER 98-007-00:on 981023,turbine Control Anomaly Caused Manual Rt.Caused by Failure to Incorporate Verbal Vendor Guidance in Operating Procedures.Addl Vendor Guidance Will Be Verified & Added to Procedures.With 981117 Ltr ML18016A7071998-11-0303 November 1998 Rev 0 to Harris Unit 1 Cycle 9 Colr. ML18016A7201998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Shearon Harris Nuclear Power Plant.With 981113 Ltr ML20154F8701998-10-0606 October 1998 Safety Evaluation Authorizing Proposed Alternative to Requirements of OMa-1988,Part 10,Section 4.2.2.3 for 21 Category a Reactor Coolant Sys Pressure Isolation Valves ML18016A6201998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Harris Nuclear Power Plant.With 981012 Ltr ML18016A5971998-09-21021 September 1998 Rev 1 to Harris Unit 1 Cycle 8 Colr. ML18016A5881998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Shnpp,Unit 1.With 980914 Ltr ML18016A5071998-07-31031 July 1998 Monthly Operating Rept for Jul 1998 for Shearon Harris Nuclear Plant.W/980811 Ltr ML18016A9431998-07-0707 July 1998 Rev 1 to QAP Manual. ML18016A4841998-07-0707 July 1998 LER 97-002-01:on 970207,determined That Cold Weather Conditions Resulted in Mfiv Being Potentially Inoperable During Period 970117-20.Caused by Inadequate Design of HVAC Sys.Implemented Mods to Steam Tunnel HVAC Sys ML18016A9371998-06-30030 June 1998 Technical Rept on Matl Identification of Spent Fuel Piping Welds at Hnp. ML18016A4861998-06-30030 June 1998 Monthly Operating Rept for June 1998 for SHNPP.W/980715 Ltr ML18016A4701998-06-30030 June 1998 LER 97-021-03:on 980210,discovered That SFP Water Level Had Not Been Verified Greater than 23 Feet Above BWR Fuel Assemblies.Caused by Misinterpretation of TS Requirements. Will Submit TS Change Request to Revise TS 3.9.1.11 ML18016A4491998-06-0808 June 1998 LER 98-006-00:on 980508,failure to Perform Insp & Preventive Maint on MCCB as Required by TS Was Noted.Caused by Inadequate Sps.Tested 9 Pressurizer Heater Bank Breakers by Cycling each.W/980608 Ltr ML18016A4521998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Shearon Harris Nuclear Power Plant.W/980612 Ltr ML18016A7711998-05-26026 May 1998 Non-proprietary Rev 2 to HI-971760, Licensing Rept for Expanding Storage Capacity in Harris Spent Fuel Pools 'C' & 'D'. 1999-09-30
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ACCELERATED DI<UTION DEMON 4TION SYSI"EI'.4i REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:8912130259 DOC.DATE: 89/12/08 NOTARIZED:
NO FACIL:50-400 Shearon Harris Nuclear Power.Plant, Unit 1, Carolina AUTH.NAME.AUTHOR AFFILIATION HOWE,A.J.Carolina Power&Light Co.RICHEY,R.B.
Carolina Power&Light Co.RECIP.NAME RECIPIENT AFFILIATION DOCKET 05000400 05000400
SUBJECT:
LER 89-017-01 on 891009,electrical fault on main generator output bus causing plant trip&fire damage in turbine bldg.W/8 ltr.DISTRIBUTION CODE IE22T COPIES RECEIVED LTR ENCL SIZE TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.NOTES:Application for permit'enewal filed.RECIPIENT ID CODE/NAME PD2-1 LA BECKER,D COPIES LTTR ENCL 1 1 1 1 RECIPIENT ID CODE/NAME PD2-1 PD COPIES LTTR ENCL 1 1 INTERNAL: ACRS MICHELSON ACRS WYLIE AEOD/DS P/TPAB DEDRO NRR/DET/EMEB9H3 NRR/DLPQ/LHFB11 NRR/DOEA/OEAB11 NRR/DST/SELB 8D NRR/DST/SPLB8D1 NUDOCS-ABSTRACT RES/DSIR/EIB 1 1 ACRS MOELLER 1 1 AEOD/DOA 1 1 AEOD/ROAB/DSP 1 1 NRR/DET/ECMB 9H 1 1 NRR/DET/ESGB 8D 1.1 NRR/DLPQ/LPEB10 1 1 NRR/DREP/PRPB11 1 1.NRR/DST/SICB 7E 1 1 NRR/~DTJSRXB 8E 1 1 REG FIL~02 1 1 GN2~ILE 01 2 2 1~1 2 2 1 1 1 1.1 1 2 2 1 1 1 1 1 1 1 1 EXTERNAL: EG&G WILLIAMS,S LPDR NSIC MAYS,G NUDOCS FULL TXT 4 4 1 1 1 1 1 1 L ST LOBBY WARD NRC PDR NSIC MURPHY,G.A 1 1 1 1 1 1 NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTETH CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT.20079)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISIS FOR DOCUMENTS YOU DON'T NEEDl FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 38 ENCL 38 0 Carojjna Power&Ught Company P.O.Box 165~New Hill~N.C.27562 R.B.RlCHEY Manager Hanta Nuclear Project OEC 0 8 1989 File Number.SHF/10-13510C Letter Number.'0-890135 (0)U.S.Nuclear Regulatory Commission ATTN: NRC Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 DOCKET NO.50-400 LICENSE NO.NPF-63 LICENSEE EVENT REPORT 89-017-01 Gentlemen'.
In accordance with Title 10 to the Code of Fedeial Regulations, the enclosed Licensee Event Report is submitted.
The original report.fulfilled the requirement for a written report'ithin thirty (30)days of a reportable occurrence and is in accordance with the format set forth in NUREG-1022, September 1983.This supplemental report provides final conclusions as to the cause of the event from the long term investigation.
RBR:djs Enclosure Very truly yours, cmH~~R.B.Richey, Manager Harris Nuclear Project cc: Mr.R.A.Becker (NRR)Mr.S.D.Ebneter (NRC-RII)Mr.J.E.Tedrow (NRC-SHNPP)8912130259 S91009 t='DR ADOCI<0=000400 PDC MEM/LER-017-01/1/OS1 NRC FORM 366 (649)U.S.NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT{LER)APPROVED OMB NO.31500104 EXPIRES'/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REQUEST: 500 HRS.FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (P430), U.S.NUCLEAR REGULATORY COMMISSION.
WASHINGTON.
DC 20555, AND TO THE PAPERWORK REDUCTION PRO/ECT (31500104), OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, OC 20503.FACILITY NAME (1I SHEARON HARRIS NUCLEAR POWER PLANT DOCKET NUMBER l2)PA E 0 5 0 0 0 4 O O 1 OF O 8/VZkfRICAL FAULT ON HAIN GENERATOR OUTPUT BUS CAUSING PLANT TRIP AND FIRE DAMAGE IN EVENT DATE ISI LER NUMBER (6)REPORT DATE (7)OTHER FACILITIES INVOLVED ISI MONTH DAY YEAR YEAR ec'2 SEQUENTIAL NVMSER'A'xc RNvtsr0rs ISVMSER MONTH OAY YEAR FACILITY NAMES DOCKET NUMBER(S)0 5 0 0 0 1 2 8 9 0 5 0 0 0 OPERATING MODE (9)POWER LEVEL (10)THIS REPORT IS SUBMITTED PURSUANT 7 50.73(~)l2)(ivl 50.73(~l(2)hl 50.73(~)(2)(vN)20AOS(c)50.36(c)Ill 50.36(cl(2) 50.73(~l(2)(I)50,7 3(e I (2)IN)50.73(~)(2)IN(I 20A02(8)20A05(~)(1)IB 20A05(e)(1)
INI 20A05(~)(1)INI)20A05(e l(1)(N)20.i05(el(ll(vl 50,73N)(2)(vIII)(Al 50.7 3 I~)(2)(viN)(Bl 50,73 (e I (2)(el I.ICENSEE CONTACT FOR THIS LER 02I 0 THE REQUIREMENTS OF 10 CFR (I:/Check one or more ol the/ollow)np/
(11)73.71GII 73.71(cl QTHER/Speclly/n Atrstmct Oe/orv enrp/n Test, HI/C Forth 3SSAI NAME W.OW R.PECIALIST TELEPHONE NUMBER AREA CODE 91 9362-2 71 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (\3)CAUSE SYSTEM COMPONENT MANUFAC.TVRER*COMPONENT MANUFAC-TURER TO HPIIOS E L N/A C E X F M R W 1 2 0 N B E L C T W 1 2 0 N X B A T AC A12 3 Y Pc'c(SÃ%%:':
SUPPLEMENTAL REPORT EXPECTED (1i)YF 5 III yes, complete EXPECTED SI/Eht/SSIDH DATE/NO ASSTRACT/Limit to tc00 sprees, I e., epprovlmcrcry I/lreen s/npleepece typevrrltten lintel I)8)EXPECTED SU 8 MI SS ION DATE R6I MONTH DAY YEAR On October 9, 1989, at 2305, a generator and main power transformer phase differential relay tripped the lockout relay of the main generator, tripping the generator and cnusing a turbine nnd reactor trip from 1004 power.The reactor was stabilized in hot standby at 557'on auxiliary feedwater and condenser steam dumps.Actuation of the generator and main power transformer differential relay and subsequent generator trip was caused by multiple ground faults.The ground faults destroyed the neutral grounding bus and caused three fires: an oil fire at the<<B'r main power transformer, a hydrogen fire underneath the main generator and a third small oil fire in the generator housing.An alert was declared, and the site" fire brigade responded to the fires, assisted Inter by off site fire departments, All fires appeared out by 0145, and the emergency condition was terminated at 0245.The initiator of the ground faults has been identified as aluminum debris in the isolated phase bus duct, which was deposited in the bus duct from previous failures of the duct cooling system dampers.Arcing from the aluminum debris in the bus led to a double phase to ground fault at the<<B<<main power transformer, Magnetic forces from this fault broke insulators in r'A'r phase and<<B'1 phase of the isolated phase bus duct.The<<A<<phase conductor contacted the bus enclosure creating another ground fault, These faults elevated the voltage at the generator neutral and led to another ground fault in the neutral grounding transformer cubicle, The turbine-driven auxiliary feedwater pump started after the reactor trip, but the pump tripped shortly thereafter', The cause of the trip is believed to be n spurious overspeed trip signal from the tachometer.
Design changes nnd repairs are being conducted while the plant conducts a refueling outage.NRC Form 366 (669)
,NRC FORM 366A 1649)i U.S.NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT ILER)TEXT CONTINUATION t APPROVED OMB NO.31500104 EXPIRES: 4/30/92 ESTIMATED BUADEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REQUEST: 500 HRS.FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH IP430), U.S.NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO 1HE PAPERWORK REDUCTION PROJECT 13150d104), OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.FACILITY NAME I'I)DOCKET NUMBER (2)LER NUMBER PS)PAGE 13)SHEARON HARRIS NUCLEAR POWER PLANT TEXT/I/mare 4/rece/4>>qu/rer/
u>>eddIo'onal HRC Farm Sr/MS/117)INITIAL CONDITIONS:
o s o o o 4 00 YEAR@c'.sEQUENTIAL Qa NUMSSR 017 REVISION NUMSSR 0 102 OF 0 8 The plant was operating at 100X power, 885 MWe net, on October 9, 1989.EVENT DESCRIPTION:
At 2305, a generator and main power transformer differential relay trip caused a generator lockout relay trip, which resulted in the following:
(1)the main generator output breakers and the generator exciter breaker tripped, (2)on-site power transferred from the unit auxiliary transformers to the startup transformers, and (3)the turbine tripped.A reactor trip directly occurred on the turbine trip, with all rods inserting into the core.Response to the trip was as expected;the main feedwater pumps tripped during the transient and the auxiliary feedwater (AFW)system actuated properly, the main steam isolation valves were manually closed to limit the cooldown.The turbine-driven AFW pump tripped shortly after it started, but the two 100X capacity motor-driven AFW pumps were available throughout the event.The turbine-driven AFW pump was capable of manual restart from the control room, but it was not needed during the event.At 2309, the Control Room received reports of two flashes having'ccurred, one at the"B" main power transformer, and the other on the second level of the turbine deck underneath the main generator.
The site fire brigade was activated, and brigade personnel reported fires at the"B" main power transformer, at the main generator housing on the top level of the turbine deck, and a hydrogen fire on the second level of the turbine deck underneath the main generator.
Off site fire departments were contacted to assist in the fire fighting efforts.At 2335, an alert was declared due to the release of flammable gas into the site protected area.At 2341, the state and local government emergency response officials were notified.Plant personnel were notified to activate the Technical Support Center (TSC).By 0013, the fire at the generator housing had been extinguished, the fire at the main power transformer was believed extinguished by actuation of the deluge system (a small oil fire was later determined to still be burning, and was extinguished using a dry chemical extinguisher), and the hydrogen fire underneath the generator was reported under control, with hydrogen to the main generator isolated.All visual flames at all three fire locations were extinguished by 0145.At 0245 when all fires were verified extinguished by walkdowns, fire watches were set, and the main generator was being purged with carbon dioxide, the alert was terminated.
NAC Form 366A)649)
,NRC FORM 368A (64)9)U.S.NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)TEXT CONTINUATION t APPROVED 0MB NO.31500104 E XP I R E S: 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REOUESTI 50.0 HRS.FORWARDCOMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH IP4)30), U.S.NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (31504104).
OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.FACILITY NAME u)DOCKET NUMBER (2)YEAR LER NUMBER (6)SEOUENTIAL NUMBER j~j1~'EVISION
'o:PJ NUMBER PAGE (3)SHEARON HARRIS NUCLEAR POWER PLANT TEXT fit moro e>>oo ir roordrod.IIBB ddrS)lono//YRC Form 3554'4/(12)PLANT DBSIGM: o s o o o 4 o 017 0 1 0 3 pF0 8 The main generator is designed with the neutral of the wye grounded through a single phase transformer.
The secondary side of this transformer is connected to a high resistance network.With this design, a single phase fault to ground of the main generator output results in a small current flow through the neutral grounding transformer and its high resistance bank.A ground detection relay will actuate to isolate the fault by tripping the main generator, exciter field breaker and the generator output breakers.CAUSE: The initiator of the event was multiple ground faults in the"delta" section of the isolated phase bus duct near the"B" phase main power transformer.
Refer to Attachment A,"Physical Layout of SHNPP Generator Output." These ground faults were apparently caused by aluminum debris carried down the bus~duct.by the forced air cooling system.The'aluminum debris entered the bus duct as a result of previous damper failures in the bus duct cooling system.These failures occurred on February 27, 1988, and in the summer of 1989.Arcing between the conductor and the enclosure occurred over a fifty (50)foot length of the"A".phase, bus immediately upstream of the"B" main power transformer.
Ionization from this arcing reduced the dielectric strength of the cooling air, which,was carried into the bushing box of the HB" main power transformer.
-This caused an"A" phase',,to ground flashover in the bushing box, which, immediately propagated
'to.the.".B"'phase bushing.The fault cracked both low voltage bushings, causing oil to'leak from the bushings, and ignited the'eaking oil.The fault at the HB" main power transformer creat'ed magnetic forces in the main section of the isolated phase bus that broke insulators (Original Manufacturer:
Westinghouse; model 113C417A01, and 133C387A01; currently supplied by Delta Unibus)in"A" and"B" phase.The 23" diameter tubular conductor is suspended in the middle of the 41" diameter aluminum enclosure by the ceramic insulators.
In the"A" bus duct five insulators pulled apart, allowing the conductor to come in contact with the ,grounded enclosure, creating a phase-to-ground fault.The faults in the HB" main power transformer bushing box and the"A" bus duct elevated the voltage of the generator neutral.A curxent transformer used for the main generator radio frequency monitor (Manufacturer'.
Westinghouse; model 608D56G01) is mounted around the neutral conductor inside the neutral grounding transformer enclosure.
The current transformer, which is at ground potential, is insulated from the neutral conductor by insulating tape wrapped around the neutral conductor.
When the voltage of the neutral became elevated, this tape failed to provide adequate insulation, and the neutral.faulted to ground.Axcing in the area burned holes in generator moisture N R 0 Form 368A (64)9)
NRC FORM 366A'(64)9)U.S.NUCLEAR REGULATORY COMMISSION i LICENSEE EVENT REPORT HLER)TEXT CONTINUATION APPROVED OMB NO.3)504))04 EXPIRES: 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REOUESTI 50.0 HRS.FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS ANO REPORTS MANAGEMENT BRANCH (P4)30), U.S.NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555.AND TO THE PAPERWORK REDUCTION PROJECT (31504104), OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON.
DC 20503.FACILITY NAME (1)DOCKET NUMBER (2)LER NUMBER (6)YEAR@3 SEOUENTIAL gxQ'EVISION NUMSER.r>i NUMSER PAGE (3)SHEARON HARRIS NUCLEAR POWER PLANT TExT///more eoece/4 n/Ir/rerL Iree I//oooo/HAc Form 36EAB/(12)CAUSE (continued) o s o o o 4 o 8 9 Ol 7 Ol 0 40F 0 8 detector piping located above the neutral grounding transformer cubicle.Hydrogen escaping from the piping was ignited by the arcing.This subsequently ignited an oil fire in the main generator housing above.The ceramic-insulators in the duct which support the bus conductor are located underneath the bus directly supporting it until the bus duct leaves the turbine'deck, after which the arrangement is inverted, so that the bus is suspended from the insulators.
This is per design documents for all three bus ducts.Testing of the insulators removed from the bus duct confirmed their adequacy for this application.
The current transformer for the radio frequency monitor was a vendor supplied modification to the neutral grounding network, and was properly installed per design.The bus duct cooling system dampers wer'e apparently undersized for their application.
Replacement dampers will be of more substantial construction.
Prompt response by site personnel and the early decision to obtain off site assistance is credited in limiting the potential damage to plant equipment.
The damage to plant equipment was as follows: main generator:
neutral bushings and current transformers, external housing, and the exciter end seal oil piping, generator moisture detection piping'"B" main power transformer'.
bushings and connections to the isolated phase bus ducts"A" isolated phase bus duct neutral grounding transformer neutral grounding bus radio frequency monitor miscellaneous cabling and piping in the vicinity The cause of the TDAFW pump trip was investigated on the following day.A review of the data indicates no overspeed condition occurred when the pump*started.A test was performed to simultaneously start all three AFW pumps with steam generator pressure near the pressure existing immediately after the reactor trip', no overspeed trip occurred, and suction pressure on the header common to all three pumps did not decrease significantly.
NRC Form 366A (64)9)
NRC FORM 386A'(649)U.S.NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT ILER)TEXT CONTINUATION t APPROVEO OMB NO.31504(04 EXPIRES.1/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REOUESTI 50JI HRS.FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (F430).U.S.NUCLEAR REGULATORY COMMISSION, WASHINGTON, OC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (3150410$), OFFICE OF MANAGEMENT AND BUDGET.WASHINGTON.
DC 20503.FACILITY NAME (1)SHEARON HARRIS NUCLEAR POWER PLANT TEXT/llrrrrrrE g>>ce/En/I/rrrrL IIJB///BBr>>JHRC%%dnn36643/(12)
CAUSE (continued)
DOCKET NUMBER (2)o s o o o 4 YEAR 8 9 LER NUMBER (8)EEOUENTIAL NUMBER 0 1 7 REvr$roN NUMBER 0 1 PAGE (3)0 5 OF 0 8 Based on recent experience during testing of the pump, it is believed that the tachometer (Manufacturer'.
Airpax', model 080-321-3X10) which actuates the electrical overspeed trip of the TDAFW pump may be providing spurious trip signals.The design of the tachometer provides two separate outputs, such that the channel experiencing spiking could trip the pump, while the other channel providing indication would show no malfunction..
SAFETY SIGNIFICANCE:
The plant response to the generator trip was as expected, wi.th the reactor stabilized in hot standby on AFW and condenser steam dumps.The unavailability of the TDAFW pump did not compromise safety since the motor-driven AFW pumps were available and operated throughout the event.The fires and the related damage were limited to the non-safety portions of the plant.No injuries occurred due to the fires.No previous fires within the protected area have occurred.Pr'eviously reported trips of the TDAFW pump had been attributed to moisture accumulation in the steam supply lines.Based on recent testing and data collection from this event, as well as the testing performed following this event, moisture accumulation is no longer believed to be the cause of the trips.The data shows that the actual speeds of the turbine may have exceeded the previous setpoint of the electrical overspeed trip in effect during previous events.The trip which occurred for this event was not an actual turbine overspeed as shown by the data.This event is reported under 10CFR 50.73(a)(2)(iv) as an actuation of engineered safety features, and under 10CFR 50.73(a)(2)(iv) due to the fire and release of hydrogen gas.CORRECTIVE ACTIONS: 1.The main power transformers were inspected and tested, and no significant damage, other than to the bushings and connections of the"B" transformer, was found.2.The generator has been fully tested and repairs are being made as necessary prior to generator restart.Inspections and testing have revealed no significant damage to the generator.
3.All other damaged components will be repaired prior to generator restart during the current refueling outage.NRC Form 388A (689)
NRC FORM 388A (6 J)9)i U.S.NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)TEXT CONTINUATION APPROVED 0MB NO,31500(oi EXPIRES: 8/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REOUEST: 50A)HRS.FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (P830), U.S.NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO 1NE PAPERWORK REDUCTION PROJECT (3(500104), OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.FACILITY NAME (I)DOCKET NUMBER (2)LER NUMBER (8)yEAR~~@'EQVENTrAL
~'VSN NVMSErr J>~C NUMBErl PAGE (3)SHEARON HARRIS NUCLEAR POWER PLANT TEXT///moro<<>>co/r Jo//r'orL rrro or/r//bono/HRC
%%dnn 35543/(IT)CORRECTIVE ACTIONS (continued) o s o o o 4 00 89 0 17 0 1 06 QF 0 8 4.The design of the isolated phase bus duct bus supports has been evaluated and found to be adequate.However, the sections in which the conductor supports failed has been-rotated 180'o place the supports underneath the conductor as a prudent design measure.The damaged duct has been replaced.5.The design of the radio frequency monitor current transformer has been revised to ensure it'an withstand expected conditions under ground faults, and it will be replaced.6.The design of the isolated phase bus duct cooling system has been evaluated and revised to preclude debris intrusion into the ducts.7.The TDAFW pump tachometer electronic trip function was evaluated as unnecessary to protect against overspeed and its trip function will be deleted.ADDITIONAL INFORMATION ON EMERGENCY RESPONSE: This event was declared an alert by the Shift Foreman, and the Technical Support Center (TSC)was required to be activated.
Certain specific requirements for achieving augmentation of the plant staff detailed in the Emergency Plan were not met.In particular, the Accident Assessment Team and Damage Control Team are required to meet certain staffing levels at a 45 minute elapsed time and a 75 minute elapsed time, following activation.
Initial activation of the pagers for TSC members was delayed due to the pre-planned absence of the on shift clerk, who normally performs this duty.Alternative personnel were not as familiar with the pager procedures.
The Accident Assessment Team leader did not hear his pager, and additional time was spent to contact backup individuals.
The Damage Control Team leader did not contact additional personnel for the team prior to his reporting to the TSC.The following corrective actions will be taken to correct these deficiencies:
1.Additional training on pager activation will be provided to appropriate shift personnel.
2.Additional instructions will be given to all personnel carrying pagers who must in turn call additional personnel.
3.An unannounced augmentation drill will be conducted to verify the effectiveness of the above corrective actions.NRC Form 388A (M9)
NRC FORM 366A'(64)9)i U.S.NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)TEXT CONTINUATION APPROVED OMB NO.3(500104 EXPIRES: 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REQUEST: 50A)HRS.FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (P4)30), U.S.NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (31504)104), OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.FACILITY NAME Ol DOCKET NUMBER (2)YEAR LER NUMBER (6)SEQUENTIAL NUMBER REVISION NUMBER PAGE (31 SHEARON HARRIS NUCLEAR POWER PLANT TEXT ill mare<<reae/4 nrtu/rerL uee er///haarre/NRC Farm 35649/(IT)HZIS CODES: 0 s o o p 4 008 9 0 l 7 0 1 0 7 pF 0 8 Main Generator TB Generator Mater Detector Neutral Grounding Transformer TL EL:XFMR Radio Frequency Monitor Current Transformer EL:XCT Electrical Support Isolated Phase Bus Ducts Main Transformers EL:BDUC EL:XFMR Startup Transformers Unit Auxiliary Transformers Main Feedwater Auxiliary Feedwater TDAFW Pump Tachometer Main Steam Isolation Valves FK'XFMR FK:XFMR SJ BA BA TAC SJ:ISV NRC Farm 366A (669)
PHYSICAL LAYOUT OF SHNPP GENERATOR OUTPUT TURBINE FIRE ALSO IN GENERATOR HOUSING 6 GENERATOR EL.514'A'HASE BUS CCtmUCTOR CONTACTS DUCT, SHORTING.TO GROUND DEBRIS IS CARRIED D9ÃN BUS DUCT BY COOLING AIR FLOW CAUSING t1ULTIPLE GROUND FAULTS TOUAT's IONIZED AIR FROt1 DUCT FAULT SHORTS 8'RANSFORtIER CONNECTORS TO GROUND IGNITIHG ANOILFIRE 0 0 0 2 OOOO OOOO FAILURE OF PIPING FRO1 ARCING IGNITES HYDROGEN F IRE WDER GENERATOR CT IN NEUTRAL GROUNDING 4 TRANSFCRt1ER SHCRTS TO GROUND.GROLNDIHG NEUTRAL BUS AND INITIATING HIGH FAULT CURRENTS.NEUTRAL BUS BUS DUCT EL.286'EUTRAL GRCUNDING TRANSFORt1ER GROUND LEVEL EL 261'UPPORTS (TYPICAL)00 0 000 0 0 0 0 OOOO 000 HAIN TRANSFORMERS 00 IS 00 00 M I 0 O'4 Co I