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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
[Table view] |
Text
CATEGORY 1 REGULATOr INFORMATION DISTRIBUTION STEM (RIDS)-
4ACCEBEION NBR:9603050326 DOC DATE: 96/03/01
~ NOTARIZED: NO DOCKET 6 FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina 05000400 AUTH. NAME- AUTHOR-AFFILIATION VERRILLI,M. --Carolina Power 6 Light Co.
DONAHUE,J.W. Carolina Power 6 Light Co.
RECIP.NAME RECIPIENT AFFILIATION
SUBJECT:
LER 96-002-01:on 960201,failed to properly perform TS surveillance testing. Caused by personnel error. Counseled personnel & revised procedure.W/960301 ltr.
DISTRIBUTION CODE: ZE22T COPIES RECEIVED:LTR ENCL SIZE:
TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.
E [
NOTES:Application for permit renewal filed. 05000400 8
RECIPIENT COPIES REC1PIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-1 PD 1 1 LE,N 1 1 INTERNAL: ACRS 1 1 AEOD/SPD RAB 2 2 Y AEOD/SPD/RRAB 1 1 NT 1 1 NRR/DE/ECGB 1 1 NR D EELB 1 1 NRR/DE/EMEB 1 1 NRR/DRCH/HHFB 1 1 NRR/DRCH/HICB 1 1 NRR/DRCH/HOLB 1 1 NRR/DRCH/HQMB 1 1 NRR/DRPM/PECB 1 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 .1 RES/DSZR/EIB 1 1 RGN2 FILE 01 1 1 D EXTERNAL: L ST LOBBY WARD 1 1 LITCO BRYCEZJ H 2 2 0 NOAC MURPHYiG.A 1' NOAC POORE,W. 1 1 r. i NRC PDR 1 1 NUDOCS FULL TXT 1 .1 C U
E N
NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK ROOM OWFN 5D-5(EXT. 415-2083) TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED/
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Carolina Power 8 Light Company Harris Nuclear Plant PO Box 165 New Hill NC 27562 U.S. Nuclear Regulatory Commission MAR 0 Serial: HNP-96-032 1 f996 ATTN: NRC Document Control Desk 10CFR50.73 Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 DOCKET NO. 50-400 LICENSE NO. NPF-63 LICENSEE EVENT REPORT 96-002-01 Gentlemen:
In accordance with Title 10 to the Code of Federal Regulations, the enclosed supplement to Licensee Event Report 96-002 is submitted. This supplement reports additional Technical Specification Testing deficiencies identified during the on-going Technical Specification testing program review.
Sincerely, J. W. Donahue General Manager Harris Plant MV Enclosure c: Mr. S. D. Ebneter (NRC - RII)
Mr. N. B. Le (NRC - PM/NRR)
Mr. D. J. Roberts (NRC - HNP)
'7603050326 96030i PDR ADOCK 05000400 S PDR 05OOVe State Road 1138 New Hill NC Pi@~
U. S. Nuclear Regulatory Commission Document Control Desk / HNP-96-032 Page 2 of 2 CC: Ms. P. B. Brannan Mr. R. K. Buckles (LIS)
Mr. W. R. Campbell (BNP)
Mr. J. M. Collins Mr. J. P. Cowan Mr. G. W. Davis Ms. S. D. Floyd Ms. S. F. Flynn Mr. H. W. Habermeyer, Jr.
Mr. G. D. Hicks (BNP)
Mr. M. D. Hill Mr. W. J. Hindman Mr. R. M. Krich (RNP)
Mr. P. M. Odom (RNP)
Mr. C. W. Martin (BNP)
Mr. R. D. Martin Mr. J. P. McKone Mr. J. W. Moyer (RNP)
Mr. W. R. Robinson Mr. G. A. Rolfson Mr. C. T. Sawyer Mr. R. S. Stancil G. M. Stokes
'r.
Mr. J. P. Thompson (BNP)
Mr. T. D. Walt HNP Real Time Training INPO NLS File: HI/A-2D (L. M. Randall)
Nuclear Records
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 FLB5) EXPIRES 04/30/BB ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS MANDATORY INFORMATION COLLECTION REOUEST: 5GD HRS. REPORTED lESSONS lEARNED ARE LICENSEE EVENT REPORT...(LER) DICORPORATEO INTO THE UCENSUIG PROCESS AND FEO BACK TO INDUSTRY.
FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE UIFORMATION ANO RECORDS MANAGEMENT BRANCH IT 6 F33L Us. NUCLEAR REGULATORY COMMISSIOIL (See reverse for required number of WASHDIGTON. OC 205550001, AND TO THE PAPERWORK REDUCTION PRIMECT 0150.
digits/characters for each block) 010)L OFFICE OF MANAGEMENT AND BUDGET, WASIUNGTON, OC 20503.
FAGILrrY NAME Il) DOCKET NUMBER I2) PAGE )3)
Harris Nuclear Plant Unit-1 50-400 1 OF 5 TITLE (4)
Failure to properly perform Technical Specification surveillance testing.
EVENT DATE {5) LER NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED (6)
FACILITYNAME DOCKET NUMBER SEOUENTIAL REVISION MONTH OAY MONTH BAY YEAR NUMBER NUMBER 05000 FACILITYNAME DOCKET NUMBER 2 01 96 96 002 01 1 96 05000 OPERATING THIS REPORT IS SUBMITTED,PURSUANT TO THE REQUIREMENTS OF 10 CFR 5: {Check one o r more} (11)
MODE (9) 20.2201(b) 20.2203(a) (2) (v) X 50.73{a)(2)(i) 50.73(a)(2)(viii)
POWER 20.2203(a) {1) 20.2203(a) (3) (i) 50.73(a)(2)(ii) 50.73(a) (2)(x) 1 oook LEVEL {10) 20.2203(a) (2) (i) 20.2203(a) (3)(ii) 50.73(a) (2) (iii) 73.71 20.2203(a)(2)(ii) 20.2203(a)(4) 50.73(a)(2)(iv) OTHER 20.2203(a)(2)(iii) 50.36(c) (1) 50.73(a)(2)(v) Specify In Abstract below or in NRC Form 366A 20,2203(a) (2) (iv) 50.36(c) (2) 50.73(a) (2) (vii)
LICENSEE CONTACT FOR THIS LER (12)
NAME TELEPHONE NUMBER linoiude Area Code)
Michael Verrilli Sr. Analyst - Licensing (919) 362-2303 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DES CRIBED IN THIS REPORT (13)
REPORTABLE REPORTABLE CAUSE SYSTEM COMPONENT MANUFACTURER CAUSE SYSTEM COMPONENT MANUFACTURER TO NPROS TO NPROS SUPPLEMENTAL REPORT EXPECTED (14) MONTH OAY EXPECTED YES SUBMISSION X (If yes, complete EXPECTED SUBMISSION DATE).
NO DATE {15)
ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single. spaced typewritten lines) (16)
On January 17, 1996, during a Technical,Specific"tion testing program review, a failure to perform required surveillance testing during a planned maintenance outage in October, 1994 was identified. Specifically, on October 30, 1994, the plant was shut down and taken to Mode-5 (Cold Shutdown). This outage exceeded 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and per Technical Specification requirements Engineered Safety Feature slave relay testing was required. To satisfy this requirement OST-1083 and OST-1084 were satisfactorily completed, however the slave relay circuits for the CSIP Alternate Mini-Flow Isolation Valves, 1CS-746 and 1CS-752 were not tested due to an error that occurred during a procedure revision in June 1993.
In September 1992, a plant modification was completed on the Charging/Safety Injection Pump (CSIP) Alternate Mini-Flow System that necessitated revisions to Operations Surveillance Test procedures OST-1083 and OST-1084. These revisions were completed in June 1993 and removed the slave relay testing for CSIP Alternate Mini-Flow Isolation Valves (1CS-746 and 1CS-752) from OST-1083 and OST-1084 and transferred the testing requirement to procedure OST-1809. The cause of the Technical Specification violation was personnel error during the June 1993 procedure revision process for OST-1083 and OST-1084. OST-1809 was successfully performed during Refueling Outage 6 on September 8, 1995. This test veriTied the operability of these circuits, thus no immediate corrective action was required upon identification of the deficiency. Additional corrective actions included personnel counseling, appropriate procedure revisions and the continuation of an in-progress Technical Specification testing program review.
Five additional Technical Specification testing deficiencies were identified during the on-going comprehensive Technical Specification testing program review and are being reported by this supplemental report.
NRC FOAM 36BA US. NUCLEAR REGULATOAY COMMISSION LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION FACILITY NAME (II DOCKET LEA NUMBEA (BI PAGE I3I SEOUENnAL REVISION YEAR NUMBER NUMBER
...Shearon Harris Nuclear Plant ~ Unit //1 50400 2 OF 5 96 - 002 - 01 TEXT Pr mort sport is rtrprarof. ost tditrdrool topitS ol iVRC Fam SBQI (IT)
EVENT DESCRIPTION:
On January 17, 1996, a failure to perform Technical Specification surveillance testing during an October 1994 planned maintenance outage was identified. The identification of this condition was a result of an on-going comprehensive Technical Specification testing program review that began in September 1995 folio'wing submittal of LER 95-07.
Specifically, on October 30, 1994, the plant was shut down and taken to Mode-5 (Cold Shutdown) for a planned maintenance outage. This outage exceeded 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and therefore, per Technical Specification 4.3.2.1 requirements, Engineered Safety Feature (ESF) slave relay testing was required for the 13 ESF relays delineated in Table 4.3-2 that had not been tested in the last 92 days due to being at full power operations. To satisfy this requirement OST-1083 and OST-1084 were completed on November 3, 1994. However, the slave relay circuits for the CSIP Alternate Mini-Flow Isolation Valves (ICS-746 and 1CS-752, EIIS Code BQ-ISV) were not tested due to an error that occurred during procedure revisions performed in June 1993 on Engineered Safety Feature (ESF) 18-Month Slave Relay Operations Surveillance Test procedures OST-1083 and OST-1084. This error involved inappropriately removing the slave relay testing for the 1CS-746 and 1CS-752 circuits from OST-1083 and OST-1084 and transferring the testing requirement to procedure OST-1809 (Refueling Water Storage Tank switchover to the Containment sumps), which is also an 18-month ESF response time test.
OST-1809 was not performed following the October maintenance outage, thus resulting in the testing omission and Technical Specification violation.
During the investigation of this event, personnel performing the Technical Specification testing program review verified tha OST-1809 had been successfully performed during Refueling Outage 6 on September 8, 1995, which verified the operability of the affected circuits.
The June 1993 revisions to OST-1083 and OST-1084 were performed to incorporate a plant modification (PCR-6547) on the Charging/Safety Injection Pump (CSIP) Alternate Mini-Flow lines. This modification removed the previously installed relief valves and provided an "open" signal to 1CS-746 and 1CS-752 upon receipt of a Safety Injection signal.
This condition was determined to be a violation of the Technical Specification surveillance test periodicity requirement and is being reported per 10CFR50.73(a)(2)(i)(b).
The following additional Technical Specification testing deficiencies have been identified by the on-going comprehensive Technical Specification testing program review:
Slave relays (K635 & K640) for the Auxiliary Feedwater (AFW) Flow Control Valves (EIIS BA-FCV) were not tested within their required quarterly surveillance interval following Refueling Outage (RFO) 5 in 1994 through RFO 6 in October 1995. This was a result of inadequate technical reviews associated with the plant modification (PCR-6502) that installed the auto-open signal to these valves. PCR-6502 specified the slave relay surveillance testing interval as once per 18 months per Technical Specification 4.7.1.2, but failed to identify the quarterly requirement contained in Technical Specification 4.3.2.1. Both of these relays were subsequently tested following RFO 6, which verified their operability. This condition was identified on February 1, 1996.
Testing for manual Safety Injection (SI, EIIS-BQ) and Containment Spray (CS, EIIS-BE) actuation has not fully tested all switch contacts within the required 18 month surveillance test interval per Technical Specification 4.3.2.1 The Operations Surveillance Test Procedures (OST-1825 & OST-1826) that verify the operability of the actuation circuits, only test one of the two manual actuation switches for each signal once per 18 months, thus resulting in the Technical Specification violation. The alternate test switch has been satisfactorily tested approximately once pe 36 months due to test performance staggering. Based on this previous testing, the SI and CS switches are currently operable. However, one set of CS switches will become inoperable on March 3, 1996 and one SI switch will become inoperable on March 19, 1996. This condition has existed since initial development of OST-1825 & OST-1826 and was identified on February 12, 1996.
RM 3 A (4- 5)
NRC FORM 366A US. NUCLEAR REGUlATORY COMMISBION
)6-65)
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION FACILITY NAME n) DOCKET LER NUMBER I6) PAGE 0)
SEOUENNAL REYIBION NUMBER NUMBER Shearon Harris Nuclear Plant - Unit //1 50400 3 OF 5 96 - 002 - 01 TEXT fffmoro spssoir foqvi od, vso sddI)d)vsf Sopd)S of hf)C Fosm 36atU Iir)
Quarterly surveillance testing was not performed for the "B" Charging/Safety Injection Pump Mini-Flow Isolation Valve (1CS-196) Slave Relay (K601) during Refueling Outage 6 in 1995. This slave relay should have been tested during the performance of OST-1086 in August of 1995, but the "B" CSIP was inoperable and 1CS-196 was under clearance at the time of the test. This was noted in the procedure, but the test was considered satisfactory by the operations control room staff due to a deficiency in the acceptance criteria section of OST-1086. The'acceptance criteria, which was changed during a recent procedure revision, did not specify the need to test the 1CS-196 slave
, relay, so no Equipment Inoperable Record was generated for tracking purposes, which would have required subsequent testing. The operability of the slave relay was successfully verified by performing OST-1086 in December 1995. This condition was identified on February 17, 1996.
Eleven Maintenance Surveillance Test (MST) Procedures were identified that did not verify automatic isolation of th effluent pathway on a loss of power for the associated radiation monitor as required by Technical Specification 4.3.3.10. This affected six radiation monitors and their related pathways. This testing omission was created when the MSTs were inappropriately revised in 1993 in an effort to eliminate procedure steps that were thought to be redundant and unnecessary. Inattention to detail and an incomplete understanding of the Technical Specification testing requirements for the radiation monitor circuitry caused the deficiency. The testing requirements for these radiation monitors were removed from Technical Specifications in May 1995, but due to the time frame of the deficiency, the condition constitutes a violation and is therefore included in this LER supplement. This condition was identified on February 14, 1996.
- 5. Proper overlap testing has not been performed for an actuation of the Fuel Handling Building Emergency Ventilation System (EIIS-VG) originating from a high radiation alarm signal, as per Technical Specification 4.9.12.
OST-1048 tests this feature, but does not include a particular section of cable (¹12913M-SA) between the North Spent Fuel Pool Radiation Monitor (RM-1FR-3567A-SA) and the South Spent Fuel Pool Radiation Monitor (RM-1FR-3564A-SA). This condition has existed since initial development of OST-1048 and was identified on February 19, 1996.
CAUSE:
The cause of the Technical Specification violation was personnel error during the June 1993 procedure revision process for OST-1083 and OST-1084. The testing requirements for the slave relay circuits for the CSIP Alteniate Mini-Flow Isolation Valves (1CS-746 and 1CS-752) were inappropriately transferred to OST-1809, which was not identified or scheduled as a Mode-5 "event related" surveillance test.
Cause For Additional Items Identified:
Item 1:
The failure to adequately test the K635 and K640 slave relays for the AFW Flow Control Valves was caused by inadequate technical reviews associated with plant modification PCR-6502. This resulted in deficient surveillance test procedures developed to verify the operability of the automatic open signal for the flow control valves on a quarterly basis.
Items2 3 4 5:
Each of these items were caused by inadequate surveillance test procedures that resulted from incorrectly interpreting how to implement Technical Specification testing requirements. The test procedures for the Safety Injection and Containment Spray manual actuation switches, as well as the FHB Emergency Ventilation system, were based upon this incorrect interpretation and have been deficient since initial development. The radiation monitor MST revisions completed in 1993, were intentionally performed to eliminate what was considered to be redundant and unnecessary testing steps. This decision was also based on the incorrect testing requirement interpretation, as was the revision to OST-1086 that resulted in the acceptance criteria section not listing 1CS-196, and subsequently resulting in the failure to test the valve.
U.S. NUCLEAR REGUIATOAT COMMISSION NRC FOAM 366A
)6-B6)
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION FACILITY NAME II] DOCKET LEA NUMBEA (6) PAGE )3)
SEQUENTIAL REVIBION YEAR NUMBER NUMBER Shearon Harris Nuclear Plant Unit 41 60400 4 OF 5
~
96 - 002 - Ol TEXT pl errors specs N seceded, ose oddrrroosl copies ol NRC For<o 36gl IIT)
SAFETY SIGNIFICANCE:
There were no adverse safety consequences as a result of this event. The CSIP Alternate Mini-Flow Isolation Valve circuits were tested satisfactorily on September 8, 1995 to verify operability. This testing provides confidence that had an accident occurred requiring CSIP mini-flow protection due to the re-pressurization of the Reactor Coolant System during a safety injection, the isolation valves would have opened to prevent pump damage.
There were no adverse safety consequences as a result of the five additional items reported in this supplement. In each cas where applicable, subsequent testing was performed that verified the operability of the effected component or circuit.
PREVIOUS SIMILAR EVENTS:
Previous events have been submitted as LERs related to surveillance testing deficiencies caused by procedural inadequacies.
LER 95-07, which was submitted on September 28, 1995, contained a corrective action to perform a comprehensive Technical Specification testing program review and it was during this review process that the CSIP Alternate Mini-Flow Isolation Valve condition was identified. This review is being performed by a multi-discipline team and is still in progress.
The five additional items reported in this LER revision were identified as a result of the on-going Technical Specification testing program review.
CORRECTIVE ACTIONS COMPLETED:
- 1. Slave relay testing was satisfactorily completed on September 8, 1995 that verified the operability of the CSIP Alternate Mini-Flow Isolation Valve circuits.
- 2. Personnel involved in the June 1993 procedure revision process for OST-1083 and OST-1084 were counseled.
- 3. Surveillance procedures OST-1083 and OST-1084 were revised on February 16, 1996 to include the requirements for CSIP Alternate Mini-Flow Isolation Valve slave relay testing.
CORRECTIVE ACTIONS PLANNED:
- 1. The Technical Specification testing program review (committed to in LER 95-07) that identified this condition is currently in progress and is scheduled for completion in 1996.
CORRECTIVE ACTIONS FOR ADDITIONALITEMS IDENTIFIED:
~Item I OST-1044 was revised in December 1995 and OST-1045 was revised in February 1996. These revisions incorporated K635 and K640 slave relay testing on a quarterly basis.
Item 2:
To address the SI switch that becomes inoperable on March 16, 1996, a Request for Exigent License Amendment was submitted to the NRC on February 16, 1996. This requests a one-time extension of the testing interval for testing the SI switch. Operations Surveillance Test procedure (OST-9016T) will be revised and performed to test the CS switches prior to their surveillance interval expiration date of March 3, 1996. Additionally, a new OST will be developed to properly test each Safety Injection and Containment Spray manual actuation switch once every 18 months. This revision will be completed as addressed in the Harris Plant response to NRC Generic Letter 96-01.
RM 3 A (4-95
NRC fORM 366A US. NUCLEAR REGULATORY COMMISSION l696)
LlCENSEE EVENT REPORT (LER)
TEXT CONTINUATION fACILITYNAME (n OOCKET LER NUMBER (6) PAGE I3)
SEOUENTIAL REVISION NUMBER NUMBER Shearon Harris Nuclear Plant - Unit //1 50400 5 OF 5 96 << 002 - 01 TEXT Pl mors spsooi rorpri od. vso sddi)dmor oopis of A'RC form 3566/ Ill)
Item 3:
OST-1086 will be revised to enhance the acceptance criteria to ensure that testing of the "B" CSIP Normal Mini-Flow Isolation Valve (1CS-196) slave relay is included. This revision will be completed as addressed in the Harris Plant response to NRC Generic Letter 96-01.
Item 4:
The radiation monitor operability and testing requirements were inoved from Technical Specification 4.3.3.10 to the Off-Site Dose Calculation Manual (ODCM) in May 1995. Upon identification of this condition, the affected radiation monitors were declared inoperable. Appropriate MST procedure revisions were completed and the tests performed, to fully verify the automatic pathway isolation function of the radiation monitors. Additional procedure changes and/or ODCM revisions will be completed to clarify the testing requirements and enhance the performance of future testing. These actions will be completed as addressed in the Harris Plant response to NRC Generic Letter 96-01.
Item 5:
OST-1048 will be revised to test the FHB Train A Emergency Ventilation actuation from Radiation Monitor RM-1FR-3567A-SA, which will properly include the previously omitted cable. This revision will be completed as addressed in the Harris Plant response to NRC Generic Letter 96-01.
EIIS CODES:
High Head Safety Injection: BQ Auxiliary Feedwater Flow Control Valves: BA-FCV Containment Spray: BE Fuel Handling Building Ventilation: VG RM 3 A (4- 5)