| | | Reporting criterion |
|---|
| 05000245/LER-1993-001-01, :on 930108,determined That Previous Snubber Failure of HSS-018 B SRV Discharge Line Resulted in Failure to Meet TS LCO for Section 3.6.I.4.Caused by Use of Incorrect Bleed Rate.Snubber Rebuilt |
- on 930108,determined That Previous Snubber Failure of HSS-018 B SRV Discharge Line Resulted in Failure to Meet TS LCO for Section 3.6.I.4.Caused by Use of Incorrect Bleed Rate.Snubber Rebuilt
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000336/LER-1993-001, :on 921227,weekly TS Surveillance in Modes 5 & 6 Not Performed within Specified Time Interval.Caused by Lack of Procedural Detail & Administrative Error.Flowpath Instruction Revised & Personnel Counseled |
- on 921227,weekly TS Surveillance in Modes 5 & 6 Not Performed within Specified Time Interval.Caused by Lack of Procedural Detail & Administrative Error.Flowpath Instruction Revised & Personnel Counseled
| 10 CFR 50.73(a)(2)(i) |
| 05000423/LER-1993-001-02, :on 930126,discovered That Signal Path from Nis Axial Flux Circuit Input Into Westinghouse 7300 Process Control Sys Not Periodically Tested.Caused by Procedure Deficiency.Test Changes Incorporated |
- on 930126,discovered That Signal Path from Nis Axial Flux Circuit Input Into Westinghouse 7300 Process Control Sys Not Periodically Tested.Caused by Procedure Deficiency.Test Changes Incorporated
| 10 CFR 50.73(a)(2)(i) |
| 05000336/LER-1993-002, :on 930107,determined That LCO, Accident Monitoring Not Entered Upon Entry Into Mode 3.Caused by Incomplete Application of Change to Ts.Event Will Be Reviewed by All Licensed Operators |
- on 930107,determined That LCO, Accident Monitoring Not Entered Upon Entry Into Mode 3.Caused by Incomplete Application of Change to Ts.Event Will Be Reviewed by All Licensed Operators
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000423/LER-1993-002, :on 930206 & 07,Train a & Train B CR Pressurization Sys Failed 18-month Surveillance Test, Respectively.Caused by Moisture in Air Banks & Pressure Oscillations.Air Banks Purged |
- on 930206 & 07,Train a & Train B CR Pressurization Sys Failed 18-month Surveillance Test, Respectively.Caused by Moisture in Air Banks & Pressure Oscillations.Air Banks Purged
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2) |
| 05000423/LER-1993-002-01, :on 930207,train a CR Pressurization Sys Failed 18 Month Pressurization Surveillance Test.Caused by Moisture in Air Banks.Cr Placed in Filtered Recirculation & Air Banks Refilled W/Dry Air |
- on 930207,train a CR Pressurization Sys Failed 18 Month Pressurization Surveillance Test.Caused by Moisture in Air Banks.Cr Placed in Filtered Recirculation & Air Banks Refilled W/Dry Air
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability |
| 05000245/LER-1993-002, Corrected Cover Sheet to LER 93-002,correcting Administrative Error.First Sentence of Cover Sheet Should Be Corrected to Read as Stated | Corrected Cover Sheet to LER 93-002,correcting Administrative Error.First Sentence of Cover Sheet Should Be Corrected to Read as Stated | 10 CFR 50.73(a)(2)(i) |
| 05000245/LER-1993-002-02, :on 930314,declared Secondary Containment Inoperable & Commenced an Orderly Shutdown.Caused by Operation of Two Redundant RB Supply Fans.Rb Supply Fans Will Be Modified |
- on 930314,declared Secondary Containment Inoperable & Commenced an Orderly Shutdown.Caused by Operation of Two Redundant RB Supply Fans.Rb Supply Fans Will Be Modified
| 10 CFR 50.73(a)(2) |
| 05000423/LER-1993-003-01, :on 930329,discovered That Slave Relay Testing of air-operated Valves for Auxiliary Feedwater Pump Alternate Suction Inadequate.Caused by Mfg Deficiency.Lco Entered & Task Force Formed to Review Relays |
- on 930329,discovered That Slave Relay Testing of air-operated Valves for Auxiliary Feedwater Pump Alternate Suction Inadequate.Caused by Mfg Deficiency.Lco Entered & Task Force Formed to Review Relays
| 10 CFR 50.73(a)(2)(i) |
| 05000245/LER-1993-003-02, :on 930426,discovered That Primary Containment Penetration X-25/202D Exceeded Max Allowed TS Leakage.Caused by Slightly Worn Seat Ring & Plug in Valve Not Fully Seating.Seat Ring Replaced |
- on 930426,discovered That Primary Containment Penetration X-25/202D Exceeded Max Allowed TS Leakage.Caused by Slightly Worn Seat Ring & Plug in Valve Not Fully Seating.Seat Ring Replaced
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2) |
| 05000336/LER-1993-003, :on 930217,discovered That Mispositioned HPSI Valve Would Have Rendered Facility 1 HPSI Sys Inoperable Due to Inadequate Procedural Guidance.Affected Valve Returned to Correct Position & Appropriate Sps Revised |
- on 930217,discovered That Mispositioned HPSI Valve Would Have Rendered Facility 1 HPSI Sys Inoperable Due to Inadequate Procedural Guidance.Affected Valve Returned to Correct Position & Appropriate Sps Revised
| |
| 05000423/LER-1993-004, :on 930331,turbine Valve Closure Resulted in Reactor Trip Followed by Turbine Trip.Caused by Faulty Power Supply in electro-hydraulic Control Sys Mfg by Crosby Valve & Gauge Co.Also Reported Per Part 21 |
- on 930331,turbine Valve Closure Resulted in Reactor Trip Followed by Turbine Trip.Caused by Faulty Power Supply in electro-hydraulic Control Sys Mfg by Crosby Valve & Gauge Co.Also Reported Per Part 21
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000423/LER-1993-004-01, :on 930331,RT Occurred Due to electro-hydraulic Control Power Supply Failure.Replaced Faulty Power Supply |
- on 930331,RT Occurred Due to electro-hydraulic Control Power Supply Failure.Replaced Faulty Power Supply
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000245/LER-1993-004-01, :on 930430,1-inch Instrument Lines from Main Steam Line Flow Venturis Found to Be Missing Pipe Restraints in Several Locations.Possibly Caused by Improper Maint &/Or Vibration.Missing Restraints Reinstalled |
- on 930430,1-inch Instrument Lines from Main Steam Line Flow Venturis Found to Be Missing Pipe Restraints in Several Locations.Possibly Caused by Improper Maint &/Or Vibration.Missing Restraints Reinstalled
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 05000336/LER-1993-004, :on 930222,reactor Trips on SG Low Water Level Occurred.Caused by Automatic Trip of MFW Pump B on Low Suction Pressure Due to High FW Flow Rates.Classroom Training on Main & Afwc Received by Licensed Operators |
- on 930222,reactor Trips on SG Low Water Level Occurred.Caused by Automatic Trip of MFW Pump B on Low Suction Pressure Due to High FW Flow Rates.Classroom Training on Main & Afwc Received by Licensed Operators
| |
| 05000336/LER-1993-004-02, Forwards LER 93-004-02,updating Corrective Actions Identified in LER 93-004-01,submitted Per 10CFR50.73(a)(2)(iv),reporting Any Event or Condition That Resulted in Manual or Automatic Actuation of ESF Sys | Forwards LER 93-004-02,updating Corrective Actions Identified in LER 93-004-01,submitted Per 10CFR50.73(a)(2)(iv),reporting Any Event or Condition That Resulted in Manual or Automatic Actuation of ESF Sys | 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000245/LER-1993-005-01, :on 930429,hydraulic Snubber HSS-039 Identifed W/Unacceptable End Attachment to Recirculation Pump Motor Due to Missing Cotter Pin.Snubber Replaced W/Rebuilt Spare & Load Pin Installed Correctly |
- on 930429,hydraulic Snubber HSS-039 Identifed W/Unacceptable End Attachment to Recirculation Pump Motor Due to Missing Cotter Pin.Snubber Replaced W/Rebuilt Spare & Load Pin Installed Correctly
| 10 CFR 50.73(a)(2)(i) |
| 05000423/LER-1993-005-02, :on 930520,cold Over Pressure Protection Sys Declared Inoperable Due to Inadequate Surveillance Testing. Caused by Mgt Deficiency.Overlap Task Force Will Continue to Review Procedures Associated W/Reactor Trip |
- on 930520,cold Over Pressure Protection Sys Declared Inoperable Due to Inadequate Surveillance Testing. Caused by Mgt Deficiency.Overlap Task Force Will Continue to Review Procedures Associated W/Reactor Trip
| 10 CFR 50.73(a)(2)(i) |
| 05000336/LER-1993-005, :on 930311,discovered That Automatic RPS Actuation Occurred on 930222 & Not Immediately Reported to Nrc.Caused by Personnel Error.Memo Sent to All Licensed Operators/Personnel Re Reporting Requirements |
- on 930311,discovered That Automatic RPS Actuation Occurred on 930222 & Not Immediately Reported to Nrc.Caused by Personnel Error.Memo Sent to All Licensed Operators/Personnel Re Reporting Requirements
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000336/LER-1993-006, Corrected LER 93-006-00:on 930324,determined That Svc Water Supply Piping to Switchgear Room Coolers X-181A & X-181B Did Not Meet TS Structural Integrity Requirements.Caused by Personnel Error.Clamp Installed | Corrected LER 93-006-00:on 930324,determined That Svc Water Supply Piping to Switchgear Room Coolers X-181A & X-181B Did Not Meet TS Structural Integrity Requirements.Caused by Personnel Error.Clamp Installed | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000245/LER-1993-006-01, Forwards Updated LER 93-006-01 Which Was Previously Submitted W/O Rev Bars | Forwards Updated LER 93-006-01 Which Was Previously Submitted W/O Rev Bars | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000245/LER-1993-006, :on 930604,dicovered Unsealed Fire Barrier Penetration in TS Fire Wall Due to Lack of Detailed Guidance Re Procedure Used in Insp.Established Fire Watch to Compensate for Unsealed Penetrations |
- on 930604,dicovered Unsealed Fire Barrier Penetration in TS Fire Wall Due to Lack of Detailed Guidance Re Procedure Used in Insp.Established Fire Watch to Compensate for Unsealed Penetrations
| 10 CFR 50.73(a)(2) |
| 05000423/LER-1993-006-02, :on 930525,two HPSI Discharge Check Valves Declared Inoperable Due to Inadequate Surveillance Testing. Caused by Personnel Error.Test Written & Performed to Demonstrate Valve Operability |
- on 930525,two HPSI Discharge Check Valves Declared Inoperable Due to Inadequate Surveillance Testing. Caused by Personnel Error.Test Written & Performed to Demonstrate Valve Operability
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2) |
| 05000245/LER-1993-006-03, :on 930604,unsealed Fire Barrier Penetration Discovered in TS Fire Wall Between Auxiliary Boiler Room & Maint Shop.Caused by Lack of Detailed Procedural Guidance. Fire Watch Established & Penetration Sealed |
- on 930604,unsealed Fire Barrier Penetration Discovered in TS Fire Wall Between Auxiliary Boiler Room & Maint Shop.Caused by Lack of Detailed Procedural Guidance. Fire Watch Established & Penetration Sealed
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000336/LER-1993-007, Incorporates NRC Comments Discussed During 940324 Telcon Into 931217 Application for Amend to License DPR-65,revising TS 3.8.1.1,as Result of LER 93-007-00,dtd 930428 & Util 930726 Response to NOV from Insp Rept 50-336/93-81 | Incorporates NRC Comments Discussed During 940324 Telcon Into 931217 Application for Amend to License DPR-65,revising TS 3.8.1.1,as Result of LER 93-007-00,dtd 930428 & Util 930726 Response to NOV from Insp Rept 50-336/93-81 | |
| 05000245/LER-1993-007, :on 930623,discovered Potential for Loss of Tbsccw Sys Due to Incomplete Review of safety-related/non- safety-related Sys Interface.Scope of Seismic Piping Reviews Expanded |
- on 930623,discovered Potential for Loss of Tbsccw Sys Due to Incomplete Review of safety-related/non- safety-related Sys Interface.Scope of Seismic Piping Reviews Expanded
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000423/LER-1993-007-01, :on 930611,plant Mgt Discovered Reduction in EDG Fuel Oil Storage Capacity Per SER & Fsar,Constituting Event Outside Design Basis of Plant.Caused by Inadequate Design Interface.Temporary Tanker Utilized |
- on 930611,plant Mgt Discovered Reduction in EDG Fuel Oil Storage Capacity Per SER & Fsar,Constituting Event Outside Design Basis of Plant.Caused by Inadequate Design Interface.Temporary Tanker Utilized
| 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition |
| 05000245/LER-1993-007-02, :on 930623,TBSCCW Sys Pressure Boundary Integrity Failed Due to Incomplete Review of Safety & non-safety-related Sys Interface.Isolation Valve (1-SC-184) 3/4-SC-105 Closed |
- on 930623,TBSCCW Sys Pressure Boundary Integrity Failed Due to Incomplete Review of Safety & non-safety-related Sys Interface.Isolation Valve (1-SC-184) 3/4-SC-105 Closed
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2) |
| 05000336/LER-1993-008, :on 930505,declared Charging Pumps Inoperable Due to Low Control Power Voltage.Established Administrative Controls & Installed Interposing Relay within C Charging Pump Control Circuit |
- on 930505,declared Charging Pumps Inoperable Due to Low Control Power Voltage.Established Administrative Controls & Installed Interposing Relay within C Charging Pump Control Circuit
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 05000423/LER-1993-008-01, :on 930614,one Channel of Electrical Environmentally Qualified Temp Monitor for Main Steam Valve Bldg Found Indicating Improperly.Caused by Personnel Error. Manual Logging of Temp Initiated |
- on 930614,one Channel of Electrical Environmentally Qualified Temp Monitor for Main Steam Valve Bldg Found Indicating Improperly.Caused by Personnel Error. Manual Logging of Temp Initiated
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) |
| 05000423/LER-1993-009, :on 930617,determined That SLCRS May Have Been Inoperable During Certain Cold Weather Period.Caused by Failure to Account for Chimney Effect in Encl Bldg.Design Change Implemented to Increase SLCRS Capacity |
- on 930617,determined That SLCRS May Have Been Inoperable During Certain Cold Weather Period.Caused by Failure to Account for Chimney Effect in Encl Bldg.Design Change Implemented to Increase SLCRS Capacity
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 05000336/LER-1993-009, :on 930506,inlet & Outlet skid-mounted Isolation Valves to Radiation Monitor Found Shut.Caused by Procedure Noncompliance by I&C Personnel.Personnel Will Review & Edit Radiation Procedures |
- on 930506,inlet & Outlet skid-mounted Isolation Valves to Radiation Monitor Found Shut.Caused by Procedure Noncompliance by I&C Personnel.Personnel Will Review & Edit Radiation Procedures
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) |
| 05000423/LER-1993-009-01, :on 930617,determined That Suppl Leak Collection & Release Sys May Have Been Inoperable During Certain Weather Periods in Past.Caused by Failure to Account for Chimney Effect.Suppl Will Be Sent |
- on 930617,determined That Suppl Leak Collection & Release Sys May Have Been Inoperable During Certain Weather Periods in Past.Caused by Failure to Account for Chimney Effect.Suppl Will Be Sent
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2) |
| 05000245/LER-1993-009-02, :on 930706,inoperability of LPCI Sys Due to Outboard LPCI to Recirculation Loop Valve 1-LP-9B Failed to Open Electrically After Being Manually Opened.Declutch Fork & Clutch Repositioned |
- on 930706,inoperability of LPCI Sys Due to Outboard LPCI to Recirculation Loop Valve 1-LP-9B Failed to Open Electrically After Being Manually Opened.Declutch Fork & Clutch Repositioned
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 05000245/LER-1993-010-01, :on 930917,determined Unit 1 Has No Automatic Reactor Recirculation Pump Runback Circuitry in Place.Caused by Incorrect Analysis Assumption in Original Plant Accident analysis.Re-analysis Performed |
- on 930917,determined Unit 1 Has No Automatic Reactor Recirculation Pump Runback Circuitry in Place.Caused by Incorrect Analysis Assumption in Original Plant Accident analysis.Re-analysis Performed
| 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition |
| 05000336/LER-1993-010-02, :on 931029,unit Failed to Perform post-work ASME Leakage Test on Valve 2-CH-223.Caused by Personnel Error.Leakage Test Repeated & Found Satisfactory |
- on 931029,unit Failed to Perform post-work ASME Leakage Test on Valve 2-CH-223.Caused by Personnel Error.Leakage Test Repeated & Found Satisfactory
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000423/LER-1993-010, :on 930707,reactor Trip Input to Turbine Trip Portion of ESFAS Declared Inoperable Due to Inadequate Surveillance Testing.Test to Verify Operability Written & Performed |
- on 930707,reactor Trip Input to Turbine Trip Portion of ESFAS Declared Inoperable Due to Inadequate Surveillance Testing.Test to Verify Operability Written & Performed
| 10 CFR 50.73(a)(2)(i) |
| 05000245/LER-1993-011, Responds to NRC 981002 Request to Counsel That NNECO Waive Any Assertion of Statue of Limitations for 60-90 Days with Respect to NRC Ability to Initiate Civil Penalty Action Based on Apparent Violation of 10CFR50.59 Re LER 93-0 | Responds to NRC 981002 Request to Counsel That NNECO Waive Any Assertion of Statue of Limitations for 60-90 Days with Respect to NRC Ability to Initiate Civil Penalty Action Based on Apparent Violation of 10CFR50.59 Re LER 93-011-00 | |
| 05000336/LER-1993-011-02, :on 931007,EDG B Declared Inoperable Due to Underrated Air Start Solenoid.Caused by Design Replacement Error.Underrated Solenoid Replaced on 931008 W/Solenoid Model 212-630-1F |
- on 931007,EDG B Declared Inoperable Due to Underrated Air Start Solenoid.Caused by Design Replacement Error.Underrated Solenoid Replaced on 931008 W/Solenoid Model 212-630-1F
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition |
| 05000245/LER-1993-011-01, :on 930917,determined That Conditions May Have Existed Where Sfpcs May Have Been Incapable of Maintaining Pool Temp.Caused by Inappropriate Assumptions in Support of SFP Project.Design Basis Documents Revised |
- on 930917,determined That Conditions May Have Existed Where Sfpcs May Have Been Incapable of Maintaining Pool Temp.Caused by Inappropriate Assumptions in Support of SFP Project.Design Basis Documents Revised
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition |
| 05000423/LER-1993-011, :on 930731,MSSV Lift Setpoint Drift Occurred Due to Unknown Cause.Reduced Setpoint for Power Range Neutron Flux High Trip to 10% |
- on 930731,MSSV Lift Setpoint Drift Occurred Due to Unknown Cause.Reduced Setpoint for Power Range Neutron Flux High Trip to 10%
| 10 CFR 50.73(a)(2)(i) |
| 05000336/LER-1993-012, :on 930524,turbine & Reactor Tripped During Mussel Cook (Thermal Backwash) Due to Lack of Heat Removal Capabilities from Main Generator Stator Water Cooling Sys. Installed Thermoconductivity Filler |
- on 930524,turbine & Reactor Tripped During Mussel Cook (Thermal Backwash) Due to Lack of Heat Removal Capabilities from Main Generator Stator Water Cooling Sys. Installed Thermoconductivity Filler
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000245/LER-1993-012-02, :on 930917,components Supporting Safety Related Function of FWCI Sys Were Not Category 1 or Seismically Qualified.Caused by Failure to Incorporate Sep. Upgrade Mepl for Millstone Unit 1 |
- on 930917,components Supporting Safety Related Function of FWCI Sys Were Not Category 1 or Seismically Qualified.Caused by Failure to Incorporate Sep. Upgrade Mepl for Millstone Unit 1
| 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition |
| 05000423/LER-1993-012-01, :on 930805,discovered Train a of SWS Inoperable Due to Inadequate Work Planning by Const Dept.Removed Plywood & Performed Evaluation |
- on 930805,discovered Train a of SWS Inoperable Due to Inadequate Work Planning by Const Dept.Removed Plywood & Performed Evaluation
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) |
| 05000423/LER-1993-013-01, :on 930901,determined Reactor at Power Permissive Bistable Set to Incorrect Value.Caused by TS W/ Mutually Exclusive Conditions for P-10 Interlock.Tss Revised |
- on 930901,determined Reactor at Power Permissive Bistable Set to Incorrect Value.Caused by TS W/ Mutually Exclusive Conditions for P-10 Interlock.Tss Revised
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) |
| 05000336/LER-1993-013, :on 930603,noted That Main Turbine Generator EHC Sys Caused an Increase in Pressurizer Pressure,Resulting in Reactor Trip,Due to Closing of Intercept & Cv.Operators Performed EOP & Sys Performed as Expected |
- on 930603,noted That Main Turbine Generator EHC Sys Caused an Increase in Pressurizer Pressure,Resulting in Reactor Trip,Due to Closing of Intercept & Cv.Operators Performed EOP & Sys Performed as Expected
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000245/LER-1993-013, :on 920330,discovered That One of Two RB Ventilation Exhaust Isolation Valves Failed to Go Fully Closed When Given Isolation Signal.Caused by Minor Valve Misalignment.Valve Realigned |
- on 920330,discovered That One of Two RB Ventilation Exhaust Isolation Valves Failed to Go Fully Closed When Given Isolation Signal.Caused by Minor Valve Misalignment.Valve Realigned
| 10 CFR 50.73(a)(2)(i) |
| 05000245/LER-1993-014-02, :on 930923,potential Uninhabitability of Control Room Occurred.Caused by Deficiency in Standby Gas Treatment.Openings Plugged to Preclude Potential Discharge of Radioactivity |
- on 930923,potential Uninhabitability of Control Room Occurred.Caused by Deficiency in Standby Gas Treatment.Openings Plugged to Preclude Potential Discharge of Radioactivity
| 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition |
| 05000423/LER-1993-014-01, :on 930903,determined That Delayed Start of Train a Auxiliary Bldg Fan During Testing Due to Inherent Design Characteristics of Flow Switch.Design Changed to Provide Uninterruptible Source of Power |
- on 930903,determined That Delayed Start of Train a Auxiliary Bldg Fan During Testing Due to Inherent Design Characteristics of Flow Switch.Design Changed to Provide Uninterruptible Source of Power
| 10 CFR 50.73(a)(2)(i) |
| 05000423/LER-1993-014, :on 930903,train a of Supplemental Leak Collection & Release Sys Was Inoperable Due to Lack of Understanding of Flow Switch Response to Loss of Power Event.Formed Task Force & Design Changed |
- on 930903,train a of Supplemental Leak Collection & Release Sys Was Inoperable Due to Lack of Understanding of Flow Switch Response to Loss of Power Event.Formed Task Force & Design Changed
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) |