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| 05000528/LER-1994-001, :on 940407,determined That SR 4.8.4.1 Not Fully Met Due to Personnel Error.Pm Task Specifying Sample Sizes of Molded Case Circuit Breakers Will Be Updated & Applicable Breakers Will Be Tested by 941014 |
- on 940407,determined That SR 4.8.4.1 Not Fully Met Due to Personnel Error.Pm Task Specifying Sample Sizes of Molded Case Circuit Breakers Will Be Updated & Applicable Breakers Will Be Tested by 941014
| 10 CFR 50.73(a)(2) |
| 05000530/LER-1994-002, :on 940317,main Steam Safety Valve Setpoints Found Out of Tolerance.Valves Adjusted,Certified & Returned to Svc |
- on 940317,main Steam Safety Valve Setpoints Found Out of Tolerance.Valves Adjusted,Certified & Returned to Svc
| |
| 05000528/LER-1994-002-02, Forwards LER 94-002-02:on 940422,condition That Resulted in Plant Being in Condition Not Covered by Plant Operating Procedures | Forwards LER 94-002-02:on 940422,condition That Resulted in Plant Being in Condition Not Covered by Plant Operating Procedures | |
| 05000528/LER-1994-002, :on 940422,determined That TS 3.1.1.1,3.3.1 & 3.9.1 LCO May Not Ensure That Plant Operation Is Maintained within Safety Analysis.Caused by Groundrules Adjunct to Ts. TS Change Request Is Being Prepared |
- on 940422,determined That TS 3.1.1.1,3.3.1 & 3.9.1 LCO May Not Ensure That Plant Operation Is Maintained within Safety Analysis.Caused by Groundrules Adjunct to Ts. TS Change Request Is Being Prepared
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2) |
| 05000530/LER-1994-002-01, :on 940318,13 of 20 MSSVs Setpoints Found to Be Out of Tolerance.Most Valves Exhibited Seat Wear.Valves Replaced w/pre-tested Spares & Approval to Amend TS LCO 3.7.1.1,MSSV Setpoints Received |
- on 940318,13 of 20 MSSVs Setpoints Found to Be Out of Tolerance.Most Valves Exhibited Seat Wear.Valves Replaced w/pre-tested Spares & Approval to Amend TS LCO 3.7.1.1,MSSV Setpoints Received
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) |
| 05000530/LER-1994-003, Corrected Ltr Forwarding LER 94-003-00,changing Ltr Number to 192-00892-JML/AKK/RKR.W/o LER | Corrected Ltr Forwarding LER 94-003-00,changing Ltr Number to 192-00892-JML/AKK/RKR.W/o LER | |
| 05000529/LER-1994-003-02, :on 940927,startup Channel High Neutron Flux Alarm Declared Inoperable.Caused by Personnel Error. Personnel Counseled |
- on 940927,startup Channel High Neutron Flux Alarm Declared Inoperable.Caused by Personnel Error. Personnel Counseled
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2) |
| 05000530/LER-1994-004-01, :on 940530,LCO 3.0.3 Entered Following Determination That Secondary Pressure Boundary Leakage Existed.Caused by Defective Weld.Control Room Personnel Returned to Mode 5 & Exited LCO 3.0.3 |
- on 940530,LCO 3.0.3 Entered Following Determination That Secondary Pressure Boundary Leakage Existed.Caused by Defective Weld.Control Room Personnel Returned to Mode 5 & Exited LCO 3.0.3
| 10 CFR 50.73(a)(2) |
| 05000528/LER-1994-004, :on 941006,Train a Declared Inoperable Due to Projection of Test Results Indicated Battery Banks Did Not Meet 90% Criteria of TS SR 4.8.2.1.e.Caused by Loss of Positive Active Matl.Proposed TS Amend Submitted |
- on 941006,Train a Declared Inoperable Due to Projection of Test Results Indicated Battery Banks Did Not Meet 90% Criteria of TS SR 4.8.2.1.e.Caused by Loss of Positive Active Matl.Proposed TS Amend Submitted
| 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2) 10 CFR 50.73(s)(2) |
| 05000529/LER-1994-004, :on 941006,class 1E Batteries Found in Degraded Condition.Caused by Step Decline in Capacity Caused by Loss of Positive Active Matl.Ts LCO 3.8.2.2 Action Was Entered to Prevent Positive Reactivity Additions |
- on 941006,class 1E Batteries Found in Degraded Condition.Caused by Step Decline in Capacity Caused by Loss of Positive Active Matl.Ts LCO 3.8.2.2 Action Was Entered to Prevent Positive Reactivity Additions
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) |
| 05000529/LER-1994-005-02, :on 941019,completed TS Required Shutdown Due to Expiration of LCO Time Limit.Design Change Options Identified & Will Be Reviewed to Determine If Valve &/Or Motor Operator Replacement or Mod Necessary |
- on 941019,completed TS Required Shutdown Due to Expiration of LCO Time Limit.Design Change Options Identified & Will Be Reviewed to Determine If Valve &/Or Motor Operator Replacement or Mod Necessary
| 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(s)(2)(v) 10 CFR 50.73(s)(2) 10 CFR 50.73(s)(2)(vii) 10 CFR 50.73(s)(2)(viii)(A) |
| 05000528/LER-1994-005, :on 940619,determined That CPC Channel D,Delta- T Power Signal Could No Longer Be Adjusted Per TS Requirements.Caused by Loop 2 Hot Leg Temp RTD Fluctuations. Channel Calibrated & Declared Operable |
- on 940619,determined That CPC Channel D,Delta- T Power Signal Could No Longer Be Adjusted Per TS Requirements.Caused by Loop 2 Hot Leg Temp RTD Fluctuations. Channel Calibrated & Declared Operable
| 10 CFR 50.73(a)(2) |
| 05000528/LER-1994-005-01, :on 940619,RTD Creating Delta-T Power Fluctuations Was Electronically Switched w/T-h RTD Used in Core Operating Limits Supervisory Sys.Caused by Condition of Fluctuating T-h RTD Signals |
- on 940619,RTD Creating Delta-T Power Fluctuations Was Electronically Switched w/T-h RTD Used in Core Operating Limits Supervisory Sys.Caused by Condition of Fluctuating T-h RTD Signals
| |
| 05000529/LER-1994-005, Forwards Suppl 1 to LER 94-005,providing Updated Info on Cause & Corrective Actions of TS Required Shutdown Due to Expiration of LCO Time Limit,Including Revised Energy Industry Identification Sys Codes | Forwards Suppl 1 to LER 94-005,providing Updated Info on Cause & Corrective Actions of TS Required Shutdown Due to Expiration of LCO Time Limit,Including Revised Energy Industry Identification Sys Codes | |
| 05000530/LER-1994-005-01, :on 940819,reactor Trip Occurred Following Degradation of Mf Flow.Fwcs cabinets,SG-1 Economizer & MFW Pumps Quarantined & FWCS-1 Master Controller Replaced.W/ |
- on 940819,reactor Trip Occurred Following Degradation of Mf Flow.Fwcs cabinets,SG-1 Economizer & MFW Pumps Quarantined & FWCS-1 Master Controller Replaced.W/
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition |
| 05000528/LER-1994-006, :on 941021,identified That Actual Flow Rate on Spray Pond Pumps May Be Exceeding Design Flow Rates.Caused by Oversized Orifices in Spray Pond Return Lines. Administrative Controls Established to Counter Condition |
- on 941021,identified That Actual Flow Rate on Spray Pond Pumps May Be Exceeding Design Flow Rates.Caused by Oversized Orifices in Spray Pond Return Lines. Administrative Controls Established to Counter Condition
| |
| 05000530/LER-1994-006, :on 940823,shutdown Cooling Loop Rendered Inoperable Due to Pump Breaker Racked Down & in Test Position.Training Provided to Licensed Operators on Procedure 40DP-9OP26, Operability. |
- on 940823,shutdown Cooling Loop Rendered Inoperable Due to Pump Breaker Racked Down & in Test Position.Training Provided to Licensed Operators on Procedure 40DP-9OP26, Operability...
| |
| 05000529/LER-1994-006-02, :on 941029,reactor Tripped on Low DNBR Trip Signal Due to Erroneous Penalty Factor.Ceac 1 Processor Board Replaced & Equipment Root Cause Failure Analysis of Processor Board Being Performed |
- on 941029,reactor Tripped on Low DNBR Trip Signal Due to Erroneous Penalty Factor.Ceac 1 Processor Board Replaced & Equipment Root Cause Failure Analysis of Processor Board Being Performed
| |
| 05000528/LER-1994-006-01, On 941021,identified Actual Flow Rates on Unit 1 Spray Pond Pumps May Be Exceeding Design Flow Rates. Caused by Oversized Orifices in Unit 1 Spray Pump Return Lines.Established Administrative Controls | On 941021,identified Actual Flow Rates on Unit 1 Spray Pond Pumps May Be Exceeding Design Flow Rates. Caused by Oversized Orifices in Unit 1 Spray Pump Return Lines.Established Administrative Controls | 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) |
| 05000530/LER-1994-007, :on 940830,reactor Trip Occurred When Steam Generator 2 Water Level Reached RPS Trip Setpoint.Caused by Component failure.FWCS-2 Master Controller Was Replaced |
- on 940830,reactor Trip Occurred When Steam Generator 2 Water Level Reached RPS Trip Setpoint.Caused by Component failure.FWCS-2 Master Controller Was Replaced
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) |
| 05000529/LER-1994-007, Forwards LER 94-007-00 Re Momentary Entry Into TS LCO 3.03 Following Determination That Action Statement for TS LCO 3.7.7 Had Not Been Met W/Both Trains of CR Essential Filtration Sys Inoperable in Modes 1 Through 4 | Forwards LER 94-007-00 Re Momentary Entry Into TS LCO 3.03 Following Determination That Action Statement for TS LCO 3.7.7 Had Not Been Met W/Both Trains of CR Essential Filtration Sys Inoperable in Modes 1 Through 4 | |
| 05000528/LER-1994-008, :on 940929,identified That Preventive Maintenance Task for Calibrating Boronometer Overdue.Caused by Personnel Error.Procedure Revised to Address Condition |
- on 940929,identified That Preventive Maintenance Task for Calibrating Boronometer Overdue.Caused by Personnel Error.Procedure Revised to Address Condition
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) |
| 05000528/LER-1994-008-02, :on 941126,controlled Reactor Shutdown Commenced to Isolate & Repair Leaking Pressurizer Vent Valves,Per TS Limiting Condition for Operation 3.4.10,action (A).Valves Reworked |
- on 941126,controlled Reactor Shutdown Commenced to Isolate & Repair Leaking Pressurizer Vent Valves,Per TS Limiting Condition for Operation 3.4.10,action (A).Valves Reworked
| |
| 05000530/LER-1994-008, Forwards LER 94-008-00,eight Incore Instruments Found cross- Wired | Forwards LER 94-008-00,eight Incore Instruments Found cross- Wired | |
| 05000528/LER-1994-009, :on 941118,determined That Letdown Isolation Valve Could Not Satisfy 10CFR50,App R Related Requirement. Caused by Personnel Error.Procedure Changes Implemented Which Eliminate Reliance on Isolation Valve During Shutdown |
- on 941118,determined That Letdown Isolation Valve Could Not Satisfy 10CFR50,App R Related Requirement. Caused by Personnel Error.Procedure Changes Implemented Which Eliminate Reliance on Isolation Valve During Shutdown
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) |
| 05000528/LER-1994-010, :on 930409,misalignment of Limitorque Torque Switch Contact Bar Prevented Remote Operation of Movs. Evaluation of All Flex Wedge Gate Valves & SB Type MOVs Was Performed |
- on 930409,misalignment of Limitorque Torque Switch Contact Bar Prevented Remote Operation of Movs. Evaluation of All Flex Wedge Gate Valves & SB Type MOVs Was Performed
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) |