| | | Reporting criterion |
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| 05000328/LER-1997-001, :on 970117,missed Surveillance on Auxiliary Contacts of Reactor Trip Breakers Discovered.Caused by Adequate PMT for Reactor Trip Breaker Was Not Performed. Multi-disciplinary Team Formed to Perform Investigation |
- on 970117,missed Surveillance on Auxiliary Contacts of Reactor Trip Breakers Discovered.Caused by Adequate PMT for Reactor Trip Breaker Was Not Performed. Multi-disciplinary Team Formed to Perform Investigation
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(i)
10 CFR 50.73(a)(2)(viii)
10 CFR 50.73(a)(2) |
| 05000327/LER-1997-001-02, :on 970125,failed to Perform Surveillance Testing on EDG Start Timer Relays Contained in Start Logic Circuitry.Caused by Inadequate Surveillance Procedures. Revised Procedures & Performed Testing |
- on 970125,failed to Perform Surveillance Testing on EDG Start Timer Relays Contained in Start Logic Circuitry.Caused by Inadequate Surveillance Procedures. Revised Procedures & Performed Testing
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000327/LER-1997-002-01, :on 970214,TS AOT Exceeded for DG 2A-A.Caused by Mechanical Failure of DG 2A-A Governor Actuator on Engine 2.DG 2A-A Governor Actuators on Both Engines Replaced, Functional Tested & PMT Performed |
- on 970214,TS AOT Exceeded for DG 2A-A.Caused by Mechanical Failure of DG 2A-A Governor Actuator on Engine 2.DG 2A-A Governor Actuators on Both Engines Replaced, Functional Tested & PMT Performed
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(viii) |
| 05000327/LER-1997-002, Forwards LER 97-002-00,documenting Condition Resulting in Granting of Enforcement Discretion & to Deal W/Problems Encountered During Maint Activities to 2A-A DG Governor | Forwards LER 97-002-00,documenting Condition Resulting in Granting of Enforcement Discretion & to Deal W/Problems Encountered During Maint Activities to 2A-A DG Governor | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000327/LER-1997-003-02, :on 970305,failed to Properly Perform Surveillance Testing on Centrifugal Charging Pump Inlet Isolation Valve Logic.Caused by Inadequate Surveillance Instruction.Prepared Special Test Procedure |
- on 970305,failed to Properly Perform Surveillance Testing on Centrifugal Charging Pump Inlet Isolation Valve Logic.Caused by Inadequate Surveillance Instruction.Prepared Special Test Procedure
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(i) |
| 05000327/LER-1997-004-02, Forwards LER 97-004-02,identifying Two Addl Molded Case Circuit Breakers That Were Not in Appropriate Surveillance Instructions.Revs Annotated by Vertical Bar in Right Margin | Forwards LER 97-004-02,identifying Two Addl Molded Case Circuit Breakers That Were Not in Appropriate Surveillance Instructions.Revs Annotated by Vertical Bar in Right Margin | 10 CFR 50.73(a)(2)(1) |
| 05000327/LER-1997-005-01, :on 970319,two of Six Tested Main Steam Safety Relief Valves Not within TS Setpoint Tolerance.Appropriate LCOs Entered & Valves Found Outside TS Setpoint Tolerance Adjusted to within TS Tolerance & Retested |
- on 970319,two of Six Tested Main Steam Safety Relief Valves Not within TS Setpoint Tolerance.Appropriate LCOs Entered & Valves Found Outside TS Setpoint Tolerance Adjusted to within TS Tolerance & Retested
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000327/LER-1997-006-01, :on 970322,failed to Perform Surveillance Requirement During Containment Entry Due to Personnel Error. RWP Was Closed to Prevent Further Use |
- on 970322,failed to Perform Surveillance Requirement During Containment Entry Due to Personnel Error. RWP Was Closed to Prevent Further Use
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
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) |
| 05000327/LER-1997-007-01, :on 970404,DG Started When Drill Bit Being Used to Drill Into Electrical Panel in Main Control Room,Cut Into Cable.Caused by Drill Bit Penetrating Energized Wire Bundle Causing Short.Work Stopped on All Electrical Mods for S |
- on 970404,DG Started When Drill Bit Being Used to Drill Into Electrical Panel in Main Control Room,Cut Into Cable.Caused by Drill Bit Penetrating Energized Wire Bundle Causing Short.Work Stopped on All Electrical Mods for Shift
| 10 CFR 50.73(a)(2)(iii)
10 CFR 50.73(a)(2) |
| 05000327/LER-1997-007, Forwards LER 97-007-00,providing Details Re Start of Three Available Diesel Generators Occurring as Result of Cable That Was Cut While Drilling Hole in Control Room Electrical Panel | Forwards LER 97-007-00,providing Details Re Start of Three Available Diesel Generators Occurring as Result of Cable That Was Cut While Drilling Hole in Control Room Electrical Panel | 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000327/LER-1997-008-01, Forwards LER 97-008-01,adding Details to Revised Rept Re Inadequate Surveillance Testing of Three Functions of Solid State Protection Sys.Revs Annotated by Vertical Bar in Right Hand Margin | Forwards LER 97-008-01,adding Details to Revised Rept Re Inadequate Surveillance Testing of Three Functions of Solid State Protection Sys.Revs Annotated by Vertical Bar in Right Hand Margin | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000327/LER-1997-008, :on 970322,noted Failure to Properly Perform Surveillance Testing of Containment Air Return Fan Start, Blackout & Auto Sequencing of Station Fire Pumps & Three Functions of Ssps Due to Inadequate Si.Revised Procedures |
- on 970322,noted Failure to Properly Perform Surveillance Testing of Containment Air Return Fan Start, Blackout & Auto Sequencing of Station Fire Pumps & Three Functions of Ssps Due to Inadequate Si.Revised Procedures
| |
| 05000328/LER-1997-009, :on 970401,licensed Failed to Maintain 2 Offsite Power Sources as Required by Ts.Caused Because Main Contact Compression Was Out of Tolerance.Start Bus 1A Was Transfered to Normal Feed Breaker |
- on 970401,licensed Failed to Maintain 2 Offsite Power Sources as Required by Ts.Caused Because Main Contact Compression Was Out of Tolerance.Start Bus 1A Was Transfered to Normal Feed Breaker
| 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)(viii) |
| 05000327/LER-1997-009-02, :on 970521,failed to Perform Response Time Testing of Containment Radiation Monitor Following Maint Activities.Caused by Misinterpretation of Surveillance Requirements.Tested Radiation Monitor |
- on 970521,failed to Perform Response Time Testing of Containment Radiation Monitor Following Maint Activities.Caused by Misinterpretation of Surveillance Requirements.Tested Radiation Monitor
| 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)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(viii) |
| 05000327/LER-1997-010, Forwards LER 97-010-00,re Failure to Properly Return Portion of Fire Protection Sys to Svc Following Mod Activity | Forwards LER 97-010-00,re Failure to Properly Return Portion of Fire Protection Sys to Svc Following Mod Activity | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000327/LER-1997-010-01, :on 970626,failure to Properly Return Portion of Fire Protection Sys to Svc Following Mod Activities Was Noted.Caused by Failure to Follow Procedures.Manual Isolation Valve Was Opened |
- on 970626,failure to Properly Return Portion of Fire Protection Sys to Svc Following Mod Activities Was Noted.Caused by Failure to Follow Procedures.Manual Isolation Valve Was Opened
| 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)(viii) |
| 05000327/LER-1997-012-01, :on 970801,manual Reactor Tripped Due to Loss of Control Air.Caused by Corrosion Products (Rust Debris) Inhibiting Full Closure of One of six-inch Gate Valves. Isolated Breached Control & Svc Air Sys Header |
- on 970801,manual Reactor Tripped Due to Loss of Control Air.Caused by Corrosion Products (Rust Debris) Inhibiting Full Closure of One of six-inch Gate Valves. Isolated Breached Control & Svc Air Sys Header
| 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)(i)
10 CFR 50.73(a)(2)(iii)
10 CFR 50.73(a)(2)(viii) |
| 05000327/LER-1997-013-02, Forwards LER 97-013-02 Re Addl Conditions Identified During Performance of Corrective Actions.Details Added to Revs for Two Fuses,Not Included in Surveillance Program | Forwards LER 97-013-02 Re Addl Conditions Identified During Performance of Corrective Actions.Details Added to Revs for Two Fuses,Not Included in Surveillance Program | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000327/LER-1997-013-01, Forwards LER 97-013-01 Re Missed Surveillance as Result of Inadequate Procedure.Revs Annotated by Vertical Bar to Right of Text | Forwards LER 97-013-01 Re Missed Surveillance as Result of Inadequate Procedure.Revs Annotated by Vertical Bar to Right of Text | 10 CFR 50.73(a)(2)(1) |
| 05000327/LER-1997-014-01, :on 971101,discovered That RCS PORVs Were Not Cycled in Mode 4 as Required by Ts.Caused by Inadequate Procedures.Procedure Revised & Unit Cooled Down to Mode 4 |
- on 971101,discovered That RCS PORVs Were Not Cycled in Mode 4 as Required by Ts.Caused by Inadequate Procedures.Procedure Revised & Unit Cooled Down to Mode 4
| 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)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(i)
10 CFR 50.73(a)(2)(iii)
10 CFR 50.73(a)(2)(viii) |
