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| Northern States Power Company Prairie Island Nuclear Generating Plant 1717 Wakonade Dr. East Welch, Minnesota 55089 4 | | Northern States Power Company Prairie Island Nuclear Generating Plant 1717 Wakonade Dr. East Welch, Minnesota 55089 4 |
| March 17,1997 10 CFR Part 50 Section 50.73 U S Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket Nos. 50-282 License Nos. DPR-42 50-306 DPR-60 Transporting a Heavy Load over Irradiated Fuel or Safe Shutdown Equipment without Establishing the Required Conditions The Licensee Event Report for this occurrence is attached. In the report, we made new NRC commitments indicated as the statements in the "Long term corrective actions" section, starting on page 14. | | March 17,1997 10 CFR Part 50 Section 50.73 U S Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket Nos. 50-282 License Nos. DPR-42 50-306 DPR-60 Transporting a Heavy Load over Irradiated Fuel or Safe Shutdown Equipment without Establishing the Required Conditions The Licensee Event Report for this occurrence is attached. In the report, we made new NRC commitments indicated as the statements in the "Long term corrective actions" section, starting on page 14. |
| This event was reported via the Emergency Notification System in accordance with 10 CFR Part 50, Section 50.72, on February 7,1997. Note that this LER is being submitted more than 30 days after the event identification date. In addition to the event which was reported in accordance with 10 CFR Part 50, Section 50.72, this report discusses two subsequent heavy load lifts. Since the most recent heavy load lift was made only thirteen days prior to the due date for the LER for the first heavy load lift and, in order to obtain the information necessary to provide a complete report on all three heavy load lifts, we requested permission to submit the LER late. An extension was granted verbally via telecon with the NRC Resident inspector on March 6,1997. | | This event was reported via the Emergency Notification System in accordance with 10 CFR Part 50, Section 50.72, on February 7,1997. Note that this LER is being submitted more than 30 days after the event identification date. In addition to the event which was reported in accordance with 10 CFR Part 50, Section 50.72, this report discusses two subsequent heavy load lifts. Since the most recent heavy load lift was made only thirteen days prior to the due date for the LER for the first heavy load lift and, in order to obtain the information necessary to provide a complete report on all three heavy load lifts, we requested permission to submit the LER late. An extension was granted verbally via telecon with the NRC Resident inspector on March 6,1997. |
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| i Please contact us if you require additional information related to this event.
| | Please contact us if you require additional information related to this event. |
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LER-1997-001, Forwards LER 97-001-00 Re Transport of Heavy Load Over Irradiated Fuel or Safe SD Equipment W/O Establishing Required Conditions.Event Reported Via Emergency Emergency Notification Sys IAW 10CFR50.72 on 970207 |
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Northern States Power Company Prairie Island Nuclear Generating Plant 1717 Wakonade Dr. East Welch, Minnesota 55089 4
March 17,1997 10 CFR Part 50 Section 50.73 U S Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket Nos. 50-282 License Nos. DPR-42 50-306 DPR-60 Transporting a Heavy Load over Irradiated Fuel or Safe Shutdown Equipment without Establishing the Required Conditions The Licensee Event Report for this occurrence is attached. In the report, we made new NRC commitments indicated as the statements in the "Long term corrective actions" section, starting on page 14.
This event was reported via the Emergency Notification System in accordance with 10 CFR Part 50, Section 50.72, on February 7,1997. Note that this LER is being submitted more than 30 days after the event identification date. In addition to the event which was reported in accordance with 10 CFR Part 50, Section 50.72, this report discusses two subsequent heavy load lifts. Since the most recent heavy load lift was made only thirteen days prior to the due date for the LER for the first heavy load lift and, in order to obtain the information necessary to provide a complete report on all three heavy load lifts, we requested permission to submit the LER late. An extension was granted verbally via telecon with the NRC Resident inspector on March 6,1997.
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| 05000282/LER-1997-001, :on 970108,auxiliary Building Crane Protective Features Defeated by Wiring Errors.Caused by Wiring Change for New Transmitter critical/non-critical Key Switch. Controllers Being Made to Agree W/One Another |
- on 970108,auxiliary Building Crane Protective Features Defeated by Wiring Errors.Caused by Wiring Change for New Transmitter critical/non-critical Key Switch. Controllers Being Made to Agree W/One Another
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | | 05000306/LER-1997-001, Forwards LER 97-001-00 Re Transport of Heavy Load Over Irradiated Fuel or Safe SD Equipment W/O Establishing Required Conditions.Event Reported Via Emergency Emergency Notification Sys IAW 10CFR50.72 on 970207 | Forwards LER 97-001-00 Re Transport of Heavy Load Over Irradiated Fuel or Safe SD Equipment W/O Establishing Required Conditions.Event Reported Via Emergency Emergency Notification Sys IAW 10CFR50.72 on 970207 | | | 05000306/LER-1997-001-01, :on 970207,heavy Load Transported Over Irradiated Fuel or Safe SD Equipment W/O Establishing Required Conditions.Caused by Failure to Follow D58.Movement of 22 RCP Placed on Hold Until Procedures Revised |
- on 970207,heavy Load Transported Over Irradiated Fuel or Safe SD Equipment W/O Establishing Required Conditions.Caused by Failure to Follow D58.Movement of 22 RCP Placed on Hold Until Procedures Revised
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii) | | 05000282/LER-1997-002-01, :on 970219,failed to Submit Relief Requests for Limited ISI Exams.Caused by Misinterpretation of 10CFR50.55a(g)(1).Prepared Procedure Restablishing Process to Identify,Quantify & Document ISI Exams |
- on 970219,failed to Submit Relief Requests for Limited ISI Exams.Caused by Misinterpretation of 10CFR50.55a(g)(1).Prepared Procedure Restablishing Process to Identify,Quantify & Document ISI Exams
| 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)(x) 10 CFR 50.73(a)(2) | | 05000306/LER-1997-002-02, :on 970318,discharge Valves to RCS Cold Legs Were Closed When RCS Was Above Shutdown Because of Administrative Error.Training Was Provided on Intent of Motherhood Clause to Operations Staff |
- on 970318,discharge Valves to RCS Cold Legs Were Closed When RCS Was Above Shutdown Because of Administrative Error.Training Was Provided on Intent of Motherhood Clause to Operations Staff
| 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)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) | | 05000282/LER-1997-003-02, :on 970325,discovered That Afp Will Trip on Low SG Pressure During Complete Loss of Feedwater ATWS Event. Operability Evaluation of Plant Was Performed |
- on 970325,discovered That Afp Will Trip on Low SG Pressure During Complete Loss of Feedwater ATWS Event. Operability Evaluation of Plant Was Performed
| 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)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) | | 05000306/LER-1997-003-01, :on 970517,Unit 2 Was Brought to Planned Hot Shutdown Condition to Perform Valve Maint in 22 RCP Containment Vault.Caused by Inattention to Detail.Will Evaluate Revising Plant Operating Procedures |
- on 970517,Unit 2 Was Brought to Planned Hot Shutdown Condition to Perform Valve Maint in 22 RCP Containment Vault.Caused by Inattention to Detail.Will Evaluate Revising Plant Operating Procedures
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000306/LER-1997-004-02, :on 970926,determined That Maint Airlock Volumetric Test Exceeded TS 4.4 Required Limit.Caused by Misalignment of Operating Mechanism Shafts W/Shaft Seal Housings.Reduced Shaft Seal Leakages & Revised Procedure |
- on 970926,determined That Maint Airlock Volumetric Test Exceeded TS 4.4 Required Limit.Caused by Misalignment of Operating Mechanism Shafts W/Shaft Seal Housings.Reduced Shaft Seal Leakages & Revised Procedure
| 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown | | 05000282/LER-1997-004-01, :on 970404,AMSAC Actuation Blocking Setpoint Was Inadvertently Set non-conservatively High.Caused by Listed Incorrect Assumption.Amsac Setpoints Were Revised Using Actual Plant Data for Impulse Pressure |
- on 970404,AMSAC Actuation Blocking Setpoint Was Inadvertently Set non-conservatively High.Caused by Listed Incorrect Assumption.Amsac Setpoints Were Revised Using Actual Plant Data for Impulse Pressure
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) | | 05000306/LER-1997-004, Forwards LER 97-004-00 Re Plant Shutdown Due to Greater than Allowable Leakage from Maint Airlock Per Ts.Commitment Made by Util Listed | Forwards LER 97-004-00 Re Plant Shutdown Due to Greater than Allowable Leakage from Maint Airlock Per Ts.Commitment Made by Util Listed | | | 05000306/LER-1997-005-02, :on 971117,sudden Pressure Lockout of Number 10 Transformer Resulted in Auto Load Rejection/Restoration on SR Bus.Caused by Transformer Being Taken Oos.Replaced 10 Transformer Sudden Transformer Relay 63T10 |
- on 971117,sudden Pressure Lockout of Number 10 Transformer Resulted in Auto Load Rejection/Restoration on SR Bus.Caused by Transformer Being Taken Oos.Replaced 10 Transformer Sudden Transformer Relay 63T10
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000282/LER-1997-005, Forwards LER 97-005-00 Which Contained One New Commitment in Italicized Statement in Corrective Action Section | Forwards LER 97-005-00 Which Contained One New Commitment in Italicized Statement in Corrective Action Section | | | 05000282/LER-1997-005-01, :on 970408,surveillance Interval Discrepancies W/Diesel Fuel Oil Sample Analyses Was Identified Due to Lack of Technical Staff Understanding.Diesel Fuel Surveillance Will Be Changed to Require Completion of Required Analyses |
- on 970408,surveillance Interval Discrepancies W/Diesel Fuel Oil Sample Analyses Was Identified Due to Lack of Technical Staff Understanding.Diesel Fuel Surveillance Will Be Changed to Require Completion of Required Analyses
| | | 05000306/LER-1997-005, Forwards LER 97-005-00 Re Sudden Pressure Lockout of Number 10 Transformer Which Resulted in Auto Load Rejection/ Restoration on SR Bus on 971117 | Forwards LER 97-005-00 Re Sudden Pressure Lockout of Number 10 Transformer Which Resulted in Auto Load Rejection/ Restoration on SR Bus on 971117 | | | 05000282/LER-1997-006-01, :on 970411,discovered Log Error in CR Ventilation Sys.Caused by Apparent Oversight During Original Plant Design.Developed Design Change to Modify Logic |
- on 970411,discovered Log Error in CR Ventilation Sys.Caused by Apparent Oversight During Original Plant Design.Developed Design Change to Modify Logic
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) | | 05000282/LER-1997-007, :on 970429,both Trains of Spent Fuel Pool Special Ventilation Were Inoperable While Handling Load Over Spent Fuel.Caused by Misinterpretation of TS 3.8.D.3.Deleted TS Interpretation 3.8-3 & Revised Procedures |
- on 970429,both Trains of Spent Fuel Pool Special Ventilation Were Inoperable While Handling Load Over Spent Fuel.Caused by Misinterpretation of TS 3.8.D.3.Deleted TS Interpretation 3.8-3 & Revised Procedures
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000282/LER-1997-007-01, :on 970429,declared Both Trains of Spent Fuel Pool Special Ventilation Inoperable Due to Handling Load Over Spent Fuel.Deleted TS Interpretation 3.8-3 & Returned Ventilation Sys to Service When Door Was Shut |
- on 970429,declared Both Trains of Spent Fuel Pool Special Ventilation Inoperable Due to Handling Load Over Spent Fuel.Deleted TS Interpretation 3.8-3 & Returned Ventilation Sys to Service When Door Was Shut
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) | | 05000282/LER-1997-008-01, :on 970602,Unit 1 Reactor Trip Occurred.Caused by Electrical Ground in Rod Control Sys.Troubleshooting Activities Were Conducted |
- on 970602,Unit 1 Reactor Trip Occurred.Caused by Electrical Ground in Rod Control Sys.Troubleshooting Activities Were Conducted
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2) | | 05000282/LER-1997-010, :on 970616,failure to Evaluate Condition of Rhrp When Vibration Level During Surveillance Test Was Recorded at Alert Value Was Noted.Caused by Personnel Error. Improved Engineers Knowledge of Requirements |
- on 970616,failure to Evaluate Condition of Rhrp When Vibration Level During Surveillance Test Was Recorded at Alert Value Was Noted.Caused by Personnel Error. Improved Engineers Knowledge of Requirements
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) | | 05000282/LER-1997-011-01, :on 971003,failure to Test Low Pressure auto- Start Function of 121 motor-driven Cooling Water Pump.Caused by Oversight During Surveillance Development.Low Header Pressure auto-start of 121 Mdclp Tested Per TS A.4.5.A 5.a |
- on 971003,failure to Test Low Pressure auto- Start Function of 121 motor-driven Cooling Water Pump.Caused by Oversight During Surveillance Development.Low Header Pressure auto-start of 121 Mdclp Tested Per TS A.4.5.A 5.a
| 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 | | 05000282/LER-1997-011, Forwards LER 97-011-00 Re Failure to Test Low Pressure auto- Start Function of 121 Motor Driven Cooling Water Pump & Inadequate Separation Between Trains a & B Low Pressure auto-start Switches.Two New Commitments Made | Forwards LER 97-011-00 Re Failure to Test Low Pressure auto- Start Function of 121 Motor Driven Cooling Water Pump & Inadequate Separation Between Trains a & B Low Pressure auto-start Switches.Two New Commitments Made | | | 05000282/LER-1997-012-01, :on 971009,chemical & Volume Control Sys Malfunction,Occurred.Caused by Failure to Recognize Shutdown Margin Requirements in Usar.Procedures Modified to Maintain Increased Shutdown Margin |
- on 971009,chemical & Volume Control Sys Malfunction,Occurred.Caused by Failure to Recognize Shutdown Margin Requirements in Usar.Procedures Modified to Maintain Increased Shutdown Margin
| | | 05000282/LER-1997-013, :on 971018,inoperability of AFW & Entry Into TS 3.0.C Was Noted Due to AFW Manual Start During Planned & Orderly Shutdown.Lar Will Be Prepared |
- on 971018,inoperability of AFW & Entry Into TS 3.0.C Was Noted Due to AFW Manual Start During Planned & Orderly Shutdown.Lar Will Be Prepared
| | | 05000282/LER-1997-014, :on 971028,maint Shop Fire in Service Building Occurred.Caused by Spark or Hot Molten Particle Drawn Into Air Filtration Device Which Ignited 1 of 2 Paper Filters. Evacuated Turbine Bldg |
- on 971028,maint Shop Fire in Service Building Occurred.Caused by Spark or Hot Molten Particle Drawn Into Air Filtration Device Which Ignited 1 of 2 Paper Filters. Evacuated Turbine Bldg
| | | 05000282/LER-1997-015, :on 971103,both Trains of CR Special Ventilation Sys Were Inoperable.Caused by Opened Outside Air Supply Dampers to CR Ventilation Sys.Caution Tag Will Be Applied to Maint Control Board |
- on 971103,both Trains of CR Special Ventilation Sys Were Inoperable.Caused by Opened Outside Air Supply Dampers to CR Ventilation Sys.Caution Tag Will Be Applied to Maint Control Board
| | | 05000282/LER-1997-016, :on 971119,condition That Did Not Fully Comply W/Prescriptive Requirements of 10CFR50,App R Section Iii.O, Was Noted.Caused by Inadequate Review.Revised Alarm Response Procedures C47012 & C47512 to Inspect Area Around RCP |
- on 971119,condition That Did Not Fully Comply W/Prescriptive Requirements of 10CFR50,App R Section Iii.O, Was Noted.Caused by Inadequate Review.Revised Alarm Response Procedures C47012 & C47512 to Inspect Area Around RCP
| 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) | | 05000282/LER-1997-017, :on 971206,concluded That Condition of Cabling to 1LT-433 & 1LT-426 Did Not Satisfy Separation Criteria of 10CFR50,App R,Section III.G.2.Caused by Incorrect Design Documentation.Noncombustible Radiant Energy Installed |
- on 971206,concluded That Condition of Cabling to 1LT-433 & 1LT-426 Did Not Satisfy Separation Criteria of 10CFR50,App R,Section III.G.2.Caused by Incorrect Design Documentation.Noncombustible Radiant Energy Installed
| | | 05000282/LER-1997-018, :on 971207,failure to Test auto-start Feature of CR Ventilation Sys Air Handlers Determined.Caused by Procedure Deficiency.Procedure Will Be Revised Prior to Next Scheduled Performance to Test auto-start |
- on 971207,failure to Test auto-start Feature of CR Ventilation Sys Air Handlers Determined.Caused by Procedure Deficiency.Procedure Will Be Revised Prior to Next Scheduled Performance to Test auto-start
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
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