PNO-III-85-093B, on 851029,reactor Trip Breaker & Associated Undervoltage Trip Actuating Device Failed.Breaker Mods Expected to Be Completed on 851105.Elements of Confirmatory Action Ltr Met Except for Cause of Device Failure
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| ML20209H282 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 11/04/1985 |
| From: | Chrissotimos N, Hehl C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| References | |
| PNO-III-85-093B, PNO-III-85-93B, NUDOCS 8511110061 | |
| Download: ML20209H282 (1) | |
Similar Documents at Cook | |
|---|---|
Category:PRELIMINARY NOTIFICATION OF EVENT OR OCCURRENCE (PNO
MONTHYEARPNO-III-94-006, on 940121,licensee Commenced Shutdown of Unit 2 to Repair Steam Leak That Was Discovered in Vicinity of SG 1.Leak Was Repaired 940125 & Plant Has Commenced Startup1994-01-25025 January 1994
[Table view]PNO-III-94-006:on 940121,licensee Commenced Shutdown of Unit 2 to Repair Steam Leak That Was Discovered in Vicinity of SG 1.Leak Was Repaired 940125 & Plant Has Commenced Startup PNO-III-92-045, on 920908,unit Shut Down Due to High Generator Vibrations.Cause Undetermined.Licensee Will Remove & Inspect Generator Rotor1992-09-0909 September 1992 PNO-III-92-045:on 920908,unit Shut Down Due to High Generator Vibrations.Cause Undetermined.Licensee Will Remove & Inspect Generator Rotor PNO-III-90-049, on 900713,one Person Killed & Three Others Injured When Fatally Injured Worker Touched Live Contact in 4-kV Cabinet.Licensee Declared Unusual Event Under Emergency Plan & Subsequently Terminated1990-07-13013 July 1990 PNO-III-90-049:on 900713,one Person Killed & Three Others Injured When Fatally Injured Worker Touched Live Contact in 4-kV Cabinet.Licensee Declared Unusual Event Under Emergency Plan & Subsequently Terminated PNO-III-90-033, on 900524,licensee Declared Emergency Plan After 765KV Switchyard Breaker Opened Unexpectedly & Control Room Received Rept of Fire & Explosion.Caused by Burning Oil from Crosstie Breaker L.Unit 1 Reduced Power to 62%1990-05-24024 May 1990 PNO-III-90-033:on 900524,licensee Declared Emergency Plan After 765KV Switchyard Breaker Opened Unexpectedly & Control Room Received Rept of Fire & Explosion.Caused by Burning Oil from Crosstie Breaker L.Unit 1 Reduced Power to 62% PNO-III-87-113A, updates Util Evaluation of Defective & Incorrectly Installed Bolts in Facility Containment Access Area.Caused by Use of Improper Cutting & Welding Procedure. Evaluation Continuing1987-09-0303 September 1987 PNO-III-87-113A:updates Util Evaluation of Defective & Incorrectly Installed Bolts in Facility Containment Access Area.Caused by Use of Improper Cutting & Welding Procedure. Evaluation Continuing PNO-III-87-100, on 870723,unusual Event Declared When Contractor Employee Wearing Slightly Contaminated Clothing Taken to Local Hosp.When Clothing Removed,Surveys of Individual & Hosp Showed No Contamination1987-07-24024 July 1987 PNO-III-87-100:on 870723,unusual Event Declared When Contractor Employee Wearing Slightly Contaminated Clothing Taken to Local Hosp.When Clothing Removed,Surveys of Individual & Hosp Showed No Contamination PNO-III-87-098, on 870714,undervoltage on Reactor Coolant Pump Bus Occurred.Caused by Tripping of Unit from 80% Power Due to Voltage Variation.Licensee Decided to Shut Down Unit to Repair Minor Leaks in Reactor Cooling Sys1987-07-15015 July 1987 PNO-III-87-098:on 870714,undervoltage on Reactor Coolant Pump Bus Occurred.Caused by Tripping of Unit from 80% Power Due to Voltage Variation.Licensee Decided to Shut Down Unit to Repair Minor Leaks in Reactor Cooling Sys PNO-III-87-081, on 870610,earthquake Measuring 5.0 on Richter Scale Occurred Near Lawrenceville,Il.Unusual Events Declared by Six Power Stations But No Damage Observed.Ground Motion Felt at Five Other Plants1987-06-11011 June 1987 PNO-III-87-081:on 870610,earthquake Measuring 5.0 on Richter Scale Occurred Near Lawrenceville,Il.Unusual Events Declared by Six Power Stations But No Damage Observed.Ground Motion Felt at Five Other Plants PNO-III-87-032, on 870302,slow,steady Increase in Primary to Secondary Steam Generator Tube Leakage Monitored.On 870303, Leak Estimated at 0.2 Gpm & Unit Taken Out of Svc.Tube Will Be Repaired & Surveillance & Maint Program Implemented1987-03-0404 March 1987 PNO-III-87-032:on 870302,slow,steady Increase in Primary to Secondary Steam Generator Tube Leakage Monitored.On 870303, Leak Estimated at 0.2 Gpm & Unit Taken Out of Svc.Tube Will Be Repaired & Surveillance & Maint Program Implemented PNO-III-86-130, on 861105,during QA Audit of Contractor, Access Badges Removed Due to Inadequacies W/Screening Program.Employees Not Permitted to Return Until Screening Performed by Independent Organization1986-11-0606 November 1986 PNO-III-86-130:on 861105,during QA Audit of Contractor, Access Badges Removed Due to Inadequacies W/Screening Program.Employees Not Permitted to Return Until Screening Performed by Independent Organization PNO-III-86-096, on 860911,bomb Threat Received at Telephone Switchboard,Stating That Bomb Placed in Training Ctr.Ctr Evacuated & Facility Searched.No Bomb Found.Nrc Info Assessment Team Notified1986-09-12012 September 1986 PNO-III-86-096:on 860911,bomb Threat Received at Telephone Switchboard,Stating That Bomb Placed in Training Ctr.Ctr Evacuated & Facility Searched.No Bomb Found.Nrc Info Assessment Team Notified PNO-III-86-094, on 860910,federal Grand Jury in State of Mi Western District Indicted Util & Jg Del Percio W/Violations of NRC Fire Protection Requirements Occurring from Mar 1981 - Apr 19821986-09-10010 September 1986 PNO-III-86-094:on 860910,federal Grand Jury in State of Mi Western District Indicted Util & Jg Del Percio W/Violations of NRC Fire Protection Requirements Occurring from Mar 1981 - Apr 1982 PNO-III-86-072, on 860722,reactor Tripped While Operating at 90% Power.Caused by Workman Error While Attempting to Calibr Stator Cooling Water Pressure Switches.Util Will Proceed to Cold Shutdown for Repairs & Perform Snubber Surveillances1986-07-23023 July 1986 PNO-III-86-072:on 860722,reactor Tripped While Operating at 90% Power.Caused by Workman Error While Attempting to Calibr Stator Cooling Water Pressure Switches.Util Will Proceed to Cold Shutdown for Repairs & Perform Snubber Surveillances PNO-III-86-050, on 860528,at 90% Power,Unit Tripped Following Main Turbine Trip on Overspeed.Caused by Small Leakage in Pressurizer Spray Valve & Letdown Valve.Failure of intermediate-range Detector Under Investigation1986-05-28028 May 1986 PNO-III-86-050:on 860528,at 90% Power,Unit Tripped Following Main Turbine Trip on Overspeed.Caused by Small Leakage in Pressurizer Spray Valve & Letdown Valve.Failure of intermediate-range Detector Under Investigation PNO-III-86-010, on 860201,auxiliary Transformer 2DC on Fire at Bushing Atop Unit.Caused by Trip from 80% Power Due to Main Electrical Fault on Transformer.Repairs & Bus Alignments Evaluated to Facilitate Restart1986-02-0303 February 1986 PNO-III-86-010:on 860201,auxiliary Transformer 2DC on Fire at Bushing Atop Unit.Caused by Trip from 80% Power Due to Main Electrical Fault on Transformer.Repairs & Bus Alignments Evaluated to Facilitate Restart PNO-III-85-099, on 851125,primary Coolant Sys Leaks Noted After Reactor Trip.Most Repairs Completed in Hot Standby. Remaining Leaks,In Two Safety Injection Check Valves & Gasket Flange for Coolant Pump,Scheduled for Cold Repair1985-11-27027 November 1985 PNO-III-85-099:on 851125,primary Coolant Sys Leaks Noted After Reactor Trip.Most Repairs Completed in Hot Standby. Remaining Leaks,In Two Safety Injection Check Valves & Gasket Flange for Coolant Pump,Scheduled for Cold Repair PNO-III-85-093C, on 851106,licensee Submitted Request for Restart Concurrence,Per 851030 Confirmatory Action Ltr.Insp & Testing of Reactor Trip Breakers Completed.Failed Breakers Shipped to Vendors for Testing & Evaluation1985-11-0707 November 1985 PNO-III-85-093C:on 851106,licensee Submitted Request for Restart Concurrence,Per 851030 Confirmatory Action Ltr.Insp & Testing of Reactor Trip Breakers Completed.Failed Breakers Shipped to Vendors for Testing & Evaluation PNO-III-85-093B, on 851029,reactor Trip Breaker & Associated Undervoltage Trip Actuating Device Failed.Breaker Mods Expected to Be Completed on 851105.Elements of Confirmatory Action Ltr Met Except for Cause of Device Failure1985-11-0404 November 1985 PNO-III-85-093B:on 851029,reactor Trip Breaker & Associated Undervoltage Trip Actuating Device Failed.Breaker Mods Expected to Be Completed on 851105.Elements of Confirmatory Action Ltr Met Except for Cause of Device Failure PNO-III-85-093, on 851029,reactor Tripped on Spurious Low Flow Signal in Primary Sys.Unit Will Remain Shut Down Until Licensee Investigation Completed & NRC Concurs W/Findings. Special Insp Team Dispatched.State of Mi Will Be Notified1985-10-29029 October 1985 PNO-III-85-093:on 851029,reactor Tripped on Spurious Low Flow Signal in Primary Sys.Unit Will Remain Shut Down Until Licensee Investigation Completed & NRC Concurs W/Findings. Special Insp Team Dispatched.State of Mi Will Be Notified PNO-III-85-059, on 850716,facility Shut Down to Investigate Increasing primary-to-secondary Sys Leakage in Two Steam Generators.Cause Not Stated.Eddy Current Testing Will Be Performed to Locate & Plug Leaking Tubes1985-07-16016 July 1985 PNO-III-85-059:on 850716,facility Shut Down to Investigate Increasing primary-to-secondary Sys Leakage in Two Steam Generators.Cause Not Stated.Eddy Current Testing Will Be Performed to Locate & Plug Leaking Tubes PNO-III-82-076A, on 820804,stuck Fuel Assembly Freed & Transferred W/O Incident to Spent Fuel Storage Pool.No Release of Radioactivity Evident.Assembly Placed in Normal Storage Location in Spent Fuel Storage1982-08-0505 August 1982 PNO-III-82-076A:on 820804,stuck Fuel Assembly Freed & Transferred W/O Incident to Spent Fuel Storage Pool.No Release of Radioactivity Evident.Assembly Placed in Normal Storage Location in Spent Fuel Storage PNO-III-82-076, on 820804,fuel Assembly Became Wedged in Device Used to Move Assemblies from Vertical to Horizontal Position for Movement Through Fuel Transfer Canal.Caused by Tilting Device in Horizontal Position Instead of Vertical1982-08-0404 August 1982 PNO-III-82-076:on 820804,fuel Assembly Became Wedged in Device Used to Move Assemblies from Vertical to Horizontal Position for Movement Through Fuel Transfer Canal.Caused by Tilting Device in Horizontal Position Instead of Vertical PNO-III-82-073, on 820731,unit Shut Down After Tube Leak Rate of 0.17 Gpm Determined in Steam Generator 2.Licensee Estimates Unit Will Be Down for Several Days for Testing & Leak Location Activities1982-08-0303 August 1982 PNO-III-82-073:on 820731,unit Shut Down After Tube Leak Rate of 0.17 Gpm Determined in Steam Generator 2.Licensee Estimates Unit Will Be Down for Several Days for Testing & Leak Location Activities ML20216J7071978-11-13013 November 1978 PNO-78-192:on 781109,Unit 2 Shutdown for Scheduled Maint & Was in Cold Shutdown at Time of fire.Carbon-dioxide & Dry Chemical Fire Extinguishers,Water to Control & Finally Extinguish Fire.State of Mi Notified ML20248L0831978-03-13013 March 1978 PNO-78-044:on 780310,plant Achieved Initial Criticality.Rod Positions & Boron Concentration at Initial Criticality Were in Very Close Agreement W/Predicted Values.Unit 2 Currently in Low Power Physics Testing ML20207G5911977-11-18018 November 1977 PNO-77-205:on 771118,DC Cook Unit 1 Reactor Initiated Shutdown in Compliance with Order Issued by NRR to Imeco & Impco.Suspension of Power Operation of Facility Will Continue Until Qualified Connectors Installed ML20126D1901977-08-12012 August 1977 PNO-77-143:Pacific Pump Co Supplied Facilities W/Production Lot of 40 Pumps Mfg Using Shafts Made of Inferior Matl. Cause Unstated.All Utils W/Pumps Were Notified.Nrc Headquarters Notified on 770812 ML20151U7061977-03-31031 March 1977 PNO-77-049:on 770330,allegation of Falsification of QC Records Occurred.Region III Personnel Have Appointment to Meet with Individual on 770407.Individual Unavailable Earlier,Due to Move of Residence ML20249B9001976-09-20020 September 1976 PNO-76-158:on 760917,util Informed Region III by Telephone That an Industrial Accident Has Resulted in Death by Asphyxiation of One Construction Worker & Hospitalization of Two Other Workers ML20249B3061976-05-11011 May 1976 PNO-76-085:on 760510,auxiliary Bldg Evacuated as Precautionary Measure for Approx 1 H Due to Leakage of Rc Water from Rc Filter Drain Valve.Region 3 Radiation Protection Specialist Conducting Routine Insp ML20236W9491975-12-0404 December 1975 PN-75-144:on 751204,oil in Oil Bath Air Cleaner for Diesel Generator Cd Was Accidentally Ignited.Plant Personnel Extinguished Fire Before Fire Department Arrived.No Injuries to Personnel & No Damage to Facility Resulted 1994-01-25 Category:TEXT-INSPECTION & AUDIT & I&E CIRCULARS MONTHYEARIR 05000315/19990271999-10-15015 October 1999
[Table view]Partially Deleted Insp Repts 50-315/99-27 & 50-316/99-27 on 990920-24 (Ref 10CFR73.21).Noncited Violation Noted.Major Areas Inspected:Plant Support Activities Re Physical Protection of Plant Facility. 15 IR 05000315/19980241998-12-14014 December 1998 Partially Withheld Insp Repts 50-315/98-24 & 50-316/98-24 on 981112-19 (Ref 10CFR73.71).Violations Noted.Major Areas Inspected:Plant Support Activities Re Physical Protection of DC Cook Facility ML20154L9861998-10-13013 October 1998 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $500,000.Violation Noted:As of 980227,licensee Had Not Provided Instructions Appropriate to Circumstances for Activity Affecting Quality IR 05000315/19980111998-06-0202 June 1998 Partially Withheld Insp Repts 50-315/98-11 & 50-316/98-11 on 980504-08 (Ref 10CFR73.21(c)(2)).No Violations Noted.Major Areas Inspected:Security Program Plans,Security Program Procedures,Security Organization & Administration IR 05000315/19970191997-11-24024 November 1997 Partially Withheld Insp Repts 50-315/97-19 & 50-316/97-19 on 970929-1003 (Ref 10CFR73.21).Violations Noted.Major Areas Inspected:Security Staff Knowledge & Performance,Training & Qualification Program & Organization & Administration IR 05000315/19970071997-04-25025 April 1997 Partially Withheld Insp Repts 50-315/97-07 & 50-316/97-07 on 970324-28 (Ref 10CFR73.21).No Violations.Major Areas Inspected:Review of Physical Security Program IR 05000315/19960081996-10-25025 October 1996 Insp Repts 50-315/96-08 & 50-316/96-08 on 960909-13.No Violations Noted.Major Areas Inspected:Licensee Assessment of Performance in Area of Physical Security PNO-III-94-006, on 940121,licensee Commenced Shutdown of Unit 2 to Repair Steam Leak That Was Discovered in Vicinity of SG 1.Leak Was Repaired 940125 & Plant Has Commenced Startup1994-01-25025 January 1994 PNO-III-94-006:on 940121,licensee Commenced Shutdown of Unit 2 to Repair Steam Leak That Was Discovered in Vicinity of SG 1.Leak Was Repaired 940125 & Plant Has Commenced Startup IR 05000315/19930231993-12-0202 December 1993 Partially Withheld Insp Repts 50-315/93-23 & 50-316/93-23 on 931117-19 & 22-24 (Ref 10CFR73.21).No Violations Noted. Major Areas Inspected:Mgt Support,Security Program Plans & Audits & Protected & Vital Area Physical Barriers IR 05000315/19930021993-02-0505 February 1993 Partially Withheld Insp Repts 50-315/93-02 & 50-316/93-02 on 930119-22.No Violations Noted.Major Areas Inspected:Mgt Support,Protected & Vital Area Physical Barriers,Detection Sys & Detection Aid & Protected & Vital Area Access Control PNO-III-92-045, on 920908,unit Shut Down Due to High Generator Vibrations.Cause Undetermined.Licensee Will Remove & Inspect Generator Rotor1992-09-0909 September 1992 PNO-III-92-045:on 920908,unit Shut Down Due to High Generator Vibrations.Cause Undetermined.Licensee Will Remove & Inspect Generator Rotor IR 05000315/19910111991-06-27027 June 1991 Insp Repts 50-315/91-11 & 50-316/91-11 on 910501-0614.No Violations Noted.Major Areas Inspected:Plant Operations, Reactor Trip,Maint & Surveillance,Engineering & Technical Support & Actions on Previously Identified Items IR 05000315/19900231990-11-29029 November 1990 Insp Repts 50-315/90-23 & 50-316/90-23 on 901010-901113.No Violations Noted.Major Areas Inspected:Plant Operations & Maintenance & Surveillance PNO-III-90-049, on 900713,one Person Killed & Three Others Injured When Fatally Injured Worker Touched Live Contact in 4-kV Cabinet.Licensee Declared Unusual Event Under Emergency Plan & Subsequently Terminated1990-07-13013 July 1990 PNO-III-90-049:on 900713,one Person Killed & Three Others Injured When Fatally Injured Worker Touched Live Contact in 4-kV Cabinet.Licensee Declared Unusual Event Under Emergency Plan & Subsequently Terminated PNO-III-90-033, on 900524,licensee Declared Emergency Plan After 765KV Switchyard Breaker Opened Unexpectedly & Control Room Received Rept of Fire & Explosion.Caused by Burning Oil from Crosstie Breaker L.Unit 1 Reduced Power to 62%1990-05-24024 May 1990 PNO-III-90-033:on 900524,licensee Declared Emergency Plan After 765KV Switchyard Breaker Opened Unexpectedly & Control Room Received Rept of Fire & Explosion.Caused by Burning Oil from Crosstie Breaker L.Unit 1 Reduced Power to 62% IR 05000315/19880181988-08-19019 August 1988 Partially Withheld Insp Repts 50-315/88-18 & 50-316/88-21 on 880705-21 (Ref 10CFR73.21).Noncompliances Noted.Major Areas Inspected:Mgt Effectiveness,Records & Repts,Testing & Maint, Power Supply,Lighting,Compensatory Measures & Vital Areas IR 05000315/19870421987-12-30030 December 1987 Partially Withheld Insp Repts 50-315/87-42 & 50-316/87-42 on 871207-10 (Ref 10CFR73.21).Violation Noted.Major Areas Inspected:Personnel Training & Qualifications,Safeguards Contingency Plan & Compensatory Measures ML20235W2421987-10-0909 October 1987 Exam Repts 50-315/OL-87-02 & 50-316/OL-87-02 on 870804-07. Exam results:3 of 5 Senior Reactor Operator Candidates & 10 of 11 Reactor Operator Candidates Passed Exams ML20235E2681987-09-16016 September 1987 Exam Rept 50-315/OL-87-01 for Units 1 & 2 on 870622-24.Exam Results:Seven Senior Reactor Operators & Two Reactor Operators Failed PNO-III-87-113A, updates Util Evaluation of Defective & Incorrectly Installed Bolts in Facility Containment Access Area.Caused by Use of Improper Cutting & Welding Procedure. Evaluation Continuing1987-09-0303 September 1987 PNO-III-87-113A:updates Util Evaluation of Defective & Incorrectly Installed Bolts in Facility Containment Access Area.Caused by Use of Improper Cutting & Welding Procedure. Evaluation Continuing IR 05000206/19870141987-08-31031 August 1987 Insp Repts 50-206/87-14,50-361/87-13 & 50-362/87-15 on 870524-0704.Violations Noted.Major Areas Inspected: Operational Safety Verification,Evaluation of Plant Trips & Events,Monthly Surveillance Activities & Maint Activities PNO-III-87-100, on 870723,unusual Event Declared When Contractor Employee Wearing Slightly Contaminated Clothing Taken to Local Hosp.When Clothing Removed,Surveys of Individual & Hosp Showed No Contamination1987-07-24024 July 1987 PNO-III-87-100:on 870723,unusual Event Declared When Contractor Employee Wearing Slightly Contaminated Clothing Taken to Local Hosp.When Clothing Removed,Surveys of Individual & Hosp Showed No Contamination PNO-III-87-098, on 870714,undervoltage on Reactor Coolant Pump Bus Occurred.Caused by Tripping of Unit from 80% Power Due to Voltage Variation.Licensee Decided to Shut Down Unit to Repair Minor Leaks in Reactor Cooling Sys1987-07-15015 July 1987 PNO-III-87-098:on 870714,undervoltage on Reactor Coolant Pump Bus Occurred.Caused by Tripping of Unit from 80% Power Due to Voltage Variation.Licensee Decided to Shut Down Unit to Repair Minor Leaks in Reactor Cooling Sys PNO-III-87-081, on 870610,earthquake Measuring 5.0 on Richter Scale Occurred Near Lawrenceville,Il.Unusual Events Declared by Six Power Stations But No Damage Observed.Ground Motion Felt at Five Other Plants1987-06-11011 June 1987 PNO-III-87-081:on 870610,earthquake Measuring 5.0 on Richter Scale Occurred Near Lawrenceville,Il.Unusual Events Declared by Six Power Stations But No Damage Observed.Ground Motion Felt at Five Other Plants IR 05000315/19870041987-03-17017 March 1987 Safety Insp Repts 50-315/87-04 & 50-316/87-04 on 870127-0223.No Violations or Deviations Noted in Five of Six Areas Inspected.Violation Re Visitor Escort Deficiency Addressed in Insp Repts 50-315/87-08 & 50-316/87-08 IR 05000315/19870081987-03-16016 March 1987 Partially Withheld Insp Repts 50-315/87-08 & 50-316/87-08 on 870127-0223 (Ref 10CFR73.21).Violation Noted:Visitor Escort Deficiency ML20207R3701987-03-0909 March 1987 EN-87-015:on 870312,notice of Violation & Proposed Imposition of Civil Penalties in Amount of $50,000 Will Be Issued for License.Action Based on Violation of Tech Spec Re ECCS Subsystems PNO-III-87-032, on 870302,slow,steady Increase in Primary to Secondary Steam Generator Tube Leakage Monitored.On 870303, Leak Estimated at 0.2 Gpm & Unit Taken Out of Svc.Tube Will Be Repaired & Surveillance & Maint Program Implemented1987-03-0404 March 1987 PNO-III-87-032:on 870302,slow,steady Increase in Primary to Secondary Steam Generator Tube Leakage Monitored.On 870303, Leak Estimated at 0.2 Gpm & Unit Taken Out of Svc.Tube Will Be Repaired & Surveillance & Maint Program Implemented IR 05000315/19860381987-03-0303 March 1987 Addendum to Insp Repts 50-315/86-38 & 50-316/86-38,providing Criteria for Comparing Results of Capability Tests & Verification Measurements IR 05000315/19870061987-02-26026 February 1987 Insp Repts 50-315/87-06 & 50-316/87-06 on 870209-11.No Violations,Deficiencies or Deviations Noted.Major Areas Inspected:Annual Emergency Preparedness Exercise.Exercise Weakness Noted in Area of Protective Action Recommendations IR 05000315/19870051987-02-20020 February 1987 Insp Repts 50-315/87-05 & 50-316/87-05 on 870211-12.No Violations or Deviations Noted.Major Areas Inspected:Insp, Testing & Seal Replacement Program for Large Bore Steam Generator Snubbers ML20211J5281987-02-18018 February 1987 Notice of Violation from Insp on 861216-870126 IR 05000315/19870031987-02-18018 February 1987 Insp Repts 50-315/87-03 & 50-316/87-03 on 861216-870126. Violations Noted:Untimely Return to Svc Testing & Inappropriate Surveillance Test Acceptance Criteria IR 05000315/19860411987-01-16016 January 1987 Insp Repts 50-315/86-41 & 50-316/86-41 on 861104-1215. Apparent Violation Noted:Failure to Perform Timely post- Maint Operability Test on Valve & Subsequent Performance of Opposite Train Maint Being Tracked as Unresolved Issue ML20207P5111987-01-0606 January 1987 Exam Rept 50-315/OL-86-03 on 861202-04.Exam Results:Two Senior Reactor Operators & Two Retake Reactor Operators Passed IR 05000315/19860391986-12-0101 December 1986 Partially Withheld Physical Protection Insp Repts 50-315/86-39 & 50-316/86-39 on 861103-06 (Ref 10CFR73.21). No Violations Noted.Licensee Identified Concerns Re Personnel Access Control Program & Contingency Personnel IR 05000315/19860401986-11-28028 November 1986 Insp Repts 50-315/86-40 & 50-316/86-40 on 861103-07.No Violations,Deficiencies or Deviations Noted.Major Areas Inspected:Emergency Preparedness Program ML20214F8181986-11-18018 November 1986 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $25,000.Violations Noted:Wire Lifted at Same Time & Crossed in Power Range Nuclear Instrument Channel NI-41 Without Use of Lifted Wire Form ML20214A3261986-11-13013 November 1986 EN-86-085:on 861118,notice of Violation & Proposed Imposition of Civil Penalties in Amount of $25,000 Issued Based on Failure of Personnel to Follow Procedures,Rendering Two of Four power-range ex-cores Inoperable PNO-III-86-130, on 861105,during QA Audit of Contractor, Access Badges Removed Due to Inadequacies W/Screening Program.Employees Not Permitted to Return Until Screening Performed by Independent Organization1986-11-0606 November 1986 PNO-III-86-130:on 861105,during QA Audit of Contractor, Access Badges Removed Due to Inadequacies W/Screening Program.Employees Not Permitted to Return Until Screening Performed by Independent Organization IR 05000315/19860321986-10-17017 October 1986 Partially Withheld Reactive Physical Security Insp Repts 50-315/86-32 & 50-316/86-32 on 860818-22 & 0908-11 (Ref 10CFR73.21).No Noncompliance Noted.Major Areas Inspected: Inadequate Maint of Safety Equipment.Details Withheld IR 05000315/19860361986-10-0101 October 1986 Insp Repts 50-315/86-36 & 50-316/86-36 on 860922-23.No Violations,Weaknesses or Deviations Noted.Major Areas Inspected:Emergency Preparedness Drill Involving Observations of Key Functions & Locations PNO-III-86-096, on 860911,bomb Threat Received at Telephone Switchboard,Stating That Bomb Placed in Training Ctr.Ctr Evacuated & Facility Searched.No Bomb Found.Nrc Info Assessment Team Notified1986-09-12012 September 1986 PNO-III-86-096:on 860911,bomb Threat Received at Telephone Switchboard,Stating That Bomb Placed in Training Ctr.Ctr Evacuated & Facility Searched.No Bomb Found.Nrc Info Assessment Team Notified PNO-III-86-094, on 860910,federal Grand Jury in State of Mi Western District Indicted Util & Jg Del Percio W/Violations of NRC Fire Protection Requirements Occurring from Mar 1981 - Apr 19821986-09-10010 September 1986 PNO-III-86-094:on 860910,federal Grand Jury in State of Mi Western District Indicted Util & Jg Del Percio W/Violations of NRC Fire Protection Requirements Occurring from Mar 1981 - Apr 1982 ML20206N4901986-08-21021 August 1986 Notice of Violation from Insp on 860707-11 IR 05000315/19860271986-08-20020 August 1986 Insp Repts 50-315/86-27 & 50-316/86-27 on 860707-11. Violation Noted:Failure to Adequately Test ESF Response Time in Unit 1 Steam Generator Water Level hi-hi Level Turbine Trip Reactor Trip Test PNO-III-86-072, on 860722,reactor Tripped While Operating at 90% Power.Caused by Workman Error While Attempting to Calibr Stator Cooling Water Pressure Switches.Util Will Proceed to Cold Shutdown for Repairs & Perform Snubber Surveillances1986-07-23023 July 1986 PNO-III-86-072:on 860722,reactor Tripped While Operating at 90% Power.Caused by Workman Error While Attempting to Calibr Stator Cooling Water Pressure Switches.Util Will Proceed to Cold Shutdown for Repairs & Perform Snubber Surveillances ML20206R9231986-06-30030 June 1986 Exam Rept 50-315/OLS-86-02 on 860519-22.Results of Exam:All Senior Reactor Operator Candidates & Seven Reactor Operator Candidates Passed IR 05000315/19860161986-06-25025 June 1986 Insp Repts 50-315/86-16 & 50-316/86-16 on 860609-11.No Noncompliance,Deviation or Deficiency Noted.Major Areas Inspected:Annual Emergency Preparedness Exercise IR 05000315/19860241986-06-20020 June 1986 Partially Withheld Physical Security Insp Repts 50-315/86-24 & 50-316/86-24 on 860604-05 (Ref 10CFR73.21).Noncompliance Noted:Items Not Searched or Secured as Required by Security Plan 1999-10-15 |
PRELIMINARY NOTIFICATION OF EVENT OR UNUSUAL OCCURRENCE--PNO-III-85-938 Date Novembe B5 This preliminary notification constitutes EARLY notice of events of POSSIBLE safety r public interest significance. The information is as initially received without varification or evaluation, and is basically all that is known by the Region III staff on this date.
Facility: American Electric Power Licensee Emergency Classification:
D. C. Cook Nuclear Plant Notification of an Unusual Event Stevensville, MI 49127 Alert Site Area Emergenc Docket Nos: 50-315; 50-316 General Emergency XX Not Applicable
Subject:
FAILURE OF REACTOR TRIP BREAKER (SECOND UPDATE)
The augmented incident response team, with staff from Region III (Chicago), Office of Nuclear Reactor Regulation, Office of Inspection and Enforcement, and a consultant, remained on site until November 2, 1985. The Region III special inspection effort c)ntinues.
Th failed reactor trip breaker and its associated undervoltage trip actuating device (UVTA) were t:sted and inspected by the licensee with NRC observers present. The testing was able to reproduce the failure of the undervoltage trip actuating device, but did nct identify the root caus5 of the failure. The equipment is to be shipped to an outside laboratary for further testing and cvaluation. NRC and licensee observers will be present for the additional analysis.
T; sting of the second Unit 2 reactor trip breaker (which successfully tripped the reactor on Octob r 29,1985), also resulted in a similar failure of the undervoltage trip actuating device.
The Unit 2 reactor trip breakers are being modified by the installation of automatic shunt trip attachments. This modification is expected to be completed on November 5, 1985, followed by testing of the reactor trip breakers and restart of the unit. All elements of the Oct:ber 30, 1985, Confirmatory Action Letter have been met except for determining the root cause of the UVTA failure, authorization to restart and submission of a formal report.
The Unit 1 breakers had previously been modified. The unit is continuing its refueling outaga startup testing program.
The State of Michigan will be informed of this updated information. This information is current as of 10 a.m. (CST), November 4 1985.
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