PNO-II-86-045, on 860627,four PORVs Opened,Dropping Primary Sys Pressure from 2,235 Psi to 702 Psi & Temp from 550 F to 450 F in 6 Minutes.Cause Under Investigation.Valves Closed & Safety Injection Initiated
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| ML20212A253 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 06/27/1986 |
| From: | Burger C, Sinkule M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| References | |
| PNO-II-86-045, PNO-II-86-45, NUDOCS 8607280147 | |
| Download: ML20212A253 (1) | |
Similar Documents at Catawba | |
|---|---|
Category:PRELIMINARY NOTIFICATION OF EVENT OR OCCURRENCE (PNO
MONTHYEARPNO-II-99-017, on 990515,indication of Main Generator Ground Fault Was Received While Performing Turbine Startup in Preparation for Placing Unit on Line.Licensee Is Conducting Investigation to Determine Actual Cause of Ground1999-05-18018 May 1999
[Table view]PNO-II-99-017:on 990515,indication of Main Generator Ground Fault Was Received While Performing Turbine Startup in Preparation for Placing Unit on Line.Licensee Is Conducting Investigation to Determine Actual Cause of Ground PNO-II-99-015, on 990503,shutdown in Excess of 72 H Occurred. Licensee Is Still Conducting Investigation Into Cause of Main Generator Protection Lockout & Making Preparations to Inspect & Remove Any Excessive Fouling from Inside Afws1999-05-0505 May 1999 PNO-II-99-015:on 990503,shutdown in Excess of 72 H Occurred. Licensee Is Still Conducting Investigation Into Cause of Main Generator Protection Lockout & Making Preparations to Inspect & Remove Any Excessive Fouling from Inside Afws PNO-II-98-037A, on 980807,update Shutdown in Excess of 72 H Made.Licensee Has Cleaned & Satisfactorily Inspected IC Flow Channels.Licensee Identified Discrepancies in Bolting of IC Intermediate Deck Door Frames & Hinges.Conditions Addressed1998-08-28028 August 1998 PNO-II-98-037A:on 980807,update Shutdown in Excess of 72 H Made.Licensee Has Cleaned & Satisfactorily Inspected IC Flow Channels.Licensee Identified Discrepancies in Bolting of IC Intermediate Deck Door Frames & Hinges.Conditions Addressed PNO-II-98-037, on 980808,shutdown in Excess of 72 H Occurred. Licensee Inspected Approximately Half of Unit 2 Ice Condenser Bay Flow Channels from Intermediate Deck W/No Ice Obstructions in Excess of TS Limit Identified1998-08-10010 August 1998 PNO-II-98-037:on 980808,shutdown in Excess of 72 H Occurred. Licensee Inspected Approximately Half of Unit 2 Ice Condenser Bay Flow Channels from Intermediate Deck W/No Ice Obstructions in Excess of TS Limit Identified PNO-II-98-025, on 980507,AFW Sys Declared Inoperable.Licensee Isolated Valves 1CM-127 & 2CM-127 in Units 1 & 2, Respectively,To Prevent Recurrence Until Permanent Corrective Actions Can Be Developed1998-05-11011 May 1998 PNO-II-98-025:on 980507,AFW Sys Declared Inoperable.Licensee Isolated Valves 1CM-127 & 2CM-127 in Units 1 & 2, Respectively,To Prevent Recurrence Until Permanent Corrective Actions Can Be Developed PNO-II-97-066, on 971230,RCS Leakage Requiring Forced Unit Cooldown Occurred.No Radioactive Release Outside of Reactor Containment Facilities Due to Leakage.Licensee Informed States on Nc & Sc1997-12-31031 December 1997 PNO-II-97-066:on 971230,RCS Leakage Requiring Forced Unit Cooldown Occurred.No Radioactive Release Outside of Reactor Containment Facilities Due to Leakage.Licensee Informed States on Nc & Sc PNO-II-97-064, on 971229,inadvertent Safety Injection Occurred Due to Operators Failing to Perform Step Which Resulted in Cold Leg Injection Valve Being Left Open. Licensee Engineers Performing Evaluation1997-12-29029 December 1997 PNO-II-97-064:on 971229,inadvertent Safety Injection Occurred Due to Operators Failing to Perform Step Which Resulted in Cold Leg Injection Valve Being Left Open. Licensee Engineers Performing Evaluation PNO-II-96-083, on 961214,Unit 2 Shutdown Due to Small Amount of Backleakage Through Injection Sys Discharge Check Valve, Causing Gas Entrainment in B Train of RHR Sys.Nrc Resident Inspectors Observed Unit Shutdown & RHR Testing1996-12-16016 December 1996 PNO-II-96-083:on 961214,Unit 2 Shutdown Due to Small Amount of Backleakage Through Injection Sys Discharge Check Valve, Causing Gas Entrainment in B Train of RHR Sys.Nrc Resident Inspectors Observed Unit Shutdown & RHR Testing PNO-II-96-082, on 961206,Unit 1 Taken Off Line in Order to Investigate/Locate Source of Increase in Unidentified Leakage.Nrc Resident Inspectors Will Continue to Closely Monitor Licensee Recovery Activities1996-12-0606 December 1996 PNO-II-96-082:on 961206,Unit 1 Taken Off Line in Order to Investigate/Locate Source of Increase in Unidentified Leakage.Nrc Resident Inspectors Will Continue to Closely Monitor Licensee Recovery Activities PNO-II-93-021, on 930503,NRC Duty Officer Notified of Suspension of Licensed Operator Who Admitted to Offsite Arrest for Possession of Cocaine.Region II Monitoring Licensee Ongoing Investigation1993-05-0404 May 1993 PNO-II-93-021:on 930503,NRC Duty Officer Notified of Suspension of Licensed Operator Who Admitted to Offsite Arrest for Possession of Cocaine.Region II Monitoring Licensee Ongoing Investigation PNO-II-93-014, on 930324,NRC Duty Officer Notified That Previous Random Screening for Drugs of Licensed Reactor Operator at Plant Had Been Confirmed Positive for Cocaine. State of Sc & Local Officials Have Been Notified1993-03-26026 March 1993 PNO-II-93-014:on 930324,NRC Duty Officer Notified That Previous Random Screening for Drugs of Licensed Reactor Operator at Plant Had Been Confirmed Positive for Cocaine. State of Sc & Local Officials Have Been Notified PNO-II-91-004, on 910227,facility Shutdown Exceeded 48 H. Caused by Leaking Exciter Cooling Water Sys.Sys Under Investigation1991-02-28028 February 1991 PNO-II-91-004:on 910227,facility Shutdown Exceeded 48 H. Caused by Leaking Exciter Cooling Water Sys.Sys Under Investigation PNO-II-89-012, on 890215,security Guard Claimed to Have Been Assaulted Onsite.Guard Treated & Released from Hosp.Guard Involved in Security Event on 890113 Re Inattentiveness on Post.Guard Claimed Inattentiveness Due to Illness1989-02-16016 February 1989 PNO-II-89-012:on 890215,security Guard Claimed to Have Been Assaulted Onsite.Guard Treated & Released from Hosp.Guard Involved in Security Event on 890113 Re Inattentiveness on Post.Guard Claimed Inattentiveness Due to Illness PNO-II-88-047, on 880805,unit Shut Down Due to Primary to Secondary Leak in D Steam Generator.Generator Found to Have Unretrievable Part in Secondary Side During Last Outage.Eddy Current Tests of Two Generators Planned1988-08-0808 August 1988 PNO-II-88-047:on 880805,unit Shut Down Due to Primary to Secondary Leak in D Steam Generator.Generator Found to Have Unretrievable Part in Secondary Side During Last Outage.Eddy Current Tests of Two Generators Planned PNO-II-88-044, on 880716,reactor Shut Down for Repair of Failed Charging Pump 2A.Shutdown Exceeded 48 H.Cause of Failure Under Investigation.Disassembly & Replacement of Pump Rotating Element Necessary.Startup Expected on 8807211988-07-18018 July 1988 PNO-II-88-044:on 880716,reactor Shut Down for Repair of Failed Charging Pump 2A.Shutdown Exceeded 48 H.Cause of Failure Under Investigation.Disassembly & Replacement of Pump Rotating Element Necessary.Startup Expected on 880721 PNO-II-88-018A, suppl to PNO-II-88-018A,issued on 880309. NRC Augmented Insp Team on 880309 Has Completed Onsite Segment of Intended Mission.Licensee Given Concurrence to Restart Unit 2 on 880318 Based on Review of Insp Results1988-03-18018 March 1988 PNO-II-88-018A:suppl to PNO-II-88-018A,issued on 880309. NRC Augmented Insp Team on 880309 Has Completed Onsite Segment of Intended Mission.Licensee Given Concurrence to Restart Unit 2 on 880318 Based on Review of Insp Results PNO-II-88-018, on 880309,unit Tripped from 21% Power Resulting in Feedwater Isolation Which Caused Steam Generator Levels to Decrease1988-03-10010 March 1988 PNO-II-88-018:on 880309,unit Tripped from 21% Power Resulting in Feedwater Isolation Which Caused Steam Generator Levels to Decrease PNO-II-88-016, approx Six Gallons of Hydrazine Was Discharged Into Lake Wylie from Waste Water Treatment Pond at Catawba Nuclear Station Near York,Sc,Between Hrs of 9:40 Monday Night & 9:20 Tuesday Morning1988-03-0303 March 1988 PNO-II-88-016:approx Six Gallons of Hydrazine Was Discharged Into Lake Wylie from Waste Water Treatment Pond at Catawba Nuclear Station Near York,Sc,Between Hrs of 9:40 Monday Night & 9:20 Tuesday Morning PNO-II-88-012, on 880208,small Unplanned Gas Released Into Auxiliary Bldg & Ventilated to Atmosphere.Release within Allowable Limits & Not Required to Be Reported to Nrc.States of Sc & Nc Informed1988-02-0909 February 1988 PNO-II-88-012:on 880208,small Unplanned Gas Released Into Auxiliary Bldg & Ventilated to Atmosphere.Release within Allowable Limits & Not Required to Be Reported to Nrc.States of Sc & Nc Informed PNO-II-87-033, on 870522,plant Taken Out of Svc to Repair Two Leaks in Resistance Temp Detector Loop on RCS Cold Leg. Shutdown of Greater than 48 H Estimated for Cleanup of Boric Acid & Repair.Unit Will Remain in Hot Standby1987-05-22022 May 1987 PNO-II-87-033:on 870522,plant Taken Out of Svc to Repair Two Leaks in Resistance Temp Detector Loop on RCS Cold Leg. Shutdown of Greater than 48 H Estimated for Cleanup of Boric Acid & Repair.Unit Will Remain in Hot Standby PNO-II-87-015A, on 870305,two High Temp Bearing Trips Occurred.Caused by Failure of California Controls Eutectic Type Temp Sensors.No Damage,Unusual Wear or Excessive Temps Revealed.Diesel Generator 1-B Journal Bearing Refurbished1987-03-11011 March 1987 PNO-II-87-015A:on 870305,two High Temp Bearing Trips Occurred.Caused by Failure of California Controls Eutectic Type Temp Sensors.No Damage,Unusual Wear or Excessive Temps Revealed.Diesel Generator 1-B Journal Bearing Refurbished PNO-II-87-015, on 870305,unit out-of-svc Greater than 48 H. Caused by Damaged Journal Bearing in One Tdi Diesel Generator.Damaged Bearing Found During Routine Maint & Replaced1987-03-0606 March 1987 PNO-II-87-015:on 870305,unit out-of-svc Greater than 48 H. Caused by Damaged Journal Bearing in One Tdi Diesel Generator.Damaged Bearing Found During Routine Maint & Replaced PNO-II-86-063, on 860901,plant Shut Down Due to Main Generator Turbine Trip Resulting from phase-to-phase Fault. Investigation of Cause & Full Extent of Damage Continuing. Unit Will Be Out of Svc for at Least 3 Months1986-09-0404 September 1986 PNO-II-86-063:on 860901,plant Shut Down Due to Main Generator Turbine Trip Resulting from phase-to-phase Fault. Investigation of Cause & Full Extent of Damage Continuing. Unit Will Be Out of Svc for at Least 3 Months PNO-II-86-057, on 860809,while Unit in Hot Standby,Reactor Coolant Pumps Experienced Seal Failure.Leak Initially Estimated at 60 Gpm But Decreased to 30 Gpm After Affected Pump Tripped.Unit Shut Down to Repair Pump Seals1986-08-12012 August 1986 PNO-II-86-057:on 860809,while Unit in Hot Standby,Reactor Coolant Pumps Experienced Seal Failure.Leak Initially Estimated at 60 Gpm But Decreased to 30 Gpm After Affected Pump Tripped.Unit Shut Down to Repair Pump Seals PNO-II-86-045B, on 860628-0701,augmented Insp Team Sent to Plant.Corrective Action Documented in 860630 Confirmatory Action Ltr Being Monitored by NRC Resident Inspectors.Plant at 6% Power1986-07-0707 July 1986 PNO-II-86-045B:on 860628-0701,augmented Insp Team Sent to Plant.Corrective Action Documented in 860630 Confirmatory Action Ltr Being Monitored by NRC Resident Inspectors.Plant at 6% Power PNO-II-86-045A, primary Sys Temp Dropped from 550 F to 465 F in 6 Minutes.Reactor Coolant Pumps Operated Throughout Event.Poor Human Factor Design Features Caused Operators Not to Be in Control1986-07-0101 July 1986 PNO-II-86-045A:primary Sys Temp Dropped from 550 F to 465 F in 6 Minutes.Reactor Coolant Pumps Operated Throughout Event.Poor Human Factor Design Features Caused Operators Not to Be in Control PNO-II-86-045, on 860627,four PORVs Opened,Dropping Primary Sys Pressure from 2,235 Psi to 702 Psi & Temp from 550 F to 450 F in 6 Minutes.Cause Under Investigation.Valves Closed & Safety Injection Initiated1986-06-27027 June 1986 PNO-II-86-045:on 860627,four PORVs Opened,Dropping Primary Sys Pressure from 2,235 Psi to 702 Psi & Temp from 550 F to 450 F in 6 Minutes.Cause Under Investigation.Valves Closed & Safety Injection Initiated PNO-II-86-041, on 860613,25 Gpm Leak Discovered Inside Containment.Caused by 360-degree Crack in Socket Weld to Flange for Variable Orifice Control Valve Outlet Side.Weld Will Be Analyzed by Westinghouse for Metal Fatigue1986-06-17017 June 1986 PNO-II-86-041:on 860613,25 Gpm Leak Discovered Inside Containment.Caused by 360-degree Crack in Socket Weld to Flange for Variable Orifice Control Valve Outlet Side.Weld Will Be Analyzed by Westinghouse for Metal Fatigue PNO-II-86-033, on 860508,Unit 2 Achieved Initial Criticality. All Parameters Near Anticipated Levels.Region II Based & Resident Inspectors Witnessed Event.Util Issuing News Release1986-05-0909 May 1986 PNO-II-86-033:on 860508,Unit 2 Achieved Initial Criticality. All Parameters Near Anticipated Levels.Region II Based & Resident Inspectors Witnessed Event.Util Issuing News Release PNO-II-86-018, on 860225,facility Began Initial Fuel Loading1986-02-25025 February 1986 PNO-II-86-018:on 860225,facility Began Initial Fuel Loading PNO-II-85-123, on 851230,two Contractor Vehicles Used to Provide Svc to Cafeteria Were Allowed Escorted Entry Into Licensee Protected Area.One of Vehicle Drivers Produced .38 Caliber Revolver Upon Entering Protected Area1985-12-30030 December 1985 PNO-II-85-123:on 851230,two Contractor Vehicles Used to Provide Svc to Cafeteria Were Allowed Escorted Entry Into Licensee Protected Area.One of Vehicle Drivers Produced .38 Caliber Revolver Upon Entering Protected Area PNO-II-85-115, licensee Reported That Transamerica Delaval DG 2B Experienced Two Failures of Main Bearing Number 7 During Test Runs Following tear-down Inspection.Believed That First Failure Due to Inadequately Supported Bearing1985-12-0606 December 1985 PNO-II-85-115:licensee Reported That Transamerica Delaval DG 2B Experienced Two Failures of Main Bearing Number 7 During Test Runs Following tear-down Inspection.Believed That First Failure Due to Inadequately Supported Bearing PNO-II-85-096, on 851018,reactor Shut Down Due to Unidentified RCS Leak of 1.3 Gpm.Cause Under Investigation. Probably Caused by RHR Valve Packing Leak.Plant in Hot Standby for 72 H1985-10-21021 October 1985 PNO-II-85-096:on 851018,reactor Shut Down Due to Unidentified RCS Leak of 1.3 Gpm.Cause Under Investigation. Probably Caused by RHR Valve Packing Leak.Plant in Hot Standby for 72 H PNO-II-85-057, on 850606,during Routine Patrol,Breach of Plant Vital Area Discovered.Security Panel in Vent Duct Adjacent to Fire Door Bent Back.Security Officer Posted at Barrier.No Abnormal Conditions Found in Vital Area1985-06-0707 June 1985 PNO-II-85-057:on 850606,during Routine Patrol,Breach of Plant Vital Area Discovered.Security Panel in Vent Duct Adjacent to Fire Door Bent Back.Security Officer Posted at Barrier.No Abnormal Conditions Found in Vital Area PNO-II-85-004, on 850107,initial Criticality Achieved.All Parameters within Predicted Ranges.Low Power Testing Proceeding According to Schedule1985-01-0808 January 1985 PNO-II-85-004:on 850107,initial Criticality Achieved.All Parameters within Predicted Ranges.Low Power Testing Proceeding According to Schedule PNO-II-82-070, on 820618,radiography Crew Experienced Disconnection of Radioactive Source While Source Outside Shield.Caused Not Stated.Source Safely Returned to Shield1982-06-22022 June 1982 PNO-II-82-070:on 820618,radiography Crew Experienced Disconnection of Radioactive Source While Source Outside Shield.Caused Not Stated.Source Safely Returned to Shield 1999-05-05 Category:TEXT-INSPECTION & AUDIT & I&E CIRCULARS MONTHYEARIR 05000413/19993021999-10-12012 October 1999
[Table view]NRC Operator Licensing Retake Exam Repts 50-413/99-302 & 50-414/99-302 (Including Completed & Graded Tests) for Tests Administered on 990921-23.Two Out of Three RO Candidates & One SRO Passed Retake Exam IR 05000413/19993011999-09-30030 September 1999 NRC Operator Licensing Exam Repts 50-413/99-301 & 50-414/99-301 (Including Completed & Graded Tests) for Tests Administered on 990524-27,0603,07-10 & 16.Eight of Fourteen Applicants Passed Exam IR 05000413/19990051999-09-24024 September 1999 Insp Repts 50-413/99-05 & 50-414/99-05 on 990718-0828. Violations Noted.Major Areas Inspected:Licensee Operations, Maint,Engineering & Plant Support IR 05000413/19990041999-08-13013 August 1999 Insp Repts 50-413/99-04 & 50-414/99-04 on 990606-0717. Non-cited Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support ML20210H2211999-07-22022 July 1999 Notice of Violation from Insp on 990314-0424.Violation Noted:Sss Was Not Inoperable for Thirteen Days Because Electrical Breakers Associated with SSS Motor Control Ctr Were Mispositioned ML20209E2831999-07-0101 July 1999 Insp Repts 50-413/99-03 & 50-414/99-03 on 990425-0605. Non-cited Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support IR 05000413/19990111999-06-0202 June 1999 Insp Repts 50-413/99-11 & 50-414/99-11 on 990422-23 & 0503. No Violations Noted.Major Areas Inspected:Licensee Identified Frost & Ice Buildup Which Affected Unit 1 Ice Condenser Lower Inlet Doors IR 05000413/19990021999-05-20020 May 1999 Insp Repts 50-413/99-02 & 50-414/99-02 on 990314-0424.No Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Maint,Engineering & Plant Support PNO-II-99-017, on 990515,indication of Main Generator Ground Fault Was Received While Performing Turbine Startup in Preparation for Placing Unit on Line.Licensee Is Conducting Investigation to Determine Actual Cause of Ground1999-05-18018 May 1999 PNO-II-99-017:on 990515,indication of Main Generator Ground Fault Was Received While Performing Turbine Startup in Preparation for Placing Unit on Line.Licensee Is Conducting Investigation to Determine Actual Cause of Ground ML20206U4161999-05-10010 May 1999 Insp Repts 50-413/99-10 & 50-414/99-10 on 990314-0424. Violation Being Considered for Escalated Enforcement Action Noted.Major Areas Inspected:Operations PNO-II-99-015, on 990503,shutdown in Excess of 72 H Occurred. Licensee Is Still Conducting Investigation Into Cause of Main Generator Protection Lockout & Making Preparations to Inspect & Remove Any Excessive Fouling from Inside Afws1999-05-0505 May 1999 PNO-II-99-015:on 990503,shutdown in Excess of 72 H Occurred. Licensee Is Still Conducting Investigation Into Cause of Main Generator Protection Lockout & Making Preparations to Inspect & Remove Any Excessive Fouling from Inside Afws IR 05000413/19990011999-04-0606 April 1999 Insp Repts 50-413/99-01 & 50-414/99-01 on 990124-0313. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support ML20207A5881999-02-17017 February 1999 Notice of Violation from Insp on 981213-990123.Violation Noted:Licensee Made Change to Procedures as Described in Updated Final Safety Analysis Rept & Failed to Perform Written Safety Evaluation IR 05000413/19980121999-02-17017 February 1999 Insp Repts 50-413/98-12 & 50-414/98-12 on 981213-990123. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000413/19980111999-01-11011 January 1999 Insp Repts 50-413/98-11 & 50-414/98-11 on 981101-1212.No Violations Noted.Major Areas Inspected:Licensee Operations, Maint,Engineering & Plant Support IR 05000413/19980151999-01-0404 January 1999 Insp Repts 50-413/98-15 & 50-414/98-15 on 981102-06 & 16-20. No Violations Noted.Major Areas Inspected:Licensee Corrective Action Program by Sampling Activities Defined in Nuclear Sys Directive 210,rev 1 IR 05000413/19980161998-12-0404 December 1998 Insp Repts 50-413/98-16 & 50-414/98-16 on 980915-1101.No Violations Rept Encl.Major Areas Inspected:Licensee Maint, Surveillance & Engineering Programs Involving Unit 2 Ice Condenser IR 05000413/19980101998-11-23023 November 1998 Insp Repts 50-413/98-10 & 50-414/98-10 on 980927-1031.No Violations Noted.Major Areas Inspected:Licensee Operations, Engineering & Plant Support ML20155B3821998-10-19019 October 1998 Insp Repts 50-413/98-13 & 50-414/98-13 on 980807-0915. Apparent Violations Being Considered for Escalated Enforcement Action.Major Areas Inspected:Review Ice Condenser Related Problems,Which Led to Forced Shutdown ML20154C4301998-09-14014 September 1998 Notice of Violation from Insp on 980705-0815.Violation Noted:Licensee Failed to Establish Adequate Surveillance Procedures IR 05000413/19980081998-09-14014 September 1998 Insp Repts 50-413/98-08 & 50-414/98-08 on 980705-0815. Violations Noted.Major Areas Inspected:Operations,Maint & Engineering PNO-II-98-037A, on 980807,update Shutdown in Excess of 72 H Made.Licensee Has Cleaned & Satisfactorily Inspected IC Flow Channels.Licensee Identified Discrepancies in Bolting of IC Intermediate Deck Door Frames & Hinges.Conditions Addressed1998-08-28028 August 1998 PNO-II-98-037A:on 980807,update Shutdown in Excess of 72 H Made.Licensee Has Cleaned & Satisfactorily Inspected IC Flow Channels.Licensee Identified Discrepancies in Bolting of IC Intermediate Deck Door Frames & Hinges.Conditions Addressed IR 05000413/19980091998-08-26026 August 1998 Insp Repts 50-413/98-09 & 50-414/98-09 on 980816-0826. Examples of Two Apparent Violations Noted.Major Areas Inspected:Operations,Maint,Engineering & Plant Support PNO-II-98-037, on 980808,shutdown in Excess of 72 H Occurred. Licensee Inspected Approximately Half of Unit 2 Ice Condenser Bay Flow Channels from Intermediate Deck W/No Ice Obstructions in Excess of TS Limit Identified1998-08-10010 August 1998 PNO-II-98-037:on 980808,shutdown in Excess of 72 H Occurred. Licensee Inspected Approximately Half of Unit 2 Ice Condenser Bay Flow Channels from Intermediate Deck W/No Ice Obstructions in Excess of TS Limit Identified ML20236V7351998-07-27027 July 1998 Notice of Violation from Insp on 980524-0704.Violation Noted:Licensee Failed to Identify & Take Prompt C/A Following Unit 1 Upper Surge Tank over-temp Events on 960120,980111 & 0507 IR 05000413/19980071998-07-27027 July 1998 Insp Repts 50-413/98-07 & 50-414/98-07 on 980524-0704. Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support,Including Physical Security IR 05000413/19980051998-06-22022 June 1998 Insp Repts 50-413/98-05 & 50-414/98-05 on 980412-0523.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support ML20236J7471998-06-11011 June 1998 Notice of Violation from Insp on 980222-0411.Violation Noted:Adminstrative & Surveillance Procedures Not Implemented as Evidenced by Listed Examples IR 05000413/19980061998-06-0505 June 1998 Insp Repts 50-413/98-06 & 50-414/98-06 on 980511-15. Violations Noted.Major Areas Inspected:Facts Surrounding Event Associated W/Degradation of CNS Unit Auxiliary Feedwater Sys During Rapid down-power on 980507 PNO-II-98-025, on 980507,AFW Sys Declared Inoperable.Licensee Isolated Valves 1CM-127 & 2CM-127 in Units 1 & 2, Respectively,To Prevent Recurrence Until Permanent Corrective Actions Can Be Developed1998-05-11011 May 1998 PNO-II-98-025:on 980507,AFW Sys Declared Inoperable.Licensee Isolated Valves 1CM-127 & 2CM-127 in Units 1 & 2, Respectively,To Prevent Recurrence Until Permanent Corrective Actions Can Be Developed IR 05000413/19980031998-04-30030 April 1998 Insp Repts 50-413/98-03 & 50-414/98-03 on 980222-0411. Violations Being Considered for Escalated Enforcement Action.Major Areas Inspected:Aspects of Licensee Operations, Maint,Engineering & Plant Support IR 05000413/19980041998-04-20020 April 1998 Insp Repts 50-413/98-04 & 50-414/98-04 on 980302-06.No Violations Noted.Major Areas Inspected:Observation & Evaluation of Biennial Emergency Preparedness Exercise for Plant ML20217G5661998-03-23023 March 1998 Insp Repts 50-413/98-01 & 50-414/98-01 on 980111-0221. Violations Noted.Major Areas Inspected:Operation,Maint, Engineering & Plant Support ML20217G5551998-03-23023 March 1998 Notice of Violation from Insp on 980111-0221.Violation Noted:Licensee Failed to Perform Written Safety Evaluation for Closing Valves 1CA-6 & 2CA-6 IR 05000413/19980021998-02-17017 February 1998 Partially Withheld Insp Repts 50-413/98-02 & 50-414/98-02 on 980112-13 (Ref 10CFR2.790).No Violations Noted.Major Areas Inspected:Plant Support,Including Malevolent Use of Vehicles at Plant ML20203L6301998-02-0909 February 1998 Insp Repts 50-413/97-15 & 50-414/97-15 on 971123-980110. Violations Noted.Major Areas Inspected:Operations,Maint & Plant Support ML20203L6251998-02-0909 February 1998 Notice of Violation from Insp on 971123-980110.Violation Noted:Changes to Radiological Conditions in 1B Residual Heat Removal Pump Room Not Logged to Reflect Changes in Dress Requirements ML20199L6301998-02-0202 February 1998 Notice of Violation from Insp & Exam on 971117-21 & 971201-19.Violation Noted:As of 971219,selected Officers from Site Security Force Had Not Been Retrained to Perform non-licensed Operator Emergency Tasks for Starting Ssf PNO-II-97-066, on 971230,RCS Leakage Requiring Forced Unit Cooldown Occurred.No Radioactive Release Outside of Reactor Containment Facilities Due to Leakage.Licensee Informed States on Nc & Sc1997-12-31031 December 1997 PNO-II-97-066:on 971230,RCS Leakage Requiring Forced Unit Cooldown Occurred.No Radioactive Release Outside of Reactor Containment Facilities Due to Leakage.Licensee Informed States on Nc & Sc PNO-II-97-064, on 971229,inadvertent Safety Injection Occurred Due to Operators Failing to Perform Step Which Resulted in Cold Leg Injection Valve Being Left Open. Licensee Engineers Performing Evaluation1997-12-29029 December 1997 PNO-II-97-064:on 971229,inadvertent Safety Injection Occurred Due to Operators Failing to Perform Step Which Resulted in Cold Leg Injection Valve Being Left Open. Licensee Engineers Performing Evaluation ML20197F2481997-12-19019 December 1997 Notice of Violation from Insp on 971012-1122.Violation Noted:Licensee Failed to Follow Radiation Protection Procedures in That,Current Radiation Dose Rates Were Not on Vacuum Cleaner Label as Required IR 05000414/19970081997-12-19019 December 1997 Notice of Deviation from Insp on 971012-1122.Deviation Noted:On 971020,licensee Had Not Performed Alarm Set Point Adjustment Evaluation Discussed in Violation 50-414/97-08-01 ML20197F2861997-12-19019 December 1997 Insp Repts 50-413/97-14 & 50-414/97-14 on 971012-1122. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support ML20199G0351997-11-10010 November 1997 Notice of Violation from Insp on 970831-1011.Violations Noted:Licensee Failed to Follow Procedures for Security Badge Access Control as Evidenced.On 970909,security Failed to Destroy & Unassign Access Badge of Terminated Individual IR 05000413/19970121997-11-10010 November 1997 Insp Repts 50-413/97-12 & 50-414/97-12 on 970831-1011. Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support as Well as Results of Announced Inspection by Regional Security Inspector ML20211L3051997-09-26026 September 1997 Notice of Violation from Insp on 970720-0830.Violation Noted:On 970727,technician Failed to Correctly Review Drawing Number CNEE-2792-01.02,connection Diagram,Main Steam Sys Terminal Cabinet 2SMTC1,rev 12 IR 05000413/19970111997-09-26026 September 1997 Insp Repts 50-413/97-11 & 50-414/97-11 on 970720-0830. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000413/19970101997-09-11011 September 1997 Insp Repts 50-413/97-10 & 50-414/97-10 on 970623-0731.No Violations Noted.Major Areas Inspected:Licensee Calculations,Analysis & Other Engineering Documents ML20210N7341997-08-18018 August 1997 Insp Repts 50-413/97-09 & 50-414/97-09 on 970608-0719. Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Maint,Engineering & Plant Support ML20210N7111997-08-18018 August 1997 Notice of Violation from Insp on 970608-0719.Violation Noted:On 970424,operations Test Group Technician Failed to Open Valve 2NV-873 as Required by Step 2.2.3 of PT/2/A/4200/01C,resulting in Closed Test Vent Flowpath 1999-09-30 |
June 27, 1986 PRELIMINARY NOTIFICATION OF EVENT OR UNUSUAL OCCURRENCE PNO-II-86-45 This preliminary notification constitutes EARLY notice of events of POSSIBLE safety or public interest significance. The information is as initially received without verifi-cation or evaluation, and is basically all that is known by the Region II staff on this date.
FACILITY: Duke Power Company Licensee Emergency Classification:
Catawba Unit 2 X Notification of Unusual Event Docket No. 50-414 Alert Rock Hill, South Carolina Site Area Emergency General Emergency Not Applicable
SUBJECT:
UNEXPECTED REACTOR DEPRESSURIZATION AND C00LDOWN During performance of a scheduled Loss of Control Room Test the four steam system Pressure Operated Relief Valves (PORV) opened at 9:40 a.m., and primary system pressure dropped from 2235 psi to 702 psi and primary sytem temperature dropped from 550 F to 450 F in approximately six minutes. The transient was initiated shortly after the reactor was manually tripped from 25 percent power and control was switched to the auxiliary shutdown panel as prescribed by the test. The event was terminated in approximately 13 minutes when control was transferred back to the control room and the PORVs were closed and safety injected was initiated. The reactor is in mode 3.
The licensee is investigating the cause of the event. Resident inspectors were on site witnessing the Test. An Augmented Inspection Team has been dispatched to the site from the ,
Regional Office to investigate the event. The licensee management has agreed not to l restart the reactor without NRC concurrence.
The State of South Carolina has been notified. The licensee has informed the press through l their regularly scheduled Weekly Generation Report.
l This information is current as of 1:00 p.m. (EDT) on June 27. !
Contact:
C. Burger, 242-4198 M. Sinkule, 242-5506 4
DISTRIBUTION:
H. Street T2I MNBB ypPhillips p.g fE/W g 25 Willste prt MAIL:
Chairman Palladino EDO NRR IE- NMSS ADM:DMB Comm. Roberts PA OIA RES DOT: Trans Only Comm. Asselstine MPA AEOD Applicable State Comm. Bernthal ELO Comm. Zech Air Rights INP0 1 0 "
SECY SP NSAC ACRS y g l, R Regions: _T 72E Licensee: A'/ O l (Reactor Licensees) !
Applicable Resident Site $ 3 7g 8607200147 e60627 PDR pAA C.
%.th6-045 1 L C 3 R o/i
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