PNO-V-86-071, on 861006,reactor Tripped from 20% Power on Low Dnbr.Caused by Feedwater Perturbations.Safety Injection Activated.All Safety Sys Responded as Designed
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| ML20215E964 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 10/07/1986 |
| From: | Miller L, Zimmerman R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| References | |
| PNO-V-86-071, PNO-V-86-71, NUDOCS 8610160034 | |
| Download: ML20215E964 (1) | |
Similar Documents at Palo Verde | |
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Category:PRELIMINARY NOTIFICATION OF EVENT OR OCCURRENCE (PNO
MONTHYEARPNO-V-93-017, on 930922,util Informed NRC That re-review of Eddy Current Test Data Identified Midspan Indications in Two Tubes in Unit 3 SG31.Review Being Performed to Determine If Nonquantifiable Indications Exist.Telcon W/Nrc Scheduled1993-09-22022 September 1993
[Table view]PNO-V-93-017:on 930922,util Informed NRC That re-review of Eddy Current Test Data Identified Midspan Indications in Two Tubes in Unit 3 SG31.Review Being Performed to Determine If Nonquantifiable Indications Exist.Telcon W/Nrc Scheduled PNO-V-93-016, on 930828,plant Restarted After Refueling Outage That Proceeded Tube Rupture Event on 930314.Cause of Tube Rupture Was Due to Intergranular Attack.Unit 3 Operating at 100% Power1993-08-30030 August 1993 PNO-V-93-016:on 930828,plant Restarted After Refueling Outage That Proceeded Tube Rupture Event on 930314.Cause of Tube Rupture Was Due to Intergranular Attack.Unit 3 Operating at 100% Power PNO-V-93-014, on 930811,NRC Was Informed That APS Supervisor Declined to Hire Contract Employee Because Employee Raised Safety Concerns at Plant & Elsewhere.Judge Ruled APS Discriminated Against Employee1993-08-11011 August 1993 PNO-V-93-014:on 930811,NRC Was Informed That APS Supervisor Declined to Hire Contract Employee Because Employee Raised Safety Concerns at Plant & Elsewhere.Judge Ruled APS Discriminated Against Employee PNO-V-93-009D, on 930325,leakage from Reactor Coolant Sys Occurred.Cause of Leak Not Determined1993-03-25025 March 1993 PNO-V-93-009D:on 930325,leakage from Reactor Coolant Sys Occurred.Cause of Leak Not Determined PNO-V-92-010, on 920331,plant Reactor Trip Breaker Failed to Open During Routine Surveillance Test.Licensee Has Unsuccessfully Attempted to Reproduce Failure,In Breaker Cubicle & on Test Stand in Electrical Shop1992-04-0202 April 1992 PNO-V-92-010:on 920331,plant Reactor Trip Breaker Failed to Open During Routine Surveillance Test.Licensee Has Unsuccessfully Attempted to Reproduce Failure,In Breaker Cubicle & on Test Stand in Electrical Shop PNO-V-90-001, on 891230,while at 12% Reactor Power W/Main Generator Sypplying Power to Grid Plants Unit 3 Phase a Main Transformer Experienced Internal Fault,Which Caused Immediate Trip of Main Generator Output Breakers1990-01-0202 January 1990 PNO-V-90-001:on 891230,while at 12% Reactor Power W/Main Generator Sypplying Power to Grid Plants Unit 3 Phase a Main Transformer Experienced Internal Fault,Which Caused Immediate Trip of Main Generator Output Breakers PNO-IV-89-020, Region IV Notified of Recent Reactor Trip at Palo Verde Unit 3 That Was Complicated by Inability to Open Steam Generator Atmospheric Dump Valves Mfg by Control Components,Inc.No Sticking Problems Noted at Other Plants1989-03-23023 March 1989 PNO-IV-89-020:Region IV Notified of Recent Reactor Trip at Palo Verde Unit 3 That Was Complicated by Inability to Open Steam Generator Atmospheric Dump Valves Mfg by Control Components,Inc.No Sticking Problems Noted at Other Plants PNO-V-89-017, on 890315,Palo Verde Unit 2 Initiated Voluntary Shutdown Due to Failures of Adv to Operate at Units 1 & 3.Unit 2 Will Remains in Mode 3 Until Advs Are Demonstrated to Be Operable1989-03-16016 March 1989 PNO-V-89-017:on 890315,Palo Verde Unit 2 Initiated Voluntary Shutdown Due to Failures of Adv to Operate at Units 1 & 3.Unit 2 Will Remains in Mode 3 Until Advs Are Demonstrated to Be Operable PNO-V-89-007, on 890303,main Generator Tripped Followed by Reactor Power Cutback Due to Main Generator Trip & Reactor Trip on Low Steam Generator 2 Pressure.Increase in One Containment Sump Level Was Noted1989-03-0303 March 1989 PNO-V-89-007:on 890303,main Generator Tripped Followed by Reactor Power Cutback Due to Main Generator Trip & Reactor Trip on Low Steam Generator 2 Pressure.Increase in One Containment Sump Level Was Noted PNO-V-88-015, on 880221,safety Injection & Containment Isolation Actuation Signals Received Due to Low Pressurizer Pressure Signal.Caused by Incorrect Bypass of Pressurizer Low Pressure Protection When Unit Entered Mode 51988-02-22022 February 1988 PNO-V-88-015:on 880221,safety Injection & Containment Isolation Actuation Signals Received Due to Low Pressurizer Pressure Signal.Caused by Incorrect Bypass of Pressurizer Low Pressure Protection When Unit Entered Mode 5 PNO-V-87-077, on 871125,facility Issued Full Power License. Unit Currently Operating in Mode 2 at Approx 3% Reactor Power.Licensee Plans to Commence Power Ascension Testing Following Entry Into Mode 11987-11-25025 November 1987 PNO-V-87-077:on 871125,facility Issued Full Power License. Unit Currently Operating in Mode 2 at Approx 3% Reactor Power.Licensee Plans to Commence Power Ascension Testing Following Entry Into Mode 1 PNO-V-87-076, on 871123-24,two Moderate Earthquakes Centered Near Westmoreland,Ca Occurred,Triggering Seismic Alarms at San Onofre.Unusal Event Declared.Plant Sys & Components Not Adversely Affected.Effects on Other Locations Noted1987-11-24024 November 1987 PNO-V-87-076:on 871123-24,two Moderate Earthquakes Centered Near Westmoreland,Ca Occurred,Triggering Seismic Alarms at San Onofre.Unusal Event Declared.Plant Sys & Components Not Adversely Affected.Effects on Other Locations Noted PNO-V-87-072, on 871029 Severe Thunderstorm Struck Site, Knocking Out One Source of Offsite Power & 26 of 39 Emergency Sirens in Maricopa County.Unit 1 Fuel Bldg Door Damaged & Two Individuals Standing Nearby Injured1987-10-30030 October 1987 PNO-V-87-072:on 871029 Severe Thunderstorm Struck Site, Knocking Out One Source of Offsite Power & 26 of 39 Emergency Sirens in Maricopa County.Unit 1 Fuel Bldg Door Damaged & Two Individuals Standing Nearby Injured PNO-V-87-070, on 871025,reactor Brought Critical Following Dilution of Rcs.Actual Critical Boron Concentration 1,010 Ppm W/Group 5 Control Bank 60 Inches Withdrawn.Resident Inspector Witnessed Approach1987-10-26026 October 1987 PNO-V-87-070:on 871025,reactor Brought Critical Following Dilution of Rcs.Actual Critical Boron Concentration 1,010 Ppm W/Group 5 Control Bank 60 Inches Withdrawn.Resident Inspector Witnessed Approach PNO-V-87-069, on 871015,licensee Informed Resident Inspectors of Findings from Ultrasonic Exams of Reactor Coolant Pump Shafts as Result of Mfg Experiences in Europe Re Crack Indicators at End of Impeller Keyway1987-10-15015 October 1987 PNO-V-87-069:on 871015,licensee Informed Resident Inspectors of Findings from Ultrasonic Exams of Reactor Coolant Pump Shafts as Result of Mfg Experiences in Europe Re Crack Indicators at End of Impeller Keyway PNO-V-87-058, on 870827,reactor Shutdown Commenced from 100% Power Level to Investigate Leak in Immediate Area of Valve Used in Refueling Level Monitoring.Caused by Crack in Valve. Valve Will Be Rewelded Following Weld Preparation1987-08-28028 August 1987 PNO-V-87-058:on 870827,reactor Shutdown Commenced from 100% Power Level to Investigate Leak in Immediate Area of Valve Used in Refueling Level Monitoring.Caused by Crack in Valve. Valve Will Be Rewelded Following Weld Preparation PNO-V-87-052, on 870715,loose Copper Windings on Rotor Pole on Train B Diesel Generator Discovered.Caused by Mfg,Parsons Peebles,Improper Application of Resin &/Or Poor Workmanship. Mfg Expected Onsite to Discuss Course of Action1987-07-16016 July 1987 PNO-V-87-052:on 870715,loose Copper Windings on Rotor Pole on Train B Diesel Generator Discovered.Caused by Mfg,Parsons Peebles,Improper Application of Resin &/Or Poor Workmanship. Mfg Expected Onsite to Discuss Course of Action PNO-V-87-050, on 870704,LPSI Pump a Tripped from Motor Overcurrent Condition & Smoke Alarm Received.No Fire Occurred.Caused by Low & Contaminated Oil in Lower Oil Reservoir.Lpsi Motor a Will Be Replaced W/Listed Model1987-07-0707 July 1987 PNO-V-87-050:on 870704,LPSI Pump a Tripped from Motor Overcurrent Condition & Smoke Alarm Received.No Fire Occurred.Caused by Low & Contaminated Oil in Lower Oil Reservoir.Lpsi Motor a Will Be Replaced W/Listed Model PNO-V-87-049, on 870628,reactor Manually Shutdown from 100% Power as Result of Rupture in Train a Circulating Water Loop.Preliminary Insp Revealed Split Weld Seams in Several Places.Licensee Plans to Inspect Condenser Internals1987-06-29029 June 1987 PNO-V-87-049:on 870628,reactor Manually Shutdown from 100% Power as Result of Rupture in Train a Circulating Water Loop.Preliminary Insp Revealed Split Weld Seams in Several Places.Licensee Plans to Inspect Condenser Internals PNO-V-87-043, on 870605,discovered Through Wall Crack in Both 8R Cylinder Head & Piston Liner of Diesel Generator B.Cause Under Review.Piston Liner Replaced.Preparations Made to Install Spare Cylinder Head1987-06-0808 June 1987 PNO-V-87-043:on 870605,discovered Through Wall Crack in Both 8R Cylinder Head & Piston Liner of Diesel Generator B.Cause Under Review.Piston Liner Replaced.Preparations Made to Install Spare Cylinder Head PNO-V-87-042, on 870604,reactor Trip Occurred Due to Low Steam Generator Level.Caused by Malfunction in Automatic Feedwater Control Sys During Sys Troubleshooting/Testing. Investigation Into Cause of Malfunction Ongoing1987-06-0404 June 1987 PNO-V-87-042:on 870604,reactor Trip Occurred Due to Low Steam Generator Level.Caused by Malfunction in Automatic Feedwater Control Sys During Sys Troubleshooting/Testing. Investigation Into Cause of Malfunction Ongoing PNO-V-87-039, on 870521,plant Worker Sprayed W/Reactor Coolant While Replacing Lead Shielding Around post-accident Sampling Sys.Worker Contaminated W/Radioactive Matl on Head & Shoulders.Investigation Initiated1987-05-22022 May 1987 PNO-V-87-039:on 870521,plant Worker Sprayed W/Reactor Coolant While Replacing Lead Shielding Around post-accident Sampling Sys.Worker Contaminated W/Radioactive Matl on Head & Shoulders.Investigation Initiated PNO-V-87-086, on 870510,reactor Shutdown Due to Inoperable Channel C 120-volt Ac Vital Inverter.Outage Tasks Will Include Surveillance Tests,Insp & Repair of Leaking Low Pressure Feedwater Heater & Equipment Problem Repairs1987-05-13013 May 1987 PNO-V-87-086:on 870510,reactor Shutdown Due to Inoperable Channel C 120-volt Ac Vital Inverter.Outage Tasks Will Include Surveillance Tests,Insp & Repair of Leaking Low Pressure Feedwater Heater & Equipment Problem Repairs PNO-V-87-032A, licensee Investigations Into Manner in Which Small Stones Introduced Into Hot Leg Side of Steam Generator 1 Determined That Stones Carried Into Generator During Erection of Work Platform.Tubes in Generators to Be Plugged1987-04-29029 April 1987 PNO-V-87-032A:licensee Investigations Into Manner in Which Small Stones Introduced Into Hot Leg Side of Steam Generator 1 Determined That Stones Carried Into Generator During Erection of Work Platform.Tubes in Generators to Be Plugged PNO-V-87-032, on 870422,small Stones in Bottom Hemispherical Head of Hot Leg Side of Steam Generator 1 Discovered.Work Activities in Steam Generators Suspended Until Primary Side of Steam Generators 1 & 2 Inspected1987-04-23023 April 1987 PNO-V-87-032:on 870422,small Stones in Bottom Hemispherical Head of Hot Leg Side of Steam Generator 1 Discovered.Work Activities in Steam Generators Suspended Until Primary Side of Steam Generators 1 & 2 Inspected PNO-V-87-023, on 870325,facility Granted Low Power Ol. Licensee Plans to Commence Fuel Load on 8703271987-03-26026 March 1987 PNO-V-87-023:on 870325,facility Granted Low Power Ol. Licensee Plans to Commence Fuel Load on 870327 PNO-V-87-012A, on 870208,emergency Diesel 2A Fire Occurred. Caused by Failure of Fuel Line Compression Fitting at Point Where Fuel Line Connected to Right Cylinder Fuel Injector 5. Fuel Line & Fitting Replaced1987-02-17017 February 1987 PNO-V-87-012A:on 870208,emergency Diesel 2A Fire Occurred. Caused by Failure of Fuel Line Compression Fitting at Point Where Fuel Line Connected to Right Cylinder Fuel Injector 5. Fuel Line & Fitting Replaced PNO-V-87-012, on 870208,fire Discovered in Emergency Diesel Train A.Apparently Caused by Ignition of Diesel Fuel Leaking from Separated Compression Fitting in Fuel Injection Line. Fire Extinguished & Room Quarantined Pending Investigation1987-02-0909 February 1987 PNO-V-87-012:on 870208,fire Discovered in Emergency Diesel Train A.Apparently Caused by Ignition of Diesel Fuel Leaking from Separated Compression Fitting in Fuel Injection Line. Fire Extinguished & Room Quarantined Pending Investigation PNO-V-87-007, on 870117,valid High Radiation Alarm on Steam Generator 1 Blowdown Radiation Monitor Received.Caused by Primary to Secondary Leak in Steam Generator.Cooldown in Preparation for Entry Into Steam Generator Continuing1987-01-20020 January 1987 PNO-V-87-007:on 870117,valid High Radiation Alarm on Steam Generator 1 Blowdown Radiation Monitor Received.Caused by Primary to Secondary Leak in Steam Generator.Cooldown in Preparation for Entry Into Steam Generator Continuing PNO-V-86-093A, notification of Util Determination of Cause of Crankcase Malfunction Which Occurred During Preoperational Testing of Train B Diesel Generator.Malfunction Result of Fatigue Cracking of Master Piston Rod 91987-01-0707 January 1987 PNO-V-86-093A:notification of Util Determination of Cause of Crankcase Malfunction Which Occurred During Preoperational Testing of Train B Diesel Generator.Malfunction Result of Fatigue Cracking of Master Piston Rod 9 PNO-V-86-094, on 861224,facility Tripped from 100% Power. Cause Believed to Be Electrical Malfunction on Vital Bus B. Definitive Cause of Malfuncion Under Investigation.Unit Will Be Maintained in Mode 3 Until Cause Identified1986-12-29029 December 1986 PNO-V-86-094:on 861224,facility Tripped from 100% Power. Cause Believed to Be Electrical Malfunction on Vital Bus B. Definitive Cause of Malfuncion Under Investigation.Unit Will Be Maintained in Mode 3 Until Cause Identified PNO-V-86-093, on 861223,crankcase Malfunction Occurred in Train B Diesel Generator Engine.Cause Under Investigation. Fire Dept Personnel Injected Foam Into Crankcase Hole.Diesel Engine Extensively Damaged1986-12-23023 December 1986 PNO-V-86-093:on 861223,crankcase Malfunction Occurred in Train B Diesel Generator Engine.Cause Under Investigation. Fire Dept Personnel Injected Foam Into Crankcase Hole.Diesel Engine Extensively Damaged PNO-V-86-083, on 861119,facility Tripped on Steam Generator 1 Low Level.Caused by Failure of narrow-range Level Instruments & Steam Generator Level Oscillations.Plant Currently in Mode 3 Preparing for Restart by 8611211986-11-20020 November 1986 PNO-V-86-083:on 861119,facility Tripped on Steam Generator 1 Low Level.Caused by Failure of narrow-range Level Instruments & Steam Generator Level Oscillations.Plant Currently in Mode 3 Preparing for Restart by 861121 PNO-V-86-071, on 861006,reactor Tripped from 20% Power on Low Dnbr.Caused by Feedwater Perturbations.Safety Injection Activated.All Safety Sys Responded as Designed1986-10-0707 October 1986 PNO-V-86-071:on 861006,reactor Tripped from 20% Power on Low Dnbr.Caused by Feedwater Perturbations.Safety Injection Activated.All Safety Sys Responded as Designed PNO-V-86-063, on 860912,reactor Trip Occurred from Low Steam Generator Pressure When Four Channels of Steam Flow Lost. Caused by Shorting of Circuit Board.Outage Extended Past 48 H to Rebuild four-way Valve.Reactor Restarted on 8609141986-09-15015 September 1986 PNO-V-86-063:on 860912,reactor Trip Occurred from Low Steam Generator Pressure When Four Channels of Steam Flow Lost. Caused by Shorting of Circuit Board.Outage Extended Past 48 H to Rebuild four-way Valve.Reactor Restarted on 860914 PNO-V-86-055, on 860828,reactor Trip Occurred Due to Generator/Turbine Trip.Caused by Overexcitation After Small Adjustment to Reactive Load.Vendor Contacted to Investigate Problem.Startup Schedule Pending1986-08-29029 August 1986 PNO-V-86-055,on 860828,reactor Trip Occurred Due to Generator/Turbine Trip.Caused by Overexcitation After Small Adjustment to Reactive Load.Vendor Contacted to Investigate Problem.Startup Schedule Pending PNO-V-86-053, on 860805,Unit 2 Turbine Tripped.On 860806,loss of Startup Transformer X03 Caused Loss of Offsite Power Train to Both Units & Resulted in Reactor Trip.Caused by Leak in Main Feed Vent Valve V2491986-08-0606 August 1986 PNO-V-86-053:on 860805,Unit 2 Turbine Tripped.On 860806,loss of Startup Transformer X03 Caused Loss of Offsite Power Train to Both Units & Resulted in Reactor Trip.Caused by Leak in Main Feed Vent Valve V249 PNO-V-86-042, on 860712,reactor Tripped from 100% Power on Low Steam Generator RCS Flow Channels a & B,Causing Turbine Generator Trip,Sys Voltage Fluctuation & Loss of Power.Cause Unknown.Plant Restored to Safe Shutdown Status1986-07-14014 July 1986 PNO-V-86-042:on 860712,reactor Tripped from 100% Power on Low Steam Generator RCS Flow Channels a & B,Causing Turbine Generator Trip,Sys Voltage Fluctuation & Loss of Power.Cause Unknown.Plant Restored to Safe Shutdown Status PNO-V-86-039, on 860708,earthquake w/6.0 Reading on Richter Scale Actuated Seismic Alarms & Recording Instruments. Procedures for Visual Insp of Plant Equipment & Start Test of Diesel Generators Implemented1986-07-0808 July 1986 PNO-V-86-039:on 860708,earthquake w/6.0 Reading on Richter Scale Actuated Seismic Alarms & Recording Instruments. Procedures for Visual Insp of Plant Equipment & Start Test of Diesel Generators Implemented PNO-V-86-037A, unit in Mode 5 Performing Replacement of Reactor Coolant Pump 2A & 2B Seals.Licensee Decided to Also Replace Pump 1A & 1B Seals as Preventive Measure.Plant Restart Projected for Latter Part of Wk1986-07-0707 July 1986 PNO-V-86-037A:unit in Mode 5 Performing Replacement of Reactor Coolant Pump 2A & 2B Seals.Licensee Decided to Also Replace Pump 1A & 1B Seals as Preventive Measure.Plant Restart Projected for Latter Part of Wk PNO-V-86-037, on 860701,licensee Initiated Shutdown from 30% Power Due to Increased Seal Leakage from Reactor Coolant Pump 2B.Shutdown Will Be Maintained to Replace Reactor Coolant Pump Seals.Outage Will Last 8-12 Days1986-07-0303 July 1986 PNO-V-86-037:on 860701,licensee Initiated Shutdown from 30% Power Due to Increased Seal Leakage from Reactor Coolant Pump 2B.Shutdown Will Be Maintained to Replace Reactor Coolant Pump Seals.Outage Will Last 8-12 Days PNO-V-86-035, updates Review of Fire Protection Panel Miswiring & Closes Safeguards Action on PNS-V-86-005 & PNS-V-86-005A Concerning Suspected Attempted Sabotage/ Vandalism & 24,respectively1986-07-0101 July 1986 PNO-V-86-035:updates Review of Fire Protection Panel Miswiring & Closes Safeguards Action on PNS-V-86-005 & PNS-V-86-005A Concerning Suspected Attempted Sabotage/ Vandalism & 24,respectively ML20206M3411986-06-24024 June 1986 PNS-V-86-005A:on 860623,two Addl Instances of Suspected Sabotage/Vandalism Found.Jumpers Identified at 140 Ft Elevation of Auxiliary Bldg & 100 Ft Elevation of Fuel Bldg. Panel Locks Will Be Rekeyed.Security Patrols Increased PNO-V-86-005, on 860618,technicians Performing Initial Sys Checks of Fire Detection Sys Discovered That Internal Wiring for at Least 1 of 18 Panels Modified,Causing Damage to Internal Components1986-06-19019 June 1986 PNO-V-86-005:on 860618,technicians Performing Initial Sys Checks of Fire Detection Sys Discovered That Internal Wiring for at Least 1 of 18 Panels Modified,Causing Damage to Internal Components ML20199F6191986-06-19019 June 1986 PNS-V-86-005:on 860618,internal Wiring for Fire Detection Sys Panel Modified.Initial Energizing of Panel Caused Several 24-volt Components to Overheat Resulting in Internal Sys Damage PNO-V-86-030, on 860527,all Four Channels of Reactor Coolant Low Flow Reactor Trip Protection Declared Inoperable While Unit 1 at 100% Power & Unit 2 at 10E-3% Power.Caused by Misset Rate & Step Channels of Low Flow Trip1986-05-30030 May 1986 PNO-V-86-030:on 860527,all Four Channels of Reactor Coolant Low Flow Reactor Trip Protection Declared Inoperable While Unit 1 at 100% Power & Unit 2 at 10E-3% Power.Caused by Misset Rate & Step Channels of Low Flow Trip ML20210U8051986-05-28028 May 1986 PNS-V-86-004:on 860528,bomb Threat Received from Unknown Male Via Telephone.Administration Bldg & Const Warehouse Searched W/Negative Results.Nrc Operations Ctr & Maricopa County Sheriff Notified PNO-V-86-028, on 860525,while Reducing Power for Turbine Overspeed Trip Test,Operator Error in Controlling Feedwater Flow Caused Reactor Trip.Sys Restored to Normal Mode 3.On 860526 Sys Started & Entered Mode 11986-05-27027 May 1986 PNO-V-86-028:on 860525,while Reducing Power for Turbine Overspeed Trip Test,Operator Error in Controlling Feedwater Flow Caused Reactor Trip.Sys Restored to Normal Mode 3.On 860526 Sys Started & Entered Mode 1 ML20195C1811986-05-21021 May 1986 PNS-V-86-003A:on 860514,licensee Lost Power on Three of Four Transmission Lines.Caused by phase-to-ground Faults at Separate & Remote Locations Possibly Resulting from Sabotage.Fbi Analyzing Evidence ML20195C1881986-05-15015 May 1986 PNS-V-86-003:on 860514,offsite Power on Three of Four Transmission Lines Lost Due to phase-to-ground Faults.Caused by Straps Slung Over Lines.Sabotage Suspected.Law Enforcement Agencies Notified 1993-09-22 Category:TEXT-INSPECTION & AUDIT & I&E CIRCULARS MONTHYEARIR 05000528/19990121999-06-30030 June 1999
[Table view]Insp Repts 50-528/99-12,50-529/99-12 & 50-530/99-12 on 990502-0612.Two Violations Occurred & Being Treated as Noncited Violations.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000528/19990051999-04-21021 April 1999 Partially Withheld Insp Repts 50-528/99-05,50-529/99-05 & 50-530/99-05 on 990322-26 (Ref 10CFR73.21).No Violations Noted.Major Areas Inspected:Licensee Physical Security Program.Details Withheld IR 05000528/19980131998-11-20020 November 1998 Partially Withheld Insp Repts 50-528/98-13,50-529/98-13 & 50-530/98-13 on 981019-24 (Ref 10CFR73.21).Violations Noted. Major Areas Inspected:Licensee Physical Security Program, Including Mgt Support,Security Audits & Plans & Procedures ML20196D6391998-11-20020 November 1998 Notice of Violation from Insp on 981019-24.Violation Noted: Licensee Submitted Physical Security Plan Rev 40 Which Contained 10 Changes to Physical Security Plan That Decreased Safeguard Effectiveness of Plan ML20236N0381998-07-10010 July 1998 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $50,000.Violation Noted:On or About 980310, Unit 3 Operators Failed to Demonstrate Operability of Operable Offsite Power Circuits IR 05000528/19970231997-10-20020 October 1997 Partially Deleted Insp Repts 50-528/97-23,50-529/97-23 & 50-530/97-23 Containing Safeguards Info (Ref 10CFR73.21) on 970922-26.No Violations Noted.Major Areas Inspected:Physical Security Program IR 05000528/19970081997-04-22022 April 1997 Partially Withheld Insp Repts 50-528/97-08,50-529/97-08 & 50-530/97-08 on 970317-21.Violations Noted.Major Areas Inspected:Plant Support.Portions Withheld (Ref 10CFR73.21) ML20138C1071997-04-22022 April 1997 Notice of Violation from Insp on 970317-21.Violation Noted:Safeguards Documents Discovered Outside Protected Area Unsecured in Terminated Employee Desk IR 05000528/19960201997-01-31031 January 1997 Partially Deleted Insp Repts 50-528/96-20,50-529/96-20 & 50-530/96-20 on 961007-11 (Ref 10CFR73.21).No Violations Noted.Major Areas Inspected:Licensee Vehicle Barrier Sys Program Utilizing Ti 2515/132,dtd 960118 IA-98-273, Partially Deleted Investigation Rept 5-93-023R.No Noncompliance Noted.Investigation Conducted to Determine Whether Technician Vacancy at Plant Had Been Discriminated by Plant1994-05-11011 May 1994 Partially Deleted Investigation Rept 5-93-023R.No Noncompliance Noted.Investigation Conducted to Determine Whether Technician Vacancy at Plant Had Been Discriminated by Plant ML20236U9511994-05-11011 May 1994 Partially Deleted Investigation Rept 5-93-023R.No Noncompliance Noted.Investigation Conducted to Determine Whether Technician Vacancy at Plant Had Been Discriminated by Plant ML20059K7021994-01-0505 January 1994 Notice of Violation from Insp on 931102-1206.Violation Noted:On 931103,operators in Unit 1 Failed to Monitor Reactor Coolant Sys Level While Draining for Approx Eight Minutes IR 05000528/19930481994-01-0404 January 1994 Insp Repts 50-528/93-48,50-529/93-48 & 50-530/93-48 on 931102-1206.Violations Noted.Major Areas Inspected:Plant Activities,Surveillance Testing,Plant Maint,Lifting of Main Steam Safety Valve & mid-loop Operations IR 05000528/19930471993-12-16016 December 1993 Insp Repts 50-528/93-47,50-529/93-47 & 50-530/93-47 on 931108-10.No Violations Noted.Major Areas Inspected:Licensee Preparations for 940101 Implementation of Changes to 10CFR20 as Set Forth in Fr 56FR23377,dtd 910521 IR 05000528/19930491993-12-15015 December 1993 Insp Repts 50-528/93-49,50-529/93-49 & 50-530/93-49 on 931115-19.No Violations Noted.Major Areas Inspected:Reviewed Licensee Implementation of Containment LLRT Program & Licensee Actions for Open Items Identified in Insp Rept IR 05000528/19930501993-12-0202 December 1993 Meeting Repts 50-528/93-50,50-529/93-50 & 50-530/93-50 on 931115.No Violations Noted.Major Areas Discussed:Status & Schedule of EOP Rewrite Program & Assessment of Recent Operator Performance Issues IR 05000528/19930431993-11-19019 November 1993 Insp Repts 50-528/93-43,50-529/93-43 & 50-530/93-43 on 930921-1101.No Violations Noted.Major Areas Inspected:Plant Activities,Engineered Safety Features Walkdowns,Surveillance Testing & Plant Maint IR 05000528/19930461993-11-17017 November 1993 Insp Repts 50-528/93-46,50-529/93-46 & 50-530/93-46 on 930913-1029.No Violations Noted.Major Areas Inspected:Review of ISI of ASME Code Class 1,2 & 3 Welds & Licensee Unit 1 SG Eddy Current Insp Activities IR 05000528/19930321993-11-17017 November 1993 Insp Repts 50-528/93-32,50-529/93-32 & 50-530/93-32 on 931018-22.No Violations Noted.Major Areas Inspected: Implementation of Licensee Program to Meet Commitments to GL 89-10, Safety-Related Motor-Operated Valve.. IR 05000528/19930391993-10-28028 October 1993 Insp Repts 50-528/93-39,50-529/93-39 & 50-530/93-39 on 930823-27.No Violations or Deviations Noted.Major Areas Inspected:Open Items in Emergency Preparedness Program Area ML20058D3311993-10-19019 October 1993 Notice of Violation from Insp on 930817-0920.Violation Noted:Between 911225-920113,licensee Engineer Worked More than 72 Hrs in 7 Day Period,Exclusive of Shift Turnover Time W/O Authorization by Manager ML20058D3571993-10-15015 October 1993 Insp Repts 50-528/93-40,50-529/93-40 & 50-530/93-40 on 930817-0920.Violations Noted.Major Areas Inspected:Review of Plant Activities,Engineered Safety Features Walkdowns, Surveillance Testing & Plant Maint ML20059C9811993-10-15015 October 1993 Notice of Violation from Insp on 920719-0824 & 1001-1102. Violation Noted:Licensee Determined That Records Required to Be Maintained by NRC Not Complete or Accurate in All Matl Respects IR 05000528/19930371993-10-0101 October 1993 Insp Repts 50-528/93-37,50-529/93-37 & 50-530/93-37 on 930920-24.One Unresolved Item Identified.Major Areas Inspected:Licensee Radiation Protection Program & Followup of Safety Evaluation Rept IR 05000528/19930421993-09-29029 September 1993 Insp Repts 50-528/93-42,50-529/93-42 & 50-530/93-42 on 930830-0903.No Violations Noted.Major Areas Inspected: on-site Followup of LER in Accordance W/Insp Procedure 92700, Onsite Followup of Written Repts.. PNO-V-93-017, on 930922,util Informed NRC That re-review of Eddy Current Test Data Identified Midspan Indications in Two Tubes in Unit 3 SG31.Review Being Performed to Determine If Nonquantifiable Indications Exist.Telcon W/Nrc Scheduled1993-09-22022 September 1993 PNO-V-93-017:on 930922,util Informed NRC That re-review of Eddy Current Test Data Identified Midspan Indications in Two Tubes in Unit 3 SG31.Review Being Performed to Determine If Nonquantifiable Indications Exist.Telcon W/Nrc Scheduled IR 05000528/19930361993-09-22022 September 1993 Insp Repts 50-528/93-36,50-529/93-36 & 50-530/93-36 on 930830-0903.Non-cited Violation Identified.Major Areas Inspected:Review of Licensee Access Authorization Program ML20057E7301993-09-16016 September 1993 Notice of Violation from Insp on 930713-0816.Violation Noted:Emergency Operating Procedures Used to Identify & Mitigate SG Tube Rupture Were Inadequate ML20057E7451993-09-10010 September 1993 Insp Repts 50-528/93-35,50-529/93-35 & 50-530/93-35 on 930713-0816.Violations Noted.Major Areas Inspected:Plant Chemistry,Fire Protection,Security & Outage Operations ML20058H4231993-09-10010 September 1993 Errata to Insp Repts 50-528/93-35,50-529/93-35 & 50-530/93-35 on 930713-0816.Provides Omitted Signature Page & Attachments IR 05000528/19930291993-09-0909 September 1993 Insp Repts 50-528/93-29,50-529/93-29 & 50-530/93-29 on 930621-0709.Violations Noted.Major Areas Inspected:External Exposure Control,Internal Exposure Control,Control of Radioactive Materials & Rms ML20057C5941993-09-0909 September 1993 Notice of Violation from Insp on 930621-0709.Violation Noted:Despite Licensee Chemistry Manager Receipt of from Combustion Engineering Identifying Potential for Dilution of Sample,Licensee Failed to Establish Measures IR 05000528/19930331993-09-0303 September 1993 Insp Repts 50-528/93-33,50-530/93-33 & 50-530/93-33 on 930802-06.No Violations Noted.Major Areas Inspected:Failure Rate of Crews & Operators During Sept 1992 & Mar 1993 Requalification Exams PNO-V-93-016, on 930828,plant Restarted After Refueling Outage That Proceeded Tube Rupture Event on 930314.Cause of Tube Rupture Was Due to Intergranular Attack.Unit 3 Operating at 100% Power1993-08-30030 August 1993 PNO-V-93-016:on 930828,plant Restarted After Refueling Outage That Proceeded Tube Rupture Event on 930314.Cause of Tube Rupture Was Due to Intergranular Attack.Unit 3 Operating at 100% Power IR 05000528/19930271993-08-26026 August 1993 Insp Repts 50-528/93-27,50-529/93-27 & 50-530/93-27 on 930726-30.No Violations Noted.Major Areas Inspected:Water Chemistry & Radiochemistry Programs,Including Water Chemistry & Health Physics Confirmatory Measurements PNO-V-93-014, on 930811,NRC Was Informed That APS Supervisor Declined to Hire Contract Employee Because Employee Raised Safety Concerns at Plant & Elsewhere.Judge Ruled APS Discriminated Against Employee1993-08-11011 August 1993 PNO-V-93-014:on 930811,NRC Was Informed That APS Supervisor Declined to Hire Contract Employee Because Employee Raised Safety Concerns at Plant & Elsewhere.Judge Ruled APS Discriminated Against Employee IR 05000528/19930241993-08-0606 August 1993 Page 27 Inadvertently Omitted from NRC Inspection Repts 50-528/93-24,50-529/93-24 & 50-530/93-24 ML20056E3691993-07-29029 July 1993 Insp Repts 50-528/93-24,50-529/93-24 & 50-530/93-24 During Wks of 930524,0607 & 28.No Violations Noted.Major Areas Inspected:Corrective Actions for Previously Identified Followup & Enforcement Items & LER Followup ML20056C8501993-07-0101 July 1993 Notice of Violation from Insp on 930427-0531.Violation Noted:Licensee Failed to Meet Surveillance Requirements for Testing Snubbers in Plants ML20056C8451993-07-0101 July 1993 Notice of Violation from Insp on 930426-0514.Violation Noted:Sgtr Event Involving RCS Leakage Greater than 44 Gpm & Previous Condition Involving RCS Leakage Greater than Charging Pump Capacity,Not Classified as SAE ML20056C8511993-06-30030 June 1993 Insp Repts 50-528/93-12,50-529/93-12 & 50-530/93-12 on 930427-0531.Violations Noted.Major Areas Inspected:Review of Plant Activities,Emergency Operating Procedures,Surveillance Testing,Plant Maint,Snubber Testing & Core Reload Analysis IR 05000528/19930281993-06-30030 June 1993 Enforcement Conference Repts 50-528/93-28,50-529/93-28 & 50-530/93-28 on 930603.Violations Noted.Major Areas Inspected:Licensee Analyses of Several Apparent Violations of NRC Requirements Re Emergency Classification PNO-V-93-009D, on 930325,leakage from Reactor Coolant Sys Occurred.Cause of Leak Not Determined1993-03-25025 March 1993 PNO-V-93-009D:on 930325,leakage from Reactor Coolant Sys Occurred.Cause of Leak Not Determined IR 05000528/19920411993-01-13013 January 1993 Insp Repts 50-528/92-41,50-529/92-41 & 50-530/92-41 on 921103-1214.No Violations Noted.Major Areas Inspected: Review of Plant Activities,Surveillance Testing & Plant Maint IR 05000528/19920381992-12-22022 December 1992 Insp Repts 50-528/92-38,50-529/92-38 & 50-530/92-38 on 921026-30 & 1116-20.Violations Noted.Major Areas Inspected: Licensee Radiation Protection Program,Surveys & Occupational Exposure During Unit 3 Refueling Outage ML20127B0961992-12-22022 December 1992 Notice of Violation from Insp on 921026-30 & 1116-20. Violation Noted:On 921110,procedures Were Not Adhered to in That Survey Not Performed or Documented to Illustrate Impact of Cumulative Dose Rates IR 05000528/19920341992-12-0808 December 1992 Insp Repts 50-528/92-34,50-529/92-34 & 50-530/92-34 on 921005-09.Violations Noted.Major Areas Inspected:Status of Emergency Preparedness Program & Followup on Open Items ML20126E0241992-12-0808 December 1992 Notice of Violation from Insp on 921005-09.Violation Noted: Licensee Lost All Meteorological Instrumentation for Approx 7 H But Failed to Declare Unusual Event within 30 Minutes of Loss of Instrumentation on 920822 ML20126B9031992-12-0404 December 1992 Notice of Violation from Insp on Stated Date.Violation Noted:Boric Acid Make Up Pump Discharge Check Valves CHN-V154 & CHN-155 Were Not in Licensee IST Program & Were Not Being Tested Individually IR 05000528/19920361992-12-0404 December 1992 Insp Repts 50-528/92-36,50-529/92-36 & 50-530/92-36 on Stated Dates.Violations Noted.Major Areas Inspected:Ist of Check Valves in safety-related Sys & Performance of Unit 3 ISI 1999-06-30 |
-__ - _ . - . . . - . . ~ . _ _ _ _ _ _ _ . ._
PRELIMINARY NOTIFICATION OF EVENT OR UNUSUAL OCCURRENCE--FNO-V-86-71 Date: 10/07/86'
- This preliminary notification constitutes EARLY notice of events of POSSIBLE safety or public interest significance. The information presented is as init.ially received without verification s or svaluation and is basically all that is known by Region V staff on this date; ,,
e -'
' FACILITY: ' Arizona Nuclear Power Project Emergen'cy Classification ,
Palo Verde Unit 1 XX Notification of. Unusual Event
"# ' DOCKET No. 50-528
_, Alert r
.'~ Site Area Emergency;
[-
General Emergency Not Applicable
- SUBJECT REACTOR TRIP AND SAFETY INJECTION On October 6, 1986, at 11:58 AM MST, the Unit i reactor tripped from approximately ,
.. 20% power on low Departure from Nucleate-Boiling Ratio.- The plant was-reducing power -
i ' .following a loss of electrical load,-turbine trip,.and reactor cutback prior to the trip.
? Fssdwater perturbations are believed to have resulted in the reactor trip and subsequent
.sefaty injection. Safety injection was activated at 11:59 AM and an Unusual Event was
- . dsclared at 12
- 08 PM. All safety systems responded as designed. The Unusual Event was
i l Tha licensee intends'to remain shut down for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to perform several maintenance items.
l The licensee has issued a press release.
This'information is current as of 8:45 AM MST October 7, 1986.
CONTACT: -L.' Miller, Jr. R. Zimmerman FTS 463-3869 (602) 386-5260 l
i i
DISTRIBUTION H St. MNBB Phillips E/W W111ste Air RightsIb'2 Mail:
- . Chairman Zech EDO NRR IE NMSS ADM
- DMB i Comm. Roberts PA OIA RES DOT:Trans Only Comm. Asselstine MPA AEOD j Comm. Bernthal ELD Comm. Carr Regions:
SECY INPO/.1' NNSAC/1 W ACRS Licensee: 1.'09 CA (Reactor Licendees) REGION V: FORM 211 i PDR Resident Inspector ~~ (Revised 3/14/83) i NQ 0$"YAMkV:102-cew72 - .
l 8610160034 861007 4 PDR ILE -
g lg i PNO-V-86-071 PDR
.