PNO-V-85-076, on 851108,licensee Reported That Studs in RCS Line Stops a & B Did Not Meet Hardness Requirements.Relief from 10CFR50,App A,Gdc 4 Requested to Preclude Retorquing Studs
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| ML20136A679 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 11/13/1985 |
| From: | Miller L, Zimmerman R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| References | |
| PNO-V-85-076, PNO-V-85-76, NUDOCS 8511200006 | |
| Download: ML20136A679 (2) | |
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 |
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PRELIMINARY NOTIFICATION OF EVENT OR UNUSUAL CCCURRENCE--PNO-V-85-76 Date: 11/13/85 This preliminary notification constitutes EARLY notice of events of POSSIBLE safety or public int: rest significance. The information presented is as initially received without verification er cvaluation and is basically all that is known by Region V staff on this date.
FACILITY: Arizona Nuclear Power Project Emergency Classification Palo Verde Units 1, 2 and 3 Notification of Unusual Event Docket Nos. 50-528, 50-529, 50-530 Alert Site Area Emergency General Emergency XX Not Applicable 8
SUBJECT:
EXTENDED PLANT SHUTDOWN WHILE ASSESSING ADEQUACY OF REACTOR COOLANT SYSTEM LINE STOP FASTENERS .
Tha licensee reported on November 8, 1985, that 29 out of 64 studs installed in the Unit 2 rc ctor coolant system (RCS) line stops A and B did not meet"the' hardness requirements for ASTM A540, Grade 23, Class II materials. The line stops serve to minimize the effects of pip 2 whip in the event of a RCS line break. A total of 32 similar studs destined for Unit 3, (Line Stops A and B) but not yet installed, also were found to have hardness values less th n required. Subsequently, the licensee checked the studs installed in the Unit I rccctor coolant system line stops A and B and found that approximately one-half of the ctuds had hardness values less than required. The ASTM AS40 studs with the questionable hardness values were supplied by Ametek-Straza Co., a distributor. These ASTM AS40 ctuds were manufactured by the Southern Bolt Company and were received at Palo Verda in 1979 with a material test report certifying the studs met ASTM A540, Grade 23, Class II r;quirements. Additionally, the licensee has determined that the installation method for all the studs and anchor bolts, on all of the reactor coolant system line stops, for Unit I was inadequate, in that the acceptance criteria for the tensioning of the studs and cnchor bolts was specified in terms of elongation rather than the appropriate predetermined force. There are 22 line stops per unit, for a total of 800 studs and bolts.
Currently Unit 1 is shutdown. The licensee has contacted NRR for relief from 10CFR50, App:ndix A, GDC-4 to preclude retorquing the anchor bolts and studs on all the line stops to verify their ability to perform as intended by design. The licensee's basis for r questing relief stema from the fact that NRR is currently reviewing the licensee's rcquest that the line stops be removed from Units 2 and 3, based on a Combustion Engineering study that has determined that the line stops are not required.
Prcrently the licensee is proceeding with their relief request and also starting to ratorque all studs and anchor bolts on all of the line stops on Unit 1. This effort is cctimated to take approximately three weeks.
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o M a U PNO-V-85-76 11/13/85 Tha licensee has discussed the situation with local media.
Thio information is current as of 10:00 am (PST) November 13, 1985.
CONTACT: L. Miller R. Zimmerman FTS 463-3869 (602) 386-5260 DISTRIBUTION 11 S t . HNBB Phillips E/W Willste Air Rights _ Mail Chairman Pallidino EDO NRR IE NMSS ADM:DMB Comm. Zech PA OIA RES DOT:Trans only C:mm. Bernthal MPA AEOD Comm. Roberts ELD Comm. Asselstine Regions:
SECY INP0f/V/ NSAC 7/o J ACRS Licensee: < 'c?
CA (Reactor Licensees) REGION V: FORM 211 PDR Resident Inspector _ (Revised 3/14/83)