PNO-I-99-023, on 990411,NMP Performed Insps That Identified Indications of Crack Growth Around Portion of One of Vertical Welds.Repair Mod for Shroud Vertical Welds Is Expected to Take Approx Five Days to Complete
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| ML20206L475 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 05/12/1999 |
| From: | Marilyn Evans, Hunegs G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| References | |
| PNO-I-99-023, PNO-I-99-23, NUDOCS 9905140034 | |
| Download: ML20206L475 (1) | |
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Category:PRELIMINARY NOTIFICATION OF EVENT OR OCCURRENCE (PNO
MONTHYEARPNO-I-99-046, on 991008,NMP,Unit 1 Declared Unusual Event,Due to Carbon Dioxide Discharge in Records Storage Room of Administration Bldg,Which Was Migrating Beyond Confines of Storage Room.Nrc Resident Inspector Staff Responded1999-10-0808 October 1999
[Table view]PNO-I-99-046:on 991008,NMP,Unit 1 Declared Unusual Event,Due to Carbon Dioxide Discharge in Records Storage Room of Administration Bldg,Which Was Migrating Beyond Confines of Storage Room.Nrc Resident Inspector Staff Responded PNO-I-99-023, on 990411,NMP Performed Insps That Identified Indications of Crack Growth Around Portion of One of Vertical Welds.Repair Mod for Shroud Vertical Welds Is Expected to Take Approx Five Days to Complete1999-05-12012 May 1999 PNO-I-99-023:on 990411,NMP Performed Insps That Identified Indications of Crack Growth Around Portion of One of Vertical Welds.Repair Mod for Shroud Vertical Welds Is Expected to Take Approx Five Days to Complete PNO-I-93-058, on 931027,licensee Discovered Two Broken 100 Milliliter Vials of Yellow Powder (Believed to Be Yellowcake) at Corporate Ofc in Syracuse,Ny.No Personnel Contaminated.State of Ny Notified1993-10-28028 October 1993 PNO-I-93-058:on 931027,licensee Discovered Two Broken 100 Milliliter Vials of Yellow Powder (Believed to Be Yellowcake) at Corporate Ofc in Syracuse,Ny.No Personnel Contaminated.State of Ny Notified PNO-I-90-092, on 901010,condensate Spill Occurred in Bldg. Caused by Malfunctioning Valve in Lineup for Transfer of New Resin from Mixing Tank to Condensate Demineralizer Bed. Excess Water Pumped Out sub-basement1990-10-11011 October 1990 PNO-I-90-092:on 901010,condensate Spill Occurred in Bldg. Caused by Malfunctioning Valve in Lineup for Transfer of New Resin from Mixing Tank to Condensate Demineralizer Bed. Excess Water Pumped Out sub-basement PNO-I-90-061, on 900806,plant Operators Manually Scrammed Reactor Due to High Vibration on Main Turbine Bearing.Caused by Blank Flange Left in Oil Supply Line to Bearing.Resident Inspectors Following Licensee Actions1990-08-0707 August 1990 PNO-I-90-061:on 900806,plant Operators Manually Scrammed Reactor Due to High Vibration on Main Turbine Bearing.Caused by Blank Flange Left in Oil Supply Line to Bearing.Resident Inspectors Following Licensee Actions PNO-I-90-059, on 900730,plant Shut Down Due to Excessive RCS Leakage.Util Will Repair Plant Electromatic Relief Valves Found to Be Leaking During Startup.State of Ny Has Been Informed1990-07-30030 July 1990 PNO-I-90-059:on 900730,plant Shut Down Due to Excessive RCS Leakage.Util Will Repair Plant Electromatic Relief Valves Found to Be Leaking During Startup.State of Ny Has Been Informed PNO-I-90-057, on 900727,restart Authorized for Facility. Util Agreed to Perform Self Assessments of Performance & Inform NRC Restart Assessment Panel of Self Assessment Results1990-07-27027 July 1990 PNO-I-90-057:on 900727,restart Authorized for Facility. Util Agreed to Perform Self Assessments of Performance & Inform NRC Restart Assessment Panel of Self Assessment Results PNO-I-89-072A, on 890828,augmented Insp Team Exit Meeting Subsequent Press Conference Held at Plant Re Licensee Use of sub-basement for Storage of Solid & Liquid Radwaste.Two Violations Noted1989-08-29029 August 1989 PNO-I-89-072A:on 890828,augmented Insp Team Exit Meeting Subsequent Press Conference Held at Plant Re Licensee Use of sub-basement for Storage of Solid & Liquid Radwaste.Two Violations Noted PNO-I-88-010, on 880120,reactor Scrammed from 42% Power Based on Low Reactor Vessel Water Level.Caused by Equipment Operator Error.Nrc Dispatched Augmented Insp Team to Site to Review Generic Safety Implications of Event1988-01-21021 January 1988 PNO-I-88-010:on 880120,reactor Scrammed from 42% Power Based on Low Reactor Vessel Water Level.Caused by Equipment Operator Error.Nrc Dispatched Augmented Insp Team to Site to Review Generic Safety Implications of Event PNO-I-88-009, on 880120,unusual Event Declared as Result of Worker Injured After Stepping Through Hole in Grating Between Reactor Vessel Flange & Refueling Cavity Floor.No Contamination Involved1988-01-21021 January 1988 PNO-I-88-009:on 880120,unusual Event Declared as Result of Worker Injured After Stepping Through Hole in Grating Between Reactor Vessel Flange & Refueling Cavity Floor.No Contamination Involved PNO-I-88-007, on 880115,present Unplanned Outage to Inspect & Repair Feedwater Sys Components & Supports Extended for Approx 3 Wks to Perform Insp of Bushings in Reactor Vessel Flange Which Hold 6-inch Diameter Reactor Vessel Head Studs1988-01-19019 January 1988 PNO-I-88-007:on 880115,present Unplanned Outage to Inspect & Repair Feedwater Sys Components & Supports Extended for Approx 3 Wks to Perform Insp of Bushings in Reactor Vessel Flange Which Hold 6-inch Diameter Reactor Vessel Head Studs PNO-I-87-120, on 871226,reactor Scram Occurred from Approx 25% Power Due to Turbine Trip on Low Condenser Vacuum Caused by Crack in Condenser Pipe Penetration.Pentration Seal Weld Repaired1987-12-29029 December 1987 PNO-I-87-120:on 871226,reactor Scram Occurred from Approx 25% Power Due to Turbine Trip on Low Condenser Vacuum Caused by Crack in Condenser Pipe Penetration.Pentration Seal Weld Repaired PNO-I-87-117, on 871219,reactor Manually Scrammed After Mechanical Vibrations from Turbine Bldg Felt in Control Room.Caused by Feedwater Control Valve Stem Separation from Disc.Outage Dependent on Availability of Repair Parts1987-12-21021 December 1987 PNO-I-87-117:on 871219,reactor Manually Scrammed After Mechanical Vibrations from Turbine Bldg Felt in Control Room.Caused by Feedwater Control Valve Stem Separation from Disc.Outage Dependent on Availability of Repair Parts PNO-I-87-114, on 871207,reactor Scrammed from Approx 96% Power Due to Low Reactor Vessel Water Level.Caused by Malfunction of Feedwater Control Valves 13A & 13B.Preventive & Corrective Maint Underway1987-12-10010 December 1987 PNO-I-87-114:on 871207,reactor Scrammed from Approx 96% Power Due to Low Reactor Vessel Water Level.Caused by Malfunction of Feedwater Control Valves 13A & 13B.Preventive & Corrective Maint Underway PNO-I-87-113, on 871128,condensate Storage Tank Ruptured Spilling Over 260,000 Gallons Nonradioactive Demineralized Water.Caused by Break in Seam Between Tank Sidewall & Floor. Vendor Onsite Inspecting Cause.Plant in Cold Shutdown1987-12-0202 December 1987 PNO-I-87-113:on 871128,condensate Storage Tank Ruptured Spilling Over 260,000 Gallons Nonradioactive Demineralized Water.Caused by Break in Seam Between Tank Sidewall & Floor. Vendor Onsite Inspecting Cause.Plant in Cold Shutdown PNO-I-87-096, on 871016,plant Scrammed on High Neutron Flux from 89% Power During Testing Causing Main Steam Pressure Oscillations Triggering APRM High Flux Scram.Crd Stub Tube Leakage Identified.Hydrostatic Tests Performed1987-10-19019 October 1987 PNO-I-87-096:on 871016,plant Scrammed on High Neutron Flux from 89% Power During Testing Causing Main Steam Pressure Oscillations Triggering APRM High Flux Scram.Crd Stub Tube Leakage Identified.Hydrostatic Tests Performed PNO-I-87-064, on 870711,reactor High Pressure Scram Experienced from Approx 3% Power.Caused by Fatigue Failure of Electrohydraulic Control Line to Turbine Control Valve 4. Repairs May Include Addl Structural Support1987-07-13013 July 1987 PNO-I-87-064:on 870711,reactor High Pressure Scram Experienced from Approx 3% Power.Caused by Fatigue Failure of Electrohydraulic Control Line to Turbine Control Valve 4. Repairs May Include Addl Structural Support PNO-I-87-045, on 870523,reactor Taken Critical for First Time.After Completion of Initial Fuel Load on 861115,power Ascension Delayed Due to Excessive Leakage Problems W/Ball Type Msivs.Valves Replaced W/Wye Pattern Glove Valves1987-05-26026 May 1987 PNO-I-87-045:on 870523,reactor Taken Critical for First Time.After Completion of Initial Fuel Load on 861115,power Ascension Delayed Due to Excessive Leakage Problems W/Ball Type Msivs.Valves Replaced W/Wye Pattern Glove Valves PNO-I-87-044, on 870516,receipt Insp of Two Radioactive Matls Shipping Packages Showed External Radiation Levels of 2,000 & 1,500 Mrem/H,Exceeding NRC & DOT Limit of 200 Mrem/H. Cause Being Investigated.States of Ny & Nc Will Be Informed1987-05-20020 May 1987 PNO-I-87-044:on 870516,receipt Insp of Two Radioactive Matls Shipping Packages Showed External Radiation Levels of 2,000 & 1,500 Mrem/H,Exceeding NRC & DOT Limit of 200 Mrem/H. Cause Being Investigated.States of Ny & Nc Will Be Informed PNO-I-87-020, on 860311,util Informed NRC That Unique MSIV Ball Valves Will Be Replaced W/Typical BWR Y Pattern Globe Valves Due to Problems W/Prototype Testing of Ball Valves. Replacement Expected to Take 3 Months1987-03-12012 March 1987 PNO-I-87-020:on 860311,util Informed NRC That Unique MSIV Ball Valves Will Be Replaced W/Typical BWR Y Pattern Globe Valves Due to Problems W/Prototype Testing of Ball Valves. Replacement Expected to Take 3 Months PNO-V-86-073, GL Mcchain,In Custody by FBI on Parole Violation,Issued Claims of Evading Security Background Checks for 6 Yrs While Working at Listed Facilities & Knows of Falsified Weld Records.Investigation in Progress1986-10-23023 October 1986 PNO-V-86-073:GL Mcchain,In Custody by FBI on Parole Violation,Issued Claims of Evading Security Background Checks for 6 Yrs While Working at Listed Facilities & Knows of Falsified Weld Records.Investigation in Progress PNO-I-86-065, on 860822,10 CRD Hydraulic Control Units Declared Inoperable Due to 860821 Maint.No post-maint Testing Performed.Plant Shut Down,Per Tech Specs.Startup Planned for 8608251986-08-25025 August 1986 PNO-I-86-065:on 860822,10 CRD Hydraulic Control Units Declared Inoperable Due to 860821 Maint.No post-maint Testing Performed.Plant Shut Down,Per Tech Specs.Startup Planned for 860825 PNO-I-86-042, on 860613,sanitized Ofc of Investigation Rept 1-84-014 Re Alleged Harassment & Intimidation of QA Auditors Was Released to Licensee & FOIA Requesters.No Decision Made on Enforcement Action1986-06-16016 June 1986 PNO-I-86-042:on 860613,sanitized Ofc of Investigation Rept 1-84-014 Re Alleged Harassment & Intimidation of QA Auditors Was Released to Licensee & FOIA Requesters.No Decision Made on Enforcement Action PNO-I-86-005, on 860118,licensee Conducted Normal Reactor Shutdown After Discovering Potential for Overstressing Containment Penetration in Event of Postulated Emergency Condenser Steam Line Break.Evaluation Continuing1986-01-21021 January 1986 PNO-I-86-005:on 860118,licensee Conducted Normal Reactor Shutdown After Discovering Potential for Overstressing Containment Penetration in Event of Postulated Emergency Condenser Steam Line Break.Evaluation Continuing PNO-I-85-084, on 851101,plant Scrammed from 100% Power Due to Loss of Instrument Air & Failure of Feed Regulator Valves to Lockup.Licensee Will Install Correct Cable to One Dc Emergency Isolation Valve1985-11-0404 November 1985 PNO-I-85-084:on 851101,plant Scrammed from 100% Power Due to Loss of Instrument Air & Failure of Feed Regulator Valves to Lockup.Licensee Will Install Correct Cable to One Dc Emergency Isolation Valve PNO-I-85-082, on 851018,4 Kv nonsafety-related Electrical Breaker Exploded,Injuring Two Const Workers.Workers Taken to Hosp for Treatment.Vendor Representatives & OSHA Investigating Cause of Event1985-10-24024 October 1985 PNO-I-85-082:on 851018,4 Kv nonsafety-related Electrical Breaker Exploded,Injuring Two Const Workers.Workers Taken to Hosp for Treatment.Vendor Representatives & OSHA Investigating Cause of Event ML20248L6051978-02-0707 February 1978 PNO-78-023:on 780206,section of Installed Reinforcing Bars Collapsed When Struck by Bundle of Reinforcing Bars Being Handled by Crane.Two Workers Pronounced Dead Upon Arrival at Hospital.Eight Others Treated for Injuries ML20151X5861977-07-0505 July 1977 PNO-77-119:pin Hole Leak Was Found in Weld in 10 Inch Emergency Condenser Condensate Return Line,During Post Outage Hydrostatic Test.Repairs in Progress.Licensee Plans to Conduct Metallographic Analysis of Flaw ML20151U1461977-04-0808 April 1977 PNO-77-053:while Shutdown for Refueling,Scheduled Liquid Penetrant Exam of One Feedwater Nozzle Disclosed Numerous Indications Located in Blend Radius.Some Indicatiions Reported to Be Six or Seven Inches in Length ML20236F2491976-12-0202 December 1976 PNO-76-207:investigation Into Geologic Fault Suspected to Be of pre-glacial Origin,Discovered During Excavation for Plant Cooling Towers Has Resulted in Evidence of post-glacial, Upward Movement of Overlying Soil ML20249B1901976-03-25025 March 1976 PNO-76-053:on 980323,licensee Conducting Nondestructive Volumetric Exam of Austenitic Stainless Steel Pipe bends,2 Inches or Greater in Diameter,Which Had Been Cold Worked W/O Subsequent Solution Annealing ML20249B2261976-03-23023 March 1976 PNO-76-050:on 760319 & 22,through Wall Cracks Found in Two Isolable Sections of Cold Worked Six Inch Diameter,Schedule 80,A376 Type 304 Stainless Steel Pipe Elbows.Generic Implication Being Evaluated ML20236W8361975-12-18018 December 1975 PN-75-152:on 751217,ltr Received from Weber Re Safeguards, Worker Health & Public Health to Transportation of Solid Waste.Ltr Ack Receipt Being Sent to Weber.Ltr Will Request Facts.State of Ny Informed 1999-05-12 Category:TEXT-INSPECTION & AUDIT & I&E CIRCULARS MONTHYEARPNO-I-99-046, on 991008,NMP,Unit 1 Declared Unusual Event,Due to Carbon Dioxide Discharge in Records Storage Room of Administration Bldg,Which Was Migrating Beyond Confines of Storage Room.Nrc Resident Inspector Staff Responded1999-10-0808 October 1999
[Table view]PNO-I-99-046:on 991008,NMP,Unit 1 Declared Unusual Event,Due to Carbon Dioxide Discharge in Records Storage Room of Administration Bldg,Which Was Migrating Beyond Confines of Storage Room.Nrc Resident Inspector Staff Responded IR 05000220/19990061999-09-14014 September 1999 Insp Repts 50-220/99-06 & 50-410/99-06 on 990620-0731.NCVs Noted.Major Areas Inspected:Licensee Operations,Engineering, Maint & Plant Support ML20196K6531999-06-29029 June 1999 Notice of Violation from NRC OI Investigation Conducted on 980701-1211.Violation Noted:For Approx Four Hours on 980616, with NMP1 at Full Power,Sro Assumed Assistant Shift Supervisor Position,Contrary to TS Requirements IR 05000220/19990041999-06-21021 June 1999 Insp Repts 50-220/99-04 & 50-410/99-04 on 990328-0508.No Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Engineering,Maint & Plant Support PNO-I-99-023, on 990411,NMP Performed Insps That Identified Indications of Crack Growth Around Portion of One of Vertical Welds.Repair Mod for Shroud Vertical Welds Is Expected to Take Approx Five Days to Complete1999-05-12012 May 1999 PNO-I-99-023:on 990411,NMP Performed Insps That Identified Indications of Crack Growth Around Portion of One of Vertical Welds.Repair Mod for Shroud Vertical Welds Is Expected to Take Approx Five Days to Complete IR 05000220/19980151998-12-23023 December 1998 Insp Repts 50-220/98-15 & 50-410/98-15 on 980927-1121.No Violations Noted.Major Areas Inspected:Licensee Operations, Engineering,Maint & Plant Support ML20196E5351998-11-19019 November 1998 Notice of Violation from Investigation on 980303-0930. Violation Noted:On 971224,individual Left Controls at NMP-2 Unattended for Six Minutes to Go Into Shift Supervisor Ofc, Area Not at Controls as Noted in NMPC UFSAR Figure 13.5-1 IR 05000220/19980141998-10-26026 October 1998 Insp Repts 50-220/98-14 & 50-410/98-14 on 980816-0926.No Violations Noted.Major Areas Inspected:Reviews of Licensee Activities in Functional Areas of Operations,Engineering, Maint & Plant Support ML20248A8001998-05-20020 May 1998 Notice of Violation from Insp on 980406-0409.Violation Noted:During Insp,Inspectors Determined That Licensee Failed to Properly Store,Control & Classify Safeguards Info ML20217L9251998-04-28028 April 1998 Insp Repts 50-220/98-08 & 50-410/98-08 on 980406-21. Violations Noted.Major Areas Inspected:Licensee Security Force Capability to Protect Facility Against Radiological Sabotage & Compliance W/Safeguards Program Commitments ML20199B8601998-01-22022 January 1998 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $55,000.Violation Noted:On 970925,package Containing Metal Samples Removed from Unit 1 Emergency Cooling Tube Sheet Was Sent to Listed Company,Not on List ML20198R4391997-11-0505 November 1997 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $50,000.Violations Noted:Listed non-safety Related SSCs Were Not Included in 10CFR50.65 Monitoring Program ML20137U8501997-04-10010 April 1997 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $200,000.Violation Noted:As of 961105,measures Were Not Established to Assure Condition Adverse to Quality Are Promptly Identified & Corrected IR 05000220/19940011994-01-24024 January 1994 Insp Repts 50-220/94-01 & 50-410/94-01 on 940103-07.No Violations Noted.Major Areas Inspected:Mgt Support, Protected Area Barriers,Detection Aids & Assessment Aids, & Protected Area & Isolation Zone Lighting IR 05000220/19930221993-12-22022 December 1993 Insp Repts 50-220/93-22 & 50-410/93-22 on 931004-20.No Violations Noted.Major Areas Inspected:Mov Program Commitments & Enhancments Identified During Team Inspection in June 1992 Were Reviewed for Progress IR 05000220/19930011993-11-12012 November 1993 Insp Repts 50-220/93-01 & 50-410/93-01 on 930919-1030. Violations Noted.Major Areas Inspected:Major Components & Sys for Leakage,Alignment,Lubrication,Cooling Water Supply IR 05000220/19930231993-11-0505 November 1993 Insp Repts 50-220/93-23 & 50-410/93-22 on 931012-14.No Violations Noted.Major Areas Inspected:Mgt Support,Program Plans & Audits,Protected & Vital Area Physical Barriers, Detection & Assessment Aids PNO-I-93-058, on 931027,licensee Discovered Two Broken 100 Milliliter Vials of Yellow Powder (Believed to Be Yellowcake) at Corporate Ofc in Syracuse,Ny.No Personnel Contaminated.State of Ny Notified1993-10-28028 October 1993 PNO-I-93-058:on 931027,licensee Discovered Two Broken 100 Milliliter Vials of Yellow Powder (Believed to Be Yellowcake) at Corporate Ofc in Syracuse,Ny.No Personnel Contaminated.State of Ny Notified IR 05000220/19930241993-10-27027 October 1993 Insp Repts 50-220/93-24 & 50-410/93-23 on 931018-22.No Violations Noted.Major Areas Inspected:Exams of Procedures, Representative Records,Interviews W/Personnel & Observations by Inspectors IR 05000220/19930191993-10-18018 October 1993 Insp Rept 50-220/93-19 on 930823-27.No Violations Noted. Major Areas Inspected:Electrical Distribution Sys ML20057G3271993-10-12012 October 1993 Notice of Violation from Insp on 930808-0918.Violation Noted:On 930803,inspector Discovered Individual That Required Escort in Protected Area W/O Escort for Approx 25 Minutes IR 05000220/19930121993-10-0606 October 1993 Insp Repts 50-220/93-12 & 50-410/93-12 on 930615-18 & 0712-14.No Violations Noted.Major Areas inspected:930615-18 Emergency Preparedness Program & 930713 annual,full- Participation Emergency Preparedness Exercise IR 05000220/19930181993-10-0101 October 1993 Insp Repts 50-220/93-18 & 50-410/93-18 on 930808-0918. Violation Noted.Major Areas Inspected:Plant Operations, Maint & Surveillance Activities,Engineering & Plant Support, W/Regard to Radiological & Chemistry Controls & Security IR 05000220/19930131993-09-21021 September 1993 Insp Repts 50-220/93-13 & 50-410/93-13 on 930802-06.No Violations Noted.Major Areas Inspected:Design Changes & Mods,Installation & Testing of Mods,Interface/Communication, QA & Technical Support,Wrs & LERs IR 05000220/19930151993-09-16016 September 1993 Insp Repts 50-220/93-15 & 50-410/93-15 on 930719-23.No Violations or Deviations Noted.Major Areas Inspected:Offsite Power Supply Sources for Plant & to Review Licensees Corrective Action on Previously Identified Insp Findings IR 05000220/19930161993-08-0404 August 1993 Insp Repts 50-220/93-16 & 50-410/93-16 on 930426-30.No Violations Noted.Major Areas Inspected:Mgt Controls,Audits, Calibration of Effluent & Process Radiation Monitoring Sys, Air Cleaning Sys & Implementation of Previous Programs ML20056C1641993-03-23023 March 1993 Notice of Violation from Insp on 930124-0227.Violation Noted:I&C Technicians Performing N1-ISP-032-004 Failed to Correctly Perform Procedural Steps 7.2.1-7.2.5 Resulting in Automatic Reactor Scram Due to False High Neutron Flux ML20056C1661993-03-12012 March 1993 Insp Repts 50-220/93-01 & 50-410/93-01 on 930124-0227. Violations Noted.Major Areas Inspected:Plant Operations, Radiological Controls,Maintenance,Surveillance,Security & Safety Assessment/Quality Verification Activities PNO-I-90-092, on 901010,condensate Spill Occurred in Bldg. Caused by Malfunctioning Valve in Lineup for Transfer of New Resin from Mixing Tank to Condensate Demineralizer Bed. Excess Water Pumped Out sub-basement1990-10-11011 October 1990 PNO-I-90-092:on 901010,condensate Spill Occurred in Bldg. Caused by Malfunctioning Valve in Lineup for Transfer of New Resin from Mixing Tank to Condensate Demineralizer Bed. Excess Water Pumped Out sub-basement PNO-I-90-061, on 900806,plant Operators Manually Scrammed Reactor Due to High Vibration on Main Turbine Bearing.Caused by Blank Flange Left in Oil Supply Line to Bearing.Resident Inspectors Following Licensee Actions1990-08-0707 August 1990 PNO-I-90-061:on 900806,plant Operators Manually Scrammed Reactor Due to High Vibration on Main Turbine Bearing.Caused by Blank Flange Left in Oil Supply Line to Bearing.Resident Inspectors Following Licensee Actions IR 05000220/19890991990-08-0101 August 1990 Final SALP Repts 50-220/89-99 & 50-410/89-99 for Mar 1989 - Feb 1990 PNO-I-90-059, on 900730,plant Shut Down Due to Excessive RCS Leakage.Util Will Repair Plant Electromatic Relief Valves Found to Be Leaking During Startup.State of Ny Has Been Informed1990-07-30030 July 1990 PNO-I-90-059:on 900730,plant Shut Down Due to Excessive RCS Leakage.Util Will Repair Plant Electromatic Relief Valves Found to Be Leaking During Startup.State of Ny Has Been Informed PNO-I-90-057, on 900727,restart Authorized for Facility. Util Agreed to Perform Self Assessments of Performance & Inform NRC Restart Assessment Panel of Self Assessment Results1990-07-27027 July 1990 PNO-I-90-057:on 900727,restart Authorized for Facility. Util Agreed to Perform Self Assessments of Performance & Inform NRC Restart Assessment Panel of Self Assessment Results PNO-I-89-072A, on 890828,augmented Insp Team Exit Meeting Subsequent Press Conference Held at Plant Re Licensee Use of sub-basement for Storage of Solid & Liquid Radwaste.Two Violations Noted1989-08-29029 August 1989 PNO-I-89-072A:on 890828,augmented Insp Team Exit Meeting Subsequent Press Conference Held at Plant Re Licensee Use of sub-basement for Storage of Solid & Liquid Radwaste.Two Violations Noted ML20247D5991989-05-0202 May 1989 Investigation Rept 89-02 Re Misconduct of Ofc of Investigations Deputy Director,Ra Fortuna.Finding of No Misconduct or Dereliction of Duty Recommended IR 05000220/19880301988-11-16016 November 1988 Insp Repts 50-220/88-30 & 50-410/88-29 on 880926-30.No Violations Noted.Major Areas Inspected:Security Plan & Procedures,Mgt Organization,Audits,Records & Repts,Testing & Maint,Barriers,Security Power Supply & Assessment Aids IR 05000220/19860991988-07-0101 July 1988 Amended SALP Repts 50-220/86-99 & 50-410/87-99 for Nov 1986 - Feb 1988 & Feb 1987 - Feb 1988,respectively. Licensee Has Shown Limited Success W/Initiatives to Improve Previously Identified Weaknesses ML20155F4171988-06-10010 June 1988 Notice of Violation from Insp on 880404-08.Violation Noted: Site Procedures CBI-SC 1,Rev 0 & NES-8042433,Rev 3 Did Not Establish Adequate Controls Over Nondestructive Testing Process for Making Precision Thickness Measurements IR 05000220/19880091988-05-19019 May 1988 Insp Repts 50-220/88-09 & 50-410/88-09 on 880307-11 & 0404- 08.Violations Noted.Major Areas Inspected:Inservice Insp Program Re First 10-yr Insp Interval & Augmented Exams Conducted by Licensee,Including Procedures PNO-I-88-010, on 880120,reactor Scrammed from 42% Power Based on Low Reactor Vessel Water Level.Caused by Equipment Operator Error.Nrc Dispatched Augmented Insp Team to Site to Review Generic Safety Implications of Event1988-01-21021 January 1988 PNO-I-88-010:on 880120,reactor Scrammed from 42% Power Based on Low Reactor Vessel Water Level.Caused by Equipment Operator Error.Nrc Dispatched Augmented Insp Team to Site to Review Generic Safety Implications of Event PNO-I-88-009, on 880120,unusual Event Declared as Result of Worker Injured After Stepping Through Hole in Grating Between Reactor Vessel Flange & Refueling Cavity Floor.No Contamination Involved1988-01-21021 January 1988 PNO-I-88-009:on 880120,unusual Event Declared as Result of Worker Injured After Stepping Through Hole in Grating Between Reactor Vessel Flange & Refueling Cavity Floor.No Contamination Involved PNO-I-88-007, on 880115,present Unplanned Outage to Inspect & Repair Feedwater Sys Components & Supports Extended for Approx 3 Wks to Perform Insp of Bushings in Reactor Vessel Flange Which Hold 6-inch Diameter Reactor Vessel Head Studs1988-01-19019 January 1988 PNO-I-88-007:on 880115,present Unplanned Outage to Inspect & Repair Feedwater Sys Components & Supports Extended for Approx 3 Wks to Perform Insp of Bushings in Reactor Vessel Flange Which Hold 6-inch Diameter Reactor Vessel Head Studs PNO-I-87-120, on 871226,reactor Scram Occurred from Approx 25% Power Due to Turbine Trip on Low Condenser Vacuum Caused by Crack in Condenser Pipe Penetration.Pentration Seal Weld Repaired1987-12-29029 December 1987 PNO-I-87-120:on 871226,reactor Scram Occurred from Approx 25% Power Due to Turbine Trip on Low Condenser Vacuum Caused by Crack in Condenser Pipe Penetration.Pentration Seal Weld Repaired PNO-I-87-117, on 871219,reactor Manually Scrammed After Mechanical Vibrations from Turbine Bldg Felt in Control Room.Caused by Feedwater Control Valve Stem Separation from Disc.Outage Dependent on Availability of Repair Parts1987-12-21021 December 1987 PNO-I-87-117:on 871219,reactor Manually Scrammed After Mechanical Vibrations from Turbine Bldg Felt in Control Room.Caused by Feedwater Control Valve Stem Separation from Disc.Outage Dependent on Availability of Repair Parts PNO-I-87-114, on 871207,reactor Scrammed from Approx 96% Power Due to Low Reactor Vessel Water Level.Caused by Malfunction of Feedwater Control Valves 13A & 13B.Preventive & Corrective Maint Underway1987-12-10010 December 1987 PNO-I-87-114:on 871207,reactor Scrammed from Approx 96% Power Due to Low Reactor Vessel Water Level.Caused by Malfunction of Feedwater Control Valves 13A & 13B.Preventive & Corrective Maint Underway IR 05000220/19870221987-12-0909 December 1987 Insp Rept 50-220/87-22 on 871019-23.No Violations Noted. Major Areas Inspected:Design Change/Mods,Maint & Previously Identified Items PNO-I-87-113, on 871128,condensate Storage Tank Ruptured Spilling Over 260,000 Gallons Nonradioactive Demineralized Water.Caused by Break in Seam Between Tank Sidewall & Floor. Vendor Onsite Inspecting Cause.Plant in Cold Shutdown1987-12-0202 December 1987 PNO-I-87-113:on 871128,condensate Storage Tank Ruptured Spilling Over 260,000 Gallons Nonradioactive Demineralized Water.Caused by Break in Seam Between Tank Sidewall & Floor. Vendor Onsite Inspecting Cause.Plant in Cold Shutdown PNO-I-87-096, on 871016,plant Scrammed on High Neutron Flux from 89% Power During Testing Causing Main Steam Pressure Oscillations Triggering APRM High Flux Scram.Crd Stub Tube Leakage Identified.Hydrostatic Tests Performed1987-10-19019 October 1987 PNO-I-87-096:on 871016,plant Scrammed on High Neutron Flux from 89% Power During Testing Causing Main Steam Pressure Oscillations Triggering APRM High Flux Scram.Crd Stub Tube Leakage Identified.Hydrostatic Tests Performed IR 05000220/19870161987-10-15015 October 1987 Exam Rept 50-220/87-16OL on 870804-06.Exam Results:All Three Senior Reactor Operator Candidates Passed Written & Operating Exams.Exam Key Encl IR 05000410/19870181987-10-0101 October 1987 Requalification & Replacement Exam Rept 50-410/87-18OL on 870707-07.Exam Results:Two of Four Senior Reactor Operator Candidates & Three of Four Reactor Operator Candidates Passed Exam.Exams Encl 1999-09-14 |
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4 May 12, 1999 PRELIMINARY NOTIFICATION OF EVENT OR UNUSUAL OCCURRENCE PNO-I-99-023 This preliminary notification constitutes EARLY notice of events of POSSIBLE safety or public interest significance. The information is as initially received without verification or evaluation, and is basically all that is known by Region I staff in King of Prussia. Pennsylvania on this date.
Facility Licensee Emeraency Classification Niagara Mohawk Power Corp. Notification of Unusual Event Nine Mile Point 1 Alert Lycoming,New York Site Area Emergency Dockets: 50-220 General Emergency X Not Applicable i
Subject:
REACTOR CORE SHROUD REPAIR - MEDIA INTEREST During the 1997 refueling and maintenance outage, Niagara Mohawk Power I Corporation (NMPC) discovered cracking in vertical welds joining sections of the cylindrical stainless steel reactor core shroud. Inspection and analyses determined that the plant could be operated safely until the next scheduled refueling outage. In 1997 and 1998, the NRC reviewed and approved the licensee's analyses.
I The current refueling outage started on April 11. During this refueling outage, NMPC performed inspections that identified indications of crack growth around a portion of one of the vertical welds. NMPC concluded .
that the crack growth rate was consistent with their previous analyses.
NMPC also concluded that the reactor core shroud continues to be structurally sound and does not pose any concern to the continued safe i operation of the plant.
Based on the results of the examination of the reactor core shroud and analysis, NMPC has decided to install a pre-planned modification, consisting of clamps over two vertical welds, including the one weld which exhibited some crack growth. The repair modif; cation for the shroud vertical welds is expected to take approximately five days to complete.
NMPC activities have been monitored by the resident staff, as well as, regional and headquarters staff.
NMFC has contacted local media representatives and has issued a press release. The State of New York has been informed. The information in this preliminary notification has been reviewed with licensee management.
Contact:
EVANS, MICHELE HUNEGS. GORDON (610)337-5224 (315)342-4041 9905140034 990512 D)
NO-I -023 PDR