PNO-I-99-028, on 990608,Susquehanna Unit 2 Automatically Shut Down from 100% Power,Due to Failure in a Main Transformer. Region I Public Affairs Prepared to Respond to Media Inquires.Resident Inspectors on-site & Responded
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| ML20195D943 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 06/09/1999 |
| From: | Cowgill C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| References | |
| PNO-I-99-028, PNO-I-99-28, NUDOCS 9906100090 | |
| Download: ML20195D943 (1) | |
Similar Documents at Susquehanna | |
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Category:PRELIMINARY NOTIFICATION OF EVENT OR OCCURRENCE (PNO
MONTHYEARPNO-I-99-028, on 990608,Susquehanna Unit 2 Automatically Shut Down from 100% Power,Due to Failure in a Main Transformer. Region I Public Affairs Prepared to Respond to Media Inquires.Resident Inspectors on-site & Responded1999-06-0909 June 1999
[Table view]PNO-I-99-028:on 990608,Susquehanna Unit 2 Automatically Shut Down from 100% Power,Due to Failure in a Main Transformer. Region I Public Affairs Prepared to Respond to Media Inquires.Resident Inspectors on-site & Responded PNO-I-93-059, on 931026,unexpected Drop of Section of Refueling Mast Occurred While Lowering Bundle in Core.Maint Investigated & Discovered Bend in Mast.Licensee Determined Fuel Bundle Did Not Drop During Event1993-10-29029 October 1993 PNO-I-93-059:on 931026,unexpected Drop of Section of Refueling Mast Occurred While Lowering Bundle in Core.Maint Investigated & Discovered Bend in Mast.Licensee Determined Fuel Bundle Did Not Drop During Event PNO-I-87-119, on 871223,reactor Scrammed Due to Leak from Intermediate Waterbox Manway C.Caused by Failure of Manway Gasket.Waterbox C Isolated & Spill Terminated.Water in Condenser Bay Area Measured 43 Inches1987-12-24024 December 1987 PNO-I-87-119:on 871223,reactor Scrammed Due to Leak from Intermediate Waterbox Manway C.Caused by Failure of Manway Gasket.Waterbox C Isolated & Spill Terminated.Water in Condenser Bay Area Measured 43 Inches PNO-I-87-079, on 870810,shift Supervisor Relieved of Duties Based on Results of Preliminary Investigation Into Allegation of Being Inattentive During Midnight Shift. Allegations Found Credible.Mgt Meeting W/Nrc Planned1987-08-12012 August 1987 PNO-I-87-079:on 870810,shift Supervisor Relieved of Duties Based on Results of Preliminary Investigation Into Allegation of Being Inattentive During Midnight Shift. Allegations Found Credible.Mgt Meeting W/Nrc Planned ML20214N4621987-05-27027 May 1987 PNS-I-87-008:on 870526,secondary Alarm Station Operator Received Telephone Bomb Threat.Licensee Implemented Search Procedures.Search Completed W/Negative Results.Commonwealth of PA Police Notified PNO-I-87-032, on 870415,Unit 1 Shut Down After Licensee Unable to Successfully Perform Local Leak Rate Test on Three Containment Isolation Valves in Drywell Purge Exhaust Line. on 870416,Unit 2 Tripped Due to MSIV Closure1987-04-16016 April 1987 PNO-I-87-032:on 870415,Unit 1 Shut Down After Licensee Unable to Successfully Perform Local Leak Rate Test on Three Containment Isolation Valves in Drywell Purge Exhaust Line. on 870416,Unit 2 Tripped Due to MSIV Closure PNO-I-86-097, on 861210,gas Leakage Initially Detected in Inboard MSIVs & Confirmed on 861211 While Testing Inboard MSIV B.Valve Maintained Closed & Unit Shutdown to Repair Gas Sys.Facility to Be Restarted by 8612141986-12-12012 December 1986 PNO-I-86-097:on 861210,gas Leakage Initially Detected in Inboard MSIVs & Confirmed on 861211 While Testing Inboard MSIV B.Valve Maintained Closed & Unit Shutdown to Repair Gas Sys.Facility to Be Restarted by 861214 PNO-I-86-088, on 861022,during Testing of HPCI Sys,Steam Accidentally Released Into RHR Pump Room.Caused by Two Mispositioned Drain Valves in Piping Associated W/Steam Condensing Mode of RHR Sys.State of PA Notified1986-10-23023 October 1986 PNO-I-86-088:on 861022,during Testing of HPCI Sys,Steam Accidentally Released Into RHR Pump Room.Caused by Two Mispositioned Drain Valves in Piping Associated W/Steam Condensing Mode of RHR Sys.State of PA Notified PNO-I-86-087, on 861022,approx 3,000 Gallons of Liquid Radwaste Spilled on Floor of Radwaste Bldg.Caused by Isolation Valve Leak.Spill Cleaned Up.Decontamination of Affected Areas Underway1986-10-22022 October 1986 PNO-I-86-087:on 861022,approx 3,000 Gallons of Liquid Radwaste Spilled on Floor of Radwaste Bldg.Caused by Isolation Valve Leak.Spill Cleaned Up.Decontamination of Affected Areas Underway PNO-I-86-052, on 860717,reactor Scrammed Due to Unidentified Coolant Leakage.Licensee Entered Drywell on 860718 & Identified LPCI Testable Check Valve as Source of Leakage. Repairs to Valve Scheduled for Completion on 8607201986-07-18018 July 1986 PNO-I-86-052:on 860717,reactor Scrammed Due to Unidentified Coolant Leakage.Licensee Entered Drywell on 860718 & Identified LPCI Testable Check Valve as Source of Leakage. Repairs to Valve Scheduled for Completion on 860720 PNO-I-86-039, on 860521,emergency Svc Water Pump C Motor Ran W/O Indication of Flow.Caused by Separation of Suction Bell & Severance of Shaft Near Impeller,Discovered on 860523. Pump Temporarily Repaired.Parts on Order1986-05-27027 May 1986 PNO-I-86-039:on 860521,emergency Svc Water Pump C Motor Ran W/O Indication of Flow.Caused by Separation of Suction Bell & Severance of Shaft Near Impeller,Discovered on 860523. Pump Temporarily Repaired.Parts on Order PNO-I-86-023, on 860321,while Replacing CRD Housing Support Underneath Reactor Vessel,Platform Gave Way Injuring & Contaminating Work Person.Employee Decontaminated Onsite Prior to Transfer to Hosp1986-03-24024 March 1986 PNO-I-86-023:on 860321,while Replacing CRD Housing Support Underneath Reactor Vessel,Platform Gave Way Injuring & Contaminating Work Person.Employee Decontaminated Onsite Prior to Transfer to Hosp PNO-I-86-022, on 860321,util Workman Fell 10 Ft to Subpile Floor Injuring Right Knee While Replacing Control Rod Housing Support.Caused When Platform Grating Gave Way. Worker Decontaminated & Hospitalized1986-03-24024 March 1986 PNO-I-86-022:on 860321,util Workman Fell 10 Ft to Subpile Floor Injuring Right Knee While Replacing Control Rod Housing Support.Caused When Platform Grating Gave Way. Worker Decontaminated & Hospitalized PNO-I-86-003, on 860115,reactor Manually Scrammed After Power Reduction to 70%.Caused When Oil Observed Spraying from Main Transformer.Oil Spray Caused by Excessive Heat Buildup.Transformer Will Be Inspected & Repaired1986-01-16016 January 1986 PNO-I-86-003:on 860115,reactor Manually Scrammed After Power Reduction to 70%.Caused When Oil Observed Spraying from Main Transformer.Oil Spray Caused by Excessive Heat Buildup.Transformer Will Be Inspected & Repaired PNO-I-85-090, on 851202,Units I & II Tripped from Full & 80% Power,Respectively.Caused by Deenergization of Engineered Safeguards Svc Transformer III & Momentary Loss of Control to Reactor Feed Pumps.Transformer Being Tested1985-12-0303 December 1985 PNO-I-85-090:on 851202,Units I & II Tripped from Full & 80% Power,Respectively.Caused by Deenergization of Engineered Safeguards Svc Transformer III & Momentary Loss of Control to Reactor Feed Pumps.Transformer Being Tested PNO-I-85-078A, on 851011,reactor Coolant Spill from RWCU Sys to 779 Ft Elevation of Reactor Bldg Occurred.Caused by Lifting of 150 Psig Precoat Feed Relief Valve.Spill Cleaned & Access to Area Restored1985-10-11011 October 1985 PNO-I-85-078A:on 851011,reactor Coolant Spill from RWCU Sys to 779 Ft Elevation of Reactor Bldg Occurred.Caused by Lifting of 150 Psig Precoat Feed Relief Valve.Spill Cleaned & Access to Area Restored PNO-I-85-078, on 851011,isolation Valve to Low Pressure Sys Piping Opened & Discharge of Reactor Coolant to Cleanup Demineralizer Precoat Pump Area Occurred.Cause Under Investigation.Cleanup in Progress1985-10-11011 October 1985 PNO-I-85-078:on 851011,isolation Valve to Low Pressure Sys Piping Opened & Discharge of Reactor Coolant to Cleanup Demineralizer Precoat Pump Area Occurred.Cause Under Investigation.Cleanup in Progress PNO-I-85-046, on 850630,reactor Scrammed from 100% Power Due to Generator Load Reject.Caused by Generator Neutral Phase Overvoltage Condition.Test & Repairs Will Be Completed by 8507071985-07-0303 July 1985 PNO-I-85-046:on 850630,reactor Scrammed from 100% Power Due to Generator Load Reject.Caused by Generator Neutral Phase Overvoltage Condition.Test & Repairs Will Be Completed by 850707 PNO-I-84-060, on 840703,cold Shutdown Plant Condition Following Reactor Scram from 100% Power1984-07-0606 July 1984 PNO-I-84-060:on 840703,cold Shutdown Plant Condition Following Reactor Scram from 100% Power ML20236F0101976-12-21021 December 1976 PNO-76-223:local of Painters Union at Construction Site Has Been Attempting to Organize Level I Concrete Testers Since Oct 1976.Union Indicated That Allegations May Be Made Re Substandard Concrete Testing Practices ML20249B3101976-06-16016 June 1976 PNO-76-101:issue Involving Low Concrete Cylinder Compressive in Both Safety Related & non-safety Related Structures Being Followed by Region I ML20236F2701976-06-0404 June 1976 PNS-76-024:on 760604,Bloomsburg Bell Telephone Co Received Phone Call That Bomb Will Go Off at Susquehanna Site.Call Traced to Pay Phone.State Police Investigating Bomb Threat ML20236F4131976-03-0808 March 1976 PNS-76-009:on 760308,licensee Nondestructive Testing Subcontractor Received Call Re 2 Bombs Placed at Site. Security & Supervisory People Conducting Search.Fbi Notified by Licensee ML20236F4541976-03-0505 March 1976 PNS-76-006:on 760305,Pennsylvania State Police Received Phone Call Re Bomb Threat.Licensee Security Force & State Police Searching for Bomb.Evacuation of Site Not Planned.Fbi Notified ML20236F3911976-02-0404 February 1976 PNS-76-002:on 760204,New York State Police Received Call, Informing Them That Bomb Placed at Susquehanna Site & Set to Go Off at 11:00 Am on That Date.Police Notified Licensee. Licensee Security Force & Police Searching for Bomb 1999-06-09 Category:TEXT-INSPECTION & AUDIT & I&E CIRCULARS MONTHYEARPNO-I-99-028, on 990608,Susquehanna Unit 2 Automatically Shut Down from 100% Power,Due to Failure in a Main Transformer. Region I Public Affairs Prepared to Respond to Media Inquires.Resident Inspectors on-site & Responded1999-06-0909 June 1999
[Table view]PNO-I-99-028:on 990608,Susquehanna Unit 2 Automatically Shut Down from 100% Power,Due to Failure in a Main Transformer. Region I Public Affairs Prepared to Respond to Media Inquires.Resident Inspectors on-site & Responded ML20198M1681998-01-0909 January 1998 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $55,000.Violation Noted:As of 970711,licensee Failed to Establish Adequate Controls for Activities Affecting Quality of EDGs ML20141D5561997-06-20020 June 1997 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $210,000.Violation Noted:Less than Four Independent DGs Were Operable & Neither Unit Was Placed in Hot Shutdown IR 05000387/19970011997-03-14014 March 1997 Insp Repts 50-387/97-01 & 50-388/97-01 on 970114-0224. Violations Noted.Major Areas Inspected:Operations, Engineering,Maint & Plant Support ML20136J3651997-03-14014 March 1997 Notice of Violations from Insp on 970114-0224.Violations Noted:Operators Failed to Ensure Automatic Actions Occurred After Unit 2 Recomb Discharge H2 Conc Hi-Hiannunciator Alarmed & After Grab Sample Show H Concentration of 8% ML20216B7331997-01-30030 January 1997 Investigation Rept 1-96-039 on 961018.No Noncompliance Noted.Major Areas Investigated:Review of PP&L Internal Investigation & Audit Repts Re Failure of NPO to Detect Misalignment of E DG Breaker from 960614 to 0704 ML20149J2871996-02-0909 February 1996 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $100,000.Violation Noted:Pp&L Discriminated Against Senior Security Officer After Concerns to NRC in 1992 Re Administration of Security Requalification Exam PNO-I-93-059, on 931026,unexpected Drop of Section of Refueling Mast Occurred While Lowering Bundle in Core.Maint Investigated & Discovered Bend in Mast.Licensee Determined Fuel Bundle Did Not Drop During Event1993-10-29029 October 1993 PNO-I-93-059:on 931026,unexpected Drop of Section of Refueling Mast Occurred While Lowering Bundle in Core.Maint Investigated & Discovered Bend in Mast.Licensee Determined Fuel Bundle Did Not Drop During Event IR 05000387/19900131990-07-11011 July 1990 Insp Repts 50-387/90-13 & 50-388/90-13 on 900625-29.No Violations Noted.Major Areas Inspected:Licensee Radiological Environ Monitoring & Radioactive Effluent Control Programs, Including Mgt Controls & Calibr of Effluent Monitors IR 05000387/19890171989-08-15015 August 1989 Insp Repts 50-387/89-17 & 50-388/89-15 on 890619-23 & 0718 & 19.No Noncompliance Noted.Major Areas Inspected:Mgt Support, Security Program Plans & Audits,Protected & Vital Area Physical Barriers,Emergency Power Supply & Testing ML20247K6691989-05-19019 May 1989 Partially Withheld Notice of Violation Resulting from Investigation to Determine Whether Willful Matl False Statement Was Made in Physical Security Plan (Ref 10CFR2.790(a)) ML20148A5861988-03-14014 March 1988 Notice of Violation from Insp on 880104-0213.Violation Noted:On 880112,areas W/Dose Rates of Up to 400 M/H,Which Constitute High Radiation Areas Not Posted as Required IR 05000387/19880021988-02-19019 February 1988 Insp Repts 50-387/88-02 & 50-388/88-02 on 880104-07.No Violations Noted.Major Areas Inspected:Security Organization & Program Audit,Lighting,Assessment Aids,Access Control, Alarm Stations & Followup to Unresolved Items PNO-I-87-119, on 871223,reactor Scrammed Due to Leak from Intermediate Waterbox Manway C.Caused by Failure of Manway Gasket.Waterbox C Isolated & Spill Terminated.Water in Condenser Bay Area Measured 43 Inches1987-12-24024 December 1987 PNO-I-87-119:on 871223,reactor Scrammed Due to Leak from Intermediate Waterbox Manway C.Caused by Failure of Manway Gasket.Waterbox C Isolated & Spill Terminated.Water in Condenser Bay Area Measured 43 Inches IR 05000387/19870201987-12-0707 December 1987 Insp Repts 50-387/87-20 & 50-388/87-18 on 871027-30.No Violation or Deviation Noted.Major Areas Inspected:Nuclear Matl Control & Accounting,Including Shipping & Receiving, Organization & Operation & Storage & Internal Control IR 05000387/19870151987-11-17017 November 1987 Exam Repts 50-387/87-15OL & 50-388/87-15OL on 870911.Exam Results:One Senior Reactor Operator Candidate Passed Exam. Weaknesses Noted PNO-I-87-079, on 870810,shift Supervisor Relieved of Duties Based on Results of Preliminary Investigation Into Allegation of Being Inattentive During Midnight Shift. Allegations Found Credible.Mgt Meeting W/Nrc Planned1987-08-12012 August 1987 PNO-I-87-079:on 870810,shift Supervisor Relieved of Duties Based on Results of Preliminary Investigation Into Allegation of Being Inattentive During Midnight Shift. Allegations Found Credible.Mgt Meeting W/Nrc Planned ML20214N4621987-05-27027 May 1987 PNS-I-87-008:on 870526,secondary Alarm Station Operator Received Telephone Bomb Threat.Licensee Implemented Search Procedures.Search Completed W/Negative Results.Commonwealth of PA Police Notified IR 05000387/19870051987-05-0707 May 1987 Exam Repts 50-387/87-05OL & 50-388/87-05OL on 870316-19. Exam Results:Three Out of Five Senior Reactor Operators & Two Out of Four Reactor Operators Issued Licenses.Exam & Answer Key Encl PNO-I-87-032, on 870415,Unit 1 Shut Down After Licensee Unable to Successfully Perform Local Leak Rate Test on Three Containment Isolation Valves in Drywell Purge Exhaust Line. on 870416,Unit 2 Tripped Due to MSIV Closure1987-04-16016 April 1987 PNO-I-87-032:on 870415,Unit 1 Shut Down After Licensee Unable to Successfully Perform Local Leak Rate Test on Three Containment Isolation Valves in Drywell Purge Exhaust Line. on 870416,Unit 2 Tripped Due to MSIV Closure IR 05000387/19870071987-03-26026 March 1987 Partially Withheld Physical Security Insp Repts 50-387/87-07 & 50-388/87-07 on 870302-06 (Ref 10CFR73.21 & 2.790).Major Areas Inspected:Programmatic Review of NRC Approved Physical Security & Security Contingency Plans IR 05000387/19870041987-03-10010 March 1987 Insp Repts 50-387/87-04 & 50-388/87-04 on 870209-13.No Violations or Deviations Noted.Major Areas Inspected: Nonlicensed Staff Training IR 05000387/19870021987-03-0505 March 1987 Insp Repts 50-387/87-02 & 50-388/87-02 on 870106-0217.No Violations Noted.Major Areas Inspected:Operations,Licensee Event Followup,Esf Sys Walkdown,Open Item Followup, Surveillance,Maint & Followup of Industry Events IR 05000387/19870031987-03-0404 March 1987 Insp Repts 50-387/87-03 & 50-388/87-03 on 870209-13.No Violations Noted.Major Areas Inspected:Nonradiological Chemistry Program,Including Measurement Control & Analytical Procedures Evaluation IR 05000387/19870011987-02-12012 February 1987 Insp Repts 50-387/87-01 & 50-388/87-01 on 870112-16. No Violations or Deviations Noted.Major Areas Inspected: Environ Monitoring Programs for Operations,Including Mgt Controls for Listed Programs ML20211B1211987-02-0909 February 1987 Notice of Violation from Insp on 861202-870105 IR 05000387/19860271987-02-0909 February 1987 Insp Repts 50-387/86-27 & 50-388/86-30 on 861202-870105. Violation Noted:Inoperability of Station Battery Supplying Common Loads IR 05000387/19860251987-01-30030 January 1987 Insp Repts 50-387/86-25 & 50-388/86-28 on 861117-21. Deficiencies Noted:Failure to Demonstrate Qualification of Valcor High Temp Wire,Rockbestos Coaxial Cables & Raychem Cable Splices.Unresolved Items Listed PNO-I-86-097, on 861210,gas Leakage Initially Detected in Inboard MSIVs & Confirmed on 861211 While Testing Inboard MSIV B.Valve Maintained Closed & Unit Shutdown to Repair Gas Sys.Facility to Be Restarted by 8612141986-12-12012 December 1986 PNO-I-86-097:on 861210,gas Leakage Initially Detected in Inboard MSIVs & Confirmed on 861211 While Testing Inboard MSIV B.Valve Maintained Closed & Unit Shutdown to Repair Gas Sys.Facility to Be Restarted by 861214 PNO-I-86-088, on 861022,during Testing of HPCI Sys,Steam Accidentally Released Into RHR Pump Room.Caused by Two Mispositioned Drain Valves in Piping Associated W/Steam Condensing Mode of RHR Sys.State of PA Notified1986-10-23023 October 1986 PNO-I-86-088:on 861022,during Testing of HPCI Sys,Steam Accidentally Released Into RHR Pump Room.Caused by Two Mispositioned Drain Valves in Piping Associated W/Steam Condensing Mode of RHR Sys.State of PA Notified PNO-I-86-087, on 861022,approx 3,000 Gallons of Liquid Radwaste Spilled on Floor of Radwaste Bldg.Caused by Isolation Valve Leak.Spill Cleaned Up.Decontamination of Affected Areas Underway1986-10-22022 October 1986 PNO-I-86-087:on 861022,approx 3,000 Gallons of Liquid Radwaste Spilled on Floor of Radwaste Bldg.Caused by Isolation Valve Leak.Spill Cleaned Up.Decontamination of Affected Areas Underway ML20205H3331986-08-14014 August 1986 Notice of Deviation from Insp on 860512-16.Appraisals of Unresolved & Open Items Also Encl IR 05000387/19860101986-08-13013 August 1986 Emergency Response Appraisal Repts 50-387/86-10 & 50-388/ 86-10 on 860512-16.One Deviation & Three Unresolved Items Noted:Calibr Procedure for Delta Temp Instrumentation Did Not Include Actual Sensor Calibr IR 05000387/19860131986-07-24024 July 1986 Insp Repts 50-387/86-13 & 50-388/86-13 on 860707-11.No Violations Noted.Major Areas Inspected:Qa & QC Program Changes,Qa Audit Program,Receipt,Storage & Handling Program for Equipment & Matl & Procurement Control Program PNO-I-86-052, on 860717,reactor Scrammed Due to Unidentified Coolant Leakage.Licensee Entered Drywell on 860718 & Identified LPCI Testable Check Valve as Source of Leakage. Repairs to Valve Scheduled for Completion on 8607201986-07-18018 July 1986 PNO-I-86-052:on 860717,reactor Scrammed Due to Unidentified Coolant Leakage.Licensee Entered Drywell on 860718 & Identified LPCI Testable Check Valve as Source of Leakage. Repairs to Valve Scheduled for Completion on 860720 PNO-I-86-039, on 860521,emergency Svc Water Pump C Motor Ran W/O Indication of Flow.Caused by Separation of Suction Bell & Severance of Shaft Near Impeller,Discovered on 860523. Pump Temporarily Repaired.Parts on Order1986-05-27027 May 1986 PNO-I-86-039:on 860521,emergency Svc Water Pump C Motor Ran W/O Indication of Flow.Caused by Separation of Suction Bell & Severance of Shaft Near Impeller,Discovered on 860523. Pump Temporarily Repaired.Parts on Order IR 05000388/19860071986-05-21021 May 1986 Insp Rept 50-388/86-07 on 860407-09.No Violations Noted. Major Areas Inspected:Emergency Preparedness Insp & Observation of partial-scale Annual Emergency Exercise Conducted on 860408 ML20202F3161986-04-0404 April 1986 Notice of Violation from Insp on 860203-0314 IR 05000387/19860011986-04-0101 April 1986 Exam Repts 50-387/86-01 & 50-388/86-01 on 860114-16. Exam Results:All Six Candidates Passed IR 05000387/19860021986-03-27027 March 1986 Insp Repts 50-387/86-02 & 50-388/86-01 on 860203-0314. Violation Noted:Rhr Pump Operated W/O Cooling Water Due to Valve Misalignment & Installation of Expired Squib Valve in Standby Liquid Control Sys PNO-I-86-022, on 860321,util Workman Fell 10 Ft to Subpile Floor Injuring Right Knee While Replacing Control Rod Housing Support.Caused When Platform Grating Gave Way. Worker Decontaminated & Hospitalized1986-03-24024 March 1986 PNO-I-86-022:on 860321,util Workman Fell 10 Ft to Subpile Floor Injuring Right Knee While Replacing Control Rod Housing Support.Caused When Platform Grating Gave Way. Worker Decontaminated & Hospitalized PNO-I-86-023, on 860321,while Replacing CRD Housing Support Underneath Reactor Vessel,Platform Gave Way Injuring & Contaminating Work Person.Employee Decontaminated Onsite Prior to Transfer to Hosp1986-03-24024 March 1986 PNO-I-86-023:on 860321,while Replacing CRD Housing Support Underneath Reactor Vessel,Platform Gave Way Injuring & Contaminating Work Person.Employee Decontaminated Onsite Prior to Transfer to Hosp PNO-I-86-003, on 860115,reactor Manually Scrammed After Power Reduction to 70%.Caused When Oil Observed Spraying from Main Transformer.Oil Spray Caused by Excessive Heat Buildup.Transformer Will Be Inspected & Repaired1986-01-16016 January 1986 PNO-I-86-003:on 860115,reactor Manually Scrammed After Power Reduction to 70%.Caused When Oil Observed Spraying from Main Transformer.Oil Spray Caused by Excessive Heat Buildup.Transformer Will Be Inspected & Repaired PNO-I-85-090, on 851202,Units I & II Tripped from Full & 80% Power,Respectively.Caused by Deenergization of Engineered Safeguards Svc Transformer III & Momentary Loss of Control to Reactor Feed Pumps.Transformer Being Tested1985-12-0303 December 1985 PNO-I-85-090:on 851202,Units I & II Tripped from Full & 80% Power,Respectively.Caused by Deenergization of Engineered Safeguards Svc Transformer III & Momentary Loss of Control to Reactor Feed Pumps.Transformer Being Tested IR 05000387/19850251985-10-21021 October 1985 Exam Repts 50-387/85-25 & 50-388/85-27 on 850806-07.Exam Results:Seven Reactor Operator Candidates Passed Oral, Simulator & Written Sections of Exams PNO-I-85-078A, on 851011,reactor Coolant Spill from RWCU Sys to 779 Ft Elevation of Reactor Bldg Occurred.Caused by Lifting of 150 Psig Precoat Feed Relief Valve.Spill Cleaned & Access to Area Restored1985-10-11011 October 1985 PNO-I-85-078A:on 851011,reactor Coolant Spill from RWCU Sys to 779 Ft Elevation of Reactor Bldg Occurred.Caused by Lifting of 150 Psig Precoat Feed Relief Valve.Spill Cleaned & Access to Area Restored PNO-I-85-078, on 851011,isolation Valve to Low Pressure Sys Piping Opened & Discharge of Reactor Coolant to Cleanup Demineralizer Precoat Pump Area Occurred.Cause Under Investigation.Cleanup in Progress1985-10-11011 October 1985 PNO-I-85-078:on 851011,isolation Valve to Low Pressure Sys Piping Opened & Discharge of Reactor Coolant to Cleanup Demineralizer Precoat Pump Area Occurred.Cause Under Investigation.Cleanup in Progress IR 05000387/19850291985-09-23023 September 1985 Meeting Repts 50-387/85-29 & 50-388/85-24 on 850828 Re Rescheduling of Senior Reactor Operator Licensing Exam. Region Agreed to Administer One Instructor Certification & One Senior Operator Exam on 851120 & 21,respectively PNO-I-85-046, on 850630,reactor Scrammed from 100% Power Due to Generator Load Reject.Caused by Generator Neutral Phase Overvoltage Condition.Test & Repairs Will Be Completed by 8507071985-07-0303 July 1985 PNO-I-85-046:on 850630,reactor Scrammed from 100% Power Due to Generator Load Reject.Caused by Generator Neutral Phase Overvoltage Condition.Test & Repairs Will Be Completed by 850707 IR 05000387/19850141985-05-24024 May 1985 Insp Repts 50-387/85-14 & 50-388/85-14 on 850430-0503.No Violations Identified.Major Areas Inspected:Emergency Preparedness & full-scale Annual Emergency Exercise on 850501 1999-06-09 |
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l June 9. 1999 fEELIMINARY NOTIFICATION OF EVENT OR UNUSUAL OCCURRENCE PNO-I-99-028 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 I known by Region I staff in King of Prussia. Pennsylvania on this date.-
Facility- Licensee Emeroency Classification
' Pennsylvania Power & Light Co. Notification of Unusual Event Susquehanna 2 Alert Allentown, Pennsylvania Site Area Emergency Dockets: 50-388 General Emergency X Not Applicable
Subject:
SUS 0VEHANNA UNIT 2 AUTOMATIC REACTOR SHUTDOWN - MEDIA INTEREST At 12:06 p.m. on June 8, 1999, Susquehanna Unit 2 automatically shut down from 100 percent power due to a failure in the "A" main transformer. All control rods fully inserted. Two safety relief valves automatically d opened for a short time and closed as designed. No emergency core cooling system initiation was required. All major plant equipment operated as designed following the. shutdown. The unit is in a cold shutdown cordition. Cold shutdown is defined by reactor vessel water temperature less than 200 degrees Fahrenheit and reactor pressure equal to atmospheric pressure. The cause of the 'A' main transformer failure is still being investigated. PP&L plans to repair or replace the ' A' main transformer prior to restarting the unit.
The Region I Public Affairs is prepared to respond to media inquiries.
The resident inspectors were on-site and responded to the shutdown.
The resident inspectors continue to follow PP&L's actions since the event.
The Commonwealth of Pennsylvania has been notified.
PP8L issued a press release concerning this event.
This information is current as of 8:00 a.m. on June 9. 1999 Cortact: COWGILL..CURTIS (610)337-5233 990610oo90 990609 fg E-rM-oas PDR j
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