ML20154H026
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| ML20154H026 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 05/24/1988 |
| From: | Goodwin E NRC OFFICE OF SPECIAL PROJECTS |
| To: | |
| References | |
| PNO-OSP-88-008A, PNO-OSP-88-8A, NUDOCS 8805250199 | |
| Download: ML20154H026 (2) | |
Similar Documents at Sequoyah | |
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Category:PRELIMINARY NOTIFICATION OF EVENT OR OCCURRENCE (PNO
MONTHYEARPNO-II-97-055, on 971006,contaminated Person Transported from Sequoyah Nuclear Plant to Offsite Medical Facility,Following Apparent Heart Attack.Victim Pronounced Dead at Hosp,Due to Apparent Heart Attack.Licensee Responded to Media Inquirie1997-10-0606 October 1997
[Table view]PNO-II-97-055:on 971006,contaminated Person Transported from Sequoyah Nuclear Plant to Offsite Medical Facility,Following Apparent Heart Attack.Victim Pronounced Dead at Hosp,Due to Apparent Heart Attack.Licensee Responded to Media Inquirie PNO-II-96-071, on 961011,Unit 2 Experienced Low Seal Flow Alarm on RCP 4,seal 1 & High Standpipe Alarm on RCP 4. Controlled Shutdown Begun as Required by Procedures.Licensee Currently Investigating Cause of Equipment Malfunctions1996-10-11011 October 1996 PNO-II-96-071:on 961011,Unit 2 Experienced Low Seal Flow Alarm on RCP 4,seal 1 & High Standpipe Alarm on RCP 4. Controlled Shutdown Begun as Required by Procedures.Licensee Currently Investigating Cause of Equipment Malfunctions PNO-II-96-069, on 961005,potential Transformer in Plant 500 Kv Switchyard Exploded.Cause Determined to Be Unusual Event. Licensee Has Developed Plans for Damage Assessment,Repairs, Investigation & Root Cause Analysis1996-10-0707 October 1996 PNO-II-96-069:on 961005,potential Transformer in Plant 500 Kv Switchyard Exploded.Cause Determined to Be Unusual Event. Licensee Has Developed Plans for Damage Assessment,Repairs, Investigation & Root Cause Analysis PNO-II-94-001, on 940107,plant Began CPR from 100% Power to Mode 4 Due to Inoperable Ccp.Resident Inspector Dispatched. State of Tn Informed1994-01-10010 January 1994 PNO-II-94-001:on 940107,plant Began CPR from 100% Power to Mode 4 Due to Inoperable Ccp.Resident Inspector Dispatched. State of Tn Informed PNO-II-93-068, on 931203,plant Tripped from 100% Power Due to Main Generator Voltage Excitation Problems.Unit Experienced High Generator Stator Water Cooling Temp Alarm.Licensee Investigating Root Cause1993-12-0606 December 1993 PNO-II-93-068:on 931203,plant Tripped from 100% Power Due to Main Generator Voltage Excitation Problems.Unit Experienced High Generator Stator Water Cooling Temp Alarm.Licensee Investigating Root Cause PNO-II-93-063, on 931116,Unit 2 Shut Down Due to Concerns Re Potential Operability of Eight CCS Check Valves.Caused by Failure in Open Position of Seven & Eight Had Internal Piston Incorrectly Installed.Unit 2 Placed in Cold Shutdown1993-11-17017 November 1993 PNO-II-93-063:on 931116,Unit 2 Shut Down Due to Concerns Re Potential Operability of Eight CCS Check Valves.Caused by Failure in Open Position of Seven & Eight Had Internal Piston Incorrectly Installed.Unit 2 Placed in Cold Shutdown PNO-II-93-058, on 930301,operators Noticed Increase in Voltage on Main Generator & 6.9 Kv Unit Boards.Caused by Rupture in Extraction Steam Line Due to Erosion.Restart Pending Completion of CAL Items1993-10-20020 October 1993 PNO-II-93-058:on 930301,operators Noticed Increase in Voltage on Main Generator & 6.9 Kv Unit Boards.Caused by Rupture in Extraction Steam Line Due to Erosion.Restart Pending Completion of CAL Items PNO-II-93-008A, on 930301,plant Was Manually Tripped from Full Power When Operators Noticed Increase in Main Generator Voltage.Leak Believed to Be Caused by Erosion of Piping1993-03-0303 March 1993 PNO-II-93-008A:on 930301,plant Was Manually Tripped from Full Power When Operators Noticed Increase in Main Generator Voltage.Leak Believed to Be Caused by Erosion of Piping PNO-II-93-007, on 930204,plant Commenced Power Reduction Due to Identified Steam Leakage on 1B1 MSR High Pressure Operating Vent Line.Resident Inspectors Have Been Following Licensee Actions.State of Tn Not Required to Be Informed1993-02-0404 February 1993 PNO-II-93-007:on 930204,plant Commenced Power Reduction Due to Identified Steam Leakage on 1B1 MSR High Pressure Operating Vent Line.Resident Inspectors Have Been Following Licensee Actions.State of Tn Not Required to Be Informed PNO-II-92-053, on 920821,plant Experienced Safety Injection & Reactor Trip.Unit Being Cooled by Dumping Steam to Main Condenser.Cause of Low Pressure Safety Injection Being Investigated.State of Tn Informed1992-08-21021 August 1992 PNO-II-92-053:on 920821,plant Experienced Safety Injection & Reactor Trip.Unit Being Cooled by Dumping Steam to Main Condenser.Cause of Low Pressure Safety Injection Being Investigated.State of Tn Informed PNO-II-90-049, on 900911,unit Lost Shutdown Cooling to Reactor for 5 Minutes.Caused by Hotleg Suction Valve to RHR Sys Closing Possibly Due to Mod Work Performed in Auxiliary Instrument Room.Operators Opened Valve & Cooling Restored1990-09-11011 September 1990 PNO-II-90-049:on 900911,unit Lost Shutdown Cooling to Reactor for 5 Minutes.Caused by Hotleg Suction Valve to RHR Sys Closing Possibly Due to Mod Work Performed in Auxiliary Instrument Room.Operators Opened Valve & Cooling Restored ML20206G9771988-11-21021 November 1988 PNO-OSP-88-018A:on 881118,Unit 1 Reactor Tripped.Caused by Electrical Ground in Main Generator.Licensee Initiated Outage Work Including Repair of Main Generator,Reactor Coolant Pump 3 Seal Package & Steam Dumps ML20212C5951988-11-18018 November 1988 PNO-OSP-88-018:on 881118,Unit 1 Tripped from 72% Reactor Power Because of Turbine Trip.All Equipment Operated as Required.Plant Currently Stable in Mode 3 (Hot Shutdown) ML20212C6081988-11-0707 November 1988 PNO-OSP-88-016:on 881105,staff Released Sequoyah Unit 1 from Mode 2 Holdpoint.Unit 1 Achieved Criticality on 881106.Plant Startup Has Been Uneventful ML20154C6221988-09-0909 September 1988 PNO-OSP-88-014:on 880908,increase in Auxiliary Bldg Radiation Levels Detected by Health Physics Personnel.Cause Under Investigation.No Alarm Received But Licensee Decided to Evacuate Auxiliary Bldg ML20196B7161988-06-21021 June 1988 PNO-OSP-88-011:ON 880619,return to Power Following 10-day Outage Subsequent to 880609 Reactor Trip.Outstanding Maint Needed on balance-of-plant Equipment Reduced ML20155E5821988-06-0909 June 1988 PNO-OSP-88-010:on 880608,reactor Tripped During Startup When Operators Attempted to Place Main Feed Pumps in Automatic Speed Control.Caused by Operator Error.Prior to Resumption of Startup Activities,Util Will Meet NRC to Discuss Trips ML20197E1751988-06-0606 June 1988 PNO-OSP-88-009:on 880606,Unit 2 Scrammed from 98% Power. Caused by Steam/Feed Flow Mismatch Combined W/Low Steam Generator Level.Tva Conducting post-trip Review of Scram ML20154M8201988-05-31031 May 1988 PNO-OSP-88-008B:on 880528,power Escalation Above 75% Power Authorized.Licensee Achieved 100% Power Operation on 880531. Util Considering Power Operation at Reduced Level in Order to Extend Fuel Cycle ML20154H0261988-05-24024 May 1988 PNO-OSP-88-008A:on 880524,criticality Achieved Following low-flow Scram on 880523.Caused by Procedural non-adherence During Calibr of Loop 4 Differential Pressure Transmitter. Ofc of Special Projects Notified of Investigation ML20212C6561988-05-23023 May 1988 PNO-OSP-88-008:on 880523,plant,Unit 2 Scrammed from 72% Power.Trip Occurred During Calibration of Reactor Coolant Flow Trip Channels ML20154G0841988-05-20020 May 1988 PNO-OSP-88-007:on 880519,reactor Trip Initiated by Steam Flow Greater than Feed Flow Coincident W/Low Steam Generator Level.Plant Stabilized in Hot Standby Condition While Util Conducts post-trip Root Cause Analysis & Completes Repairs ML20154D9161988-05-13013 May 1988 PNO-OSP-88-006a:on 880512,NRC Authorized Entry Into Mode 2 & Util Commenced Withdrawal of Shutdown Banks & RCS Dilution. Util Achieved 1,200 Ppm Boron Concentration on 880513.Util Commenced Approach to Criticality After NRC Review ML20154D8841988-05-12012 May 1988 PNO-OSP-88-006:on 880512,director Authorized Entry Into Mode 2 & Util Withdrawal of Shutdown Banks & RCS Dilution. Criticality Expected to Occur on 880513 ML20151J9121988-04-12012 April 1988 PNO-OSP-88-004A:on 880406,calculated Unidentified Leak Rate of 1.09 Gpm Obtained,Exceeding Tech Spec Limit of 1 Gpm. Differential Pressure Transmitter Reactor Coolant Seal Return Line Isolated.Plant Currently in Mode 5 for Repairs ML20198M8271988-04-0404 April 1988 PNO-OSP-88-004:on 880330,Ofc of Special Projects Gave Authorization to TVA to Begin B Dilution of RCS in Approach to Criticality (Mode 2) ML20212C6351988-03-15015 March 1988 PNO-OSP-88-002:on 880309,during Walkdown of Unit 2 Control Room Panels,Nrc Shift Manager Noted That Control Switch for 2A-A CCP Was in Pull-to-Lock Position,Which Would Inhibit Pump from Automatically Starting on SI Signal ML20212C6271988-03-15015 March 1988 PNO-OSP-88-003:on 880310,licensee Determined That B Concentration in Loop 3 Cla Was 2,102 Ppm.Increase Outside TS 3.5.1.1 Limits of 1,900 - 2,100 Pp,Caused by in-leakage from RCS ML20212C6491988-02-0404 February 1988 PNO-OSP-88-001:on 880204,Director of Ofc of Special Projects Released Plant,Unit 2 from First of 5 pre-established NRC Hold-Points to Allow Plant Heatup for Testing & Shakedown Activities ML20212F0651987-11-13013 November 1987 PNO-OSP-87-013:TVA Indicated Desire to Conduct non-nuclear Heat Up of Unit 2 Before Restart ML20212E3241987-11-13013 November 1987 Revised PNO-OSP-87-013:util Indicated Desire to Conduct non- Nuclear heat-up of Plant,Unit 2 Before Restart of Plant ML20212E2371987-09-14014 September 1987 PNO-OSP-87-009:Ofc of Special Projects Completed Integrated Design Insp of ERCW Sys at Plant,Unit 2.Insp Involved multiple-discipline Review of Technical Adequacy of Design Documents & Calculations ML20237L3601987-08-20020 August 1987 PNO-OSP-87-008 Re Completed as-built Portion of Integrated Design Insp of ERCW Sys at Plant.Specific Deficiencies Identified Must Be Corrected Prior to Startup of Unit 2.Insp Rept to Be Issued in mid-Sept ML20214W4061987-06-0909 June 1987 PNO-OSP-87-005:on 870608,JG Keppler & Ofc of Special Projects Met W/Sa White & TVA Representatives Re Contents & Implementation of Independent Design Verification for Plant.Nrc & Contractor Will Perform Integrated Design Insp ML20215J4881987-05-0404 May 1987 PNO-OSP-87-004:on 870429,approx 11,000 Gallons of Primary Coolant Water Spilled Into Containment Sump.Caused by Pressurizer Spray Line Vent Valve Which Had Been Left Open. Water Pumped from Sump to Radwaste Sys ML20209D2231987-04-24024 April 1987 PNO-OSP-87-003:investigation Into Drug Use by Facility Personnel Initiated Due to Allegation Against Guard Force Lieutenant.Drug Tests Administered to 26 Individuals on 870421.Individuals Testing Positive Restricted from Site ML20209D3471987-04-24024 April 1987 PNO-OSP-87-002:11 Member Team Appointed by Util to Commence Independent Review to Assess Plant Readiness for Restart. Major Areas to Be Evaluated Include Maint,Plant Operations & Radiation Control Protection & Mgt Programs PNO-II-87-010, on 870201,approx 3,000 to 4,000 Gallons of Reactor Coolant Spilled Through Steam Generator Manway & Into Containment.No Water Released Outside Plant.Caused by Failure to Close RHR Suction Valves to RCS1987-02-0202 February 1987 PNO-II-87-010:on 870201,approx 3,000 to 4,000 Gallons of Reactor Coolant Spilled Through Steam Generator Manway & Into Containment.No Water Released Outside Plant.Caused by Failure to Close RHR Suction Valves to RCS PNO-II-86-083, on 861024,util Could Not Determine Exact Location of 11 of 23 in-core Detectors Containing 0.004 G U-235.Region Will Monitor Util Followup Actions During 861029-30 Insp1986-10-31031 October 1986 PNO-II-86-083:on 861024,util Could Not Determine Exact Location of 11 of 23 in-core Detectors Containing 0.004 G U-235.Region Will Monitor Util Followup Actions During 861029-30 Insp PNO-II-86-049, on 860711,earth Tremor Measuring 3.7 on Richter Scale Occurred in Dalton,Ga.No Seismic Monitor Alarms Received.No Damage Occurred to Plant.Remote Seismic Monitoring Instruments Being Checked1986-07-11011 July 1986 PNO-II-86-049:on 860711,earth Tremor Measuring 3.7 on Richter Scale Occurred in Dalton,Ga.No Seismic Monitor Alarms Received.No Damage Occurred to Plant.Remote Seismic Monitoring Instruments Being Checked PNO-II-86-007, on 860117,local Media Interest Developed as Result of Detection of Contamination on Outside Wall of Condensate Demineralizer Waste Evaporator on 860115.Licensee Analyzing Addl Soil Samples for Possible Contamination1986-01-17017 January 1986 PNO-II-86-007:on 860117,local Media Interest Developed as Result of Detection of Contamination on Outside Wall of Condensate Demineralizer Waste Evaporator on 860115.Licensee Analyzing Addl Soil Samples for Possible Contamination PNO-II-85-080, on 850821,orderly Shutdown Directed by TVA Due to Independent Contractor Concerns That Documentation Inadequate for Environ Qualification of Electrical Equipment.State of Tn Informed1985-08-21021 August 1985 PNO-II-85-080:on 850821,orderly Shutdown Directed by TVA Due to Independent Contractor Concerns That Documentation Inadequate for Environ Qualification of Electrical Equipment.State of Tn Informed PNO-II-85-078, crack Identified on Weld of 3/4-inch Sample Line Running Off RCS Letdown Line.Weld Crack in Identical Location to One Found on 850729.Weld Repaired.Pipe Supports Being Installed1985-08-14014 August 1985 PNO-II-85-078:crack Identified on Weld of 3/4-inch Sample Line Running Off RCS Letdown Line.Weld Crack in Identical Location to One Found on 850729.Weld Repaired.Pipe Supports Being Installed PNO-II-85-074, on 850729,employees Received Minor Contamination.Caused by Weld Leak Off RCS Letdown Line.Flow Rate Reduced & Path Opened to Maintain Water Control. Employees Decontaminated at Plant1985-07-30030 July 1985 PNO-II-85-074:on 850729,employees Received Minor Contamination.Caused by Weld Leak Off RCS Letdown Line.Flow Rate Reduced & Path Opened to Maintain Water Control. Employees Decontaminated at Plant PNO-II-82-066, on 820612,12 TVA Employees Slightly Contaminated After Radioactive Gas Leaked from Check Valve Flange on Waste Gas Compressor.Employees Decontaminated. Leaking Flange Repaired.Release Limits Not Exceeded1982-06-14014 June 1982 PNO-II-82-066:on 820612,12 TVA Employees Slightly Contaminated After Radioactive Gas Leaked from Check Valve Flange on Waste Gas Compressor.Employees Decontaminated. Leaking Flange Repaired.Release Limits Not Exceeded PNO-II-80-164, on 801123,unanticipated Safety Injection Occurred During Testing Involving Loss of Offsite Power. Safeguards Actuation Signal Reset Locally.Caused by Inverter Failure1980-11-24024 November 1980 PNO-II-80-164:on 801123,unanticipated Safety Injection Occurred During Testing Involving Loss of Offsite Power. Safeguards Actuation Signal Reset Locally.Caused by Inverter Failure PNO-III-80-113, on 800623,while Heating Up Plant for Initial Criticality,Inadvertent Actuation of Safety Injection Occurred.Caused by Manual Opening of Main Steam Isolation Valves.All Equipment Functioned as Expected1980-06-24024 June 1980 PNO-III-80-113:on 800623,while Heating Up Plant for Initial Criticality,Inadvertent Actuation of Safety Injection Occurred.Caused by Manual Opening of Main Steam Isolation Valves.All Equipment Functioned as Expected ML20126D1901977-08-12012 August 1977 PNO-77-143:Pacific Pump Co Supplied Facilities W/Production Lot of 40 Pumps Mfg Using Shafts Made of Inferior Matl. Cause Unstated.All Utils W/Pumps Were Notified.Nrc Headquarters Notified on 770812 ML20249B9461976-08-30030 August 1976 PNO-76-149:on 760827,Leeway Motor Freight Truck & Trailer Hauling 75 Drums of Yellowcake (U) from Utah Intl,Wyoming,To Kerr-McGee Sequoyah Plant,Gore,Ok,Overturned Near Wotanga, Ok.No Fatalities or Contamination to Environ Occurred 1997-10-06 Category:TEXT-INSPECTION & AUDIT & I&E CIRCULARS MONTHYEARIR 05000327/19990051999-09-27027 September 1999
[Table view]Insp Repts 50-327/99-05 & 50-328/99-05 on 990718-0828. Violations Noted.Major Areas Inspected:Mitigating Sys ML20210V1621999-08-13013 August 1999 Insp Repts 50-327/99-04 & 50-328/99-04 on 990601-0717.One Potentially Safety Significant Issue Noted.Major Areas Inspected:Licensee Emergency Preparedness IR 05000327/19990031999-06-30030 June 1999 Insp Repts 50-327/99-03 & 50-328/99-03 on 990328-0531.Non- Cited Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Maint & Engineering IR 05000327/19990021999-04-23023 April 1999 Insp Repts 50-327/99-02 & 50-328/99-02 on 990214-0327.No Violations Noted.Major Areas Inspected:Licensee Operations, Maint & Engineering IR 05000327/19990011999-03-15015 March 1999 Insp Repts 50-327/99-01 & 50-328/99-01 on 990103-0213. Violations Noted & Being Treated as non-cited Violations. Major Areas Inspected:Aspects of Licensee Operations,Maint & Engineering IR 05000327/19983021999-03-12012 March 1999 NRC Operator Licensing Exam Repts 50-327/98-302 & 50-328/98-302 (Including Completed & Graded Tests) for Test Administered on 980928-1001 ML20202J5471999-02-0101 February 1999 Notice of Violation from Insp on 981122-990102.Violation Noted:Following Unit 1 Rt on 981109,procedural Requirements of EOP ES0.1 Were Not Properly Implemented,In That RCS Temperatures Were Not Monitored & Steam Not Dumped IR 05000327/19980111999-02-0101 February 1999 Insp Repts 50-327/98-11 & 50-328/98-11 on 981122-990102. Violations Noted.Major Areas Inspected:Licensee Operations, Maint & Engineering IR 05000327/19980101998-12-0707 December 1998 Insp Repts 50-327/98-10 & 50-328/98-10 on 981011-1121.No Violations Noted.Major Areas Inspected:Operations,Maint & Engineering IR 05000327/19980141998-12-0404 December 1998 Insp Repts 50-327/98-14 & 50-328/98-14 on 981102-06.No Violations Noted.Major Areas Inspected:Observation & Evaluation of Biennial Emergency Preparedness Exercise for Sequoyah Nuclear Plan ML20196D6081998-11-24024 November 1998 Notice of Violation from Insp on 980914-1016.Violation Noted:As of 980916,requirements of 0-MI-MXX-061-001 Not Implemented IR 05000327/19980131998-11-24024 November 1998 Insp Repts 50-327/98-13 & 50-328/98-13 on 980914-1016. Violations Noted.Major Areas Inspected:Aspects of Licensee maint,testing,engineering,self-assessment & Problem Evaluations of Licensee Ice Condenser Sys ML20195G5521998-11-0909 November 1998 Notice of Violation from Insp on 980830-1010.Violation Noted:Licensee Failed to Assure That All Testing Required to Demonstrate That Safety Related Circuit Breakers Would Perform Satisfactorily in Svc IR 05000327/19980091998-11-0909 November 1998 Insp Repts 50-327/98-09 & 50-328/98-09 on 980830-1010. Violations Noted.Major Areas Inspected:Licensee Operations, Maint,Engineering Plant Support & Effectiveness of Licensee Controls in Identifying,Resolving & Preventing Problems IR 05000327/19980081998-09-18018 September 1998 Insp Repts 50-327/98-08 & 50-328/98-08 on 980719-0829.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support,Licensee Conducted Radiological Emergency Plan Drill IR 05000327/19980071998-08-0404 August 1998 Insp Repts 50-327/98-07 & 50-328/98-07 on 980607-0718. Violations Noted.Major Areas Inspected:Aspects of Licensee Operation,Maint,Engineering,Plant Support & Effectiveness of Licensee Controls in Identifying & Preventing Problems ML20237B1851998-08-0404 August 1998 Notice of Violation from Insp on 980606-0718.Violations Noted:On or Before 971103,conditions Adverse to Qualify Were Not Promptly Identified & Corrected,In That Licensee Failed to Correct &/Or Initiate Problem Evaluation Rept ML20236J6631998-06-26026 June 1998 Insp Repts 50-327/98-06 & 50-328/98-06 on 980426-0606. Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support ML20236J6591998-06-26026 June 1998 Notice of Violation from Insp on 980426-0606.Violation Noted:Inservice Testing of Valves Not in Accordance with Section XI of ASME Boiler & Pressure Vessel Code & Applicable Addenda as Required by 10CFR50.55a IR 05000327/19983001998-06-25025 June 1998 NRC Operator Licensing Exam Repts 50-327/98-300 & 50-328/98-300 (Including Completed & Graded Tests) for Tests Administered on 980601-02 IR 05000327/19980051998-06-12012 June 1998 Insp Repts 50-327/98-05 & 50-328/98-05 on 980504-08.No Violations Noted.Major Areas Inspected:Maint Procedure.Insp Team Comprised Region II & Headquarters Personnel.Switchgear & Surrounding Areas Found in Good Matl Condition ML20247L5781998-05-15015 May 1998 Notice of Violation from Insp on 980315-0425.Violation Noted:Licensee Failed to Perform Surveillance Requirement 4.8.1.1.1.a,within 1 H & at Least Once Per 8 H Thereafter IR 05000327/19980041998-05-15015 May 1998 Insp Repts 50-327/98-04 & 50-328/98-04 on 980315-0425. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support ML20216H7841998-04-10010 April 1998 Insp Repts 50-327/98-03 & 50-328/98-03 on 980201-0314. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support ML20216H7701998-04-10010 April 1998 Notice of Violation from Insp on 980201-0314.Violation Noted:License Failed to Rept an Adverse Condition on Work Request/Work Order &/Or Problem Evaluation Rept IR 05000327/19980991998-04-0101 April 1998 SALP Repts 50-327/98-99 & 50-328/98-99 for Period 960728- 980221 ML20217K3751998-03-30030 March 1998 Notice of Violation from Insp on 980126-0213.Violation Noted:On Listed Dates,Licensee Made Changes to Facility as Described in FSAR W/O Adequate Written SE Which Provides Bases for Determination That Changes Did Not Involve USQ ML20217K3801998-03-30030 March 1998 Insp Repts 50-327/98-01 & 50-328/98-01 on 980126-0213.No Violations Noted.Major Areas Inspected:Operations,Maint & Engineering IR 05000327/19980021998-03-0505 March 1998 Insp Repts 50-327/98-02 & 50-328/98-02 on 980202-06.No Violations Noted.Major Areas Inspected:Aspects of Licensee Operations & Maint.Review of Initial & Requalification Training Programs Were Also Conducted ML20203J5411998-02-19019 February 1998 Notice of Violation from Insp on 971231-980131.Violation Noted:On 980126 Individuals Failed to Monitor Themselves in Whole Body Contamination Monitor or W/Hand & Foot Frisk Monitor ML20203J5541998-02-19019 February 1998 Insp Repts 50-327/97-18 & 50-328/97-18 on 971221-980131. Violations Noted.Major Areas Inspected:Licensee Operations, Maint,Engineering,Plant Support & Effectiveness of Licensee Controls in Identifying & Resolving Problems ML20216D8431998-02-0606 February 1998 EN-97-109A:on 980206,informs of Withdrawal of Proposed Civil Penalty of $55,000 Issued to Licensee.Credit for Identification Appropriate to Recognize Diligence of TVA Training Instructor Who Discovered Vital Battery Problem IR 05000327/19970171998-01-16016 January 1998 Insp Repts 50-327/97-17 & 50-328/97-17 on 971109-1220.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering,Plant Support & Effectiveness of Licensee Controls in Identifying,Resolving & Preventing Problems IR 05000327/19970141997-12-0808 December 1997 Insp Repts 50-327/97-14 & 50-328/97-14 on 970928-1108.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering,Plant Support,Effectiveness of License Controls in Identifying,Resolving & Preventing Problems ML20197F5541997-12-0808 December 1997 Notice of Violation from Insp on 970725-0704 & Proposed Imposition of Civil Penalty in Amount of $55,000.Violation Noted:Sro Failed to Implement Step 8.4.8 of Soi 0-S0-250-1. Predecisional EC Agenda & Documentation Encl IR 05000327/19970161997-12-0505 December 1997 Insp Repts 50-327/97-16 & 50-328/97-16 on 971103-06.No Violations Noted.Major Areas Inspected:Evaluation of 971017 Wire Damage Event at Electrical Penetration 22 ML20197F6971997-12-0303 December 1997 EN-97-109:on 971208,notice of Proposed Imposition of Civil Penalty in Amount of $55,000 Issued to Licensee.Action Based on Severity Level III Problem Re Failure to Maintain Direct Current Vital Battery Channel Energized & Operable ML20199H1451997-11-0606 November 1997 Exam Repts 50-327/97-300 & 50-328/97-300 on 970919-1007. Exam Results:Four Out of Seven Candidates Passed Exam.One Candidate Was Marginal Performer IR 05000327/19970121997-10-24024 October 1997 Insp Repts 50-327/97-12 & 50-328/97-12 on 970824-0927.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support & Operator Requalification Program IR 05000327/19970151997-10-23023 October 1997 Insp Repts 50-327/97-15 & 50-328/97-15 on 970922-29.No Violations Noted.Major Areas Inspected:Emergency Preparedness PNO-II-97-055, on 971006,contaminated Person Transported from Sequoyah Nuclear Plant to Offsite Medical Facility,Following Apparent Heart Attack.Victim Pronounced Dead at Hosp,Due to Apparent Heart Attack.Licensee Responded to Media Inquirie1997-10-0606 October 1997 PNO-II-97-055:on 971006,contaminated Person Transported from Sequoyah Nuclear Plant to Offsite Medical Facility,Following Apparent Heart Attack.Victim Pronounced Dead at Hosp,Due to Apparent Heart Attack.Licensee Responded to Media Inquirie ML20211E2531997-09-22022 September 1997 Notice of Violation from Insp on 970706-0823.Violation Noted:On 970714,containment Isolation Valve 1-FCV-31C-229 Failed to Exhibit Required Change of Obturator Position & Was Not Repaired or Replaced & Data Not Analyzed IR 05000327/19970081997-09-22022 September 1997 Insp Repts 50-327/97-08 & 50-328/97-08 on 970706-0823. Violations Noted.Major Areas Inspected:Licensee Operations, Maint,Engineering,Plant Support & Effectiveness of Licensee Controls in Identifying,Resolving & Preventing Problems IR 05000327/19970091997-09-15015 September 1997 Insp Repts 50-327/97-09 & 50-328/97-09 on 970804-08.No Violations Noted.Major Areas Inspected:Operations,Maint & Engineering Re Effectiveness of Licensee Controls in Identifying,Resolving & Preventing Problems ML20198H7911997-09-11011 September 1997 Insp Repts 50-327/97-13 & 50-328/97-13 on 970725-0904. Violations Noted.Major Areas Inspected:Insp Scope,Event Synopsis & Observations & Findings ML20141H9581997-07-28028 July 1997 Insp Repts 50-327/97-06 & 50-328/97-06 on 970525-0705. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support ML20141H9531997-07-28028 July 1997 Notice of Violation from Insp on 970525-0705.Violation Noted:Licensee Failed to Implement Prompt Corrective Actions to Resolve Condition Adverse to Quality ML20149L5671997-07-24024 July 1997 Notice of Violation from Insp on 970623-27.Violation Noted: on 960627,licensee Had Loss of Security Electronic Equipment & Failed to Post Officers in Position to Provide Surveillance of Entire Protected Area Perimeter IR 05000327/19970071997-07-24024 July 1997 Insp Repts 50-327/97-07 & 50-328/97-07 on 970623-27. Violations Noted.Major Areas Inspected:Aspects of Licensee Plant Support ML20149G8681997-07-10010 July 1997 Notice of Violation from Insp on 970324-0522.Violation Noted:Licensee Failed to Esatblish Measures to Assure That Significant Condition Adverse to Quality Was Promptly Identified & Corrected & C/A Taken to Preclude Repetition 1999-09-27 |
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May 24, 1988 PRELIMINARY NOTIFICATION OF EVENT OR UNUSUAL OCCURRENCE PNO-0SP-88-008a 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 all that is known by the OSP staff on this date.
FACILITY: Tennessee Valley Authority Licensee Emergency Sequoyah Unit 2 Classification:
Docket No. 50-328 Notification of Unusual Soddy-Daisy, Tennessee Event Alert Site Area Emergency General Emergency X Not Applicable
SUBJECT:
SEQU0YAH 2 SCRAM - UPDATE At 3:23 a.m. on May 24, 1988, Sequoyah 2 achieved critically in a restart following.a low-flow scram that occurred early in the morning of May 23, 1988. TVA's post-trip review identified the cause of the scram as procedural non-adherence during calibration of a loop 4, low-flow differential pressure transmitter. Contrary to procedure, the technicians had vented the isolated dp cell using a drain, rather than a v* lit valve. This left a void in the isolated high pressure side piping of the dp cell. When the dp cell was put back into service, the filling of the void caused a pressure fluctuation on all loop 4 dp cells. This fluctuation caused the other dp cells of that loop to sense a low-flow condition and the plant tripped. TVA was able to duplicate the sequence during their post-trip investigation.
TVA reported the results of the investigation and their preliminary plans for corrective action to the OSP staff prior to startup. The startup began late in the evening of May 23rd and proceeded uneventfully. At 8:00 a.m. on May 24, 1988, Sequoyah 2 was held at 28% power to adjust secondary chemistry and complete calibration of reactor coolant system flow instruments. As of 4:00 p.m., those actions were completed and Sequoyah was moving towards 75%
power. The unit has not yet been released from the NRC-imposed 75% hold point.
CONTACT: E. Goodwin (301) 492-0794 l
DISTRIBUTION see next page f l
l 50T 8805250199 880524 0)
h ,-
V' DISTRIBUTION:
5520: Mail:
WaTrman Zech - INRC1718/Leadop XG5 Comissioner Roberts - 1NRC1718/Leadop DCS Comissioner Bernthal - INRC1718/Leadop OIA-MNBB-8607 Comissioner Carr - 1NRC1718/Leadop OI - 3E4-DLewis Comissioner Rogers - INRC1718/Leadop OSP SECY - INRC1718/Leadop CA - 1NRC1718/Leadop PA - 1NRC02/Leadop ARM - NRCRM/ Brown Regional Offices A0ED - NRCRMPN Region I - RI/Leadop Hqs Oper. Office - NRCRMPN Region II - RII/Leadop NRR - INRC1112/Berean Sequoyah Resident Inspector OE - INRC0708/Sumers Licensee: TVA NMSS - INRC0506/Leadop Region III - RIII/Leadop OGC - INRC1516/Leadop Region IV - RIV/Leadop SP - 1NRC0304/SGindes Region V - RV/Leadop ED0 - INRC1718/Leadop DEDR0 - 1NRC1718/Leadop GPA - INRC1718/Leadop
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