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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO
MONTHYEARML18022B0421998-05-14014 May 1998 Special Rept:On 970719,declared Channel 751 of Digital Metal Impact Monitoring Sys Monitors Inoperable.Caused by Noise Originating in Channel 751 pre-amplifier/accelerometer Sensor Located in Containment.Channel 751 in Containment ML18012A4101996-10-23023 October 1996 Ro:On 960916,fish Kill Occurred in Harris Lake.Caused by Heavy Precipitation That Accompanied Hurricane Fran.Will Perform Monitoring of Dissolved Oxygen Concentrations to Document Return of Sufficient Oxygen to Aquatic Life ML18011B1271996-02-0505 February 1996 Special Rept:On 951105,actuation of ECCS & Subsequent Injection of Water Into RCS Occurred.Unusual Event (Ue) Declared Due to ECCS Actuation & Ue Exited Based on Termination of SI & Stabilization of Plant in Mode-3 ML18022A9751995-10-0505 October 1995 Special Rept,Identifying Number of SG Tubes Plugged as Result of Recent SG Tube ISI Conducted During Refueling Outage 6 ML18011B0091995-09-0505 September 1995 Special Rept:On 950817,WPB Stack 5A WRGM Was Declared Inoperable to Allow for Testing of Associated Stack 5A Exhaust Flow Rate Monitor.Monitor Returned to Svc on 950825 ML18011A2241993-10-27027 October 1993 Special Rept:On 930928,identified That 10 Used Incore Detectors Not Accounted For.Most Probable Disposition Is That Detectors Inadvertently Mixed W/Other LLW Matl & Shipped to Seg in Apr 1993.Procedures FMP-108 & 109 Revised ML18010B1291993-07-12012 July 1993 Special Rept:On 930621,violation of TS 3.3.3.6 Occurred Due to Time Required to Install New Operating System for Inoperable RCS Subcooling Margin Monitor & Pressurizer Safety Valve Position Indication Sys ML18010A6311992-05-0808 May 1992 Special Rept:On 920420,RCS Subcooling Monitor Declared Inoperable to Install New & Improved Disk Drives in ERF Info Sys.Monitor Out of Svc for More than 7 Days.New Disk Drives & Circuit Board Upgrade Completed by Vendor on 920412 ML18010A3671991-08-15015 August 1991 Special Rept:On 910706,seismic Monitoring Sys Declared Inoperable.Caused by Unsatisfactory Surveillance Test Results.Maint Calibration Procedure & Operations Surveillance Test Performed Satisfactorily ML18009A9391991-06-14014 June 1991 Special Rept:On 910528,stack 5 Exhaust Sys Radiation Monitor Declared Inoperable When Monitor Removed from Svc to Perform Test Procedure.Caused by Failed Capacitor.Capacitor Replaced ML18009A9361991-06-14014 June 1991 Special Rept:On 910516,plant Experienced LTOP Event While RCS Operated Under Solid Water Conditions.Actuation of LTOP Sys Resulted from Pressure Induced by Start of Reactor Coolant Pump ML18009A7041990-10-11011 October 1990 Special Rept:On 900922,main Steam Line Radiation Monitor Declared Inoperable Due to Communication Failure ML18022A7541990-01-15015 January 1990 Special Rept:On 891223,reactor Coolant Subcooling Monitor Declared Inoperable Due to Erratic Indications & Out of Svc Beyond 7-day Time Limit in Spec 6.9.2.Caused by Normal End of Life of Data Isolator Board.Board Replaced on 900103 ML18009A3331990-01-0505 January 1990 Special Rept:On 891220,plant Vent High Range Noble Gas Monitor RM-21AV-3509-1SA Declared Inoperable When Monitor Found to Be Out of Calibr During Performance of Test Procedure.Caused by Detector Being Out of Calibr ML18005B1201989-10-13013 October 1989 Special Rept:On 890904,seismic Monitor Sys Declared Inoperable Due to Seismic Annunciator Panel in Main Control Room Had Annunciators Lit for No Apparent Reason.Cause Believed to Be Defective Logic Board.Repairs Made by Vendor ML18005A6051988-09-19019 September 1988 Special Rept:On 880912,first Inservice Insp of Steam Generators Completed,Per Tech Specs 4.4.5.5.a & 6.9.2. Reporting Requirements of IE Bulletin 88-002 Will Be Submitted Under Separate Cover ML18005A5861988-09-0808 September 1988 Suppl to Special Rept:On 880412,vent Stack 5A Wide Range Gas Monitor 1WV-3547-1 Declared Inoperable.Initially Reported on 880502.Plant Calibr Procedure Revised Incorporating Changes Recommended by Vendor & Sample Flow Transmitter Calibr ML18022A6441988-05-0202 May 1988 Special Rept:On 880412,vent Stack 5A wide-range Gas Monitor Declared Inoperable.Caused by Loss of Sample Flow That Would Occur While Attempting Calibr of Sample Flow Transmitter. Correct low-range Flow Transmitter Ordered ML18005A2861988-02-0505 February 1988 Special Rept:On 880118,main Steam Line Radiation Monitor C Failed to Adequately Respond to Routine Source Check.Caused by Source Sticking in Partially Inserted Position.Work Request Initiated to Repair Monitor ML18022A6001988-01-0404 January 1988 Special Rept:On 871102,vent Stack 5A Wide Range Gas Radiation Monitor Inoperable.Caused by Potential Loss of Sample Flow Due to Calibr of Transmitter & iso-kinetic Sampling Skid.Mass Flow Meter Replaced ML18022A6011988-01-0404 January 1988 Special Rept:On 871212,waste Processing Bldg Vent Stack 5 Wide Range Gas Monitor Declared Inoperable in Excess of 7 Days.Caused by Defective photo-multiplier Tube on Low Range Channel.Tube Replaced ML18022A5731987-10-15015 October 1987 Special Rept:On 870924,vent Stack Wide Range Gas Monitor RM-3536-1 Declared Inoperable Due to Loss of Process Control.Caused by Equipment Failure.Flow Sensing Elements Removed & Cleaned to Remove Corrosion ML18004B8551987-06-15015 June 1987 Special Rept:On 870523,turbine Bldg Vent Stack wide-range Gas Monitor RM-35361-1 Declared Inoperable Due to Loss of Process Flow.Caused by Shorted Sensing Element.Element & Current Card Adjusted & Calibr ML18004B7541987-04-0303 April 1987 Special Rept:On 870305,util Notified by Sorrento Electronics of Environ Qualification Problem W/Interconnecting Cable on Digital high-range Radiation Monitors.Caused by Misapplication of Cable by Vendor.Alternate Monitor Used 1998-05-14
[Table view] Category:LER)
MONTHYEARML18022B0421998-05-14014 May 1998 Special Rept:On 970719,declared Channel 751 of Digital Metal Impact Monitoring Sys Monitors Inoperable.Caused by Noise Originating in Channel 751 pre-amplifier/accelerometer Sensor Located in Containment.Channel 751 in Containment ML18012A4101996-10-23023 October 1996 Ro:On 960916,fish Kill Occurred in Harris Lake.Caused by Heavy Precipitation That Accompanied Hurricane Fran.Will Perform Monitoring of Dissolved Oxygen Concentrations to Document Return of Sufficient Oxygen to Aquatic Life ML18011B1271996-02-0505 February 1996 Special Rept:On 951105,actuation of ECCS & Subsequent Injection of Water Into RCS Occurred.Unusual Event (Ue) Declared Due to ECCS Actuation & Ue Exited Based on Termination of SI & Stabilization of Plant in Mode-3 ML18022A9751995-10-0505 October 1995 Special Rept,Identifying Number of SG Tubes Plugged as Result of Recent SG Tube ISI Conducted During Refueling Outage 6 ML18011B0091995-09-0505 September 1995 Special Rept:On 950817,WPB Stack 5A WRGM Was Declared Inoperable to Allow for Testing of Associated Stack 5A Exhaust Flow Rate Monitor.Monitor Returned to Svc on 950825 ML18011A2241993-10-27027 October 1993 Special Rept:On 930928,identified That 10 Used Incore Detectors Not Accounted For.Most Probable Disposition Is That Detectors Inadvertently Mixed W/Other LLW Matl & Shipped to Seg in Apr 1993.Procedures FMP-108 & 109 Revised ML18010B1291993-07-12012 July 1993 Special Rept:On 930621,violation of TS 3.3.3.6 Occurred Due to Time Required to Install New Operating System for Inoperable RCS Subcooling Margin Monitor & Pressurizer Safety Valve Position Indication Sys ML18010A6311992-05-0808 May 1992 Special Rept:On 920420,RCS Subcooling Monitor Declared Inoperable to Install New & Improved Disk Drives in ERF Info Sys.Monitor Out of Svc for More than 7 Days.New Disk Drives & Circuit Board Upgrade Completed by Vendor on 920412 ML18010A3671991-08-15015 August 1991 Special Rept:On 910706,seismic Monitoring Sys Declared Inoperable.Caused by Unsatisfactory Surveillance Test Results.Maint Calibration Procedure & Operations Surveillance Test Performed Satisfactorily ML18009A9391991-06-14014 June 1991 Special Rept:On 910528,stack 5 Exhaust Sys Radiation Monitor Declared Inoperable When Monitor Removed from Svc to Perform Test Procedure.Caused by Failed Capacitor.Capacitor Replaced ML18009A9361991-06-14014 June 1991 Special Rept:On 910516,plant Experienced LTOP Event While RCS Operated Under Solid Water Conditions.Actuation of LTOP Sys Resulted from Pressure Induced by Start of Reactor Coolant Pump ML18009A7041990-10-11011 October 1990 Special Rept:On 900922,main Steam Line Radiation Monitor Declared Inoperable Due to Communication Failure ML18022A7541990-01-15015 January 1990 Special Rept:On 891223,reactor Coolant Subcooling Monitor Declared Inoperable Due to Erratic Indications & Out of Svc Beyond 7-day Time Limit in Spec 6.9.2.Caused by Normal End of Life of Data Isolator Board.Board Replaced on 900103 ML18009A3331990-01-0505 January 1990 Special Rept:On 891220,plant Vent High Range Noble Gas Monitor RM-21AV-3509-1SA Declared Inoperable When Monitor Found to Be Out of Calibr During Performance of Test Procedure.Caused by Detector Being Out of Calibr ML18005B1201989-10-13013 October 1989 Special Rept:On 890904,seismic Monitor Sys Declared Inoperable Due to Seismic Annunciator Panel in Main Control Room Had Annunciators Lit for No Apparent Reason.Cause Believed to Be Defective Logic Board.Repairs Made by Vendor ML18005A6051988-09-19019 September 1988 Special Rept:On 880912,first Inservice Insp of Steam Generators Completed,Per Tech Specs 4.4.5.5.a & 6.9.2. Reporting Requirements of IE Bulletin 88-002 Will Be Submitted Under Separate Cover ML18005A5861988-09-0808 September 1988 Suppl to Special Rept:On 880412,vent Stack 5A Wide Range Gas Monitor 1WV-3547-1 Declared Inoperable.Initially Reported on 880502.Plant Calibr Procedure Revised Incorporating Changes Recommended by Vendor & Sample Flow Transmitter Calibr ML18022A6441988-05-0202 May 1988 Special Rept:On 880412,vent Stack 5A wide-range Gas Monitor Declared Inoperable.Caused by Loss of Sample Flow That Would Occur While Attempting Calibr of Sample Flow Transmitter. Correct low-range Flow Transmitter Ordered ML18005A2861988-02-0505 February 1988 Special Rept:On 880118,main Steam Line Radiation Monitor C Failed to Adequately Respond to Routine Source Check.Caused by Source Sticking in Partially Inserted Position.Work Request Initiated to Repair Monitor ML18022A6001988-01-0404 January 1988 Special Rept:On 871102,vent Stack 5A Wide Range Gas Radiation Monitor Inoperable.Caused by Potential Loss of Sample Flow Due to Calibr of Transmitter & iso-kinetic Sampling Skid.Mass Flow Meter Replaced ML18022A6011988-01-0404 January 1988 Special Rept:On 871212,waste Processing Bldg Vent Stack 5 Wide Range Gas Monitor Declared Inoperable in Excess of 7 Days.Caused by Defective photo-multiplier Tube on Low Range Channel.Tube Replaced ML18022A5731987-10-15015 October 1987 Special Rept:On 870924,vent Stack Wide Range Gas Monitor RM-3536-1 Declared Inoperable Due to Loss of Process Control.Caused by Equipment Failure.Flow Sensing Elements Removed & Cleaned to Remove Corrosion ML18004B8551987-06-15015 June 1987 Special Rept:On 870523,turbine Bldg Vent Stack wide-range Gas Monitor RM-35361-1 Declared Inoperable Due to Loss of Process Flow.Caused by Shorted Sensing Element.Element & Current Card Adjusted & Calibr ML18004B7541987-04-0303 April 1987 Special Rept:On 870305,util Notified by Sorrento Electronics of Environ Qualification Problem W/Interconnecting Cable on Digital high-range Radiation Monitors.Caused by Misapplication of Cable by Vendor.Alternate Monitor Used 1998-05-14
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML18017A9181999-10-0808 October 1999 LER 99-008-00:on 991008,CR Emergency Filtration Sys Tech Specs Occurred.Caused by Site Personnel Failed to Recognize That Blocking Open CR Emergency Filtration Sys.Procedures Revised.With 991008 Ltr ML18017A9151999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Shearon Harris Npp. with 991012 Ltr ML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data ML18017A8671999-09-10010 September 1999 LER 99-007-00:on 990811,determined That Cvis ARMs High Alarm Setpoints Were Not within TS Limit.Caused by Not Having Procedure to Verify If Cvis ARM High Alarm Setpoints Were within TS Requirements.Revised Procedures.With 990910 Ltr ML18017A8621999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Harris Nuclear Plant.With 990908 Ltr ML18016B0481999-08-0404 August 1999 LER 99-006-01:on 981124,noted Failure to Comply with TS 4.0.4 & TS 3/4.6.3, Civs. Caused by post-maint Testing That Did Not Adequately Test Control Circuitry & Verify Isolation Time Following Maint.Procedure Was Revised ML18017A8361999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Shearon Harris Nuclear Power Plant.With 990811 Ltr ML18016B0151999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Shearon Harris Npp. with 990713 Ltr ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML18016A9801999-06-0404 June 1999 LER 99-006-00:on 981124,failed to Comply with TS 4.0.4 & TS 3/4.6.3, Civ. Caused by post-maint Testing That Did Not Adequately Test Control Circuitry & Verify Isolation Time Following Maint.Procedure Will Be Revised.With 990604 Ltr ML18016A9851999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Shearon Harris Nuclear Plant,Unit 1.With 990614 Ltr ML18017A8981999-05-12012 May 1999 Technical Rept Entitled, Harris Nuclear Plant-Bacteria Detection in Water from C&D Spent Fuel Pool Cooling Lines. ML18016A9581999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Shearon Harris Nuclear Plant,Unit 1.With 990513 Ltr ML18016A9011999-04-12012 April 1999 Part 21 Rept Re Defect in Component of DSRV-16-4,Enterprise DG Sys.Caused by Potential Problem with Connecting Rod Assemblies Built Since 1986,that Have Been Converted to Use Prestressed Fasteners.Affected Rods Should Be Inspected ML18016A9111999-04-12012 April 1999 LER 99-005-00:on 990313,plant Exceeded ESFAS TS 3.3.2,Action 21.Caused by Inadequate Procedure Rev Preparation.Licensee Revised Applicable Maint Surveillance Test Procedure (MST-10072) to Identify TS Required Actions.With 990412 Ltr ML18016A8971999-04-0808 April 1999 LER 99-004-00:on 990312,unit Trip Was Noted.Caused by Degraded Condition of SG Water Level Flow Control Valve. Replaced Positioners on All Three FW Regulating Valves.With 990408 Ltr ML18016A8941999-04-0505 April 1999 Revised Pages 20-25 to App 4A of non-proprietary Version of Rev 3 to HI-971760 ML18016A9101999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Shearon Harris Nuclear Power Plant.With 990413 Ltr ML18016A8661999-03-31031 March 1999 Shnpp Operator Training Simulator,Simulator Certification Quadrennial Rept. ML18017A8931999-02-28028 February 1999 Risks & Alternative Options Associated with Spent Fuel Storage at Shearon Harris Nuclear Power Plant. ML18016A8551999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Shearon Harris Npp. with 990312 Ltr ML18016A8261999-02-22022 February 1999 LER 99-003-00:on 990123,noted That Plant Was Outside Design Basis Due to Isolation of Fire Protection Containment Sprinkler Sys.Caused by Human Error.Restored Containment Sprinkler Sys to Operable Status.With 990222 Ltr ML18016A8531999-02-18018 February 1999 Non-proprietary Rev 3 to HI-971760, Licensing Rept for Expanding Storage Capacity in Harris SFP 'C' & 'D'. ML18016A8111999-02-12012 February 1999 LER 99-002-00:on 990114,RT Due to Not Removing Temporary Device from Relay Following Calibration Was Noted.Caused by Human Error.Counseled Personnel Involved in Event.With 990212 Ltr ML18016A7971999-02-0505 February 1999 LER 99-001-00:on 990106,SF Pool Water Level Was Not Maintained Greater than 23 Feet Above Stored BWR Fuel Assemblies.Caused by Fasteners Bending Under Specific Circumstances.Increased Water Level.With 990205 Ltr ML18022B0631999-02-0404 February 1999 Rev 0 to Nuclear NDE Manual. with 28 Oversize Uncodable Drawings of Alternative Plan Scope & 4 Oversize Codable Drawings ML20202J1161999-02-0101 February 1999 SER Accepting Relief Requests Associated with Second 10-year Interval Inservice Testing Program ML18016A8041999-01-31031 January 1999 Monthly Operating Rept for Jan 1999 for Shearon Harris Nuclear Power Plant.With 990211 Ltr ML18016A7941999-01-29029 January 1999 LER 98-004-01:on 980313,identified Design Deficiency Re Potential Runout of Tdafwp.Caused by Inadequate Original AFW Sys Design.Operability Evaluation Was Completed on 980313 & Addl Engineering Analysis Was Performed by Vendor ML18016A7801998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Shearon Harris Npp. with 990113 Ltr ML18016A7671998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Shnpp,Unit 1.With 981215 Ltr ML18016A9731998-11-28028 November 1998 Changes,Tests & Experiments, for Harris Nuclear Plant.Rept Provides Brief Description of Changes to Facility & Summary & of SE for Each Item That Was Implemented Under 10CFR50.59 Between 970608-981128.With 990527 Ltr ML18016A8351998-11-28028 November 1998 ISI Summary 8th Refueling Outage for Shearon Harris Power Plant,Unit 1. ML18016A7411998-11-25025 November 1998 Rev 1 to Shnpp Cycle 9 Colr. ML18016A7211998-11-17017 November 1998 LER 98-007-00:on 981023,turbine Control Anomaly Caused Manual Rt.Caused by Failure to Incorporate Verbal Vendor Guidance in Operating Procedures.Addl Vendor Guidance Will Be Verified & Added to Procedures.With 981117 Ltr ML18016A7071998-11-0303 November 1998 Rev 0 to Harris Unit 1 Cycle 9 Colr. ML18016A7201998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Shearon Harris Nuclear Power Plant.With 981113 Ltr ML20154F8701998-10-0606 October 1998 Safety Evaluation Authorizing Proposed Alternative to Requirements of OMa-1988,Part 10,Section 4.2.2.3 for 21 Category a Reactor Coolant Sys Pressure Isolation Valves ML18016A6201998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Harris Nuclear Power Plant.With 981012 Ltr ML18016A5971998-09-21021 September 1998 Rev 1 to Harris Unit 1 Cycle 8 Colr. ML18016A5881998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Shnpp,Unit 1.With 980914 Ltr ML18016A5071998-07-31031 July 1998 Monthly Operating Rept for Jul 1998 for Shearon Harris Nuclear Plant.W/980811 Ltr ML18016A9431998-07-0707 July 1998 Rev 1 to QAP Manual. ML18016A4841998-07-0707 July 1998 LER 97-002-01:on 970207,determined That Cold Weather Conditions Resulted in Mfiv Being Potentially Inoperable During Period 970117-20.Caused by Inadequate Design of HVAC Sys.Implemented Mods to Steam Tunnel HVAC Sys ML18016A9371998-06-30030 June 1998 Technical Rept on Matl Identification of Spent Fuel Piping Welds at Hnp. ML18016A4861998-06-30030 June 1998 Monthly Operating Rept for June 1998 for SHNPP.W/980715 Ltr ML18016A4701998-06-30030 June 1998 LER 97-021-03:on 980210,discovered That SFP Water Level Had Not Been Verified Greater than 23 Feet Above BWR Fuel Assemblies.Caused by Misinterpretation of TS Requirements. Will Submit TS Change Request to Revise TS 3.9.1.11 ML18016A4491998-06-0808 June 1998 LER 98-006-00:on 980508,failure to Perform Insp & Preventive Maint on MCCB as Required by TS Was Noted.Caused by Inadequate Sps.Tested 9 Pressurizer Heater Bank Breakers by Cycling each.W/980608 Ltr ML18016A4521998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Shearon Harris Nuclear Power Plant.W/980612 Ltr ML18016A7711998-05-26026 May 1998 Non-proprietary Rev 2 to HI-971760, Licensing Rept for Expanding Storage Capacity in Harris Spent Fuel Pools 'C' & 'D'. 1999-09-30
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ACCELERATF 9 DOCUMENT DISTB~~UTION SYSTEM REGULAT . 1NFORMATION DISTRIBUTIOh~~YSTEM (RIDS)
ACCESSION NBR:9311030349 DOC.DATE: 93/10/27 NOTARIZED: NO DOCKET I FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina 05000400 AUTH. NAME , AUTHOR AFFILIATION ROBINSON, Wi.R. Carolina Power & Light Co.
RECIP.NAME -
RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Special rept:on 930928,identified that 10 used incore detectors not accounted for. Most probable disposition is that detectors inadvertently mixed w/other LLW matl & D shipped to SEG in Apr 1993.Procedures FMP-108 & 108 revised.
DISTRIBUTION CODE: IE22D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.
/
NOTES:Application for permit renewal filed. 05000400 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL D PD2-1 LA 1 1 PD2-1 PD 1 1 LE,N 1 1 D INTERNAL: ACRS 2 2 AEOD/DOA 1 1 AEOD/DSP/TPAB 1 1 AEOD/ROAB/DSP 2 2 NRR/DE/EELB 1 1 NRR/DE/EMEB 1 1 NRR/DORS/OEAB 1 1 NRR/DRCH/HHFB 1 1 NRR/DRCH/HICB 1 1 NRR/DRCH/HOLB 1 1 NRR/DRIL/RPEB 1 1 NRR/DRSS/PRPB 2 2 RR/~D pSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 REO FILR 02 1 1 RES/DSIR/EIB 1 1 GN2 FILE 01 1 1 EXTERNAL: EG&G BRYCEpJ.H 2 2 L ST LOBBY WARD 1 1 NRC PDR 1 1 NSIC MURPHY,G.A 1 1 NSIC POORE,W. 1 1 NUDOCS FULL TXT 1 1 D
A NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP VS TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 504-2065) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED: LTTR 30 ENCL 30
Carolina Power 5 Light Company Harris Nuclear Plant P. O. Box 165 New Hill, NC 27562
'OCT 2'7 1995 Letter Number: HO-930195 U.S. Nuclear Regulatory Commission ATTN: NRC Document Control Desk Washington, DC 20555 SHEARON HARMS NUCLEAR POWER PLANT UNIT 1 DOCKET NO. 50-400 LICENSE NO. NPF-63 30 DAY WRITTEN FOLLOW-UP REPORT Gentlemen:
In accordance with Title 10, Parts 20 and 70 of the Code of Federal Regulations, the enclosed Written Follow-up Report is submitted. This report fulfills the requirement for a written follow-up report within thirty (30) days for missing Special Nuclear Material per 10CFR20.2201 and within thirty (30) days following a loss of Special Nuclear Material per 10CFR70.52. This report is in accordance with the format and content requirements set forth in the above parts as well as Title 10 Part 50.73.
Very truly yours, W. R. Robinson General Manager Harris Nuclear Plant MV:
Enclosure cc: Mr. S. D. Ebneter (NRC - RII)
Mr. N. B. Le (NRC - PM/NRR)
Mr. J. E. Tedrow (NRC - SHNPP) o oog,,-
931i030349 93i027 PDR ADOCK 05000400 S PDR
NRC FORM 366 APPROVED BY OHB NO. 3150-0104 (5-92) EXPIRES 5/31/95 EST I HATED BURDEN PER RESPONSE TO COMPLY WITH SPECEAL REPORT THIS INFORMATION COLLECTION REQUEST: 50.0 HRS.
FORWARD COMMENTS REGARDING BURDEN ESTIHATE TO THE INFORMATION AND RECORDS MANAGEMENT BRANCH (See reverse for required number of digits/characters for each block) (HNBB 77I4), U.S. NUCLEAR REGULATORY COMMISSION, I WASHINGTON, DC 20555-0001, AND TO THE PAPERWORK REDUCTION PROJECT (3150-0'l04), OFFICE OF MANAGEMENT AND BUDGET WASHINGTON DC 2D503.
FACILITY NAME (1) Shearon Harris Nuclear Plant-Unit ¹1 DOCKET NUMBER (2) PAGE (3)
. o5ooo/4oo 1 OF 3 TITLE (4) 30 Day Written Follow-up Report for the loss of ten (10) used Incore Detectors (S ecial Nuclear Material).
EVENT DATE (5) LER NUHBER (6) REPORT DATE 7) OTHER FACILITIES INVOLVED B SEOUENTIAL REVISION FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR NUHBER HUNGER HONTH DAY YEAR 05000 FACILITY NAME 9- 28 93 N/A 10 27 DOCKET NUMBER 05000 OPERATING THIS REPORT IS SUBHITTED PURSUANT TO THE REQUIREMENTS. OF 10 CFR 5: (Check one or mor e) (11)
HODE (9) 20.402<b) 20.405(c> 50.73(a>(2)(iv) 73.71(b)
POWER 20.405(a)(1)(i) 50.36(c) <1) 50.73(a)(2)(v) 73.71(c)
'IOO/
LEVEL (10) 20.405(a)(1)(ii ) 50.36(c)(2) 50.73(a)(2)(vii) OTHER 20.405(a)(1)(iii) 50.73(a)(2)(i) 50.73(a)(2)(viii)(A) (Specify in 20.405(a)(1)(iv) 50.73(a)(2)(ii) 50.73(a)(2)(viii)(B) Abstract below and in Text, 20.405(a)(1)(v) 50.73(a)(2)(iii) 50.73(a)(2)(x) NRC Form 366A)
LICENSEE CONTACT FOR THIS LER (12)
(Include Area Code)
NAME Michael Verrilli TELEPHONE NUMBER (919) 362-2303 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)
REPORTABLE REPORTABLE CAUSE SYSTEM COMPONENT MAHUFACTURER CAUSE SYSTEM COMPONENT MANUFACTURER TO NPRDS TO HPRDS SUPPLEHENTAL REPORT EXPECTED (14 EXPECTED MONTH DAY YEAR YES SUBHISSION (If yes, complete EXPECTED SUBHISSION DATE). X NO DATE (15)
ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) (16)
On September 28, 1993, during efforts to consolidate radioactive material for a future burial shipment, Health Physics personnel identified that used incore detectors were not accounted for in the designated ten'10) radioactive waste. storage areas. These detectors utilize a f3.ssion chamber containing enriched Uranium 235, which classifies them as Special Nuclear Material g(SNM) . The combined SNM we'ght contained in the missing detectors is approximately 0.03 grams. An extensive search was conducted over the=
next Sour days, including a trip to the contracted low-level waste processing fac3.lity, S.E.G. in Oak Ridge Tennessee, but the detectors were not found. On October 4, 1993, a meeting was conducted to ensure that all possible efforts to locate the detectors had been exhausted. A conclusion was reached that a loss of non-fuel Special Nuclear Material (SNM) had occurred. The root cause of this event was a lack of accountability on the part of the SNM custodian designee. This included performing a paperwork, vice physical six-month inventory, poor maintenance of SNM records and not roperly marking/segregating non-fuel SNM. There was also a lack of nowledge/train>.ng among various work groups on what non-fuel SNM means and it's importance. Corrective actions included assignment of a new SNM custodian designee, development of labeling for SNM to distinguish it from other radioact3.ve material, designation of separate locked storage areas for non-fuel SNM, development of access controls and clear posting for the non-fuel SNM storage areas, and revising the SNM inventory procedure.
Additional actions will: include a revise.on to the SNM accountability procedure and training for applicable personnel.
The most probable disposition scenario is that this material was inadvertently mixed with other low-level radwaste and was shipped to S.E.G.
in Oak Ridge Tennessee in April 1993.
NRC FORH 366A U.S. NUCLEAR REGULATORY COHHISSION APPROVED BY OHB NO. 3150-0104 (5-92) EXPIRES 5/31/95 ESTIHATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORHATION COLLECTION REOUEST: 50.0 HRS.
SPECIAL REPORT FORWARD COHHENTS REGARDING BURDEN ESTIHATE TO THE INFORHATION AND RECORDS HANAGEHENT BRANCH (HNBB 7714), U.S. NUCLEAR REGULATORY COHHISSION, WASHINGTON, DC 20555-0001, AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF HANAGEHENT AND BUDGET WASHINGTON DC 20503.
FACILITY NAHE (1) DOCKET NUHBER (2) LER NUHBER (6) PAGE (3)
Shearon Harris Nuclear Plant YEAR SEQUENTIAL REVISION Unit Nl 05000/400 2 OF 3 N/A TEXT (If more space is required. use additional copies of NRC Form 36Q) (17)
DESCRIPTION OF MATERIAL INVOLVED:
The Special Nuclear Material involved in this event is enriched Uranium 235 (and decay products), which is utilized in, the incore detector's fission chamber. The combined SNM weight of the ten missing detectors is approximately 0.03 grams.
DESCRIPTION OF CIRCUMSTANCES UNDER WHICH LOSS OCCURRED:
On September 28, 1993, during efforts to consolidate radioactive material for a future burial shipment, Health Physics personnel identified that ten (10) used incore detectors were not accounted for in the designated radioactive waste storage areas. These detectors utilize a fission chamber containing enriched Uranium 235, which classifies them as Special Nuclear Material (SNM). The combined SNM weight contained in the missing detectors is approximately 0.03 grams. An extensive search was conducted over the next four days, including a trip to the contracted low-level waste processing facility, S.E.G. in Oak Ridge Tennessee, but the detectors were not found. On October 4, 1993, a meeting was conducted to ensure that all possible efforts to locate the detectors had been exhausted. A conclusion was reached that a loss of non-fuel Special Nuclear Material (SNM) had occurred. The root cause of this event was a lack of accountability on the part of the SNM custodian designee. This included performing a paperwork vice physical six-month inventory, poor maintenance of SNM records and not properly marking/segregating non-fuel SNM. There was also a lack means of knowledge/training among various work groups on what non-fuel SNM and it's importance. Corrective actions included assignment of a new SNM custodian designee, development of labeling/tagging for SNM to distinguish it from other radioactive material, designation of separate locked storage areas for non-fuel SNM, development of access controls and clear posting for the non-fuel SNM storage areas, and revising the SNM inventory procedure. Additional actions will include a revision to the SNM accountability procedure and training for applicable personnel.
DISPOSITION OF MATERIAL:
Based on a review of the above listed circumstances and sequence of events, the most probable disposition of the ten incore detectors is that material while in it was storage inadvertently mixed with other low-level radwaste in WPB room 144A, then shipped to SEG in April of 1993 for processing prior to burial.
RADIATION EXPOSURES TO INDIVIDUALS IN UNRESTRICTED AREAS:
Based on the fact that the incore detectors had low radiation levels and that they were handled as low-level radwaste, no exposures to personnel in unrestricted areas occurred as a result of this event.
NRC FORH 366A (5-92))
NRC FORM 366A REGULATORY COMMISSION APPROVEO BY OMB NO. 3150 ~ 0104 (5.92) EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS ~
FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO SPECIAL REPORT tHE INFORHATION AND RECORDS HANAGEHENT BRANCH (HNBB 7714), U.S. NUCLEAR REGULATORY COMHISSION,
'WASHINGTON, DC 20555-0001, AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF MANAGEMENT AND BUDGET WASHINGTON DC 20503.
FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3)
Shearon Harris Nuclear Plant YEAR SEQUENTIAL REVISION Unit g1 osooo/4oo N/A 3 OF 3 TEXT (If more space is required, use additional copies of NRC Form 36Q) (17)
ACTIONS TAKEN or will be taken TO RECOVER THE MATERIAL:
An extensive search was conducted in all plant areas that the used incore detectors could reasonably have been placed. A trip was also made to SEG's facility in Oak Ridge Tennessee to search the remaining radwaste material received from HNP that had not been incinerated. Based on the conclusion that the material was processed by SEG, no further actions will be taken to locate the detectors.
PROCEDURES OR MEASURES WHICH HAVE BEEN or will be ADOPTED TO PREVENT RECURRENCE:
- 1. A new Special Nuclear Material Custodian Designee was assigned.
- 2. Labeling/tagging for non-fuel SNM has been created to ensure that it will be distinguished from other radioactive materials.
- 3. Separate locked storage areas for non-fuel SNM have been designated.
- 4. Access controls and clear postings for the non-fuel SNM storage areas have been developed.
- 5. FMP-108 (governing procedure for conducting SNM inventory) has been.
revised to specifically define SNM inventory requirements.
- 6. Revise FMP-109 (SNM Accountability Plan/Procedure) to clearly delineate HP/Maint/Stores/Deconners responsibilities regarding SNM.
This shall include the requirement for a "pre-job" briefing prior to SNM transfer activities and specific guidance on the completion of the transfer form.
- 7. The review and approval process for SNM procedures (FMP-108 & FMP-109) has been changed to include all affected organizations.
- 8. Provide training on the above listed actions for applicable personnel.
- 9. Perform a 'follow-up review to assess the effectiveness of above corrective actions.
This condition is being reported per 10CFR20.2201(a)(ii) and 10CFR70.52(b) to satisfy the requirement for a written follow-up report within 30 days.
NRC FORM 366A (5-92)