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Category:ABNORMAL OCCURRENCE REPORTS (SEE ALSO LER & RO)
MONTHYEARML20084S9121977-03-25025 March 1977 Telecopy Ao:On 770324,containmet Spray Pump a Out of Svc During Training Startup,Violating Tech Spec ML20084S9091976-05-31031 May 1976 Ao:On 770527,HPCI Pressure Switches E41-PSH-NO12 A,B,C & D Exceeded Tech Spec Calibr Limits.Switches Immediately Recalibr ML20086D4211976-02-0909 February 1976 AO 50-261/76-3:on 760128,high Level Alarm Received on Safety Injection Accumulator B.Caused by Check Valve 875 Leaking Resulting in Dilution.Accumulator Partially Drained & Refilled ML20086D4421976-02-0202 February 1976 AO 50-261/76-2:on 760121 & 22,failure of One & Delayed Operation of Two Reactor Trip Relays Occurred.Caused by Open Coil Winding.Three Defective Relays Replaced ML20086D4271976-01-29029 January 1976 Telecopy Ao:On 760128,sample of Safety Injection Accumulator B Indicated Boron Concentration of 1,939 Ppm,Below Tech Specs.Accumulator Partially Drained,Refilled & Verified ML20086D4391976-01-22022 January 1976 Ao:On 760124 & 22,discovered That Reactor Trip Relay RT3 in Reactor Protection Logic Train a Operating Erratically. Further Investigation Revealed That Relays RT-4 & RT-8 on Logic Train B Defective.Relays Replaced ML20086D4471976-01-13013 January 1976 AO 50-261/76-1:on 760102,failure of Boric Acid Transfer Pump Resulted in Failure of One ESF Component That Caused or Threatened to Render Sys Incapable of Functioning.Caused by Damaged Rotor ML20086F5211976-01-0202 January 1976 Ao:On 760102,boric Acid Pump B Stopped Running.Caused by Defective Stator & Damaged Rear Bearing.Investigation Continuing NG-75-2222, AO 50-261/75-20:on 751210,channel 950 of Containment Pressure Protection Found Inoperable.Caused by Open Output Fuse in Comparator PC-950.Fuse Replaced1975-12-23023 December 1975 AO 50-261/75-20:on 751210,channel 950 of Containment Pressure Protection Found Inoperable.Caused by Open Output Fuse in Comparator PC-950.Fuse Replaced NG-75-2210, AO 50-261/75-19:on 751208,boron Concentration Found Below Limits in Safety Injection Accumulator B.Cause Not Stated. Accumulator Partially Drained & Refilled from Refueling Water Storage Tank1975-12-22022 December 1975 AO 50-261/75-19:on 751208,boron Concentration Found Below Limits in Safety Injection Accumulator B.Cause Not Stated. Accumulator Partially Drained & Refilled from Refueling Water Storage Tank ML20086F5161975-12-0808 December 1975 Ao:On 751208,boron Sample from Safety Injection Accumulator B Indicated 1,915 ppm,35 Ppm Below Tech Specs.Cause Unknown. Accumulator Partially Drained & Refilled from Refueling Water Storage Tank NG-75-2017, AO 50-261/75-18:on 751102,auxiliary Feedwater Pump a Failed to Start Following Safety Injection Signal.Caused by Tarnished Contacts.Contacts within Local/Remote Switch Cleaned.Further Investigation Underway1975-11-13013 November 1975 AO 50-261/75-18:on 751102,auxiliary Feedwater Pump a Failed to Start Following Safety Injection Signal.Caused by Tarnished Contacts.Contacts within Local/Remote Switch Cleaned.Further Investigation Underway NG-75-2010, AO 50-261/75-17:on 751101,both Containment Personnel Air Lock Doors Opened Simultaneously W/Rcs Temp Above 200 F, Violating Tech Spec 3.6.1.a.Caused by Broken Rod,Bearing & Cam Follower on Outer Door Mechanism1975-11-12012 November 1975 AO 50-261/75-17:on 751101,both Containment Personnel Air Lock Doors Opened Simultaneously W/Rcs Temp Above 200 F, Violating Tech Spec 3.6.1.a.Caused by Broken Rod,Bearing & Cam Follower on Outer Door Mechanism NG-75-2001, AO 50-261/75-16:on 751028,svc Water Booster Pump B Failed to Start.Caused by Actuation of Pump Suction Pressure Switches Provided to Protect Pumps from Low Npsh.Containment Recirculation Fans Stopped to Prevent Overheating Motors1975-11-11011 November 1975 AO 50-261/75-16:on 751028,svc Water Booster Pump B Failed to Start.Caused by Actuation of Pump Suction Pressure Switches Provided to Protect Pumps from Low Npsh.Containment Recirculation Fans Stopped to Prevent Overheating Motors ML20086F5291975-11-0404 November 1975 Ao:On 751102,motor Driven Auxiliary Feedwater Pump a Failed to Start.Remote Electrical Contacts Cleaned ML20086F5401975-11-0303 November 1975 Ao:On 751101,containment Integrity Broken for Approx 10 Minutes Due to Simultaneous Opening of Both Personnel Air Lock Doors ML20086F5491975-10-29029 October 1975 Ao:On 751028,sequence of Switch Operations Resulted in Breakers for Both Svc Water Booster Pumps a & B Tripping on Overload NG-75-1575, AO 50-261/75-15:on 750921,more than One Inoperable Rod Present W/Reactor at Power as Result of Rod Control Urgent Failure.Caused by Defective Fuse in Ac Power Supply to Rod Control Cabinet 1AC.Fuse Replaced1975-10-0101 October 1975 AO 50-261/75-15:on 750921,more than One Inoperable Rod Present W/Reactor at Power as Result of Rod Control Urgent Failure.Caused by Defective Fuse in Ac Power Supply to Rod Control Cabinet 1AC.Fuse Replaced ML20086F5611975-09-22022 September 1975 Ao:On 750921,urgent Failure Alarm Received.Caused by Phase Failure in Cabinet 1AC Which Rendered 12 Rods Inoperable. Reactor Manually Tripped NG-75-1212, Revised AO 50-261/75-11:on 750527,RCS Oxygen Concentration Found to Be 0.16 Ppm,Exceeding Limit.Caused by Inattention to Hydrogen Concentration & Dilution of RCS to Hot Shutdown Boron Concentration.Vol Control Tank Vented1975-08-0404 August 1975 Revised AO 50-261/75-11:on 750527,RCS Oxygen Concentration Found to Be 0.16 Ppm,Exceeding Limit.Caused by Inattention to Hydrogen Concentration & Dilution of RCS to Hot Shutdown Boron Concentration.Vol Control Tank Vented NG-75-1158, AO 50-261/75-14:on 750715,valve V2-14B Steam Driven Auxiliary Feedwater Pump Discharge to Steam Generator B Failed to Open.Caused by Belleville Spring Being Filled W/Grease.Belleville Spring Packs & Shafts to Be Inspected1975-07-25025 July 1975 AO 50-261/75-14:on 750715,valve V2-14B Steam Driven Auxiliary Feedwater Pump Discharge to Steam Generator B Failed to Open.Caused by Belleville Spring Being Filled W/Grease.Belleville Spring Packs & Shafts to Be Inspected ML20086F5961975-07-16016 July 1975 Telecopy Ao:On 750715,steam Drive Auxiliary Feedwater Pump Discharge Valve V2-14B to Steam Generator B Failed to Open Electrically ML20086F6151975-07-14014 July 1975 Ao:On 750711,control Rod L-5 Dropped,Causing Load Runback to Approx 70% Power.Caused by Defective Stationary Gripper Coil NG-75-1089, Revised AO 50-261/75-8:on 750429,RHR Suction Valve RHR-862A Failed.Caused by Torque Switch on Motor Operator Being Out of Adjustment,Causing Valve to Be Wedged Onto Seat & Preventing Motor from Opening Valve1975-07-11011 July 1975 Revised AO 50-261/75-8:on 750429,RHR Suction Valve RHR-862A Failed.Caused by Torque Switch on Motor Operator Being Out of Adjustment,Causing Valve to Be Wedged Onto Seat & Preventing Motor from Opening Valve NG-75-1044, AO 50-261/75-12:on 750625,boric Acid Transfer Pump a Failed. Caused by Pump Shaft Being Broken at Keyway.Pump Rebuilt & Reinstalled.New Pump Model GVH-10K Will Be Installed Upon Receipt1975-07-10010 July 1975 AO 50-261/75-12:on 750625,boric Acid Transfer Pump a Failed. Caused by Pump Shaft Being Broken at Keyway.Pump Rebuilt & Reinstalled.New Pump Model GVH-10K Will Be Installed Upon Receipt ML20086F6081975-06-26026 June 1975 Telecopy Ao:On 750625,boric Acid Transfer Pump a Noted Off. Caused by Pump Shaft Being Broken at Keyway.Also on 750625, Employee Received Whole Body Dose of 3,080 Mrem for Quarter Ending 750630 ML20086F6741975-06-12012 June 1975 Revised AO 50-261/75-9:on 750501,reactor Coolant Pump Seal Failed,Resulting in Discharge of Reactor Coolant Fluid to Containment Floor.Caused by Pump Running W/Seal Leaking. Seals,Shaft,Impeller & Hearings Replaced ML20086F6201975-06-0606 June 1975 AO 50-261/75-11:on 750527,RCS Oxygen Concentration Noted to Be 0.16 Ppm,Exceeding Limit.Caused by Mixture of Hydrogen & Nitrogen in Vol Control Tank,Limiting Hydrogen to Rcs.Vol Control Tank Vented ML20086F6271975-06-0202 June 1975 AO 50-261/75-10:on 750521,boric Acid Transfer Pump B Failed.Caused by Shaft Being Broken at Keyway & Worn Pump Bearing.Pump Rebuilt ML20086F6231975-05-27027 May 1975 Ao:On 750527,RCS Sample Indicated 0.16 Ppm Oxygen,Exceeding Tech Specs.No Cause Stated.Concentration Reduced ML20086F6301975-05-21021 May 1975 Ao:On 750521,boric Acid Pump B Stopped.Caused by Broken Shaft in Keyway Area ML20086F5791975-05-12012 May 1975 AO 50-261/75-9:on 750501,reactor Coolant Pump Seal Failed, Resulting in Discharge of Reactor Coolant Fluid to Containment Floor.New Seal & Associated Parts Being Installed.Parts Shall Be Certified ML20086F6441975-05-0909 May 1975 AO 50-261/75-8:on 750429,RHR Pump Suction Valve RHR-862A Failed.Caused by Torque Switch on SMB-O Motor Operator Being Out of Adjustment.Torque Switch Adjusted.On 750430,complete Insp of Operator Found Excess Grease.Grease Removed ML20086F6911975-05-0202 May 1975 Telecopy Ao:On 750501,seal 1 on Reactor Coolant Pump C Failed,Producing Leak to Containment Floor.Seal 2 Failed on 750502.Cooldown Initiated.Rcs Depressurized & Drained to Below Pump Seals ML20086F6471975-04-29029 April 1975 Ao:On 750429,valve RHR-862A Failed to Open from RTGB When RHR Sys Being Aligned.Cause Under Investigation.Valve Opened Locally Using Manual Operator & All Flow Paths Restored ML20086F6981975-04-10010 April 1975 AO 50-261/75-7:on 750331,diesel B Tripped Due to Low Lube Oil Pressure.Caused by Lube Oil Filter High Differential Pressure Resulting from Dirty Filters.Lube Oil Filters Replaced ML20086F6961975-04-0101 April 1975 Telecopy Ao:On 750331,emergency Diesel B Tripped.Caused by Low Lube Oil Pressure.Filters Changed & Unit Returned to Svc ML20086F6991975-03-27027 March 1975 AO 50-261/75-6:on 750314,contractor Personnel Exposed to Radiation in Excess of Limits.Caused by Exceeding Stay Time in Localized Field of High radiation.Chem-Nuclear,Inc & Util Investigating Use of Addl Shielding ML20086F7001975-03-0707 March 1975 AO 50-261/75-5:on 750225 & 26,boric Acid Transfer Pump B Failed.Cause Not Identified.Pump Replaced ML20086F7011975-02-14014 February 1975 AO 50-261/75-4:on 750206,reactor Protection Overpower Channel Set I Failed to Generate Rod Stop Signal for Simulated Overpower Condition.Caused by Failure of Comparator Circuit in Dual Circuit Signal Comparator ML20086F7051975-02-0707 February 1975 Ao:On 750206,signal Comparator TO-412B Failed to Operate. Portion of Comparator Which Generates Rod Stop & Turbine Runback Signal Failed While Overpower Reactor Trip Signal Still Generated ML20086F7111975-02-0606 February 1975 AO 50-261/75-3:on 750126,component Cooling Water Pump C Tripped Due to Overcurrent.Caused by Backleakage Through Pump Discharge Side Check Valve Due to Debris.Leaking Mechanical Seal & Status Light Module Replaced ML20086F7201975-01-30030 January 1975 AO 50-261/75-2:on 750120,pressurizer Level Channel II Failed to Generate Reactor Trip Signal or Safety Injection Signal Upon Insertion of Simulated High & Low Levels.Caused by Malfunctioning Filter Capacitor C.3 ML20086F7281975-01-27027 January 1975 AO 50-261/75-1:on 750114,boric Acid Transfer Pump a Failed. Caused by Failed Shaft in Vicinity of Impeller Keyway.Pump Replaced.Replacement Pump Model GVH-10K on Order ML20086F7141975-01-27027 January 1975 Telecopy Ao:On 750126,component Cooling Pump C Failed to Start from Rtgb.Cause Under Investigation.Pump Breaker Racked Out,Inspected & Racked in ML20086F7241975-01-20020 January 1975 Telecopy Ao:On 750120,level Comparator LC-460A Failed to Operate.Cause Not Stated ML20086F7351975-01-15015 January 1975 Ao:On 750114,boric Acid Transfer Pump a Noted to Be in Off Indication at Rtgb.Caused by Broken Shaft ML20085D0621973-07-17017 July 1973 Ao:On 730628-0705 & 09-10,changes Performed on Safeguards Equipment W/O Demonstrating Operability of Redundant Equipment Before Removal.Safety Injection Pumps B & C Tripped & Circuit Breaker Tripped,Respectively ML20085D0661973-07-11011 July 1973 Telecopy Ao:On 730709,two Safety Injection Pumps Experienced Overcurrent Trips.Caused by New Overcurrent Trip Devices Tripping at Lower than Desired Value.Trip Setting Increased ML20085D0771973-07-10010 July 1973 Telecopy Ao:On 730710,circuit Breaker for Containment Cooler Fan 2 Tripped.Caused by Overcurrent Due to Misalignment of Calibr Spring in Overcurrent Trip Device.Spring Realigned 1977-03-25
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217A1691999-09-22022 September 1999 Part 21 Rept Re Engine Sys,Inc Controllers,Manufactured Between Dec 1997 & May 1999,that May Have Questionable Soldering Workmanship.Caused by Inadequate Personnel Training.Sent Rept to All Nuclear Customers RA-97-0258, LER 97-S12-00:on 971119,discovered Uncompensated Security Zone.Caused by Inattention to Detail by Members of Security Force.Provided Event Info to Security Shift Personnel & Changed Practice Re Zone Review1997-12-19019 December 1997 LER 97-S12-00:on 971119,discovered Uncompensated Security Zone.Caused by Inattention to Detail by Members of Security Force.Provided Event Info to Security Shift Personnel & Changed Practice Re Zone Review ML20211M6491997-10-0808 October 1997 Addenda 1 to Part 21 Rept Re Weldments on Opposed Piston & Coltec-Pielstick Emergency stand-by Diesel gen-set lube-oil & Jacket Water Piping Sys.Revised List of Potentially Affected Utils to Include Asterisked Utils,Submitted ML20217Q2751997-06-30030 June 1997 CP&L Fitness for Duty Program Performance Data for Period 970101-0630 ML14183A6951995-09-18018 September 1995 Safety Evaluation Approving Relocation of Technical Support Ctr ML20059H7721994-01-17017 January 1994 Part 21 Rept Re Virginia Power Notifying Fairbands Morse Via Failure Analysis Rept NESML-Q-058 of Defective Air Start Distributor cam,16104412 ML17352A8691993-05-31031 May 1993 Technical Rept, Assessment of Aging Degradation of Civil/ Structural Features at Selected Operating Nuclear Power Plants. ML20125C7161992-12-0707 December 1992 Part 21 Rept Re Possibility for Malfunction of Declutching Mechanisms in SMB/SB-000 & SMB/SB/SBD-00 Actuators. Malfunction Only Occurs During Seismic Event.Balanced Levers May Be Purchased from Vendor.List of Affected Utils Encl ML20127P5861992-11-23023 November 1992 Followup to 921005 Part 21 Rept Re Potential Defect in SB/SBD-1 Housing Cover Screws.Procedure Re Replacement of SBD-1 Spring Cover Bolts Encl.All Fasteners Should Be Loosened & Removed.List of Affected Utils Encl ML20118B4391992-09-11011 September 1992 Part 21 Rept Re Degradation in Abb Type 27N Undervoltage Relays Used in Electrical Switchgear.Recommends That Users Review Applications Requiring Exposures Greater than 1E03 Rads TID W/Time Delay Function Option ML20079H1571991-09-30030 September 1991 Nonproprietary Evaluation of Revised Transfer to Cold Leg Recirculation Procedure,Hb Robinson Unit 2 ML20086T2951991-06-14014 June 1991 Rev 1 to EQ Documentation Package Eqdp 36.0, Boston Insulated Wire Cable ML20086T2861991-03-0808 March 1991 Rev 1 to EQ Documentation Package Eqdp 11.1, Dekoron Instrumentation Cables ML20086T2561991-03-0808 March 1991 Rev 1 to EQ Documentation Package 10.0, Continental Shielded Instrument Cable ML20065K6961990-10-31031 October 1990 Mechanical Licensing Rept for Hb Robinson High Thermal Performance Fuel Assemblies ML20065K6971990-10-31031 October 1990 Thermal Hydraulic Compatibility Analysis of Anf High Thermal Performance Fuel for Hb Robinson,Unit 2 ML20005G6831990-01-0505 January 1990 Part 21 Rept Re Installation Instructions for Grommet Use Range for Patel Conduit Seal P/N 841206.Conduit Seals in Environ Qualification Applications Inspected for Proper Wire Use Range & Grommets Replaced ML20247E0701989-07-20020 July 1989 Info Rept:On 890717-0804,fire Penetration Seals Will Be Removed from Svc to Allow Access for Ventilation Sys Mod. Addl Fire Barrier Penetrations Will Be Made in Wall Between RHR Pump Pit & Fuel Handling Bldg,Per Tech Spec 3.14.7.2 ML20246E9111989-03-31031 March 1989 PDC-3:Advanced Nuclear Fuels Corp Power Distribution Control for PWRs & Application of PDC-3 to Hb Robinson Unit 2 ML20245H0821989-01-25025 January 1989 Criticality Safety Analysis of Hb Robinson Spent Fuel Pool W/4.2% Nominal Enrichment Fuel Assemblies ML20205T0551988-10-31031 October 1988 Responses to NRC Questions on RTD Bypass Elimination Licensing Rept ML20147E2371988-02-29029 February 1988 1987 Annual Rept - Primary Coolant Iodine Spikes ML20147B1971987-12-31031 December 1987 1987 Annual Rept - Primary Safety & Relief Valve Challenges ML20236K7731987-10-31031 October 1987 Monthly Operating Rept for Oct 1987 ML20235W3781987-09-30030 September 1987 Monthly Operating Rept for Sept 1987 ML20238E2741987-08-31031 August 1987 Monthly Operating Rept for Aug 1987 ML20235H3151987-06-30030 June 1987 Monthly Operating Rept for June 1987 ML17261A5301987-06-18018 June 1987 Part 21 Rept Re Potential Util Failure to Comply W/Component Containment Isolation Licensing Commitment If Proposed Mods to Component Cooling Water Sys Instituted.Utils Advised to Evaluate Containment Isolation Sys ML20214W3241987-05-31031 May 1987 Monthly Operating Rept for May 1987 ML20214R5101987-04-30030 April 1987 Rev 1 to Monthly Operating Rept for Apr 1987,correcting Operation Statistics & Shutdown Experience Due to Mathematical Errors ML20215L4941987-04-30030 April 1987 Monthly Operating Rept for Apr 1987 ML20206F3561987-03-31031 March 1987 Monthly Operating Rept for Mar 1987 ML20210B4141987-03-31031 March 1987 Revised Monthly Operating Rept for Mar 1987 ML20205F6021987-03-23023 March 1987 Special Rept:On 870302,noble Gas Effluent Monitor for Main Steam Line B Declared Inoperable & Svc Not Returned Until 870312.Caused by Defective Detector.Detector Replaced.High Voltage for Detector Adjusted & Sys Operation Checked ML20212P3101987-02-28028 February 1987 Monthly Operating Rept for Feb 1987 ML20214Q7891987-01-31031 January 1987 Cycle 12,SAR ML20210R6341987-01-31031 January 1987 Monthly Operating Rept for Jan 1987 ML20207M2451986-12-31031 December 1986 Monthly Operating Rept for Dec 1986 L-18-120, Rev 0 to Supplemental Info in Support of Conservatisms in Criticality Analysis Performed for Hb Robinson Isfsi1986-12-18018 December 1986 Rev 0 to Supplemental Info in Support of Conservatisms in Criticality Analysis Performed for Hb Robinson Isfsi ML20215C7911986-11-30030 November 1986 Monthly Operating Rept for Nov 1986 ML20213F3121986-10-31031 October 1986 Monthly Operating Rept for Oct 1986 ML20215G1081986-09-30030 September 1986 Monthly Operating Rept for Sept 1986 ML20215F0361986-09-29029 September 1986 Special Rept:On 860902,during Cold Shutdown,Pressurizer PORV Lifted Twice to Prevent Overpressurization.Caused by Inadvertent Action by Unit Operators.Operations Personnel Counseled Re Importance of Breaker Position Indicators ML20211C0641986-09-0909 September 1986 Rev 0 to Final Rept Criticality Safety Analysis Hb Robinson Spent Fuel Storage Racks (Unpoisoned,Low Density) W/4.2% Enriched 15x15 Fuel Assemblies ML20211C0491986-09-0202 September 1986 Rev 0 to Final Rept Criticality Safety Analysis Hb Robinson New Fuel Storage Vault W/4.2% Enriched 15x15 Fuel Assemblies ML20212F5321986-07-31031 July 1986 Monthly Operating Rept for Jul 1986 ML20203D0221986-07-14014 July 1986 Part 21 Rept Re Air Monitoring Sys Probes Exhibiting Blue Tip Rather than Normal White Tip & Insensitive to Chlorine. Caused by Improper Handling/Storage.Advisory Bulletin Encl. Item Not Reportable Per Part 21 ML20202G3371986-06-30030 June 1986 Monthly Operating Rept for June 1986 ML20211B5601986-05-31031 May 1986 Monthly Operating Rept for May 1986 ML20197D2651986-04-30030 April 1986 Monthly Operating Rept for Apr 1986 1999-09-22
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Carolina Power & Light Company Deceraber 22, 1975 File: NG-3513 (R) Serial: NG-75-2210 N I Mr. Norman C. Moseley, Director U. S. Nuclear Regulatory Commission
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Regien II, Suite S18 230 Peachtree Street, N. W.
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Atlanta, Georgia 30393 g.
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Dear Mr. Moseley:
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H. B. ROBINSON UNIT NO. 2 ' c.5, h
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DOCKET 50-261 'T BORON CONCENTRATION BELok LIMITS IN "B" SAFETY INJECTION ACCUMULATOR In accordance with 6.6.2.a of the Technical Specifications for
- H. B. Robinson Unit No. 2, the attached Abnormal Occurrence Report is sub-
.i mitted for your information. This report fulfills the requirement for a 4 written report within ten days of an Abnormal Occurrence and is in accor-dance with the format set forth in Regulatory Guideline 1.16, Revision 1.
Yours very truly,
\
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E. E. Utley l Vice-President Bulk Power Supply CSB:me Attachment cc: Messrs. D. C. Knuth W. G. Mcdonald l
1 B401030360 751222
, PDR ADOCK 05000261 S PDR 14326
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ABNORMAL OCCliRRENCE P2 PORT Robinson Fils No. 2-0-4-a-1
- 1. Renort No. 50-261/75-19 2a. Renort Date December 11, 1975 .
2b. Occurrence Date December 8, 1975 3 Facility H. B. Robinson Unit No. 2 i Hartsville, South Carolina 29550 4 Identification of Occurrence l Baron Concentration was found to be below limits in "B" Safety Injection Accumulator. This constitutes a violation of Technical Specificetion 3.3.1.1.c which is a limiting condition for operation as defined in Technical Specification 1.8.b. '
5 Conditions Prier to Occurrence The reactor was critical after refueling shutdown with low power physics tests in progress.
- 6. Descriution of Occurrence At 0155 hours0.00179 days <br />0.0431 hours <br />2.562831e-4 weeks <br />5.89775e-5 months <br />, December 8,1975, "B" Accumulator was sampled and boron concentration found to be 1915 ppm. A Radiation Control and Teat Te hnician notified the control room of the sample. However, the Shif t Foreman was busy in the plant area cnd the message was relayed to the Control Operator via a startup physics test engineer.
The significance of the sample was not recognized by these personnel and no action was taken. The Shift Foreman was not advised regard-ing the information.
At 0600 hours0.00694 days <br />0.167 hours <br />9.920635e-4 weeks <br />2.283e-4 months <br /> a subsequent sample was ana3yzed to be 1917. ppm baron.
The Control Roo= vas called and the Shift Foreman was notified. He then consulted the Operating Supervisor by telephone and' they con-cluded that the Technical Specifications provided an exception.for the boron requirement since the plant was at low power with physics tests in progress. Specifically, paragraph 3.3.1.1 of the Technical Specifications states, "The reactor shall not be made critical except for low temperature physics tests, unless the following-
- conditions are met:....". The interpretation was that the phrase-
" low temperature physics test" applied to low fuel temperatures which exist at low pozer physics testing and thus the exception was applicable.
Another-accumulator sample was taken at 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br /> and found to be 1916 ppm boron concentration. Action was then taken to partially drain and refill "B" accumulator.
p p d d i Draining of "B" accmulator from 70% level and 644 psig to 0%
level (0-100% level span covers only a small portion of total accumulator volume) and 370 psig was completed at 1018 hours0.0118 days <br />0.283 hours <br />0.00168 weeks <br />3.87349e-4 months <br />. It was then refilled from the refueling water storage tank using the safety injecticn punps. The level at 1032 was 72% at 640 psig.
At 1040 hours0.012 days <br />0.289 hours <br />0.00172 weeks <br />3.9572e-4 months <br /> "B" accumulator was sampled and found to have a boron concentration of 1991 ppm. The accumulator was then declared operable at 1055 hours0.0122 days <br />0.293 hours <br />0.00174 weeks <br />4.014275e-4 months <br />. The plant was maintained at low power levels for physics testing during these evolutions based on the previously stated Technical Specification interpretation.
- 7. Desicnaticn of Annarent Ceuse of Occurrence The Safety Injection Accumulators are required to be sampled once a month with a maximum of 45 days between samples. The last previous sample vas obtained November 1, 1975, and found to be 2383 ppm boron.
This concentration was used for heatup and initial criticality fellowing the November refueling outage. At some' time between November 1,1975 and December 8,1975, during the refueling outage, apparently enough dilution occurred to reduce the concentration below limits. An exhaustive investigation was conducted, but, due to variable plant conditions prevailing during the outage, lack of sample data for the period in question, and numerous tests conducted during the outage it vac not possible to ascertain the exact time and source of apparent dilution. This points out a need for baron analyses following outsges to assure that the accumulator cencentra-tions are adequately defined. The dilution was apparently caused by come outage activity. Regardless of the cause, if an analysis is conducted prior to heatup the problem can be identified and corrected in a timely manner. No further investigation is planned to establish the exact cause nor is it felt auch investigation would be conclusive.
The cause of the delay in proper notifier. tion of the concentration and the realization of the analysis significance is of concern. Upon receiving notification from the laboratory, Control Operators checked their accumulator levels and pressures. However, due to their activity and the fact that the Shift Foreman was out of the Control Room at the time, they failed to notify him concerning the concentration until the second sample was analyzed. This'was an oversight on their part.
Once the Shift Foreman became aware of the problem he acted appropriately in contacting the Operating Supervisor. The decision that the problem did not constitute an abnormal occurrence was then made in good faith.
A follow-up session of the Plant Nuclear Safety Ccmmittee resulted in an indecisive discussion as to reportability of tnis incident and whether a violation had actually occurred. Close scrutiqr of the Technical Specifications revealed that the low temperature referred to regarding physics testing var defined as low reactor coolant 1
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temperature. Therefore the conclusion that lcw power and low temperature physics testing were the same did not appear valid.
The applicability of Technical Specification sections was then questioned. There are sections governing hot shutdown, criticality, and power operation (greater than 2% of rated power) but none that specifically address low power physics testing below 2%
power. This further confused the interpretation and no headway was made in reaching a PNSC consensus. Therefore, with the committee still in cession Mr. Marvin Sincule of the NRC was called at 1455 hourc and requested to resolve the situation with a ruling. He returned the call at 1530 hours0.0177 days <br />0.425 hours <br />0.00253 weeks <br />5.82165e-4 months <br /> with the decision that a violation had occurred and should be reported as such.
- 8. Analysic of Occurrence There cere no personnel injuries, nor was there a release cf radio-active materials involved in this occurrence.
Initial criticality, after the 37 day refueling outage, was achieved at 1053 hours0.0122 days <br />0.293 hours <br />0.00174 weeks <br />4.006665e-4 months <br /> December 7, 1975, and a trip occurred at 1059 hours0.0123 days <br />0.294 hours <br />0.00175 weeks <br />4.029495e-4 months <br />.
The reactor was brought back critical at 1618 hours0.0187 days <br />0.449 hours <br />0.00268 weeks <br />6.15649e-4 months <br /> for initiation of low power physics test. At the time "B" accumulator boron concentration var determined to be out of limits the reactor had been critical, at essentially hot zero power, for nine hours and 42 minutes. No significant decay heat was produced; therefore, an emergency cooldown from this condition would be essentially the same as from hot shutdown.
- 9. Corrective Action The accumulator was partially drained and refilled from the refueling water storage tank. Boron concentration was then determined to be 1991 ppm. This completed immediate action.
To rectify the communication problem and failure to premptly recognize that a potential safety hazard existed, Operations have been instructed to notify the Shift Foreman immediately of any condition of this significance.
To assure that accumulator concentrations are positively identified following cold plant conditions which might affect their contents,
, a change has been incorporated into GP-1A checklist (Overall Plant j Operating Procedure) to require sampling and logging of accumulator boron concentration prior to heatup. This action should prevent l reoccurrence of the specific concentration violation.
i 10. Failure Data l There is nc previous failure data regarding boron concentration j specification violations concerning accumulators.
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