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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARL-99-078, Special Rept:On 990326,seismic Monitoring Instruments Were Declared Inoperable.Caused by Resolution of Potential TS Compliance Issue & Work Scheduling Issue.Instrumentation Was Returned to Svc Following Calibr & Declared Operable1999-05-0303 May 1999 Special Rept:On 990326,seismic Monitoring Instruments Were Declared Inoperable.Caused by Resolution of Potential TS Compliance Issue & Work Scheduling Issue.Instrumentation Was Returned to Svc Following Calibr & Declared Operable L-99-054, Special Rept:On 990320,meteorological Tower Wind Speed Sensors Were Declared Inoperable.Caused by Calibration Completed by Vendor Did Not Adequately Cover Full Operating Range of Sensors.Removed Sensors & Sent Offsite1999-04-0505 April 1999 Special Rept:On 990320,meteorological Tower Wind Speed Sensors Were Declared Inoperable.Caused by Calibration Completed by Vendor Did Not Adequately Cover Full Operating Range of Sensors.Removed Sensors & Sent Offsite L-99-019, Special Rept:On 990120,meteorological Tower Wind Speed Sensors Declared Inoperable.Caused by Processor Card for Sensor Locked Up & Needed to Be Reset.Heater That Fit Around Shaft of Sensor Replaced1999-02-0505 February 1999 Special Rept:On 990120,meteorological Tower Wind Speed Sensors Declared Inoperable.Caused by Processor Card for Sensor Locked Up & Needed to Be Reset.Heater That Fit Around Shaft of Sensor Replaced L-98-188, Special Rept:During 1998,Unit 2 SG Eddy Current exam,26 Tubes Were Improperly Encoded in SG 2RCS-SG21C During Previous Outage.Use of Independent Databases to Track New Indications Being Implemented as Preventive Measure1998-09-21021 September 1998 Special Rept:During 1998,Unit 2 SG Eddy Current exam,26 Tubes Were Improperly Encoded in SG 2RCS-SG21C During Previous Outage.Use of Independent Databases to Track New Indications Being Implemented as Preventive Measure L-98-157, Special Rept:On 980423,inoperability of Seismic Monitoring Instrument Noted.Caused by Obsolescence of Instrument & Inability to Obtain Necessary Spare Parts.Design Change Is Being Pursued to Obtain Replacement Product1998-07-29029 July 1998 Special Rept:On 980423,inoperability of Seismic Monitoring Instrument Noted.Caused by Obsolescence of Instrument & Inability to Obtain Necessary Spare Parts.Design Change Is Being Pursued to Obtain Replacement Product L-98-079, Special Rept:On 980423,noted That 2ERS-RRA-1,triaxial Time History Accelerograph Was Unable to Be Returned to Service within 30 Days.Caused by Obsolescence of Equipment & Failure to Obtain Spare Parts.Will Obtain Replacement Product1998-04-23023 April 1998 Special Rept:On 980423,noted That 2ERS-RRA-1,triaxial Time History Accelerograph Was Unable to Be Returned to Service within 30 Days.Caused by Obsolescence of Equipment & Failure to Obtain Spare Parts.Will Obtain Replacement Product ML20084U7461995-06-0808 June 1995 Special Rept:On 931210,suppl Info Re Unacceptable Recirculation Spray Sys Operation for Supporting Long Term Core Cooling Capability & Maintaining Containment Pressure Subatmospheric in Event of LOCA ML20069M0461994-06-10010 June 1994 Rev 1 to Special Rept,On 940202,notified That Five Moveable Incore Detectors Unacounted For.Subsequent to Original Rept Dtd 940304,defective non-irradiated Detector Located, Reducing Number of Unaccounted for Incore Detectors to Four ML20064G4001994-03-0404 March 1994 Special Rept:On 940202,notification Made Via ENS That Five Moveable Incore Detectors Could Not Be Traced from Receipt to Final Disposition.Unaccounted SNM in Detectors Not Considered to Be Hazard to Health & Safety of Public ML20059M9411993-11-15015 November 1993 Special Rept:On 930922,seismic Monitor 2ERS-RRA-1 Declared Inoperable.Caused by High Radiation Dose Rate in SG Support Cubicle Elevation 718'6.Monitor Repaired & Returned to Operable Status on 931014 ML20059C4181993-10-27027 October 1993 Rev to Special Rept,Documenting Results of ISI of SG Tubes Performed During Fourth Refueling Outage Completed on 931014.Rev Issued to Correct Duplication in Table,W/Regard to Number of Tubes Plugged as Precautionary Measure ML20059B3751993-10-25025 October 1993 Special Rept:On 931014,inservice Insp of Tubes in Steam Generator Completed.Two Tubes Removed from Svc Due to Tube Degradation in Excess of TS Limit of 40 Percent Through Wall ML20058N7951993-10-15015 October 1993 Special Rept:On 930907,seismic Accelerometer Located on Operating Deck of Containment XT-ER-105B Failed Monthly Operating Surveillance Test & Declared Inoperable.Cause of Malfunction Cannot Be Determined.Accelerometer Replaced ML20128G3741993-02-0909 February 1993 Special Rept:On 930111,discovered That 80 of 90 Nozzles in Train B Charcoal Filter Bank Fire Suppression Sys Clogged W/ White Scale Matl.Caused by Use of Undersize Strainer.Nozzles Removed & Cleaned & New Strainers Installed ML20086U5121991-12-23023 December 1991 Special Rept Re Failure to Test ultra-violet Flame Detectors Via Separate Procedures W/Different Frequencies than Smoke Detector 6-month Procedures.Caused by Inadequate Review of NFPA Code Changes.Hads Provide CR Indication of Fire ML20065Q3851990-12-14014 December 1990 Special Rept Re Potentially Overstressed Feedwater Supports Due to Postulated Monoball Binding Discovered During 1989 Feedwater Line Monitoring Program.Administrative Controls Implemented.Possibly Reportable Per Part 21 ML20065G9511990-10-15015 October 1990 Special Rept:On 900830,alert Declaration Received Following Inadvertent Carbon Dioxide Discharge.Normal & Emergency Portable Ventilation Established to Purge Affected Areas. Repairs on Valve Scheduled ML20059C2041990-08-23023 August 1990 Special Rept:On 900531,automatic Overpower Turbine Runback Alarm Occurred.Caused by Failure of Electrolytic Capacitor in Governor Valve Servo Card.Governor Valve Closed & Isolated Unit Control Problem Corrected ML20247J7731989-09-15015 September 1989 Special Rept:On 890815,dampers Failed to Comply W/Ul Requirements of Std 555-1968.Caused by Improper Fabrication. All Applicable Fire Dampers in Affected Areas W/Combustible Loading Exceeding 1 H Per 10CFR50,App R Will Be Replaced ML20247E9731989-05-16016 May 1989 Special Rept Re Pressurizer Surge Line Displacement Phenomenon Noted at Facility.In Late 1986,rotation of Trapeze for Snubbers Located on Pressurizer Surge Line Noted.On 870728,thermal Gradient of 100 F Noted ML20236E4751989-05-16016 May 1989 Special Rept Re Hydrogen Gas Accumulation in Charging (High Head Safety Injection) Pump Suction Piping.Caused by Diverse Set of Hydrogen Accumulation Situations Between Two Units Due to Difference in Piping Design.Design Change Initiated ML20246N7681989-05-0909 May 1989 Special Rept:On 890401,seismic Instrumentation Central Control Cabinet 2ERS-CCC-1 Not Returned to Svc within 30 Days & Trigger Card Output Could Not Be Reset Correctly. Replacement Accelerograph Expected by 890605 ML20147D7231988-02-29029 February 1988 Special Rept:On 880122,electrical motor-driven Fire Pump Declared Out of Svc for Corrective Maint Due to Packing Leak.Repair Activities Will Not Be Completed within 7 Days. Temporary Diesel Fire Pump Added to Supply Suppression Sys ML20195H1951988-01-13013 January 1988 Special Rept:Seven Fire Dampers Failed to Fully Close During Operational Testing & Not Restored within 7 Days.Cause Undertermined.Dampers Adjusted & Returned to Svc After Retesting Except VS-D-260 & 285.Fire Watch Established ML20235V2071987-10-0909 October 1987 Special Rept:On 870928,train a Upper Range Static Reactor Vessel Level Indication Declared Inoperable Based on Input Failures from Transmitter & Hydraulic Isolator.Transmitter Under Investigation ML20237J0141987-08-0303 August 1987 Special Rept:On 870726,main Steam Effluent Monitor Declared out-of-svc.Caused by Sample Line Steam Leakage.Alternate Preplanned Monitoring Methods in Effect Until Channels Placed Back in Svc ML20237J0301987-08-0303 August 1987 Special Rept:On 870728,in Containment high-range Monitor Declared out-of-svc Due to Loss of Detector Signal & Repeated Check Source Failure.Caused by Overheating pico- Ampmeter Board.No Potential for Radiation Levels Noted ML20236M3021987-07-29029 July 1987 Special Rept:On 870723,auxiliary Feed Pump Turbine Exhaust Monitor Declared Out of Svc Due to Receipt of High & hi-hi Alarms W/Normal Background Radioactivity Present.Replacement Detector Will Be Procured from Vendor ML20215F8581987-06-12012 June 1987 Special Rept:On 870508,triaxial Time History Accelerometer in Primary Auxiliary Bldg Removed from Svc for More than 30 Days to Replace Acceloremeter in Containment Bldg,Removed for Recalibr.Vendor Return Shipment Scheduled for 870629 ML20207S8541987-03-16016 March 1987 Ro:On 870305,w/both Units 1 & 2 Fire Suppression Sys High Pressure Pumps Inoperable,Diesel Driven Fire Pump FP-P-2 Repeatedly Attempted to auto-start.Caused by Clogged Lines Between Fire Suppression Sys Header & Hydropneumatic Tank ML20212J6481987-03-0505 March 1987 Ro:On 870305,both Fire Suppression Sys High Pressure Pumps Inoperable.Caused by Diesel Driven Fire Pump FP-P-2 Repeatedly Attempting to Autostart When Pump FP-P-1 Removed from Svc.Pump FP-P-1 Returned to Svc.Rept Will Be Submitted ML20215B0841986-12-0505 December 1986 Special Rept:On 861027,triaxial Time History Accelerometer Declared Out of Svc.Accelerometer Removed & Partially Decontaminated.Components Corroded Due to Inadvertent Refueling Cavity Overflow.Replacement Components Ordered ML20203F9911986-07-17017 July 1986 Special Rept Per Tech Specs 6.9.2, Special Repts & 3.12.1, Land Use Census, Re Comparison of Dose Calculations.Change to Offsite Dose Commitment Manual Unnecessary Based on Listed Reasons ML20207C9761986-07-0909 July 1986 Special Rept:On 860616,fire Dampers VS-D-93,95A & 95B Declared Inoperable After Not Fully Closing During Testing. Caused by Damper Binding.After Mechanical Adjustments, Lubrication & Testing,Dampers Returned to Svc on 860707 ML20203G2431986-04-22022 April 1986 Ro:On 860410,SPING Radiation Monitor RM-VS-109 Taken Out of Svc Due to Complete Unit Failure.Caused by Failure on Memory Board.Unit Software Replaced W/Updated Version.Unit Will Be Returned to Svc on Completion of Maint Surveillance ML20137R3421986-01-21021 January 1986 Special Rept:On 860109,main Steam Monitor RM-MS-100A Declared Out of Svc to Perform Troubleshooting.Caused by Bad Discriminator Board & Failed Detector.Both Components Replaced & Monitor Returned to Svc ML20141H9111985-11-29029 November 1985 Special Rept:On 851031,contaminated Water Emptying from Open End of Uncompleted cross-connecting Pipe Discharged Into Sump in Condensate Polishing Bldg & Sump Discharged to River.Caused by Personnel Error.Barrier Installed ML20137C7601985-11-12012 November 1985 Rev 1 to Special Rept ND1SS1:2506:on 850720,main Steam Monitor RM-MS-100B Declared Out of Svc Due to Receipt of High Alarm W/Normal Background Radioactivity Present.Caused by Loose Triaxial Connector.Replacement Parts Installed ML20132A7571985-07-29029 July 1985 Special Rept:On 850720,maint Steam Monitor RM-MS-100B Declared Out of Svc Due to Receipt of High Alarm W/Normal Background Radioactivity Present.Cause Undetermined. Alternate Monitoring Planned Until Channel Returned to Svc ML20116C7631985-04-0202 April 1985 Special Rept:On 840912 - 850116,fire Protection Audit Revealed Lack of Suitable Fire Barriers in Duct Work Between Control Room HVAC Equipment Room,Cable Tray Mezzanine & Process Instrument/Rod Position Room ML20090D8681984-06-20020 June 1984 Rev 1 to Special Rept:On 840215,Channels 7 & 9 of Special Particulate,Iodine Noble Gas Monitor for Radiation Monitor RM-VS-110 Declared Out of Svc.Cause Undetermined.Bubble Memory Manipulated & Parameter Files re-edited ML20091N8681984-05-25025 May 1984 Ro:On 840429,diesel Engine Driven Fire Pump FP-P-2 Failed to Complete Surveillance Test & Declared Inoperable.Cause Unknown.Fuel Shutoff Valve Assembly,Voltage Regulator, Generator & Indicating Lamp Bulb & Socket Replaced ML20084K4911984-04-13013 April 1984 Rev to 840224 Special Rept:On 840215,Channels 7 & 9 of Particulate Iodine,Noble Gas Monitor Declared out-of-svc Due to Constant Receipt of High Radiation Alarms.Complete Spare Parts Kit for Monitors Will Be Acquired ML20086T1021984-02-29029 February 1984 Ro:On 840215,high Radiation Alarms W/Normal Activity Present Received Constantly for Channels 7 & 9 of Special Particulate Iodine,Noble Gas Monitor.Cause Could Not Be Determined.Vendor Will Assist in Investigation ML20072N3171983-03-0202 March 1983 Ro:On 830225,Discharge 302 (Sewage Treatment Plant Effluent) Discovered Out of Spec in Fecal Coliform.Caused by Abnormally High Amount of Solids Floating on Chlorine Contact Tank.Effluent Will Be hand-chlorinated ML20054E1231982-04-16016 April 1982 RO 82-011/01P & 82-012/01P:on 820416,overstress Conditions Identified at Four Locations in Safety Injection Sys & Three Locations in Main Steam Sys.Required Mods to Bring Supports within Acceptable Limits Will Be Made ML20126H3451981-03-26026 March 1981 RO 81-029/01P:on 810325,reported Discrepancy Between Plant Mod Manual & Tech Specs Found During 810312 Review of Inservice Insp Requirements for Mods Recently Completed on RCS & Safety Injection Sys ML20126F2771981-03-0606 March 1981 RO 81-019/01P:on 810305,RHR Low Flow Alarm Actuated W/Low Running Current on Pump 1 B During Reactor Shutdown at 100 F & Atmospheric Pressure.Cause Not Stated.Sys Vented & Reactor Coolant Piping Refilled to Approx 65% ML20064K3991980-11-21021 November 1980 RO Followup on 800403 Rept:On 800225,two Frequencies on Peak Shock Annunciator Sys Actuated Visual Alarms W/O Occurrence of Seismic Event.Problem Traced to Reed Switches in Containment Transmitter.Sys Checked & Recalibr ML20064K3691980-11-17017 November 1980 RO 80-77/01P:on 801114,evaluation Per IE Bulletin 79-14 Indicated That Support on a Main Steam Header Line Was Less Conservative than Assumed in Tech Specs.Support Mods Were Complete on 801115 1999-05-03
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARL-99-154, Monthly Operating Repts for Sept 199 for Bvps,Units 1 & 2. with1999-09-30030 September 1999 Monthly Operating Repts for Sept 199 for Bvps,Units 1 & 2. with L-99-139, LER 99-S01-00:on 990813,uncompensated Loss of Ability to Detect within Single Intrusion Security Detection Zone Occurred.Caused by Procedure non-compliance.Involved Personnel Received Counseling Re Event.With1999-09-0202 September 1999 LER 99-S01-00:on 990813,uncompensated Loss of Ability to Detect within Single Intrusion Security Detection Zone Occurred.Caused by Procedure non-compliance.Involved Personnel Received Counseling Re Event.With L-99-140, Monthly Operating Repts for Aug 1999 for Bvps,Units 1 & 2. with1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Bvps,Units 1 & 2. with L-99-126, Monthly Operating Repts for Jul 1999 for Beaver Valley Power Station,Units 1 & 2.With1999-07-31031 July 1999 Monthly Operating Repts for Jul 1999 for Beaver Valley Power Station,Units 1 & 2.With L-99-107, Monthly Operating Repts for June 1999 for Bvps,Units 1 & 2. with1999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Bvps,Units 1 & 2. with ML20209D9531999-06-27027 June 1999 Inservice Insp Ninety-Day Rept Bvps,Unit 2 Outage 7,Year 1999 L-99-096, Monthly Operating Repts for May 1999 for BVPS Units 1 & 2. with1999-05-31031 May 1999 Monthly Operating Repts for May 1999 for BVPS Units 1 & 2. with L-99-078, Special Rept:On 990326,seismic Monitoring Instruments Were Declared Inoperable.Caused by Resolution of Potential TS Compliance Issue & Work Scheduling Issue.Instrumentation Was Returned to Svc Following Calibr & Declared Operable1999-05-0303 May 1999 Special Rept:On 990326,seismic Monitoring Instruments Were Declared Inoperable.Caused by Resolution of Potential TS Compliance Issue & Work Scheduling Issue.Instrumentation Was Returned to Svc Following Calibr & Declared Operable L-99-079, Monthly Operating Repts for Apr 1999 for Beaver Valley Power Station,Units 1 & 2.With1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Beaver Valley Power Station,Units 1 & 2.With ML20205L0401999-04-0909 April 1999 SER Accepting Util Relief Requests for Inservice Insp Second 10-year Interval for Beaver Valley Power Station, Unit 2 L-99-054, Special Rept:On 990320,meteorological Tower Wind Speed Sensors Were Declared Inoperable.Caused by Calibration Completed by Vendor Did Not Adequately Cover Full Operating Range of Sensors.Removed Sensors & Sent Offsite1999-04-0505 April 1999 Special Rept:On 990320,meteorological Tower Wind Speed Sensors Were Declared Inoperable.Caused by Calibration Completed by Vendor Did Not Adequately Cover Full Operating Range of Sensors.Removed Sensors & Sent Offsite L-99-058, Monthly Operating Repts for Mar 1999 for Bvps,Units 1 & 2. with1999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Bvps,Units 1 & 2. with ML20196K7981999-03-25025 March 1999 Rev 4 to COLR, for Cycle 8 L-99-038, Monthly Operating Repts for Feb 1999 for Bvps,Units 1 & 2. with1999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Bvps,Units 1 & 2. with ML20203E1181999-02-10010 February 1999 SER Accepting Proposed Revs to Plant,Units 1 & 2 Quality Assurance Program Description L-99-019, Special Rept:On 990120,meteorological Tower Wind Speed Sensors Declared Inoperable.Caused by Processor Card for Sensor Locked Up & Needed to Be Reset.Heater That Fit Around Shaft of Sensor Replaced1999-02-0505 February 1999 Special Rept:On 990120,meteorological Tower Wind Speed Sensors Declared Inoperable.Caused by Processor Card for Sensor Locked Up & Needed to Be Reset.Heater That Fit Around Shaft of Sensor Replaced ML20196F7011999-01-31031 January 1999 BVPS Unit 2 Heatup & Cooldown Limit Curves During Normal Operation at 15 EFPY Using Code Case N-626 ML20203D4811999-01-31031 January 1999 Monthly Operating Repts for Jan 1999 for Bvps,Units 1 & 2, in Accordance with NRC GL 97-02.With ML20207E6631999-01-28028 January 1999 Rev 0 to EMECH-0713-1, Operational Assessment of SG Tubing at Beaver Valley Unit 1,Cycle 13 ML20210G7041999-01-22022 January 1999 BVPS Unit 1 Facility Changes,Tests & Experiments for 980123-990122 ML20207E5861998-12-31031 December 1998 Annual Rept 1998 for Toledo Edison ML20207E5601998-12-31031 December 1998 Annual Rept 1998 for Pennpower ML20198B9021998-12-31031 December 1998 BVPS Unit 1 Simulator Four Yr Certification Rept for 1995-1998 ML20207E5901998-12-31031 December 1998 Dqe 1998 Annual Rept to Shareholders ML20199C9971998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Bvps,Units 1 & 2. with ML20207E5521998-12-31031 December 1998 Annual Rept 1998 for Ohio Edison ML20207E5761998-12-31031 December 1998 Annual Rept 1998 for Illuminating Co ML20204J6751998-12-31031 December 1998 1998 Annual Rept for Dbnps,Unit 1,PNPP,Unit 1 & BVPS Units 1 & 2 ML20199F5341998-12-29029 December 1998 Safety Evaluation Granting Relief Requests 1-TYP-3-B3.140-1, 1-TYP-3-B5.70-1,1-TYP-3-RH-E-1-1,1-TYP-3-B-G-1, 1-TYP-3-APP-I-1,1-TYP-3-UT-1,1-TYP-3-N-509,1-TYP-3-N-521, 1-TYP-3-N-524,1-TYP-3-B3.120-1 & 1-TYP-3-C6.10-1 ML20198K8551998-12-21021 December 1998 SER Granting Relief Request PRR-5 for Third 10-year Inservice Testing for Beaver Valley Power Station,Unit 1 ML20198A1631998-12-0909 December 1998 SER Approving Implementation Program to Resolve USI A-46 at Facility That Has Adequately Addressed Purpose of 10CFR50.54(f) Request L-98-229, Monthly Operating Repts for Nov 1998 for Bvps,Units 1 & 2. with1998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Bvps,Units 1 & 2. with ML20195J3131998-11-12012 November 1998 Safety Evaluation Granting First & Second 10-yr Interval Inservice Insp Request for Relief L-98-210, Monthly Operating Repts for Oct 1998 for Bvps,Units 1 & 2. with1998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Bvps,Units 1 & 2. with ML20206G0291998-10-31031 October 1998 BVPS Unit 2 Facility Changes,Tests & Experiments for Period 971101-981031 ML20154R9121998-10-20020 October 1998 Safety Evaluation Accepting Proposed Changes to QA Program Description in Chapter 17.2 of BVPS-2 Ufsar.Proposed Changes Would Modify QA Organization to Allow Warehouse QC Inspectors to Report to Manager of Nuclear Procurement Dept ML20154P7491998-10-19019 October 1998 SE Accepting Second ten-year Interval Inservice Insp Request for Relief RR-1-TYP-2-B5.40-1,Rev 0,for Plant, Unit 1 ML20198F7611998-10-0606 October 1998 Duquesne Light Co,Beaver Valley Power Station 1998 Emergency Preparedness Ingestion Zone Exercise, Conducted on 981006 ML20154C6711998-10-0101 October 1998 Safety Evaluation Concluding That Revised Model Identified in Dl Submittal Was Appropriate for Analysis of Installed Conduit Ampacity Limits.Determined That There Are No Outstanding Safety Concerns with Respect to Ampacity ML20154D5001998-09-30030 September 1998 Special Rept on Overview of BVPS-1 & BVPS-2 TS Compliance Issues & Corrective Action Taken L-98-197, Monthly Operating Repts for Sept 1998 for Beaver Valley Power Station,Units 1 & 2.With1998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Beaver Valley Power Station,Units 1 & 2.With ML20154E2171998-09-28028 September 1998 Follow-up Part 21 Rept Re Defect with 1200AC & 1200BC Recorders Built Under Westronics 10CFR50 App B Program. Westronics Has Notified Bvps,Ano & RBS & Is Currently Making Arrangements to Implement Design Mods L-98-188, Special Rept:During 1998,Unit 2 SG Eddy Current exam,26 Tubes Were Improperly Encoded in SG 2RCS-SG21C During Previous Outage.Use of Independent Databases to Track New Indications Being Implemented as Preventive Measure1998-09-21021 September 1998 Special Rept:During 1998,Unit 2 SG Eddy Current exam,26 Tubes Were Improperly Encoded in SG 2RCS-SG21C During Previous Outage.Use of Independent Databases to Track New Indications Being Implemented as Preventive Measure L-98-178, Monthly Operating Repts for Aug 1998 for Bvps,Units 1 & 2. with1998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Bvps,Units 1 & 2. with ML20155B5871998-08-28028 August 1998 Non-proprietary Rev 1 to 51-5001925-01, Risk Assessment for Installation of Electrosleeves at BVPS & Callaway Plant ML20236X2351998-08-0505 August 1998 Part 21 Rept Re Defect Associated W/Westronics 1200AC & 1200BC Recorders Built Under Westronics 10CFR50,App B Program.Beaver Valley,Arkansas Nuclear One & River Bend Station Notified.Design Mod Is Being Developed L-98-168, Monthly Operating Repts for July 1998 for Bvps,Units 1 & 21998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Bvps,Units 1 & 2 L-98-157, Special Rept:On 980423,inoperability of Seismic Monitoring Instrument Noted.Caused by Obsolescence of Instrument & Inability to Obtain Necessary Spare Parts.Design Change Is Being Pursued to Obtain Replacement Product1998-07-29029 July 1998 Special Rept:On 980423,inoperability of Seismic Monitoring Instrument Noted.Caused by Obsolescence of Instrument & Inability to Obtain Necessary Spare Parts.Design Change Is Being Pursued to Obtain Replacement Product L-98-139, Monthly Operating Repts for June 1998 for Bvps,Units 1 & 21998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Bvps,Units 1 & 2 L-98-119, Monthly Operating Repts for Bvps,Units 1 & 21998-05-31031 May 1998 Monthly Operating Repts for Bvps,Units 1 & 2 1999-09-30
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May 16, 1989 ND3MNO:1885 Beaver Valley Power Station, Unit No.s 1 and 2 Docket No. 50-334, 412, License No.s DPR-66, NPF-73 Soecial Report United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
The attached report is being submitted to provide information regarding the Hydrogen Gas Accumulation in the Charging (High Head Safety Injection) Pump Suction Piping for Beaver Valley Power Station Units 1 and 2.
Very truly yours.
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T. P. Noonan General Manager Nuclear Operations Attachments
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May 16, 1989 ND3MNO:1885 Page two 4
cc: Mr. William T. Russell Regional Administrator United States Nuclear Regulatory Commission Region 1 475 Allendale Road King of Prussia, PA 19406 C. A. Roteck, Ohio Edison Mr. Teter Tam, BVPS Licensing Project Manager United States Nuclear Regulatory Commissicn Washington, DC 20555 J. Beall, Nuclear Regulatory Commission, BVPS Senior Resident Inspector CAPCO Nuclear Projects Coordinator Toledo Edison INPO Records Center Suite 1500 1100 Circle 75 Parkway Atlanta, GA 30339 G. E. Muckle, Factory Mutual Engineering, Pittsburgh Mr. J. N. Steinmetz, Operating Plant Projects Manager Mid Atlantic Area Westinghouse Electric Corporation Energy Systems Service Division Box 355 Pittsburgh, PA 15230 American Nuclear Insurers c/o Dottie Sherman, ANI Library The Exchange Suite 245 270 Farmington Avenue Farmington, CT 06032 Mr. Richard Janati Department of Environmental Resources P. O. Box 2063 16th Floor, Fulton Building Harrisburg, PA 17120 Director, Safety Evaluation & Control Virginia Electric & Power Co. 1 P. O. Box 26666 One James River Plaza Richmond, VA 23261
May 16, 1989 ND3MNO:1885 Page three BACKGROUND Unit 1 had experienced hydrogen accumulation in sections of Charging (HHSI) Pump piping which was attributed to degassing of Reactor Coolant System water. An investigation was performed and as a result periodic venting was initiated. In addition, procedural I requirements to vent charging pumps when returning to service following maintenance were already in practice. Past operating experience indicated no operational difficulties related to hydrogen accumulation. Unit 2 began venting shiftly following discovery of gas accumulation in March 1988. Based on engineering analysis of the quantities of gas found and the venting schedule being performed, system OPERABILITY was maintained as an investigation was initiated.
Following the discovery of hydrogen accumulation at Unit 2 and the issuance of NRC Information Notice 88-23 " Potential For Gas Binding of High Pressure Safety Injection Pumps During a Loss-of-Coolant Accident", dated May 12, 1988, further investigation was also initiated at Unit 1. The investigations, found a diverse set of
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hydrogen accumulation situations between the two units, due to a difference in piping design. Additionally, NRC Information Notice 88-23, provided supplementary information on this area.
In March 1988, Unit 2 experienced gas accumulation in the suction piping of a charging pump during testing associated with a design change. Gas was detected in the suction piping of the "A" Charging Pump (the third Charging Pump not required operable per Technical Specifications). Samples collected from the suction piping vent were ;
determined to be primarily hydrogen gas. Following this occurrence, l a periodic venting schedule was initiated to preclude the excessive )
accumulation of hydrogen and ensure pump operability. l At Unit 1, the gas accumulation was first noted when starting the "A" Charging Pump (CH-P-1A), due to the differences in recirculation !
flows for this pump as compared to the other pumps. The "A" Pump recirculation flow is higher than the other pumps causing an increased pressure drop across the recirculation piping orifice, contributing to the off-gassing which is assumed to occur. The condition manifested itself whenever the "A" Pump was started with the "B" or "C" Pump already running. Immediate indications were fluctuating pump discharge pressure, charging header flow, and seal injection flow to the Reactor Coolant Pumps, followed by a recovery
.% to normal parameters within three (3) to five (5) seconds. Due to the rapid recovery it was not readily apparent what was causing this condition. Subsequent evaluations at Unit 1 noted that during a pressure increase to the Volume Control Tank (VCT) from hydrogen gas addition, there was a concurrent decrease in VCT level. As a result, the presence of a gas void somewhere else in the system was recognized. The most likely places being local high points in the system, such as the suction header piping to the Charging Pur.ps.
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DIFFERENCE IN DESIGN At Unit 2, the design utilizes one (8 inch) suction. header for normal charging flow and for both phases of Safety Injection. The-suction header is located below the pumps with an inverted-u design-suction and discharge piping delivering flow to and from each individual pump. The idle pumps can then potentially collect' gas individually as hydrogen is capable of accumulating in the suction piping, pump casing, and discharge piping. Presently a venting schedule has been implemented to preclude excessive gas accumulation I from occurring.
The Unit 1 design utilizes a main (8' inch) suction header during normal charging operations and to deliver flow from the Refueling Water ' Storage Tank (RWST) during the Injection. Phase of Safety Injection and from the "B" Train Low Head Safety Injection.(LESI)
Pump during the Recirculation Phase of Safety Injection. The suction header is located above the pumps with no inverted-u' piping:- !
therefore, gas accumulation occurs in the main suction header end'not in the suction piping associated with each individual pump. A second (6 inch) header delivers flow from the "A" Train LHSI Pumps during the Recirculation Phase of Safety Injection also located in a suction header above the pumps. No gas has been detected in the discharge piping at Unit 1.
INVESTIGATION Investigations at both Units included venting at various locations during various system configurations to determine where and when hydrogen was accumulating and to determine desired operating configurations. In June 1988, numerous Ultrasonic Inspections (UT) were initiated to locate and quantify the hydrogen voids which had been detected. Specific locations and . quantities of voids were determined. The largest voids found were 11.0 cubic feet _at Unit 2 and 19.7 cubic feet at Unit 1. Based on the data taken and subsequent engineering review / evaluations, it was determined that the maximum voids which could exist are approximately 11 0 cubic feet at Unit 2 (same as actual worst case found) and 25.1 cubic feet at Unit
- 1. Venting schedules and desired operating configurations were recommended for both units as a prudent measure to prevent excessive hydrogen accumulation.
. May 16, 1989 ND3MNO:1885 Page five APPARENT CAUSE The apparent source of h'ydrogen gas is the Volume control Tank (VCT), in which an overpressure of hydrogen is maintained to enable control of the oxygen content of the Reactor Coolant System (RCS).
During normal plant operations, one (1) of the three (3) Charging Pumps is continuously operated to provide charging and seal injection water to the RCS and Reactor Coolant Pumps respectively. Part of the Charging Pump discharge flow is directed through an orifice into miniflow recirculation piping, which traverses back to the Charging Pump suction header. The miniflow path ensures that the Charging Pump will not operate in a " dead head" mode. It is the miniflow orifices which are suspected of being the primary point of introduction of gas bubbles into the Charging Pumps piping. This is due to the stripping of gas out of solution as the fluid undergoes the .large pressure drop (approximately 2500 psid) across the orifice. It is believed that once stripped from solution the gas bubbles remain out of solution and travel back tc the suction piping, via the recirculation lines, where they collect and form a large void. There are other possible locations, such as piping tees and elbows, where stripping may occur; however, no locations have yet :
been verified.
SAFETY ANALYSIS No safety implications have resulted from this condition. To date, no Safety Injections, at Units 1 or 2, have occurred in which j the Charging Pumps have failed to perform their intended safety function as required by Technical Specifications 3.5.2 (Unit 1 and 2 Tech. Specs.). Based on an engineering analysis, a venting Echedule I has been implemented as a prudent temporary measure at both Units 1 along with a desired configuration list to paintain acceptable void i volumes in the Charging (HHSI) Pump piping. A design change to provide better accessibility for venting has been initiated for both Units. In addition, in the unlikely event that any or all of the !
Operating, Standby, or Reserve High Head Safety injection (HHSI)
Pumps fail to perform their intended safety function when needed, Emergency Operating Procedures FR-C.1 " Response to Inadequate Core Cooling Condition" and FR-C.2 " Response to Degraded Core Cooling Condition", provide actions for operators to ensure a safe shutdown of the plant with alternate means of core cooling.
It is recognized that operating with hydrogen voids in the Charging (HHSI) Pump piping is not desirable; however, due to past operating experience and an engineering evaluation there is no l evidence that the gas voids would have prohibited a pump from performing its intended safety function if requirad. There_are, based on operating experience, data r and a engineering analysis, the pumps have been determined to be operable at both Units 1 and 2. In addition, prudent temporary measures have been taken.
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CORRECTIVE ACTIONS i
The following actions have been or will be performed to ensure l operability of the Unit 1 and 2 Charging (HHSI) Pumps: l l
- 1. As previously stated, venting schedules have been implemented at both Units 1 and 2, along with desired ,
developed i configuration lists, which were to maintain continued acceptable void volumes in the Charging System.
- 2. A design change has been initiated to provide better 1 accessibility for venting at both Units and to direct the !
hydrogen to the gaseous waste system at' Unit 1.
- 3. Westinghouse has been requested to .onduct an investigation ,
of this phenomena. This investigation includes the j fabrication of a clear plastic model of the Unit 2 piping, i which will be used to simulate actual flow conditions at Unit 2 Fabrication of the model has been completed and testing has commenced. It ic believed this model will aid in determining the locations of gas stripping and long term i corrective actions for both Units 1 and 2. i
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