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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARML20247E0701989-07-20020 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 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 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 ML20203P0981986-04-25025 April 1986 Special Rept:On 860329,mechanical Fire Penetration Returned to Svc After Being Inoperable for Greater than 7 Days.Caused by Unacceptable Repair on 860327.Foam Sealant Equipment Repaired & Personnel Trained ML20154R0261986-03-13013 March 1986 Special Rept:On 860204,motor-driven Fire Pump Taken Out of Svc to Permit Divers to Enter Circulating Water Intake Structure.Intake Bay Dewatered on 860206 to Perform Addl Insps & Maint.Intake Bay Flooded on 860211.Part 21 Related ML20128C2161985-04-16016 April 1985 Special Rept:On 850318,RCS Iodine Radioactivity Spike Occurred.Cause Not Stated.Subsequent Sampling Met Requirements of Tech Spec 3.1.4.RCS I-131 Dose Equivalent Returned to Previously Experienced Levels on 850320 ML20093M0131984-10-0505 October 1984 Special Rept:As Result of Extensive Util Fire Barrier Penetration Insp Program,Number of Deficient Fire Barrier Penetrations Discovered.Penetrations Will Be Upgraded/ Dispositioned Prior to Startup ML20081C9881984-03-0606 March 1984 Special Rept:On 840131,six Hose Stations,Seven non-Tech Spec Hose Stations & Two Hydrants Inoperable Due to Isolation of Water Loop for Bldg Const.Addl Support for Rerouted Fire Water Piping Provided ML20082H6531983-11-23023 November 1983 Ro:On 831103,plant Shutdown for Steam Generator Tube Insp. Results Listed.Outage Still in Progress.Final Insp Results Forthcoming in 14-day LER ML20081M0991983-11-0909 November 1983 RO 82-009:specific Procedures to Test Motor Operated Valve Torque Switch Settings Not in Place by 830930.Caused by Committing Resources to Other Recent Regulatory Requirements.Procedures Will Be Established ML20080P7031983-09-29029 September 1983 Ro:On 830928,svc Water Leak Discovered on Containment Fan Cooler HVH-2.Event Considered Degradation of Containment Boundary Per IE Bulletin 80-24 ML20078D4291983-09-27027 September 1983 Ro:On 830926,svc Water Leak Discovered on Containment Fan Cooler HVH-2.Cooler Declared Inoperable.Repairs Initiated. Event Considered Degradation of Containment Boundary Per IE Bulletin 80-24 ML20080M0281983-09-19019 September 1983 Ro:On 830916,Tech Spec Instantaneous Release Limit for Radioiodine Exceeded.Investigation Continuing ML20081F8571983-09-12012 September 1983 Ro:On 830905,facility Shut Down Due to Secondary Leak in Steam Generator A.Two Tubes Exhibited through-wall Indications Which Should Have Been Plugged.Tubes Plugged & Tested Satisfactorily ML20076H7021983-08-24024 August 1983 Ro:On 830823,svc Water Leak Discovered on Containment Fan Cooler HVH-2.Svc Water to Cooler Isolated.Repairs Performed ML20081F8821983-07-0505 July 1983 Ro:On 830704,svc Water Leak Discovered on Containment Fan Cooler HVH-2.Operability Testing of Containment Spray Pumps Completed.Event Considered Degradation of Containment Boundary Per IE Bulletin 80-24 ML20151H7281983-04-28028 April 1983 Ro:On 830427,svc Water Pump a Removed from Svc for Normal Preventative Maint & Replaced W/Rebuilt Spare Pump. Post-maint Testing Resulted in Pump Over Current Trip.Caused by Internal Binding of Rebuilt Pump ML20073R2761983-04-25025 April 1983 Ro:On 830424,svc Water Booster Pump B Declared Inoperable Due to Bearing Failure & Plant Shutdown Commenced Following Pump a Trip Due to Blown Control Power Fuses.Fuses Replaced & Pump a Restarted.Investigation Continuing ML20073H9381983-04-11011 April 1983 Ro:On 830410,svc Water Leak Discovered on Containment Fan Cooler HVH-3.Svc Water Immediately Isolated.Condition Reportable Per IE Bulletin 80-24 as Degradation of Containment Boundary ML20072E1681983-02-28028 February 1983 RO-82-009 Re Failure of Motor Operated Valve RHR-759A. Due to Larger than Anticipated Work Scope,Completion Date for Corrective Actions Revised.Insp & Testing of Torque Switch Will Be Completed by End of Next Refueling Outage ML20063M1101982-08-31031 August 1982 Ro:On 820811,RHR Containment Suction Valve RHR-861A Found Opening Only Halfway & Promptly Declared Inoperable. Requests Extended 48-h Maint on Valve.Valve Not Completely Disassembled & Total Scope of Repair Not Established ML20063M1411982-08-0303 August 1982 Ro:On 820731,during Hot Shutdown,Leak Observed Coming from Control Rod Drive Mechanism Valve for Rod L-11.Leak Identified as Abnormal Degradation of RCPB ML20063M1141982-07-16016 July 1982 Ro:On 820715,small Leak in Form of Mist Found on Hydrogen Vent Header 2 Motor Cooler.Header Secured & Svc Water Isolated.Event Considered Degradation of Containment Boundary Per IE Bulletin 80-24 ML20054H4561982-06-18018 June 1982 Ro:On 820428,PT-9.13 Revealed Failure in Power Supply to Damper Relay Panel B1 (Train B) Concurrent W/Failed Relay for Zone 10 (South Cable Vault) on Panel A1 (Train A). Correction in Progress & Completion Expected by 821231 ML20063M1051982-04-27027 April 1982 Ro:On 820426,during Refueling outage,100% Eddy Current Insp of All Steam Generators Revealed Pluggable Indications of 4.4% & 1.5% on Generators B & C,Respectively.Generators Classified as Sampling Category C-3 ML20063M3131982-04-21021 April 1982 Ro:On 820416,routine Reading of Contractor Health Physics Technician TLD Indicated 6.6 Rem.Cause Not Stated.Backup Dosimetry Did Not Confirm Reading.Investigation Results to Be Submitted ML20084S8631978-01-30030 January 1978 Ro:On 780129,RCS Pressure Exceeded Tech Spec Limit by 60 Psig.Cause Not Stated.Rhr Pumps Restarted to Reduce Pressure ML20084S8831977-08-26026 August 1977 Ro:On 770825,Westinghouse Notified Util of Probable Error in Calculation of Sodium Hydroxide Concentration in Containment Spray Additive Tank.Caused by Procedural Error. Concentration Increased & New Analysis Initiated ML20084S8901977-08-15015 August 1977 Telecopy Ro:On 770812,Westinghouse Informed Util of Incorrect Tech Spec Limits of Pressurizer Heatup & Cooldown Limits.Tech Spec States Heatup & Cooldown Rates Shall Not Exceed 200 F & New Limits Equal 300 F ML20084S9041977-06-0707 June 1977 Telecopy Ro:On 770607,charging Pump High Speed Alarm Received & Pressurizer Level Decreased.Charging Pump C from Svc for Venting,Pump B Failed to Maintain Normal Pressurizer Level & Pump a Being Repaired ML20084S9211977-01-26026 January 1977 Telecopy Ro:On 770125,flow Paths from Boric Acid Tanks Made Inoperable for Valve Repair ML20086D2601976-12-0101 December 1976 RO:761117,discovered Canopy Seal Welds for Two Control Rod Drive Mechanism Housings Had Small Pin Hole Leaks BSEP-76-1374, Ro:On 761119,RHR Low Pressure Coolant Injection Valves E11-FO15A & B Had Marginal Breaker Magnetic Trip Settings. Cause Appears to Be Generic.Breakers Being Replaced1976-11-19019 November 1976 Ro:On 761119,RHR Low Pressure Coolant Injection Valves E11-FO15A & B Had Marginal Breaker Magnetic Trip Settings. Cause Appears to Be Generic.Breakers Being Replaced ML20086F4061976-11-17017 November 1976 Rept of Incidents/Occurrences for 760102-1117 BSEP-76-1143, Ro:On 760922,engineering Analysis Delineated Potential Problem W/Primary Containment Instruments 2-CAC-AT-1259 & 2-CAC-AT-1263.Dehumidifiers May Trip in Event of Loca.Caused by Excessive Heat.Short Sensing Lines Isolated1976-09-23023 September 1976 Ro:On 760922,engineering Analysis Delineated Potential Problem W/Primary Containment Instruments 2-CAC-AT-1259 & 2-CAC-AT-1263.Dehumidifiers May Trip in Event of Loca.Caused by Excessive Heat.Short Sensing Lines Isolated ML20086D3391976-08-18018 August 1976 Ro:On 760817,while Performance PT 22 on Auxiliary Feedwater sys,V2-16A Would Not Open Electrically from Rtgb.Redundant Equipment Operated Satisfactorily,Proving Ability to Feed Steam Generator in Emergency Conditions ML20086D3621976-08-0606 August 1976 Ro:On 760806,util Notified by Westinghouse of Recent Developments Re Westinghouse Safety Analyses.Limiting Values for Fq & Pnh Reduced to 2.27 & 1.49,pending Further Investigation ML20086D4021976-04-0202 April 1976 Ro:On 760402,discovered That Boric Acid Heat Tracing Circuit 56 Had No Current Flow & Was Inoperative.Breaker Opened in Each Heat Trace Power Panels ML20086D4121976-03-15015 March 1976 Ro:On 760312,util Notified by Westinghouse of Possible Error in LOCA Analysis.Error Involves Oversight of Potential Effect of Steam Generator Tube Plugging.Limiting Valve of Fq Reduced to 2.26 Pending Further Investigation ML20085D0361973-08-0909 August 1973 Ro:Water Vol in Safety Injection Accumulators Found Below Min Required Tech Spec Limit.Caused by Incorrectly Fixed High & Low Level Alarm Setpoints.New Setpoint Documentation Approved ML20085D1121973-06-27027 June 1973 Ro:On 730620,during Test on Turbine Redundant Overspeed Trip Sys,Turbine Trip Inadvertently Initiated.Caused by Turbine Stop Valve Limit Switch Failure.Switch Adjusted ML20085D2321973-04-26026 April 1973 Ro:On 730327,individual Received Overexposure to Radiation While Checking for Leakage in Reactor Sump Area.Technicians Instructed on Importance of Knowing Exposure Limit & Remaining Dose of Individual Working in Area ML20085D2241973-04-24024 April 1973 Ro:On 730410,spill of Water from Refueling Water Storage Tank to Plant Storm Drainage Sys Occurred.Caused by Leakage in Line Between Spent Fuel Cooling Sys & Safety Injection Sys Due to High Pressure.Piping & Valves Pressurized ML20085D3171973-02-0909 February 1973 Ro:On 721220,leak Detected Inside Containment Vessel in Joint Where Auxiliary Feedwater Pipe B,4-FW-23 Joins Main Feedwater Pipe B,16-FW-10.Caused by Saddle Welds Not Designed as Pressure Boundary.Boundary Rewelded ML20085D2631972-11-30030 November 1972 Ro:On 721105,power Operated Relief Valve RV-2 on Steam Line B Failed to Close.Caused by Relief Valve Sticking in Open Position.Inner Valve & Guide Bushing Polished ML20085D3991972-11-10010 November 1972 Ro:On 721019,boric Acid Tank B & Boron Injection Tank Found Low in Boron Concentration.Caused by Improper Seating of Suction & Discharge Isolation Valves of Tank.Tank Recirculated W/Boric Acid Tank a ML20085D4071972-10-20020 October 1972 Telecopy Ro:On 721019,boron Injection Tank & Boric Acid Tank B Found to Have Low Concentration of Boric Acid.Steps Initiated to Return Tanks to Normal Concentration ML20085D3731972-09-11011 September 1972 Ro:On 720726 Following Part Length Rod Control Sys Alarm, Frequency Sensor Relay Found Inoperable.Relay Replaced ML20085D4221972-07-24024 July 1972 Ro:On 720716,concentration of Boron Injection Tank Found Diluted Below Tech Spec Limit.Caused by Plugged Recirculation Path Between Boric Acid & Injection Tanks. Temporary Hose Rigged to Recirculate Acid Between Two Tanks ML20085D1371972-07-18018 July 1972 Ro:On 720709,steam Line Isolation Valve B Malfunctioned During Periodic Test.Caused by Sheared Pin in Linkage Between Valve Stem & Disc.Valve Repaired 1989-07-20
[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
[Table view] |
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Dr. Peter A. Morris Division of Reactor Licensing U. S. Atomic Energy Commission Washington, D. C. 20545 FACILITY LICENSE NO. DPR-23 DOCKET NO. 50-261
Dear Dr. Morris:
On March 14, 1971 at approximately 2:55 P.M. an incident occurred at the II. B. Robinson Unit No. 2 that led to the failure of the turbine. After a reactor trip and subsequent turbine trip, lubricating oil flow was lost to the turbine and generater bearings.
The rotor came to rest in the abnormally short time of approximately 17 minutes and seized in several failed bearings.
Assessment of the damage indicated that all eight turbine and generator bearings had suffered some damage. Bearings 4 and 5, between the two low pressure turbines, failed to the extent that molten babbit flowed through the bearings. As a result, the No. I low pressure turbine rotoi- dropped sufficiently to cause rubbing between the rotor and the shell. Damage in the turbine was limited to failure of some steam seal strips and cracking of three shroud segments on the No. 6 wheel nearest No. 4 bearing. The most serious damage to the No. 1 rotor was surface hardening of the rotor material 4 on the oil seal adjacent to the No. 4 bearing. The rotor was removed to the Westinghouse turbine shop.in Charlotte, North Carolina,_for a complete inspection. The "hard spot" was removed by machining.
The No.1 low pressure rotor was removed from the shell and inspected thoroughly at the plant. Magna-flux readings were taken on all critical areas. No damage was indicated on the No. 2 rotor or shell and that unit is being re-assembled. i During the reactor shutdown, seal flow was interrupted to two reactor coolant pumps for approximately one minute. Subsequent investigation indicated.the shaft for "A" reactor coolant pump may have been distorted by uneven heating.- This pump has been disassembled and a new shaft is being installed. The seal on "C" reactor coolant pump will be disassembled for inspection before the unit is returned to vice.
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The unit was on the line carrying a load of 615 MWe as directed by the system load dispatcher. All plant conditions were normal. The operating staff was conducting the weekly routine checkoff of plant equip-ment.
8:30 A.M. Auxiliary Operator checked battery room and noted all indications normal in process of completing the shift Auxiliary Operator check-off list.
10:30 A.M. Auxiliary Operator started DC emergency oil pump, fed from "A" battery bus, for routine two (2) hour test run. This~ pump _was not stooped as planned atJ12:30.. EL,-
because the. Auxiliary Operator became involved in other routine duties. All conditions remained normal until shortly before the reactor trip. One momentary alarm was received on "B" battery charger trouble annunciator. _
The alarm cicared immediately and no further troubic ~
was experienced on "B". battery or battery charger.
2:49 P.M. The plant computer failed. Subsequent investigation indicated the failure was due to low DC voltage fed from battery bus "A". ,
2:50 P.M. The Control Operator observed reactor . trip breaker "A" indication light was.out and the Shift Foreman was notified.
The_ bulb was changed with no s'uccess. Several other lights on'RTGB were observed to be out. The Shift Foreman'and Control Operator suspected instrument bus (AC) trouble.
I & C technician assistance was summoned:and Shift Foreman .
proceeded to. check out MCC-5 and MCC-6 and all instrument busses for failure.
2:5.1 P.M.. . Received reactor coolant pumps thermal barrier cooling water low flow alarm. -Outlet. isolation valve 735 (air /
. operated) closed on low DC control voltage. RTGB valve-f position indication also lost. .
- 2
- 55 P.M.- Received reactor - trip due to low voltage on' DC trip coils;
.on react'or trip breakers. Reactor trip initiated turbine trip. ;No battery charger alarms were received.
l' 2:56 P.M.~ Received generator lockout (one minuteLtime delay) due to-OCB. closed.and stop. valves closed.. A portion of the control -
. room lights were lost. 4KV~ bus 4 switched 'to start-up -
transformer. properly leaving 4KV bus 3 and '4 on start-up.
transformer. 4KV busses 1 and 2 were lost-because DC con-trol voltage on "A" battery was;too low to'close breaker s (_,,
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52/12 and put these busses on the start-up transformer.
"A" diesel started properly due to loss of E-1 bus voltage.
Diesel supply breaker 17B to E-1 bus did not close because of low DC control voltage from "A" battery.
The Shift Foreman and several other individuals while checking on 4KV voltage found no DC control voltage on several breakers.
The batteries were checked immediately and "A" battery was found with 60 volts and "0" amps. All breakers on "A" "A" battery battery bus were closed. The AC supply from MCC-5 to the charger was lost when 4KV busses 1 and 2 were lost.
It should be noted that the battery chargers are rated at 300 amps with a current limiting device set at approximately 375 amps. It has been reported that the normal DC load on the "A" bus is approximately 150 amps. Assuming a 350 amp load imposed by the DC cmcrgency oil pump, the load on the i
DC bus could have been as high as 500 amps. This would have ,
imposed a minimum discharge rate on the "A" battery of at 1 cast 125 and possibly as much as 200 amps. A 200 amp ~
discharge rate will lower battery voltage to 105V DC in approximately four hours assuming a fully charged battery initially.
'3:00 P.M. The "B" charging pump was lost when E-1 voltage was lost.
The "C" charging pump was started bnmediately to re-establish seals and charging flow. The seal leak-off temperature on reactor coolant pumps "A" and "C" rose sharply as indicated.
- A RCP Recorder Point No.1 - Seal leakoff 300 F.
Recorder Point No. 2 - Upper thrust 300 F.
Recorder Point No. 7 - Pump bearing is 280 F. ' q dB RCP Recorder Point No.15 - Pump bearing is 230 F.
- C RCP Recorder Point No. 17 - Seal leak'off 300 F.
Recorder Point No. 23 - Pump bearing 230 F.
"A" and "C" pumps tripped when 4KV b'usses 1 and 2 were lost.
The seal flow on "A" and "C" pumps decreased to zero. "B" pump continued to run with normal temperature and seal flow.
Charging flow was lost for less than one minute.
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The volume control tank had no level indicated. Operator switched to. refueling water storage tank for supply to re-establish volume control tank for supply to re-establish volume control tank level. Switched back to normal lineup after 30 inches indicated in volume control tank.
A safety injection signal was activated due to instrumentation power supply failure. Pressurizer icvel remained above 20*/.
and pressure above 2000 psig. All safety injection equipment except that from E-1 bus operated satisfactorily.
Operator observed turning gear oil pump and emergency DC oil pump lights we: e out.
3:12 P.M.- The turbine rolled to a stop approximately 17 minutes after the turbine trip. Condenser vacuum was maintained.. The AC turbine gear oil pump was not operable due to loss of MCC-5 power supply; i.e. , loss of 4KV bus 1.and inability of diesel , ,
breaker 17B to close. The DC emergency oil pump was not operable due to low voltage on "A" battery. ,
3:20 P.M. The battery bus. tie.was closed and "A" battery voltage immediately increased to 125 volts. Breaker 15B closed re-establishing voltage on E-1 from "A" diesel. The Control Operator closed breaker 52/12 and picked up 4KV busses 1 and 2 from the start-up transformer. The Control Operator're-established power to 480V bus 1 via station service trans '
former "A". The' turning gear ' oil pump started when E-1 power was're-established.- The generator oil lif t pump . started and the turning gear engaged attempting to roll the turbine. The' turbine would not turn and the turning--gear motor began smoking >
heavily. -The turning gear motor was manually tripped. . Unsuc-cessful attempts were made to roll the turbine manually.and with an air drive motor. . Oil was pouring from.the No. 5 turbine bearing. All attempts to roll the turbine were unsuc-
.cessful.
Condens'er vacuum and steam seals-vere maintained on'the unit' and steam dump continued to the' condenser.
3 Restoration of DC power provided f6r opening.of ' valve 735.-
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l to restore reactor coolant pump thermal barrier flow.'.
i 3525P.M. - Restored normal letdown from reactor. coolant system? -
[, - Approximately five -(5) minutes after restoring power to nErmal,
- - ' MCC-6 ~ tripped. Operator was unable to close breaker, j The'-
> control fuses were-replaced and the breaker then closed properly.. "
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3:30 P.M. Turning gear oil and lift pump were secured due to oil leakage from No. 5 turbine bearing.
With the reactor in a safe condition, assessment of the tur-bine damage commenced.
The incident was determined to have been initiated by the decrease l in "A" battery voltage to the point where components supplied by the "A" i DC bus could not function as designed. Several factors contributed to the loss of voltage on "A" DC bus and the failure to detect this decrease in .
voltage.
- 1. The DC emergency oil pump was operating from the "A" -- t DC bus. This resulted in an unanticipated discharge of the "A" battery. Due to personnel error, this pump l was left operating and not shutdown after the scheduled i two hour test, j l
Operating procedures and operator training are being reviewed to insure that unsatisfactory conditions *
. are corrected.
2 No alarm is provided to warn the Control Operator of low DC bus voltage. The installation cif suitable alarms '
is being investigated.
- 3. The AC oil pump is currently fed off of MCC-5. With the loss of E-1 voltage, MCC-5 is without a power supply.
'Ihe possibility of changing the AC oil pump power supply to MCC-6 is being investigated in order to provide a (
completely redundant back-up lubricating oil supply to the I turbine.
It is estimated that the unit will be returned to service by May 15, .n, 1971.
Yours ver trul ,
- f f E. ,E.~Ut1ey
-Manap,er Generation & System Op'erations NBB:dds cc:. Mr. J. A. Jones G 9
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