ML20209D029
ML20209D029 | |
Person / Time | |
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Site: | Nine Mile Point ![]() |
Issue date: | 07/02/1999 |
From: | Conway J NIAGARA MOHAWK POWER CORP. |
To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
References | |
NMP1L-1447, NUDOCS 9907130012 | |
Download: ML20209D029 (2) | |
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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARML20216J9251999-09-30030 September 1999
[Table view]Suppl to Special Rept:On 990621,11 Containment Hydrogen Monitoring Sys Chart Recorder Was Indicating Below Normal Operating Range.Caused by Excessive Wear on Valve Body & Discs of Bypass Pump.Sample Pump Replaced ML20212F7301999-09-21021 September 1999 Special Rept:On 990907,CR Operators Declared 12 Containment Hydrogen Monitoring Sys Inoperable for Planned Maint.Cause of Low Flow Condition Was Determined to Be Foreign Matl. Replaced Sample Pump Valve Discs ML20212B9081999-09-14014 September 1999 Special Rept:On 990901, 12 Containment Hydrogen Monitoring Sys Was Declared Inoperable for Planned Maint.Caused by Planned Maint Being Performed as Corrective Action.Check Valves with O Rings Were Replaced ML20209D0291999-07-0202 July 1999 Special Rept:On 990621,operator Identified That Number 11 Hydrogen Monitoring Sys (Hms) Chart Recorder Was Indicating Below Normal Operating Range.Cause Indeterminate.Licensee Will Complete Troubleshooting of Subject Hms by 990709 ML20207G2671999-03-0101 March 1999 Special Rept:On 990315,Nine Mile Point,Unit 1 Declared Number 12 Containment Hydrogen Monitoring Sys Inoperable. Caused by Degraded Encapsulated Reed Switch within Flow Switch FS-201.2-1495.Technicians Replaced Flow Switch ML20206P2391998-12-31031 December 1998 Special Rept:On 981222,operators Removed non-TS Channel 12 Drywell Pressure Recorder & Associated TS Pressure Indicator from Svc.Caused by Intermittent Measuring Cable Connection in non-TS Recorder Circuitry.Replaced Cable ML20206P2421998-12-30030 December 1998 Special Rept:On 981219,number 12 Hydrogen Monitoring Sys (Hms) Was Declared Inoperable When Operators Closed Valve 201.2-601.Caused by Indeterminate Failure of Valve 201.2-71. Supplemental Rept Will Be Submitted After Valve Is Repaired ML20198M3571998-12-23023 December 1998 Special Rept:On 981210,operators Declared Number 11 Inoperable,Due to Failure of CR Chart Recorder.Caused by Inverter Board in Power Supply Circuitry of Recorder Due to Component Aging.Maint Personnel Replaced Failed Inverter ML18040A3121997-06-23023 June 1997 Special Rept:On 970523,Division II EDG Output Breaker Failed to Close When Given Close Demand for Surveillance Testing & Was Not Reported as Required by TS 4.8.1.1.3.Caused by Degraded Subcomponent.Replaced Division II EDG Breaker ML20078A9311994-08-31031 August 1994 Special Rept:On 940818,inoperability of Containment Hydrogen Monitoring Unit 11 Occurred.Caused by Failure of K4 Relay in Auto Calibr Unit.Sticking Relay Released & Exercised ML17059A3761994-07-25025 July 1994 Special Rept:On 940710,containment Hydrogen Monitoring Unit 11 Inoperable.Caused by Air Regulator for Valve Operator Set at 73 Psig Air Pressure.Regulator Reset to 29 Psig ML18040A0851993-05-20020 May 1993 Special Rept:On 930504,reactor Bldg Ventilation Gaseous Effluent Monitoring Sys Declared Inoperable to Perform Calibr.Caused by Problem in Identifying 81 Kev Xe-133 peak.Analog-to-digital Converter Adjusted ML17056C0011992-09-14014 September 1992 Special Rept:On 920826,alarm Annunicated for Vent Effluent Monitor & Lightning Strike Occurred Near Plant Main Stack. Caused by Failed Allen Bradley Analog Input Power Supply & Broken Sample Pump Coupling.Work Request Issued ML18038A7111992-09-14014 September 1992 Special Rept:On 920813,DG Accelerated to Approximately 300 Rpm & Tripped on High Main & Connecting Rod Bearing Temperature. Caused by Clogged or Dirty Check Valve in Pneumatic Trip Sys.Valve Removed & Inspected ML17056B0541990-10-15015 October 1990 Special Rept:On 900926,radwaste/reactor Bldg Vent Noble Gas Activity Monitor Declared Inoperable ML18038A7631989-10-10010 October 1989 Special Rept:On 890829,seismic Monitoring Instrumentation Declared Inoperable Over 30 Days Due to Inability to Successfully Complete Calibr Procedure.Equipment Vendor Contacted to Discuss Resolution of Problems ML18038A4421989-02-0606 February 1989 Special Rept:On 881227,inoperability of Seismic Monitoring Instrumentation Occurred.Instrument Struck by Personnel Installing Insulation on Pipe or Performing Sys Walkdowns. Problem Rept Written on 890112 for Indications on Plates ML18038A4321989-01-16016 January 1989 Special Rept:On 881208,seismic Monitoring Instrumentation Declared Inoperable.Cause Unknown.Surveillance Interval Will Be Started as Soon as New Record Plates Can Be Obtained & Installed ML20211P6331986-11-24024 November 1986 Special Rept:On 861110,diesel Fire Pump Taken Out of Svc to Troubleshoot Lube Oil Pressure Switch.Sys Cross Tied to Unit 2 Fire Suppression Sys as Back Up.On 861026 & 28,occurrence Repts Written for Inoperable Fire Door & Pump,Respectively ML20211F4441986-10-17017 October 1986 Special Rept:On 860903 & 04,some Fire Barrier Penetrations Declared Nonfunctional & Fire Door D-107 Rubbing Against Side Jamb.Measures to Maintain Compliance W/Tech Spec Section 3.6.10.1 Implemented ML20205B3171986-07-18018 July 1986 Special Rept:On 860606,Fire Door 137 Breached to Perform Mod to Door.On 860612,fire Detection Sys DA4116W Removed from Svc to Support Welding Activities in Area.Door & Sys Returned to Svc on 860624 & 26,respectively ML20206F8311986-06-0505 June 1986 Special Rept:On 860423,29,0502,05,06,09 & 14 Certain Fire Barrier,Detection & Suppression Sys Out of Svc for More than 14 Days Until Work Associated W/Refueling Outage Completed. Continuous Fire Watches Established ML20211E2471986-05-19019 May 1986 Special Rept:On 860407,09,11,12,14,15,17,18 & 22,certain Fire Barrier,Detection & Suppression Sys out-of-svc for More than 14 Days Until Work Associated W/Refueling Outage Completed.Protective Measures Will Be Continued ML20198J7671986-05-0909 May 1986 Ro:On 860329,fire Detection Sys in East End of Turbine Bldg Taken Out of Svc to Support Welding Activities for Piping Mods.Fire Watch Patrol Will Continue Until Sys Operable ML20197D3151986-04-30030 April 1986 Special Rept:On 860317,26,28,31 & 0402,certain Fire Barrier, Detection & Suppression Sys Out of Svc for More than 14 Days Until Work Associated W/Refueling Outage Completed.Fire Watch Patrols Initiated ML20137Q0091985-12-13013 December 1985 Suppl to Special Rept:On 851119,Beckman Instruments,Inc Channel 11 hydrogen-oxygen Monitoring Unit Declared Inoperable.Caused by Excess Condensation Due to Insufficient Suction of Worn Sample Pump.Pump Replaced ML20139A2941985-11-22022 November 1985 Special Rept:On 851109,Channel 11 hydrogen-oxygen Monitoring Unit (Beckman Instruments,Inc) Declared Inoperable Due to Loss of Sample Flow.Caused by Reboiler Subject to Excessive Condensation.Next Rept by 851213 ML20138A0201985-11-13013 November 1985 Special Rept:On 851031,while out-of-svc for Trouble Shooting,Channel 11 Containment high-range Radiation Monitor Tripped Upscale.Caused by Spurious Electrical Spike Induced by Welding Activities.Trip Setpoint Readjusted ML20138E1231985-11-0505 November 1985 Special Rept:On 851022,ground Fault Inadvertently Induced on Station Battery Board 11.Caused by Removal of Electric Fire Pump Svc to Perform Mod.Fault Cleared & Fire Pumps Returned to Svc ML20137V0101985-09-0909 September 1985 Special Rept:On 850808,fire Barrier Penetrations I-849 & I-2310 Declared Inoperable Due to Maint Mods on Floor Drains.Fire Watch Patrols Performed Hourly Insps Until Completion of Mods on 850830 ML20132E1821985-06-25025 June 1985 Special Rept:On 850611,number of Operable Channels in Svc Less than Required by Tech Specs.Caused by Removal of Primary Containment hydrogen-oxygen Monitor to Replace Faulty Stepper Switch.Sys Returned to Operable Status ML20127B2941985-06-0505 June 1985 Special Rept:On 850508,ventilation Duct Fire Penetration in Reactor Bldg Track Bay Wall Found Unequipped W/Fire Damper, Per Tech Spec 3.6.10.1.Hourly Fire Watch Patrols Established.Reevaluating Fire Design ML20116M1131985-04-15015 April 1985 Special Rept:On 850314,ventilation Duct Fire Penetrations Discovered Not Equipped W/Fire Dampers & Declared Inoperable.Fire Watches Established.Penetrations Will Be Included in Review of Fire Hazards Analysis ML20114D5121985-01-23023 January 1985 Nonroutine Environ Operating Rept:On 841226,data Indicated Sensitivity Spec Not Met for Radiological Analysis of Environ Fish Samples,Per Reg Guide 4.8 & NUREG-0473.Caused by Short half-lives of Radionuclides ML20098G5601984-09-21021 September 1984 Nonroutine Environ Operating Rept, Re Fish Samples Showing Radionuclides W/Sensitivity of Greater than 80 pCi/kg-dry When Analyzed by Gamma Spectral Analysis ML20090E6511984-06-29029 June 1984 Nonroutine Radiological Environ Operating Rept:On 840423, Shoreline Sediment Samples Showed Concentrations of Cs-137 & Sr-90 in Excess of 10 Times Applicable Control Sample.Caused by Past Liquid Effluent Discharges at Site ML20090L0841984-05-14014 May 1984 Ro:On 840414,accuracy of Temp Difference Between Nominal Meteorological Tower Elevations of 27 & 200 Ft Found Inconsistent.Caused by Electronic Drift of 200-ft Elevation Delta Temp Translator Card.Card Recalibr 05000220/LER-1983-044, Special Rept of Actions Taken to Assess Current Status of Fire Barrier Penetrations & to Assure Future Integrity of Barriers Following Improper Sealing of One Penetration Reported in LER 83-441984-04-24024 April 1984 Special Rept of Actions Taken to Assess Current Status of Fire Barrier Penetrations & to Assure Future Integrity of Barriers Following Improper Sealing of One Penetration Reported in LER 83-44 ML20083F5151983-12-0707 December 1983 Nonroutine Rept:One Aug 1983 Cladophora (Algae) Sample Showed Co-60 Concentration Slightly Greater than 10 Times Control Result.Caused by Liquid Effluents at Site.No Corrective Actions Required ML20078K6321983-09-26026 September 1983 Updated RO 83-23:on 830809,circuit Breaker for Core Spray Pump Suction Valve 81-21 Taken Out of Svc for Preventive Maint While Leaving Valve in Open Position.Event Did Not Violate Tech Spec 3.3.4.b as Previously Reported ML20072R1541983-03-16016 March 1983 Telecopy Message of RO 83-05:on 830315,cleanup Sludge Tank Vent Overflowed Into Reactor Bldg Exhaust Ventilation Sys Causing Emergency Ventilation Sys to Initiate. Decontamination of Exhaust Ductwork in Progress ML20032C7661981-10-30030 October 1981 Ro:On 810708-09,controlled Discharge of Liquid Radwaste Into Lake Ontario Occurred.Caused by Influx of Drain Waters Into Radwaste Facility & Poor Performance of Radwaste Demineralizer.Two Larger Demineralizers Procured ML20009E4371981-07-10010 July 1981 RO 81-33:on 810709,after Start of Shaft Driven Feedwater Pump,Injection of High Conductivity Water in Dead Leg Caused Reactor Water Conductivity & Chloride Excursion.Caused by Incomplete Flush of Feedwater Sys ML18037A2391980-02-0505 February 1980 RO-80-05:on 800203,triple Low Level Setpoint Required to Be Raised 20 Inches to Account for Differences in Indicated Vs Actual Water Level.Caused by Large Increase in Drywell Temp During Loca.Setpoint Adjusted Upward ML20148G9911978-10-20020 October 1978 RO 78-35:on 781028 During Routine Surveillance Test All 8 Main Stream High Flow Transmitters Were Set Less Conservatively than Req Due to Test Pressure Gauge Out of Calibr ML20084B5191976-10-14014 October 1976 RO 76-28:during Mgt Review of Existing Plant Design, Containment Spray Pump Control Switch Found to Preclude Sister Pump from Automatic Starting,If Control Switch in Lockout.Cause Not Stated.Operating Procedure OP-19 Revised ML20090E1671974-10-31031 October 1974 Ro:On 741001,during Containment Spray Raw Water Pump Testing,Flow Measurement Was Not Adequate to Determine Specified Performance.Caused by Design Error.Flowthrough Pumps Will Be Adjusted ML20090D3321973-09-0707 September 1973 Ro:On 730829,four Fuel Bundle Segments Were Operating Slightly in Excess of Allowable Average Planar Linear Heat Generation Rate.Adjustments Made in Power Distribution to Obtain Optimum Power Distribution & Output from Reactor ML20090D3901973-09-0707 September 1973 Ro:On 730626,stack Gas Monitor Sample Pump Tripped & Could Not Be Restarted.Caused by Bound Motor.Leakage Detected in Reservoir Jar.Sample Pump Piped Up.Third Sampling Pump Will Be Used as Spare ML20090D3361973-08-30030 August 1973 Ro:On 730829,fuel Bundle Segments Found Operating Slightly in Excess of Allowable Average Planar Linear Heat Generation Rate.Core Thermal Power Reduced Using Reactor Recirculation Flow 1999-09-30 Category:TEXT-SAFETY REPORT MONTHYEARML20217G2161999-10-15015 October 1999
[Table view]Errata Pages 2 & 3 for Safety Evaluation Supporting Amend 168 Issued to FOL DPR-63 Issued on 990921.New Pages Change Description of Flow Control Trip Ref Cards to Be Consistent with Application for Amend ML20216J9251999-09-30030 September 1999 Suppl to Special Rept:On 990621,11 Containment Hydrogen Monitoring Sys Chart Recorder Was Indicating Below Normal Operating Range.Caused by Excessive Wear on Valve Body & Discs of Bypass Pump.Sample Pump Replaced ML20217K4631999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Nine Mile Point, Unit 1.With ML20212F7301999-09-21021 September 1999 Special Rept:On 990907,CR Operators Declared 12 Containment Hydrogen Monitoring Sys Inoperable for Planned Maint.Cause of Low Flow Condition Was Determined to Be Foreign Matl. Replaced Sample Pump Valve Discs ML20212D3611999-09-21021 September 1999 Safety Evaluation Supporting Amend 168 to License DPR-63 ML20212B9081999-09-14014 September 1999 Special Rept:On 990901, 12 Containment Hydrogen Monitoring Sys Was Declared Inoperable for Planned Maint.Caused by Planned Maint Being Performed as Corrective Action.Check Valves with O Rings Were Replaced ML20212C4601999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Nine Mile Point Nuclear Station,Unit 1.With ML20216F5141999-08-31031 August 1999 Rept on Status of Public Petitions Under 10CFR2.206 05000220/LER-1999-005-01, :on 990801,RT During Plant Startup on IRM Spiking Was Noted.Caused by electro-magnetic Interference. Inspected,Cleaned,Burnished & Tested IRM 11 Range Switch. with1999-08-30030 August 1999
ML17059C3941998-12-0303 December 1998 Safety Evaluation Supporting Amend 84 to License NPF-69 ML20198D9361998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Nine Mile Point,Unit 1.With 1999-09-30 |
Text
NiagarahMohawk'
~
John T. Conway Phone: 315.349.4213 Vice President Fax: 315.349.2605 Nuclear Generation July 2,199)
NMPIL 1447 1
U, S. Nuclear Regulatory Commission
. Attn: Document Control Desk Washington, DC 20555 RE:
Nine Mile Point Unit 1 j
Docket No. 50-220 l
Subject:
Special Report Gentlemen:
In accordance with Nine Mile Point Unit 1 (NMPI) Technical Specification Table 3.6.11-1,
" Accident Monitoring Instrumentation," Action Statement 4.a., Niagara Mohawk Power Corporation (NMPC) is submitting the following Special Report concerning the inoperability of the #11 Containment Hydrogen Monitoring System (HMS).
Description of Event On June 21,1999, at 0441 hours0.0051 days <br />0.123 hours <br />7.291667e-4 weeks <br />1.678005e-4 months <br />, with the reactor mode switch in the "RUN" position during normal operations, NMP1 Operators identified that the #11 HMS chart recorder was indicating below normal operatir.g range. Operators investigaMand found that the sample pump appeared to be operating improperly, and at 05% hours on June 21,1999, declared the #11 HMS inoperable. The #11 HMS remains out of service for troubleshooting.
The #12 HMS was placed in service during :nnrtup from Refueling Outage 15, and remains in D
service.
nmcr of Event v
The cause of the event is unknown and troubleshooting is on-going.
h,b 9907130012 990702 PDR ADOCK 05000220 S
PDR 120054 Nine Mile Point Nuclear Station R0. Box 63. Lycorning, New York 13093 0063
- www.nimo com j
F Page 2 l
{
Cornedu Actions NMPC is currently troubleshooting the #11 HMS. The work is scheduled to be completed by July 9,1999.
NMPC will submit a supplement to this report when the #11 HMS has been returned to service and the cause of the event has been determined.
Very truly youts, I.
ohn T. Conway Vice President Nu r Generation -
JTC/KLUmlh xc:
Regional Administrator, Region I Mr. Gordon K. Hunegs, Senior Resident Inspector Records Management a - - -
..