ML20090E205
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| ML20090E205 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 03/25/1974 |
| From: | Perkins T NIAGARA MOHAWK POWER CORP. |
| To: | |
| Shared Package | |
| ML20090E199 | List: |
| References | |
| AO-50-220-74-2, NUDOCS 8303140121 | |
| Download: ML20090E205 (1) | |
Similar Documents at Nine Mile Point | |
|---|---|
Category:ABNORMAL OCCURRENCE REPORTS (SEE ALSO LER & RO)
MONTHYEARML20090C4331975-12-29029 December 1975
[Table view]AO-75-09:on 751123-29,licensee Failed to Analyze Stack Cartridges Weekly.Technician Reinstructed ML20090C4551975-11-28028 November 1975 AO-75-032:on 751117,acid Leak Occurred in Makeup Demineralizer Acid Storage Tank.Caused by Partially Open Discharge Valve.Valve Repaired ML20090C4491975-11-26026 November 1975 AO-75-031:on 751114,both Radiation Monitors in Reactor Bldg Ventilation Duct Failed to Provide Transfer to Emergency Ventilation Sys at 5 M/H.Caused by Incorrect Adjustment Made Prior to Calibr ML20090D8901975-08-29029 August 1975 AO 50-220/75-23:on 750826,during Audit of Contractor Facility Used in Analyzing Milk Samples,Required Sensitivity Not Achieved.Caused by Inadequate Procedure.Contractor Informed That Milk Counting Time Must Increase ML20090E0411975-04-0202 April 1975 AO 50-220/75-05:on 750401,during Routine Surveillance Testing,Emergency Vent Sys Failed to Function When Sys Inlet Ventilation Valve Bv 202-36 Failed to Open.Caused by Broken Stem in Solenoid Valve.Solenoids Will Be Replaced ML20090E1581975-01-0606 January 1975 AO 50-220/74-17:on 741227,source Range Monitor 14 Declared Inoperable.Caused by Component Failure.Detector Replaced W/Spare ML20090E1611974-12-19019 December 1974 AO 50-220/74-16:on 741210,intermediate Range Monitor 12 Found Inoperable.Cause Apparently Due to Defect in Cable or Detection.Repair Will Be Conducted on Sys ML20090E1631974-12-17017 December 1974 AO 50-220/74-15:during Markup of Motor Generator 167, Operator Tripped Supply Breaker for Power Board.Caused by Operator Error.Operator Educated in Proper Procedures. Training Sessions for All Operators Conducted ML20090E1591974-12-10010 December 1974 Ao:On 741110,fuel Channel Deflections Indicated Increase in Core Bypass Flow Over Calculations Assumed in Original Design.Channels Will Be Replaced.Finger Springs Will Be Used to Control Leakage ML20090E1651974-11-27027 November 1974 AO 50-220/74-14:on 741120,during Mgt Review of Monthly Surveillance Tests,Station Batteries Found Not Tested at Specified Intervals.Caused by Misinterpretation of Requirements by Maint Foreman.Foreman Notified ML20090E1661974-09-20020 September 1974 AO 74-13:on 740918,during Routine Testing,Containment Spray Pump Found Inoperable.Caused by Foreign Object Restricting Suction Flow of Pump.Object Removed ML20090E1681974-08-28028 August 1974 AO 50-220/74-12:on 740824,during Surveillance Testing,One Barton Instrument Used in Drywell High Pressure Reactor Protection Sys Drifted High.Caused by Setpoint Drift. Switch Recalibr ML20090E1701974-08-21021 August 1974 AO 74-10:on 740817,during Routine Surveillance Testing, Barton Differential Pressure Instrument 1 B05C (Emergency Cooling High Flow) Tripped at Lower than Required Value. Caused by Setpoint Drift ML20090E1731974-07-0101 July 1974 AO 74-9:on 740628,during Restart,Reactor Protection Sys Relay RE-230 Failed.Caused by Open Relay Coil.Relay Replaced ML20090E1751974-06-0303 June 1974 AO 50-220/74-8:on 740531,setpoint on Barton Instruments Used in Drywell High Pressure Reactor Protection Sys Drifted Higher than Required.Barton Switch Recalibr ML20090E1771974-05-0303 May 1974 AO 50-220/74-7:on 740425,eddy Current Testing Evaluation Showed Two Control Rod Blades W/Possible Inverted Tubes. Caused by Mfg Deficiency.Two Control Blades Will Be Changed ML20090E1791974-04-29029 April 1974 AO 50-220/74-6:during Releak Testing,Msiv Leaked Excessively.Cause Unknown & Being Investigated.Valve Will Be Inspected ML20090E1801974-04-24024 April 1974 AO 74-5:on 740415,during Annual Refueling Shutdown Testing, Three High Temp Main Steam Line Tunnel Sensors Found to Actuate at Lower than Required Temp.Caused by Setpoint Drift on Sensor.Sensors Recalibr ML20090E1831974-04-11011 April 1974 AO 50-220/74-4:on 740402,during Refueling Outage Test,Low Condenser Vacuum Sensors Actuated Low Resulting in Reactor Scram.Caused by Switch Setpoint Drift.Sensor Switch Recalibr ML20090E1841974-04-0909 April 1974 AO 50-220/74-3:on 740402,both Inside MSIVs Failed to Meet Required Limit of 12.9 Std Cubic Ft Per Inch.Caused by Drift in Position Switch on Valve Controller.Valves Will Be Repaired & Retested ML20090E1871974-04-0202 April 1974 AO 50-220/74-3:on 740402,during Leak Testing,Both Inside MSIVs Exceeded Leakage Limit.Caused by Either Drifting Position Switch or Improper Seating of Disc.Investigation Continuing.Position Switch Will Be Readjusted ML20090E1941974-04-0101 April 1974 AO 50-220/74-2:on 740323,concentrator Steam Seeped Through Insulation Surrounding 12-inch Section of Pipe Leading from Side Arm Heater to Concentrator Bottom.Caused by Improper Installation.Pipe Will Be Replaced ML20090E2051974-03-25025 March 1974 AO 50-220/74-2:on 740323,during Routine Concentrator Steam Operation,Pipe Crack Found in Waste Concentrator Piping Leading from Side Arm Heater.Caused by Improper Installation.Pipe Section Will Be Replaced ML20090E2151974-03-0808 March 1974 AO 50-220/74-1:on 740225,during Routine Surveillance Testing,Core Spray Differential Pressure Instrument (Barton 288-4802,RV-30A) Actuated Low.Caused by Setpoint Drift. Instrument Will Be Modified ML20126F6041974-03-0404 March 1974 AO 50-220/74-1:on 740225,core Spray Differential Pressure Instrument RV-30A Found to Actuate Lower than Specified. Caused by Setpoint Drift.Barton Switch to Be Modified to Eliminate Drift ML20090E2311973-12-10010 December 1973 AO 73-12-1:on 731201,Magnetrol Switch 352624 in Scram Dump Vol Level Sys Failed.Caused by Oxidized Mercury in Switch Bulb.Bulb Replaced ML20090E2351973-12-0404 December 1973 AO 73-12-1:on 731201,during Surveillance Test,Magnetrol Switch 352624 in Scram Dump Vol Level Sys Failed to Operate. Caused by Oxidized Mercury in Bulb of Switch.Mercury Bulb Replaced ML20090E2931973-12-0303 December 1973 AO 73-11-29:on 731126,15 Control Rod Drives Failed to Insert to Position 00 Following Reactor Scram.Caused by Leakage Past Stop Piston Seals ML20090E3051973-11-30030 November 1973 AO 73-11-12:during Review of Spring 1973 Refueling Outage Tech Spec Update,Discrepancy Noted in Pressure Setpoint Trip of Recirculation Pumps.Caused by Design Error.Design Will Be Changed ML20090E3131973-11-28028 November 1973 AO 73-11-20:on 731120,during Routine startup,11 Control Rod Drives Failed to Insert to Position 00 Following High Flux Scram.Caused by Damaged Stop Piston Seals Resulting in Excessive Leakage.Control Rods Will Be Overhauled ML20083Q8111973-11-28028 November 1973 AO 73-11-17:on 731117,during Maint Work,Facility Experienced Loss of Offsite Power.Caused by Electrician Bumping 50FDS/SI Seal in Relay.Electricians Cautioned ML20083Q8061973-11-21021 November 1973 AO 73-11-17:on 731117,relay 945 de-energized,tripping Only 115-kV Line,Thus Leaving Plant W/O Offsite Power.Caused by Electrician Accidentally Bumping Relay.Power Restored in 10 ML20083Q8181973-11-19019 November 1973 AO 73-11-10:on 731110,reactor low-low Water Level Switch Setting Found to Actuate Above Normal Setpoint.Caused by Setpoint Drift.Switch Recalibr ML20083Q8151973-11-16016 November 1973 AO 73-11-13:on 731113,one Reserve Power Transformer Removed from Svc.Caused by Ground in Wire Supplying Duct Heater Across One Phase of Secondary Transformer.Wire Removed & Transformer Returned to Svc ML20083Q8221973-11-13013 November 1973 AO 73-11-10:on 731110,reactor low-low Water Level Switch Setting Actuated Above Normal Setpoint.Caused by Setpoint Drift on Yarway RE02D Sensor.Sensor Recalibr 1975-08-29 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 ML20217K4631999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Nine Mile Point, Unit 1.With 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 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 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 ML20210U4591999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Nine Mile Point, Unit 1.With 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 ML20210B9081999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Nine Mile Point Unit 1.With ML20209F8811999-06-0808 June 1999 Rev 1 to NMP Unit 1 COLR for Cycle 14 ML20207G2261999-06-0707 June 1999 SER Accepting Proposed Mod to Each of Four Core Shroud Stabilizers for Implementation During Current 1999 Refueling Outage at Plant,Unit 1 ML20196E2111999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Nmp,Unit 1.With ML20207B0241999-05-18018 May 1999 Safety Evaluation of Topical Rept TR-107285, BWR Vessel & Intervals Project,Bwr Top Guide Insp & Flaw Evaluation Guidelines (BWRVIP-26), Dtd December 1996.Rept Acceptable ML20206U5351999-05-17017 May 1999 SER Accepting GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Plant, Units 1 & 2 ML20196L2301999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Nmp,Unit 1.With ML20205L0541999-04-0101 April 1999 Nonproprietary Replacement Pages to HI-91738,consisting of Section 5.0, Thermal-Hydraulic Analysis ML20205S5701999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for NMP Unit 1.With ML20207M9231999-03-12012 March 1999 Amended Part 21 Rept Re Cooper-Bessemer Ksv EDG Power Piston Failure.Total of 198 or More Pistons Have Been Measured at Seven Different Sites.All Potentially Defective Pistons Have Been Removed from Svc Based on Encl Results 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 ML20204C9971999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Nine Mile Point,Unit 1.With ML20207E9311999-02-26026 February 1999 Part 21 Rept Re Sprague Model TE1302 Aluminum Electrolytic Capacitors with Date Code of 9322H.Caused by Aluminum Electrolytic Capacitors.Affected Capacitors Replaced ML17059C5501999-01-31031 January 1999 Rev 0 to MPR-1966(NP), NMP Unit 1 Core Shroud Vertical Weld Repair Design Rept. ML20199M0891999-01-22022 January 1999 Part 21 Rept Re Failure of Square Root Converters.Caused by Failed Aluminum Electrolytic Capacitory Spargue Electric Co (Model Number TE1302 with Mfg Date Code 9322H).Sent Square Root Converters Back to Mfg,Barker Microfarads,Inc ML20199K9331998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Nine Mile Point Nuclear Station,Unit 1.With ML20210R8441998-12-31031 December 1998 1998 Annual Rept for Energy East 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 ML20198D9361998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Nine Mile Point,Unit 1.With ML20155E2001998-11-0202 November 1998 Safety Evaluation Approving NMP 980227 Request for Extension of Reinspection Interval for Core Shroud Vertical Welds at NMP1 from 10,600 Hours to 14,500 Hours of Hot Operation ML20195J4141998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Nine Mile Point Nuclear Station,Unit 1.With ML20154D8401998-10-0505 October 1998 Safety Evaluation Accepting Proposed Changes Related to PT Limits in Plant,Unit 1 TSs ML20154P1821998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Nine Mile Point Nuclear Station,Unit 1.With ML20153B2001998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Nmpns,Unit 1.With ML20237C6351998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Nine Mile Point Nuclear Station,Unit 1 ML20236T5911998-07-20020 July 1998 LER 98-S01-00:on 980618,security Force Member Left Nine Mile Point,Unit 2 Vehicle Gate Unattended Without Ensuring,Gate Alarm Had Been Reactivated.Caused by Inadequate Work Practice.Vehicle Gate Alarm Was Activated ML18040A3491998-07-0202 July 1998 LER 98-017-00:on 980602,control Room Ventilation Sys Was Declared Inoperable.Caused by Original Design Deficiency. Mod Designed,Tested & Implemented Prior to Startup from RF06 to Correct Design deficiency.W/980702 Ltr ML20236Q1701998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Nine Mile Point Nuclear Station,Unit 1 ML17059C1011998-06-24024 June 1998 LER 98-014-00:on 980525,noted Differences Between Actual Valve Weights & Weights Shown on Engineering Drawings.Caused by Vendor Failing to Provide Accurate Valve Weights.Revised Valve Drawings & Associated Calculation,Per 10CFR21 ML20151P1751998-06-16016 June 1998 Rev 0 to SIR-98-067, Evaluation of NMP Unit 2 Feedwater Nozzle-to-Safe End Weld Butter Indication (Weld 2RPV-KB20, N4D) ML18040A3451998-06-0404 June 1998 LER 98-004-01:on 980302,TS Required LSFT of Level 8 Trip of Main Turbine Was Missed.Caused by Knowledge Deficiency of EHC Sys.Revised Applicable LSFT Procedures Prior to Refueling Outage 6.W/980604 Ltr ML20249B4971998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Nine Mile Point Nuclear Station,Unit 1 ML20248F3531998-05-21021 May 1998 Part 21 Rept Re Electronic Equipment Repaired or Reworked by Integrated Resources,Inc from Approx 930101-980501.Caused by 1 Capacitor in Each Unit Being Installed W/Reverse Polarity. Policy of Second Checking All Capacitors Is Being Adopted ML20198B4991998-05-15015 May 1998 Non-proprietary Replacement Pages for Attachment F to Which Proposed to Change TS 5.5, Storage of Unirradiated & Sf ML20247R1141998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Nine Mile Point Nuclear Station,Unit 1 ML20217B0621998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Nine Mile Point Nuclear Station,Unit 1 ML17059C1681998-03-19019 March 1998 Revised Niagara Mohawk Powerchoice Settlement Document for NMPC PSC Case Numbers 94-E-0098 & 94-E-0099, Vols 1 & 2 ML20217F4341998-03-19019 March 1998 SER Related to Proposed Restructuring New York State Electric & Gas Corp,Nine Mile Point Nuclear Station,Unit 2 ML17059B9051998-02-28028 February 1998 NMP Unit 1 Boat Samples Analyses Part Iii:Tension Tests, RDD:98:55863-004-000:01 1999-09-30 |
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. - ?n0:!: T.J. PEREINS t E !!ILE l'0 INT NU"LPAR STATION
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PERSU/JIT M TECllNICAL $1'ECIFICATION 1.13d WE ARE REPORTING AS AN ABN0FPAL OCCURhENCE CPJscr.ING IN HIE WASTE CONCENTRATOR PIPING FROM TliE SIDE APJ!
IIEATER.
ON }!ARCl{ 23, 1974 DURING R0trTINE OPEPATION OF Tile CONCENTRATOR A SLlGif PUFF OF STEA!! KAS SE$N W BE E)(1TTED PRO:: A SECTION OP 12" PIPE ' LEADING FRO't SIDE AISt llEATER T0 t!E t0110M OF UIE CONCENTRATVR, FOLLOWING SIPJTD0hH OF 1{E CONCENTPATOR /J;D REMOVAL OF ttE INSU!ATION SURROUNDING bib PIPE, SEVERAL CRACKS WERE REVEALED IN (/J"D NtAR ONE WELD. .
ele CAUSE OF Ti!E FAILURE IS CURRENTLY UNDER INVESTIGATION AND WOULD OF l COURSE DICTATE WE CORRECTIVE ACTION. NO !!AZARD WAS PRESEl7ED TO Tile GENERAL PUBLIC AS A REf'lLT OF Ulls FAILURE.,
T,J. PERKINS STATION SUPERINTENDENT NINE HILE POINT NUCLPAR STATION e
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