|
---|
Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO
MONTHYEARML18040A3121997-06-23023 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 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 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 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 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 1997-06-23
[Table view] Category:LER)
MONTHYEARML18040A3121997-06-23023 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 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 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 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 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 1997-06-23
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217G2161999-10-15015 October 1999 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
- on 990801,RT During Plant Startup on IRM Spiking Was Noted.Caused by electro-magnetic Interference. Inspected,Cleaned,Burnished & Tested IRM 11 Range Switch. with
05000220/LER-1999-004-01, :on 990723,reactor Scram Was Noted.Caused by Mechanical Pressure Regulator Suppressor Valve Failure. Cleaned Pressure Suppressor Valve & Provided Guidance for Valve Disassembly & Insp.With1999-08-23023 August 1999
- on 990723,reactor Scram Was Noted.Caused by Mechanical Pressure Regulator Suppressor Valve Failure. Cleaned Pressure Suppressor Valve & Provided Guidance for Valve Disassembly & Insp.With
ML20210U4591999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Nine Mile Point, Unit 1.With ML20210H7851999-07-29029 July 1999 Corrected SER Supporting Amend 167 to License DPR-63, Replacing Pages 4,5 & 11.New Pages Correct SE to Be Consistent with Application for Amend 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 05000220/LER-1999-003-01, :on 990320,noted That Plant Operated with Average Planear LHGR Exceeding TS Limits.Caused by Inadequate Interface Design Between Color Graphics Terminal & 3-D Monicore Sys.Lowered Reactor Power.With1999-04-22022 April 1999
- on 990320,noted That Plant Operated with Average Planear LHGR Exceeding TS Limits.Caused by Inadequate Interface Design Between Color Graphics Terminal & 3-D Monicore Sys.Lowered Reactor Power.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 05000220/LER-1999-002, :on 990217,noted That ASME Code Preservice Exams Had Not Been Performed on Emergency Condensers.Caused by Misinterpretation of ASME Code Requirements.Required Preservice Exams Were Completed on 990218.With1999-03-19019 March 1999
- on 990217,noted That ASME Code Preservice Exams Had Not Been Performed on Emergency Condensers.Caused by Misinterpretation of ASME Code Requirements.Required Preservice Exams Were Completed on 990218.With
ML20204C8001999-03-16016 March 1999 Safety Evaluation Supporting Amend 165 to License DPR-63 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 05000220/LER-1999-001, :on 990125,noted That Plant Operated Outside Design Basis Due to Failure to Revise Satellite pre-fire Plans.Satellite Copies of pre-fire Plans Were Revised & Procedure Re pre-fire Plans Was Revised.With1999-02-24024 February 1999
- on 990125,noted That Plant Operated Outside Design Basis Due to Failure to Revise Satellite pre-fire Plans.Satellite Copies of pre-fire Plans Were Revised & Procedure Re pre-fire Plans Was Revised.With
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 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 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 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 05000220/LER-1998-019-01, :on 981110,ASME Section XI ISI Was Missed. Caused by Cognitive Error Involving Technical Inaccuracies. Util Will Revise Second 10-yr Interval ISI Program Plan to Incorporate Visual Exam Requirements.With1998-12-10010 December 1998
- on 981110,ASME Section XI ISI Was Missed. Caused by Cognitive Error Involving Technical Inaccuracies. Util Will Revise Second 10-yr Interval ISI Program Plan to Incorporate Visual Exam Requirements.With
ML20198D9361998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Nine Mile Point,Unit 1.With 05000220/LER-1998-018-01, :on 981006,determined That Actual Total Crds Flow Exceeded Indicated Crds Total Flow.Caused by Degraded Crds Filter Bypass Valve.Plant Has Been Limited to 1847 Mwt & Shift Check Procedure Was Revised.With1998-11-0505 November 1998
- on 981006,determined That Actual Total Crds Flow Exceeded Indicated Crds Total Flow.Caused by Degraded Crds Filter Bypass Valve.Plant Has Been Limited to 1847 Mwt & Shift Check Procedure Was Revised.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 05000220/LER-1998-017-01, :on 980902,breach of Primary Containment Was Noted.Caused by Personnel Error in 1994.Immediately Upon Discovery,Asss Directed That CS Heat Exchanger Vent Valves Be Closed.With1998-10-0202 October 1998
- on 980902,breach of Primary Containment Was Noted.Caused by Personnel Error in 1994.Immediately Upon Discovery,Asss Directed That CS Heat Exchanger Vent Valves Be Closed.With
ML20154P1821998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Nine Mile Point Nuclear Station,Unit 1.With 05000220/LER-1998-016-01, :on 980820,determined That CS Pump Motor Bearing Cooling Flow Outside Design Basis Requirement.Caused by Error in Maint Reassembly That Crimped Cooling Coil.Cs Pump 122 Repaired.With1998-09-21021 September 1998
- on 980820,determined That CS Pump Motor Bearing Cooling Flow Outside Design Basis Requirement.Caused by Error in Maint Reassembly That Crimped Cooling Coil.Cs Pump 122 Repaired.With
05000220/LER-1998-015-01, :on 980804,breach of Primary Containment Was Noted.Caused by Personnel Error.Closed Heat Exchanger Vent Valves & Restored Torus Pressure.With1998-09-0303 September 1998
- on 980804,breach of Primary Containment Was Noted.Caused by Personnel Error.Closed Heat Exchanger Vent Valves & Restored Torus Pressure.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 1999-09-30
[Table view] |
Text
gccp~~TED DlKBUTION 'EMONS'lTION SYSI'EM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:8910190145 DOC.DATE: 89/10/10 NOTARIZED: NO , DOCKET FACIL:50-410 Nine Mile Point Nuclear Station, Unit 2, Niagara Moha 05000410 AUTH. NAME AUTHOR AFFILIATION WILLIS,J.L. Niagara Mohawk Power Corp.
RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
Special rept:on 890829,inoperability of seismic monitoring S UBJECT:
instrumentation.
DISTRIBUTION CODE: IE22D COPIES RECEIVED:LTR TITLE: 50.73/50.9 Licensee Event, Report (LER), Incident Rpt, etc.
i ENCL J SIZE:
NOTES:'ECIPIENT RECIPIENT COPIES COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD1-1 LA 1 1 PD1-1 PD 1 1 SLOSSON,M 1 1 BENEDICT,R 1 1 INTERNAL: ACRS MICHELSON 1 1 ACRS MOELLER 2 2 ACRS WYLIE 1 1 AEOD/DOA 1 1 AEOD/DS P/TPAB 1 1 AEOD/ROAB/DSP 2 2 DEDRO 1 1 NRR/DEST/ESB 8D 1 1 NRR/DEST/ICSB 7 1 1 NRR/DEST/MEB 9H 1 1 NRR/DEST/MTB 9H 1 1 NRR/DEST/PSB 8D 1 1 NRR/DEST/RSB 8E 1 1 NRR/DEST/SGB 8D 1 1 NRR/DLPQ/HFB 10 1 1 NRR/DLPQ/PEB 10 1 1 NRR/DOEA/EAB 11 1 1 NR~RDRE~RPB 10 2 2 NUDOCS-ABSTRACT 1 1 G FILE 02 1 1 RES/DSIR/EIB 1 1 CH1 FILE 01 1 1 EXTERNAL EG&G WILLIAMSE S 4 4 L ST LOBBY WARD 1 1 LPDR 1 1 NRC PDR 1 1 NSIC MAYS,G 1 1 NSIC MURPHY,G.A 1 1 NUDOCS FULL TXT 1 1 NOTE 'IO ALL RIDS" RZCZPZHQS'URSE HELP US Io REKKZ %RKRf CXNZACZ GHE DtXXMWZ CXNZROL DESKi RXM P1-37 (EXP. 20079) %0 ELQMRTH KRR MHE PKN DISTRIBUTICN LISTS FOR DOCQMEÃIS KRJ DCSERT NEEDt TOTAL NUMBER OF COPIES REQUIRED: LTTR 39 ENCL 39
NMP 56851 NINE MILE POINT NUCLEAR STATION/P.O. BOX 32. LYCOMING, N.Y. 13093/TELEPHONE (315) 343-2110 October >0, 1989 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 RE: Docket No. 50-410 SPECIAL REPORT Gentlemen:
In accordance with Nine Mile Point Unit 2 (NMP2) Technical Specification (TS) 3.3.7.2 ACTION Statement a., we are submitting the following Special Report concerning the inoperability of the Seismic Monitoring Instrumentation (specifically, the Triaxial Response Spectrum Recorder, Primary Containment Residual Heat Removal Piping Penetration Elevation 294'6").
On August 28, 1989 at 1020 hours0.0118 days <br />0.283 hours <br />0.00169 weeks <br />3.8811e-4 months <br />, with the reactor mode switch in "RUN",
the Triaxial Response Spectrum Recorder (2ERS-RSR3B) was declared 'inoperable.
It was found inoperable during the performance of procedure N2-ISP-ERS-R104 (Operating Cycle Calibration of Seismic Monitoring Response Spectium Recorders Instrument Channels). The East/West Horizontal (E/W), and North/South Horizontal (N/S) permanent record plates were found to have indications that were determined not to be a result of seismic activities. Additionally, certain sensor/accelerometers (16 sensors are located within each E/W and N/S Triaxial Response Spectrum Recorder) failed to meet calibration requirements.
Failure to return the monitors to an operable status within 30 days requires submission of this Special Report of the U.S. Nuclear Regulatory Commission within 10 days as specified in TS 3.3.7.2 ACTION Statement a.
The immediate cause of the failure to restore the seismic monitors to operable status within 30 days was the inability to successfully complete calibration procedure N2-ISP-ERS-R104. Symmetry test accuracies of 5X required by procedure could not be achieved. Also, frequency test checks performed on certain accelerometers/sensors were found to be damaging to these sensors.
A Special Report was issued (copy attached) on January 16, 1989 documenting that recorder 2ERS-RSR3B had been declared inoperable due to indications of seismic activities being found on permanent record plates, yet
~""i'019014> y(OIq) +$ 2
@DOCK 05(OOOO I<> I (
PDI
'age 2 NMP ~68~1 no evidence of an event existed. It was determined that background vibration was causing false recordings.
Immediate corrective action included contacting equipment vendor, Engdahl Enterprises, to discuss resolution of; (1) inability of NMPC Instrument and Controls Department to meet vendor manual calibration requirements for the Triaxial Response Spectrum Recorder (2ERS-RSR3B); and (2) the damaging of certain sensor/accelerometers during surveillance frequency checks as outlined in vendor manual.
Engdahl Enterprises has provided revised vendor manual frequency calibration data which omit frequency checks for certain sensors which could be susceptible to damage. Additionally, the vendor manual symmetry test data for the seismic monitoring recorders has been revised to change accuracies from 5X to 8X.
A Problem Report (PR) 808835 has been written recommending vendor manual changes be made to include new vendor specifications.
Corrective actions outlined in the January 16, 1989 Special Report detailed steps that have been taken to monitor background vibrations and their effects on seismic monitor (2ERS-RSR3B). New permanent record plates were installed and surveillances of these have been completed. Based on these results, a new installation location for this monitor will be provided by NMPC Engineering. A temporary surveillance vibration monitoring program will be initiated to measure background vibration at this new location. If acceptable low level readings are observed, a Modification Request will be initiated to permanently relocate seismic vibration monitor (2ERS-RSR3B) to this location.
A Technical Specification change will then be submitted to the V.S. Nuclear Regulatory Commission prior to completion of the first refueling outage to change Table 3.3.7.2-1 to reflect this new location. This seismic monitor will remain inoperable until the above actions have been completed.
Sincerely, J. L. Willis General Superintendent Nuclear Generation JLW/GB/mdiv (1002V)
At tachment cc: Regional Administrator, Region 1 Sr. Resident Inspector, W. A. Cook