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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
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
1997-06-23
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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
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
1997-06-23
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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
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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Text
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9408030272 DOC.DATE: 94/07/25 NOTARIZED: NO DOCKET g FACIL:50-220 Nine Mile Point Nuclear Station, Unit 1, Niagara Powe 05000220 AUTH. NAME AUTHOR AFFILIATION ABBOTT,R.B. Niagara Mohawk Power Corp.
RECIP.NAME RECXPIENT AFFXLXATION Document Control Branch (Document Control Desk)
SUBJECT:
Special rept:on 940710,re inoperability of hydrogen monitoring unit. Caused by air regulator for valve Ill containment operator set at 73 psig air pressure. Regulator reset to 29 Ps'lg DISTRIBUTION CODE: IE22D COPXES RECEIVED:LTR TITLE: 50.73/50.9 Licensee Event Report (LER),
ENCL 5 SXZE:
ncident Rpt, etc.
NOTES:
RECXPIENT COPXES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD1-1 PD BRINKMAN,D.
INTERNAL: ACRS AEOD/DSP/TPAB AEOD/ROAB/DSP NRR/DE/EELB NRR/DE/EMEB NRR/DORS/OEAB NRR/DRCH/HHFB NRR/DRCH/HICB NRR/DRCH/HOLB NRR/DRSS/PRPB NRR/DSSA/SPLB /J3SSA/SRXB NRR/PMAS/IRCB-E RES/DSXR/EIB REG RGN1 FIL~
FILE 01 02 EXTERNAL EG&G BRYCE g J ~ H L ST LOBBY WARD NRC PDR NSIC MURPHY,G.A NSIC POORE,W. NUDOCS FULL TXT NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE KVASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 504-2083 ) TO ELIh!!NATE YOUR VAME FROM DISTRIBUTIONLISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED: LTTR 27 ENCL
V NIAGAR U MOHAWK NINE MILE POINT NUCLEAR STATION/P.O. BOX 63. LYCOMING, NEW YORK 13093/TELEPHONE (315) 343-2110 Richard D. Abbott Plant Manat,cr - Unit EI July 25, 1994 (315) 349-1812 NMP1L 0839 (315) 3494417 (PAX)
U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 RE: Nine Mile Point Unit 1 Docket No. 50-220 DPR- "
Subject:
Special Report Gentlemen:
In accordance with Nine Mile Point Unit 1 (NMP1) Technical Specification Table 3.6.11-1, "Accident Monitoring Instrumentation," Action Statement 4.a, Niagara Mohawk Power Corporation is submitting the following Special Report concerning the inoperability of the
¹11 Containment Hydrogen Monitoring Unit (HMS).
De cri 'vent On July 10, 1994 at 0930 hours0.0108 days <br />0.258 hours <br />0.00154 weeks <br />3.53865e-4 months <br />, with the reactor mode switch in the "RUN" position and the plant operating at approximately 100 percent of rated thermal power, the ¹11 HMS was removed from service. During the performance of procedure Nl-ST-Q5, "Primary Containment Isolation Valve Operability Test," on a group of eight primary containment isolation valves on the ¹11 containment monitoring system, the "open to close" time of one of these valves, i.e., valve 201.7-03, as measured in the control room, was 8.9 seconds.
The Inservice Test (IST) limit is ~ 8.5 seconds and the Technical Specification limit is ~60 seconds, Procedure Nl-S P-Q5 requires tkat a 1 eioht valves be declared inoperabl if any one of them exceeds the IST limit. All eight of these valves are controlled by one switch.
At 0930 hours0.0108 days <br />0.258 hours <br />0.00154 weeks <br />3.53865e-4 months <br /> on July 10, 1994, valve 201.7-03 was declared inoperable and closed, as were the seven other primary containment isolation valves, and, consequently ¹11 HMS was also declared inoperable and removed from service. Number 12 HMS remained in service.
Cause Event Troubleshooting was performed that included the following steps:
~ The limit switches were inspected for signs of sticking or degradation, and none was found.
'tI4080>0-7 ttt 4072'5
~.pP PDR ADOCK 0 PDR 9
Page 2
~ Testing was done to determine if the solenoid operated air pilot valves were degraded. Minor leakage was found, but this was not the cause of the slow stroke time.
The valve actuator was disassembled and inspected for signs of degradation, and none was found.
The valve actuator was reassembled and the valve manually restroked and found to move freely. However, the air regulator for the valve operator was found to be set at 73 psig air pressure. This was reset to 29 psig, the correct value, and the valve was found to stroke at 60% open. The 60% open was determined to be acceptable because this provided more than the required flow for the ¹11 HMS to be operable.
~ After troubleshooting, valve 201.7-03 successfully passed its 10 CFR 50 Appendix J local leak rate test and its IST stroke timing test.
None of these troubleshooting steps provided insight into the cause of the failed IST stroke time test.
Corrective Action After successfully restroking and retiming valve 201.7-03, the valve was declared operable and opened, along with the seven other primary containment isolation valves. Number 11 HMS was started, tested using procedure Nl-ISP-201-020, "Containment H, Atmosphere Monitoring System Functional Verification," and was returned to service at 1048 hours0.0121 days <br />0.291 hours <br />0.00173 weeks <br />3.98764e-4 months <br /> on July 15, 1994.
Because the root cause of the slow stroke time could not be determined by this troubleshooting, and because this valve has failed its IST stroke time testing before (on May 10, 1994; reference Special Report NMP1L 0818, dated May 24, 1994), valve 201.7-03 will remain on an increased stroke time testing frequency of once per month for at least three months, and its operation will be observed locally. Additional testing will be performed, by September 30, 1994, which will include an actuator benchset. This testing will isolate the timing problem to the valve/packing assembly or the actuator assembly, and will provide insight on the valve's stroke limitation. Corrective actions will then be taken, as appropriate, to resolve any identified problems.
Very truly yours, g8Ci~
R. B. Abbott Plant Manager - NMP1 RBA/JTP/ksj xc: Mr. Thomas T. Martin, Regional Administrator, Region I Mr. Barry S. Norris, Senior Resident Inspector
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