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Category:MONTHLY OPERATING ANALYSIS REPORT
MONTHYEARML20217K4631999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Nine Mile Point, Unit 1.With ML20212C4601999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Nine Mile Point Nuclear Station,Unit 1.With ML20210U4591999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Nine Mile Point, Unit 1.With ML20210B9081999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Nine Mile Point Unit 1.With ML20196E2111999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Nmp,Unit 1.With ML20196L2301999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Nmp,Unit 1.With ML20205S5701999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for NMP Unit 1.With ML20204C9971999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Nine Mile Point,Unit 1.With ML20199K9331998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Nine Mile Point Nuclear Station,Unit 1.With ML20198D9361998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Nine Mile Point,Unit 1.With ML20195J4141998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Nine Mile Point Nuclear Station,Unit 1.With 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 ML20236Q1701998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Nine Mile Point Nuclear Station,Unit 1 ML20249B4971998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Nine Mile Point Nuclear Station,Unit 1 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 ML20217B5371998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Nine Mile Point Nuclear Station,Unit 1 ML20203A3071998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Nine Mile Point Nuclear Station,Unit 1 ML20198T0601997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Nine Mile Point Nuclear Station,Unit 1 ML20197B4531997-11-30030 November 1997 Monthly Operating Rept for Nov 1997 for NMP Nuclear Station, Unit 1 ML20199H3131997-10-31031 October 1997 Monthly Operating Rept for Oct 1997 for NMP Nuclear Station, Unit 1 ML20212A7001997-09-30030 September 1997 Monthly Operating Rept for Sept 1997 for Nine Mile Point Nuclear Station,Unit 1 ML20211A4981997-08-31031 August 1997 Monthly Operating Rept for Aug 1997 for Nine Mile Point Nuclear Station Unit 1 ML20217M4101997-07-31031 July 1997 Monthly Operating Rept for July 1997 for NMPNS ML20141H1921997-06-30030 June 1997 Monthly Operating Rept for June 1997 for Nine Mile Point Nuclear Station,Unit 1 ML18037A1361997-04-30030 April 1997 Monthly Operating Rept for Apr 1997 for Nine Mile Point Nuclear Station,Unit 1 ML17059B5541997-03-31031 March 1997 Revised Monthly Operating Rept for Mar 1997 for Nine Mile Point Nuclear Station,Unit 1 ML17059B5531997-02-28028 February 1997 Revised Monthly Operating Rept for Feb 1997 for Nine Mile Point Nuclear Station,Unit 1 ML18037A1351996-10-31031 October 1996 Monthly Operating Rept for Oct 1996 for Nine Mile Point, Unit 2.W/961115 Ltr ML18038A5001991-12-31031 December 1991 Monthly Operating Rept for Dec 1991 for Unit 2 Shutdowns & Power Reductions.W/920115 Ltr ML18038A3541991-05-31031 May 1991 Narrative Rept of Operating Experience for May 1991 for Nine Mile Point Nuclear Station Unit 1 ML17058A8061991-05-31031 May 1991 Monthly Operating Rept for May 1991 for Nine Mile Point Nuclear Station Unit 1 ML17058A7071991-03-31031 March 1991 Monthly Operating Rept for Mar 1991 for Nine Mile Point Unit 1 ML17058A7091991-02-28028 February 1991 Corrected Monthly Operating Rept for Feb 1991 for Nine Mile Point Unit 1 ML18038A3401991-01-31031 January 1991 Monthly Operating Rept for Jan 1991 for Nine Mile Point Nuclear Station Unit 1 ML18038A3421990-12-31031 December 1990 Revised Monthly Operating Rept for Dec 1990 for Nine Mile Point Nuclear Station Unit 1 ML18038A3391990-12-31031 December 1990 Monthly Operating Statistics Rept for Dec 1990 for Nine Mile Point Unit 2.Narrative Rept of Operation Experience for Dec 1990 encl.W/910111 Ltr ML17056B2961990-11-30030 November 1990 Revised Monthly Operating Rept for Nov 1990 for Nine Mile Point Nuclear Station Unit 1 ML17056B2971990-10-31031 October 1990 Revised Monthly Operating Rept for Oct 1990 for Nine Mile Point Nuclear Station Unit 1 ML17056B2981990-09-30030 September 1990 Revised Monthly Operating Rept for Sept 1990 for Nine Mile Point Nuclear Station Unit 1 ML17056B2991990-08-31031 August 1990 Revised Monthly Operating Rept for Aug 1990 for Nine Mile Point Nuclear Station Unit 1 ML17056B3001990-07-31031 July 1990 Revised Monthly Operating Rept for Jul 1990 for Nine Mile Point Nuclear Station Unit 1 ML17056B3011990-06-30030 June 1990 Revised Monthly Operating Rept for June 1990 for Nine Mile Point Nuclear Station Unit 1 ML20043H5261990-05-31031 May 1990 Monthly Operating Rept for May 1990 for Nine Mile Point, Unit 2.W/900614 Ltr ML17056B3021990-05-31031 May 1990 Revised Monthly Operating Rept for May 1990 for Nine Mile Point Nuclear Station Unit 1 ML17056B3031990-04-30030 April 1990 Revised Monthly Operating Rept for Apr 1990 for Nine Mile Point Nuclear Station Unit 1 ML17056B3041990-03-31031 March 1990 Revised Monthly Operating Rept for Mar 1990 for Nine Mile Point Nuclear Station Unit 1 ML17056B3051990-02-28028 February 1990 Revised Monthly Operating Rept for Feb 1990 for Nine Mile Point Nuclear Station Unit 1 1999-09-30
[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 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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OPERATING DATA REPORT DOCKET NO.: 50-220 DATE: 2/13/91 PREPARED BY: D. E. Coleman TELEPHONE: (315) 349-2558 OPERATING STATUS
- 1. Unit Name: Nine Mile Point Unit //I
- 2. Reporting Period: I/I/91 through I/31/91 Notes
- 3. Licensed Thermal Power (MWt): 1850
- 4. Nameplate Rating (Gross MWe): 642
- 5. Design Electrical Rating (Net MWe): 625
- 6. Maximum Dependable Capacity (Gross MWe): 635
- 7. Maximum Dependable Capacity (Net MWe): 615
- 8. If Changes Occur in Capacity Ratings (items Number 3 through 7) Since Last Report, Give Reasons:
Nameplate rating (Gross MWe) corrected to 642 from 645 (755 MVA x .85)
- 9. Power Level To Which Restricted, IfAny (Net MWe):
- 10. Reasons For Restrictions, IfAny:
This Month Yr-to-Date Cumulative
- 11. Hours in Reporting Period 744.0 744.0 187,393.2
- 12. Number of Hours Reactor Was Critical 549.5 549.5 119,149.6
- 13. Reactor Reserve Shutdown Hours 0.0 0.0 1,204.2
- 14. Hours Generator On-Line 533.8 533.8 115,696.3
- 15. Unit Reserve Shutdown Hours 0.0 0.0 20.4
- 16. Gross Thermal Energy Generated (MWH) 917,214.0 917,214.0 193,459,892.0
- 17. Gross Electrical Energy Generated (MVGQ 316,069.0 316,069.0 64,118,986.0
- 18. Net Electrical Energy Generated (MWH) 306,160.0 306,160.0 62,112,000.0
- 19. Unit Service Factor 71.7 71.7 61.7
- 20. Unit Availability Factor 71.7 71.7 61.7
- 21. Unit Capacity Factor (Using MDC Net) 66.9 66.9 54.3
- 22. Unit Capacity Factor (Using DER Net) 65.8 65.8 53.5
- 23. Unit Forced Outage Rate 28.3 28.3 25.9
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date and Duration of Each):
Midcycle Outage for surveillance testing 3 March 91 through 13 April 91.
- 25. IfShut Down At End of Report Period, Estimated Date of Startup:
- 26. Unit is Test Status (Prior to Commercial Operation): Forecast Achieved INITIALCRlTICALITY INITIALELECTRIClTY COMMERCIAL OPERATION
OPERATING DATA REPORT DOCKET NO.: 50-220 DATE: 2/13/91 PREPARED BY: D. E. Coleman TELEPHONE: (315) 349-2558 MONTH January 1991 DAY AVERAGE DAILYPOWER LEVEL DAY AVERAGE DAILYPOWER LEVEL (MWe-Net) (MWe-Net) 1 0 17 609 2 0 18 601 3 0 19 605 4 0 20 608 5 0 21 603 6 0 22 606 7 0 23 604 8 0 24 609 9 21 25 565 10 303 26 578 11 501 27 583 12 571 28 593 13 600 29 590 14 598 30 595 15 602 31 605 16 606 INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the reporting month.
Compute to the nearest whole megawatt.
UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO: 50-220 UNIT NAME: NMPiItl 2/13/91 'ATE:
REPORT MONTH - January 1991 PREPARED BY: D. E. Coleman TELEPHONE: (315) 349-255S Method of & Corrective Date Duration (Hours) Reason'own Reactor'icensee Qlut tmg Event Report S Code'ode'ause System Component Action to Prevent Recurrence No.
9004 901229 210.2 A I 13 90-19 Continued - While pcrfonning a forced reactor shutdown duc to a failure of MSIV 0142, a full reactor scram occurred. Ihc reactor scram was caused by a spike on IRM 12 (Channel 11 RPS) with a half scram already in on channel 12RPS duc to the failure of MSIV OIM.
F: Forced Reason: Method: Exhibit G - Instructions Exhibit I-Same Source S: Schcdulcd A-Erluipmcnt Failure (Explain) I-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scnun Entry Shccts for Liccnsce C-Rcfucling 3-Automatic Scram Event Rcport (LER) File (NUREG-0161)
D-Regulatory Restriction 4Mhcr (Explain)
E-Operator Training & License Exam F-Administrative G43pcrational Error (Explain)
HMhcr (Explain)
NIAGARAMOHAWK POWER CORPORATION NINE MILE POINT NUCLEAR STATION UNIT ¹I NARRATIVE OF OPERATING EXPERIENCE The Station operated during the month of January 1991 with a Unit Availability Factor of 71.7%
and a Net Design Electrical Capacity Factor of 65.8%. There were no challenges to Electromatic Relief Valves. Reductions in Capacity Factor were due to the forced outage which started on December 29, 1990. While shutting down, due to a failure of MSIV 01-02, a spike occurred on IRM 12 causing the reactor to scram. The unit was synchronized to the grid on January 9, 1991 at 1810. Other reductions in Capacity Factor were due to weekly control rod exercising and the inability to obtain 100% CTP due to turbine steam flow limitation. Also, load was reduced to stabilize Turbine oil pressure.
CLASS I WORK - MECHANICALMAINTENANCE- January 1991 See attached printout.
CLASS I WORK - INSTRUMENTS AND CONTROLS - January 1991'ee attached printout.
CLASS I WORK - ELECTRICAL MAINTENANCE- January 1991 See attached printout.
l NINE HI LE POINT UNIT ONE Hechanical Haintenance - COHPLETED SAFETY RELATED MRs FOR JANUARY 02"06-91 PAGE 1 MR Number EPN Number TITLE Description Corrective Action
'W185 292 01-01 INBOARD" HSIV THE INBOARD HSIV 01-01 IN THE DRYMELL IS REHOVED OLD PACKING INSTALLED NEll LEAKING - PLEASE ADJUST PACKING REPAIR 9 RINGS AS NECESSARY M185 675 01-11 ELECTROHATIC LEAKAGE HAS BEEN DETECTED FROH PACKING REHOVED OLD PACKING CLEANED STEH BLOCKING VALVE 01-11 AREA VALVE IS LOCATED IN DRYWELL AND STUFFING BOX AND REPACKED WITH ELEVATION 259 9 RINGS OF GRAFOIL TAPE 1 3/4 INCHES X 2 3/4 INCHES X 1/2 INCH
'M185672 01"HS9 INSIDE DRYMELL HYDRO TRENDING OF DRYMELL LEAKAGE INDICATES UPON INSPECTION OF DRYMELL IT 'WAS TEST LINE VALVE THAT HS9 IS LEAKING VALVE IS LOCATED IN FOUND THAT THIS VALVE WAS NOT DRYMELL ELEVATION 313 SOUTH OF H EAST OF LEAKING 8 VALVE IS A*2 INCH STAINLESS STEEL GLOBE M185677 32-NG038 REACTOR LEAKAGE DETECTED FROH PACKING AREA VALVE ADJUSTED ALL THREE PACKING GLANDS RECIRCULATION PUHP LOCATEO IN DRYWELL ELEVATION 237 AZH 90 OUTLET IV DEGREES M185478 38"13 SHUTDOWN COOLING IV PACKING LEAK ADJUST PACKING TOOK UP ON PACKING FOLLOMER PER SSS INSTRUCTIONS W185 894 39-12R EHERGENCY CONDENSER VALVE IS LEAKING FROH BONNET AREA REPLACED BONNET GASKET 95"36-877 DRAIN LINE ISOLATION DISASSEHBLE AND REPLACE GASKET LOCATED AND TORQUE BONNET TO 90 FOOT POUNDS VALVE IN ECIV ROOH 28 RX BLDG M163649 40-12 TOPPING PUHP VALVE PACKING LEAKS REPAIR AS NECESSARY TIGHTENED PACKING GLAND DISCHARGE VALVE
'M186189 57-AO-202 JET ASSIST VALVE TO VALVE HAS A BLOWN DIAPHRAH LEAKING MATER REPLACED DIAPHRAGH 'MITH 93-39-696 COND OEHINS A0-202 LOC TB 261 1ST AND BRIDGE SM OVERHEAD M185 179 70-NA PIPE CAP ON DRAIN CAP IS HISSING ON DRAIN LINE OOWNSTREAH INSTALLED PIPE NIPPL'E AND PIPE CAP LINE DO'WNSTREAH OF OF RCLC 716 - REPLACE CAP LOCATED IN AUX TO DRAIN VALVE RCLC 716 CLEANUP PUHP ROON IN REACTOR BUILDING 261 M185 264 201"DRYMELL EHERGENCY AIR LOCK PLEASE REPLACE DRY'MELL EHERGENCY OLO GASKET= REHOVED SURFACES CLEANED EHERGENCY HA DRYMELL INNER DOOR DOOR SEAL - AIRLOCK'NNER LOCATED AT REACTOR NEM GASKET INSTALLED TCH SEAL BUILDING 237 AT EHERGENCY AIRLOCK INNER DOOR M185678 201-DRYMELL DRYWELL PERSONNEL REPLACE DOOR SEAL INNER DRYMELL HATCH CHANGE RUBBER SEAL HATCHES HATCH SEAL DOOR - REACTOR BUILDING 237 NORTH REPLACEHENT M185182 201 8"96 N2 STORAGE TANK 12 12 'N2 STROAGE TANK 250 POUND RELIEF REPLACED N2 STORAGE TANK 250 POUND 250 POUND RELIEF VALVE IS NOT RELIEVING AT 250 PSIG RELIEF VALVE 201 8-96'SYHBOL NUHBER VALVE PLEASE REPAIR LOCATED NORTH OF REACTOR 93-34-600 WITH NEM VALVE BUILDING AND MEST OF SCREEN HOUSE OUTSIDE M168354 210-01 EHERGENCY VENT FAN MORN BELLO'WS ON SUCTION SIDE TB 300 CAN NOT BE PATCHED " HUST BE 11 AND 12 CONTROL RH REPLACED - WR 185645 WRITTEN VENT
'W185136 301-38-35 HCU 38-35 SCRAH SCRAH OUTLET VALVE 127 FOR HCU 38-35 IS REQUIRED BY HECHANICAL OUTLET VALVE 127 LEAKING BY AS INDICATED BY INCREASING NO MORK HAINTENANCE - 910105 - I AND C SCRAH DISCHARGE VOLUHE HOLDING TANK LEVEL - LOCATION REACTOR BUILDING 237 COHPLETED
NINE HILE 'POINT UNIT<<ONE 02-06-91 Mechanical Maintenance - COHPLETED SAFETY~RELATED llRs FOR JANUARY PAGE 2 C llR Number EPN Number TITLE Description Corrective Action,.
II185265 305"125 CRD HCU 46-27 PISTON CONTROL ROD DRIVE HYDRAULIC CONTROL UNIT REPLACE IIATER BOTTLE ACCUMULATOR 46-27 PISTON IS LEAKING EXCESSIVLY MITH NEII - NR 185623 HAS BEEN ALARHS ABOUT EVERY 2 1/2 HOURS PLEASE G)NERATEO TO REBUILD OLD REPAIR OR REPLACE LOCATED REACTOR A CUHULATOR BUILDING 237 'REST DEF TAG 24314
it
> .r E,
NINE MILE POINT UNIT ONE 02-06-91 Instrument & Controls " COHPLETED SAFETY RELATED WRs FOR JANUARY PAGE 3 MR Number EPN Number TITLE Description Corrective ActIon M186941 32" IA72A CHANNEL 11 APRH FLOW 11 APRH FLOW SUHHER IS READING HIGH REPLACED FLOW SUHHER 'WITH ANOTHER SUHHER REPAIR AS NECESSARY REPLACE FLOW SUHHER SUHHER
'W18248 5 33-95 33-96 AREA TEHPERATURE IN SUPPORT OF HAINTEN NCE SUPPORT REHOVED COVERS TO ALLOM WIRING 33-97 HONITORS FOR CLEANUP PROCEDURE GROUP REHOV BACK COVER FROH INSPECTION - REPLACED COVERS WHEN SYSTEH ALL.THREE 3'ARE TEHPERATURE HONITORS INSPECTIONS COHPLETED TH-400 IN ORDER TO PERFORH MIRING INSPECTIONS W187850 36-ATWS RELAY RP12 CONTACTS WHILE PERFORMING N1-ISP-036-H009 A REPLACED RELAY RPT-12 T4-H3 HEASUREHENT MAS TAKEN ACROSS TERMINALS TR"H3 ON RP 12 RELAY OF 1 24 OHHS THIS VALUE IS SUPOSE TO BE 0 0 DHHS OR LESS THAN 1 0 OHHS AS STATED IN THE PROCEDURE LOCATION AUX CONTROL ROOH CABINET 1548
'M187851 36-AT'MS I/V CONVERTER NEST WHILE PERFORHING N1-ISP"036-H009 A AS REPLACED IV 'MITH NEll ONE FROH 500 SLOT 2 LEFT VOLTAGE OF APPROXIHATELY HINUS 14 STORES VOLTS WAS HEASURED ACROSS '523 PLUS AND 523 HINUS THIS CONVERTERS NORHAL OUTPUT IS 0 TO 10 VOL'TS - LOCATION AUX CONTROL ROOH CABINET 1S48 W182486 38-62 AREA TEHPERATURE IN SUPPORT OF HAINTENANCE 'SUPPORT REHOVED COVER TO ALLOW 'MIRING MONITOR 'FOR SHUTDOWN PROCEDURE GROUPREHOVE BACK COVER FROH INSPECTION " REPLACED COVER WHEN COOLING SYSTEH AREA'EHPERATURE HONITOR TH-400 IN ORDER INSPECTION COHPLETED TO PERFORH WIRING'NSPECTIONS W185 480 92-IRH-12 12 IRH DRIVE UNITS 12 IRH DRIVE UNIT LIGHTS ARE NOT RESET RFH RELAY ILLUHINATED ON CONSOLE IN UNIT 1 CONTROL ROOH - E TROUBLESHOOT W185 481 92-IRH-15 15 IRH DRIVE UNITS 15 DRIVE UNITS LIGHTS ARE NOT RESET RFH RELAY ILLUHINATED ON E CONSOLE IN'UNIT 1 CONTROL ROOH M187820 92-RH-01G IRH 17 WHILE PERFORHING N1-ISP-092-V205 STEP TCN TO PROCEDURE
- SYSTEM 'WORKS AS 7.7~48 THE CONSOLE E INOPERABLE LAHP DESIGNED NO WORK PERFORHED FAILED TO ILLUHINATE PLEASE TROUBLESHOOT M187694 201 2-217 11 H2 AUTO THE OUT OF RANGE SPAN LIGHT IS CALIBRATION UNIT RECALIBRATE - P AND ON ID 26939 TURBINE PLEASE RECALIBRATED H2 HONITOR BUILDING 291 MEST M185 603 201 2-217A 2 H2-02 AUTO PLEASE SET AUTO CALIBRATION UNITS TO HADE ADJUSTHENT TO AUTO CALIBRATION 01 2-218A 20 CALIBRATION SAHPLE AND HOLD HODE TO PREVENT UNIT 1 2-330A 201 ANNUNCIATORS FROH COHING IN AFTFR AUTO 2-331A CAL SEQUENCE - C-27003"C C27004-C TURBINE 'BUILDING 291 NORTH 'MALL W186150 NEU-04-33A LPRH 04"33A LPRH 04-33A 'MOULD NOT PRODUCE A READING NO WORK PERFORHED TDR.SHOWS A BAD EVEN 'MITH FLUX AHP STRAPPED TO HAXIHUH DETECTOR AND I/V CURVE, SHOWS OPEN GAIN DURING Nl-RPSP-7 PLEASE PERFORH TDR DETECTOR TO BE REPLACE'N FUTRUE AS AND REPAIR - REPLACES W186121 DIRECTED BY REACTOR ANALYSTS
'M185279 NEU-33I/IRH1 IRH 12 POSITION LIHIT. SMITCH - 33I 'IRH 12 APPARENTLY HAS SMITCH - IN DRYMELL 2
REPLACED CONNECTOR AT VESSEL END FAILED OPEN PLEASE REPAIR OR REPLACE PRINT C-19438-C SHEET 5 M187 762 NEU-Fi FUSE 10 Fi POWER FOR FUSE BLOMN PLEASE CHECK OUT AND REPLACE REPLACED FUSE BYPASS OF 11 SIDE FUSE CANNOT BYPASS 11 SIDE NEUTRON INSTRUHENTS M187726 PHS-X"58 NITROGEN PURGE LINE PLEASE REPLACE CONNECTION. NUT AND REPLACED NUT AND FERRULE CONNECTION TO FERRULE AT PENETRATION X-58 LOCATION PENETRATION X-58 REACTOR BUILDING 281 ECIV ROON
NINE HILE POINT UNIT ONE f 02-06-91 Instrument 8 Controls COHPLETED SAFETY RELATED MRs FOR JANUARY PAGE MR Number EPN Number TITLE Description Corrective,. Action M185467 RPS-RE16A AN REACTOR 600 PSIG TROUBLESHOOT REACTOR EQUAL TO OR LESS CALIBRATED SMITCHES PER D RE16B PRESSURE BYPASS THAN 600 PSIG PRESSURE BYPASS CIRCUIT Nl-ISP-001-R005 PARTIAL - INDICATOR CIRCUIT NOT DONE - HONITOREO TRIP RELAYS llK39 AND 12K39 - NO PROBLEHS NOTED
I' HILE POINT UNIT 02-06-91 Electrical Haintenance NINE
- COHPLETED SAFETY ONE RELATED MRs FOR JANUARY PAGE 5 MR Number EPN Number TITLE Descriotion Corrective Action r M185257 01-02 121 HAIN STEAH LINE DURING HAIN STEAH FEEDMATER VALVE TROUBLESHOOT SYSTEH PER ATTACHED ISOLATION VALVE TESTING Nl-ST-Q26 HAIN STEAH LINE IV 121 AP-5 4.2 - HOTOR BURNED OUT 01-02 01-02 BREAKER TRIPPED LOCATED PB 1718 REPLACED HOTOR - VALVE MAS STUCK REACTOR BUILDING 261 EAST TROUBLESHOOT COULD NOT OPERATE HANUALL'Y M185683 RPS-FUSES REACTOR TRIP BUS 131 REPLACE EXISTING REACTOR TRIP BUS FUSES REPLACED FUSES PER DCR AND 141 FUSES IN AUX CONT CABINET 1S53 BUS 131 AND AUX N1-90-001LS368 CONT CABINET 1555 BUS 141 MITH GOULD SHAMHUT OT FUSES PER DCR N1-90-001LS368 M185611 RPS-RPS911K3 ROD BLOCK AND RECIRC HFA RELAY 11K37B IS EXTREHELY NOISY DID TROUBLESHOOTING AS REQUIRED 7B SCOOP TUBE LOCK HFA ESPECIALLY MHEN COHPARED TO OTHER HFA FOUND LOOSE COIL SCREMS IN RELAY RELAY RELAYS - PLEASE INVESTIGATE - IF PROBLEH REFERRED PROBLEM TO HETER AND TEST FOUND REPAIR OR REPLACE AS REQUIRED LOCATED IN H PANEL
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