ML18038A340

Monthly Operating Rept for Jan 1991 for Nine Mile Point Nuclear Station Unit 1

ML18038A340
Person / Time
Site:	Nine Mile Point
Issue date:	01/31/1991
From:	Coleman D NIAGARA MOHAWK POWER CORP.
To:
Shared Package
ML17056B295	List: ML17056B294 ML17056B296 ML17056B297 ML17056B298 ML17056B299 ML17056B300 ML17056B301 ML17056B302 ML17056B303 ML17056B304 ML17056B305 ML17056B306 ML17056B307 ML17056B308 ML17056B309 ML17056B310 ML17056B311 ML17056B312 ML17056B313 ML17056B314 ML17056B315 ML17056B316 ML17056B317 ML17056B318 ML18038A340 ML18038A342
References
NUDOCS 9102200078
Download: ML18038A340 (18)

Text

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

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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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