ML18038A340
| ML18038A340 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 01/31/1991 |
| From: | Coleman D NIAGARA MOHAWK POWER CORP. |
| To: | |
| Shared Package | |
| ML17056B295 | List: |
| References | |
| NUDOCS 9102200078 | |
| Download: ML18038A340 (18) | |
Text
OPERATING STATUS OPERATING DATAREPORT DOCKET NO.:
50-220 DATE: 2/13/91 PREPARED BY: D. E. Coleman TELEPHONE:
(315) 349-2558 Notes
- 1. Unit Name:
Nine Mile Point Unit //I
- 2. Reporting Period: I/I/91 through I/31/91
- 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. IfChanges Occur in Capacity Ratings (items Number 3 through 7) Since Last Report, Give Reasons:
Nameplate rating (Gross MWe) corrected to 642 from 645 (755 MVAx.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
- 12. Number of Hours Reactor Was Critical 549.5
- 13. Reactor Reserve Shutdown Hours 0.0
- 14. Hours Generator On-Line 533.8
- 15. Unit Reserve Shutdown Hours 0.0
- 16. Gross Thermal Energy Generated (MWH) 917,214.0
- 17. Gross Electrical Energy Generated (MVGQ 316,069.0
- 18. Net Electrical Energy Generated (MWH) 306,160.0
- 19. Unit Service Factor 71.7
- 20. Unit AvailabilityFactor 71.7
- 21. Unit Capacity Factor (Using MDC Net) 66.9
- 22. Unit Capacity Factor (Using DER Net) 65.8
- 23. Unit Forced Outage Rate 28.3
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date and Duration ofEach):
Midcycle Outage for surveillance testing 3 March 91 through 13 April91.
744.0 549.5 0.0 533.8 0.0 917,214.0 316,069.0 306,160.0 71.7 71.7 66.9 65.8 28.3 187,393.2 119,149.6 1,204.2 115,696.3 20.4 193,459,892.0 64,118,986.0 62,112,000.0 61.7 61.7 54.3 53.5 25.9
- 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 COMMERCIALOPERATION
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 (MWe-Net)
DAY AVERAGE DAILYPOWER LEVEL (MWe-Net) 1 2
3 4
5 6
7 8
9 10 11 12 13 14 15 16 0
0 0
0 0
0 0
0 21 303 501 571 600 598 602 606 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 609 601 605 608 603 606 604 609 565 578 583 593 590 595 605 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 REPORT MONTH - January 1991 DOCKET NO:
50-220 UNIT NAME: NMPiItl
'ATE:
2/13/91 PREPARED BY: D. E. Coleman TELEPHONE:
(315) 349-255S No.
Date Duration (Hours)
Method of Qluttmg Reason'own Reactor'icensee Event Report S System Component Code'ode'ause
& Corrective Action to Prevent Recurrence 9004 901229 210.2 A
I13 90-19 Continued - While pcrfonning a forced reactor shutdown duc to a failure ofMSIV0142, 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 ofMSIVOIM.
F: Forced S:
Schcdulcd Reason:
A-Erluipmcnt Failure (Explain)
B-Maintenance or Test C-Rcfucling D-Regulatory Restriction E-Operator Training &License Exam F-Administrative G43pcrational Error (Explain)
HMhcr (Explain)
Method:
I-Manual 2-Manual Scnun 3-Automatic Scram 4Mhcr (Explain)
Exhibit G - Instructions for Preparation of Data Entry Shccts for Liccnsce Event Rcport (LER) File (NUREG-0161)
Exhibit I-Same Source
NIAGARAMOHAWKPOWER CORPORATION NINE MILEPOINT NUCLEAR STATION UNIT¹I NARRATIVEOF OPERATING EXPERIENCE The Station operated during the month ofJanuary 1991 with a Unit AvailabilityFactor of71.7%
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 - ELECTRICALMAINTENANCE-January 1991 See attached printout.
l
02"06-91 PAGE 1
MR Number
'W185 292 M185 675
'M185672 M185677 M185478 W185 894 M163649
'M186189 M185 179 M185 264 M185678 M185182 M168354
'W185136 EPN Number TITLE 01-01 INBOARD" HSIV 01-11 ELECTROHATIC BLOCKING VALVE 01-11 01"HS9 INSIDE DRYMELL HYDRO TEST LINE VALVE 32-NG038 38"13 39-12R 40-12 57-AO-202 70-NA REACTOR RECIRCULATION PUHP OUTLET IV SHUTDOWN COOLING IV EHERGENCY CONDENSER DRAIN LINE ISOLATION VALVE TOPPING PUHP DISCHARGE VALVE JET ASSIST VALVE TO COND OEHINS A0-202 PIPE CAP ON DRAIN LINE DO'WNSTREAH OF RCLC 716 201"DRYMELL EHERGENCY AIR LOCK EHERGENCY HA DRYMELL INNER DOOR TCH SEAL 201-DRYMELL HATCHES 201 8"96 DRYWELL PERSONNEL HATCH SEAL REPLACEHENT N2 STORAGE TANK 12 250 POUND RELIEF VALVE 210-01 301-38-35 EHERGENCY VENT FAN 11 AND 12 CONTROL RH VENT HCU 38-35 SCRAH OUTLET VALVE 127 Description THE INBOARD HSIV 01-01 IN THE DRYMELL IS LEAKING - PLEASE ADJUST PACKING REPAIR AS NECESSARY LEAKAGE HAS BEEN DETECTED FROH PACKING AREA VALVE IS LOCATED IN DRYWELL ELEVATION 259 TRENDING OF DRYMELL LEAKAGE INDICATES THAT HS9 IS LEAKING VALVE IS LOCATED IN DRYMELL ELEVATION 313 SOUTH OF H EAST OF 8
VALVE IS A*2 INCH STAINLESS STEEL GLOBE LEAKAGE DETECTED FROH PACKING AREA VALVE LOCATEO IN DRYWELL ELEVATION 237 AZH 90 DEGREES PACKING LEAK ADJUST PACKING VALVE IS LEAKING FROH BONNET AREA DISASSEHBLE AND REPLACE GASKET LOCATED IN ECIV ROOH 28 RX BLDG VALVE PACKING LEAKS REPAIR AS NECESSARY VALVE HAS A BLOWN DIAPHRAH LEAKING MATER LOC TB 261 1ST AND BRIDGE SM OVERHEAD CAP IS HISSING ON DRAIN LINE OOWNSTREAH OF RCLC 716 - REPLACE CAP LOCATED IN AUX CLEANUP PUHP ROON IN REACTOR BUILDING 261 PLEASE REPLACE DRY'MELL EHERGENCY AIRLOCK'NNER DOOR SEAL - LOCATED AT REACTOR BUILDING 237 AT EHERGENCY AIRLOCK INNER DOOR REPLACE DOOR SEAL INNER DRYMELL HATCH DOOR - REACTOR BUILDING 237 NORTH 12 'N2 STROAGE TANK 250 POUND RELIEF VALVE IS NOT RELIEVING AT 250 PSIG PLEASE REPAIR LOCATED NORTH OF REACTOR BUILDING AND MEST OF SCREEN HOUSE OUTSIDE MORN BELLO'WS ON SUCTION SIDE TB 300 SCRAH OUTLET VALVE 127 FOR HCU 38-35 IS LEAKING BY AS INDICATED BY INCREASING SCRAH DISCHARGE VOLUHE HOLDING TANK LEVEL - LOCATION REACTOR BUILDING 237 Corrective Action REHOVED OLD PACKING INSTALLED NEll 9 RINGS REHOVED OLD PACKING CLEANED STEH AND STUFFING BOX AND REPACKED WITH 9 RINGS OF GRAFOIL TAPE 1 3/4 INCHES X
2 3/4 INCHES X 1/2 INCH UPON INSPECTION OF DRYMELL IT
'WAS FOUND THAT THIS VALVE WAS NOT LEAKING ADJUSTED ALL THREE PACKING GLANDS TOOK UP ON PACKING FOLLOMER PER SSS INSTRUCTIONS REPLACED BONNET GASKET 95"36-877 AND TORQUE BONNET TO 90 FOOT POUNDS TIGHTENED PACKING GLAND REPLACED DIAPHRAGH 'MITH 93-39-696 INSTALLED PIPE NIPPL'E AND PIPE CAP TO DRAIN VALVE OLO GASKET= REHOVED SURFACES CLEANED NEM GASKET INSTALLED CHANGE RUBBER SEAL REPLACED N2 STORAGE TANK 250 POUND RELIEF VALVE 201 8-96'SYHBOL NUHBER 93-34-600 WITH NEM VALVE CAN NOT BE PATCHED " HUST BE REPLACED -
WR 185645 WRITTEN NO MORK REQUIRED BY HECHANICAL HAINTENANCE - 910105 - I AND C
COHPLETED NINE HILE POINT UNIT ONE Hechanical Haintenance - COHPLETED SAFETY RELATED MRs FOR JANUARY
02-06-91 PAGE 2
llR Number EPN Number NINE HILE 'POINT UNIT<<ONE Mechanical Maintenance - COHPLETED SAFETY~RELATED llRs FOR JANUARY C
Corrective Action,.
TITLE Description II185265 305"125 CRD HCU 46-27 PISTON CONTROL ROD DRIVE HYDRAULIC CONTROL UNIT 46-27 PISTON IS LEAKING EXCESSIVLY ALARHS ABOUT EVERY 2 1/2 HOURS PLEASE REPAIR OR REPLACE LOCATED REACTOR BUILDING 237
'REST DEF TAG 24314 REPLACE IIATER BOTTLE ACCUMULATOR MITH NEII -
NR 185623 HAS BEEN G)NERATEO TO REBUILD OLD A CUHULATOR
it
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02-06-91 PAGE 3
MR Number EPN Number TITLE Description Corrective ActIon NINE MILE POINT UNIT ONE Instrument
& Controls " COHPLETED SAFETY RELATED WRs FOR JANUARY M186941
'W18248 5 32" IA72A 33-95 33-96 33-97 CHANNEL 11 APRH FLOW SUHHER AREA TEHPERATURE HONITORS FOR CLEANUP SYSTEH W187850 36-ATWS RELAY RP12 CONTACTS T4-H3
'M187851 36-AT'MS I/V CONVERTER NEST 500 SLOT 2
W182486 38-62 AREA TEHPERATURE MONITOR 'FOR SHUTDOWN COOLING SYSTEH W185 480 W185 481 92-IRH-15 15 IRH DRIVE UNITS M187820 92-RH-01G IRH 17 M187694 M185 603 201 2-217 201 2-217A 2
01 2-218A 20 1 2-330A 201 2-331A 11 H2 AUTO CALIBRATION UNIT H2-02 AUTO CALIBRATION W186150 NEU-04-33A LPRH 04"33A
'M185279 NEU-33I/IRH1 2
IRH 12 POSITION SMITCH - IN DRYMELL M187 762 NEU-Fi FUSE 10 Fi POWER FOR BYPASS OF 11 SIDE M187726 PHS-X"58 NITROGEN PURGE LINE CONNECTION TO PENETRATION X-58 92-IRH-12 12 IRH DRIVE UNITS 11 APRH FLOW SUHHER IS READING HIGH REPAIR AS NECESSARY REPLACE FLOW SUHHER IN SUPPORT OF HAINTEN NCE SUPPORT PROCEDURE GROUP REHOV BACK COVER FROH ALL.THREE 3'ARE TEHPERATURE HONITORS TH-400 IN ORDER TO PERFORH MIRING INSPECTIONS WHILE PERFORMING N1-ISP-036-H009 A
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 WHILE PERFORHING N1-ISP"036-H009 A
AS LEFT VOLTAGE OF APPROXIHATELY HINUS 14 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 IN SUPPORT OF HAINTENANCE 'SUPPORT PROCEDURE GROUPREHOVE BACK COVER FROH AREA'EHPERATURE HONITOR TH-400 IN ORDER TO PERFORH WIRING'NSPECTIONS 12 IRH DRIVE UNIT LIGHTS ARE NOT ILLUHINATED ON E
CONSOLE IN UNIT 1 CONTROL ROOH -
TROUBLESHOOT 15 DRIVE UNITS LIGHTS ARE NOT ILLUHINATED ON E
CONSOLE IN'UNIT 1 CONTROL ROOH WHILE PERFORHING N1-ISP-092-V205 STEP 7.7~48 THE CONSOLE E
INOPERABLE LAHP FAILED TO ILLUHINATE PLEASE TROUBLESHOOT THE OUT OF RANGE SPAN LIGHT IS ON PLEASE RECALIBRATE -
P AND ID 26939 TURBINE BUILDING 291 MEST PLEASE SET AUTO CALIBRATION UNITS TO SAHPLE AND HOLD HODE TO PREVENT ANNUNCIATORS FROH COHING IN AFTFR AUTO CAL SEQUENCE - C-27003"C C27004-C TURBINE 'BUILDING 291 NORTH
'MALL LPRH 04-33A
'MOULD NOT PRODUCE A READING EVEN 'MITH FLUX AHP STRAPPED TO HAXIHUH GAIN DURING Nl-RPSP-7 PLEASE PERFORH TDR AND REPAIR - REPLACES W186121 LIHIT.SMITCH 33I 'IRH 12 APPARENTLY HAS FAILED OPEN - PLEASE REPAIR OR REPLACE PRINT C-19438-C SHEET 5
FUSE BLOMN PLEASE CHECK OUT AND REPLACE FUSE CANNOT BYPASS 11 SIDE NEUTRON INSTRUHENTS PLEASE REPLACE CONNECTION. NUT AND FERRULE AT PENETRATION X-58 LOCATION REACTOR BUILDING 281 ECIV ROON REPLACED FLOW SUHHER
'WITH ANOTHER SUHHER REHOVED COVERS TO ALLOM WIRING INSPECTION - REPLACED COVERS WHEN INSPECTIONS COHPLETED REPLACED RELAY RPT-12 REPLACED IV 'MITH NEll ONE FROH STORES REHOVED COVER TO ALLOW 'MIRING INSPECTION " REPLACED COVER WHEN INSPECTION COHPLETED RESET RFH RELAY RESET RFH RELAY TCN TO PROCEDURE -
SYSTEM
'WORKS AS DESIGNED -
NO WORK PERFORHED RECALIBRATED H2 HONITOR HADE ADJUSTHENT TO AUTO CALIBRATION UNIT NO WORK PERFORHED TDR.SHOWS A BAD DETECTOR AND I/V CURVE, SHOWS OPEN DETECTOR TO BE REPLACE'N FUTRUE AS DIRECTED BY REACTOR ANALYSTS REPLACED CONNECTOR AT VESSEL END REPLACED FUSE REPLACED NUT AND FERRULE
NINE HILE POINT UNIT ONE Instrument 8 Controls COHPLETED SAFETY RELATED MRs FOR JANUARY 02-06-91 PAGE MR Number EPN Number TITLE
. Corrective,. Action CALIBRATED SMITCHES PER Nl-ISP-001-R005 PARTIAL - INDICATOR NOT DONE -
HONITOREO TRIP RELAYS llK39 AND 12K39 -
NO PROBLEHS NOTED Description TROUBLESHOOT REACTOR EQUAL TO OR LESS THAN 600 PSIG PRESSURE BYPASS CIRCUIT M185467 RPS-RE16A AN REACTOR 600 PSIG D RE16B PRESSURE BYPASS CIRCUIT f
I'
02-06-91 PAGE 5
MR Number EPN Number TITLE Descriotion Corrective Action NINE HILE POINT UNIT ONE Electrical Haintenance COHPLETED SAFETY RELATED MRs FOR JANUARY r M185257 01-02 121 HAIN STEAH LINE ISOLATION VALVE 01-02 M185683 M185611 RPS-RPS911K3 7B ROD BLOCK AND RECIRC SCOOP TUBE LOCK HFA RELAY RPS-FUSES REACTOR TRIP BUS 131 AND 141 FUSES DURING HAIN STEAH FEEDMATER VALVE TESTING Nl-ST-Q26 HAIN STEAH LINE IV 121 01-02 BREAKER TRIPPED LOCATED PB 1718 REACTOR BUILDING 261 EAST TROUBLESHOOT REPLACE EXISTING REACTOR TRIP BUS FUSES IN AUX CONT CABINET 1S53 BUS 131 AND AUX CONT CABINET 1555 BUS 141 MITH GOULD SHAMHUT OT FUSES PER DCR N1-90-001LS368 HFA RELAY 11K37B IS EXTREHELY NOISY ESPECIALLY MHEN COHPARED TO OTHER HFA RELAYS - PLEASE INVESTIGATE - IF PROBLEH FOUND REPAIR OR REPLACE AS REQUIRED LOCATED IN H PANEL TROUBLESHOOT SYSTEH PER ATTACHED AP-5 4.2 -
HOTOR BURNED OUT REPLACED HOTOR - VALVE MAS STUCK COULD NOT OPERATE HANUALL'Y REPLACED FUSES PER DCR N1-90-001LS368 DID TROUBLESHOOTING AS REQUIRED FOUND LOOSE COIL SCREMS IN RELAY REFERRED PROBLEM TO HETER AND TEST
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