ML20207R686

Monthly Operating Rept for Feb 1987

ML20207R686
Person / Time
Site:	Indian Point
Issue date:	02/28/1987
From:	Josiger W, Kelly L POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
IP3-LMK-059H, IP3-LMK-59H, IP3-WAJ-017Z, IP3-WAJ-17Z, NUDOCS 8703180023
Download: ML20207R686 (7)

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OPERATING DATA REPORT Docket No. 50-286 Date' 03-02-87 Completed By L. Kelly-

! Telephone 914-736-8000 OPERATING STATUS

.1, Unit Name: Indian Point No.'3' Nuclear Power Plant Notes

~2. Rsporting Period: February 1987

3. Licensed Thermal Power (MWt): 3025

4. Nimeplate Rating (Gross MWe): 1013

5. D3 sign Electrical Rating (Net MWe): 965

-6. ' Maximum Dependable capacity (Gross MWe): 965 7.. .

MIximum Dependable Capacity (Net MWe): 930

8. ..If Changes'0ccur in Capacity Ratings (Items Number 3 through 7) Since Last Report.

Give Reasons:

9. Power Level to Which Restricted, If Any (Net MWe): 930 Net MWe-

10. Reasons for Restrictions, If Any: .# 33 Low pressure turbine was modified by replacing tws rows of blades with baffle assemblies.

This Month Yr. to Date Cumulative

.11. Hours In Reporting Period 672 1416 92,041

12. Number of Hours Reactor Was Critical 605.67 1339.75 55,188.91

.13. Reactor Reserve Shutdown Hours 0 0 0

14. Hours Generator On-Line 591.80 1325.88 53,391.47 15.- Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 1,680,056.824 3,897,976 142,430,837

17. Gross Electrical Energy Generated (MWH) 534,360 1,243,730 44,548,345

18. Net Electrical Generated (MWH) 514,493 1,198,907 42,739,187

-19.- Unit-Service Factor 88.1 93.6 58.0

- 20. . Unit Availability Factor 88.1 93.6 58.0

21. Unit Capacity Factor (Using MDC Net) 82.3 91.0 50.1*

22. Unit Capacity Factor (Using DER Net) 79.3 87.7 47.5 6.4 19.6

23. Unit Forced Outage Rate 11.9

. 24. ' Shutdowns Scheduled Over Next 6 Months (Type Date,and Duration of Each):

• Weighted Average 90 Day Cycle 5/6 Refueling Outage Starting 5/1/87 l

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25. If Shut Down at End of Report Period. Estimated Date of Startup:

, 26. - Units In Test Status (Prior to Commercial Operation): Forecast Achieved .

INITIAL CRITICALITY

. INITIAL ELECTRICITY COMMERCIAL OPERATION f

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AVERAGE DAILY UNIT POWER LEVEL

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DATE 03-02-87

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[ ,,7 -COMPLETED BY L. Kelly

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MONTH ygbruary 1987

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1sAY- AVERAGE DAILY POWER LEVEL- DAY AVERAGE DAILY POWER LEVEL T

(MWe-Net) (MWe-Net)

-c , s 1 - ' />' ' O 17 928 f

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2 i.~-. f 180 18 931

, '.i 3 7' 806~ 19 932 w ' *L ', [

y- 4 A ~' % 931 20 933 k.x - s -

AJ 5 932 21 933 N '

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932 24 930

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INSTRUCTIONS:

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4 On this fornat, list the average daily unit power level in MWe-Net for each day inthere[ortingmonth. Compute to the nearest whole megawatt.

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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET No. 50-286-UNIT NAME Indirn P7.ipt 3 DATE 03/02/97 REPORT MONTH powruary log 7 TELEPHONE 914-739-8230-m we o a *?U tm o O en E ,s U E Licensee a E= Cause & Corrective S

U$ E S$" Event 3$ E.'o Action to No. Date jj0 $ jN Report # [p O 8" Prevent Recurrence 01 870131 F 33.47 A 3 87-001-00 HH Pump XXH Unit trip due to low level in 33 Stean Generator Caused by a trip of 32 Main Boiler Feed Pump.

02 870211 F 46.73 A 3 87-002-00 10C Valvop-E A solenoid valve in the Penetration

and Liner Weld Joint Pressurization ,

System short circuited and tripped-

1. 34 Instrument bus. The loss of the instrument bus caused a runback of both main boiler feedpump speed control systems and led to a unit trir caurad by a steam flow / feed flow mismatch signal coincident with a low level in steam generator #34.

i 1 2 3 4 i F: Forced Reason: Method: Exhibit F - Instructions l S: Scheduled A- Equipment Failure (Explain) 1- Manual for Preparation of Data B- Maintenance of Test 2- Manual Scram Entry Sheets for Licensee l, C- Refueling 3- Automatic Scram Event Report (LER) File (NUREG-D- Regulatory Restriction 4- Other (Explain) 0161) i E- Operator Training & License Examination

, F- Administrative G- Operational Error (Explain) 5 H- Other (Explain) Exhibit H - Same Source r

2 ,

MONTHLY I & C CATEGORY I' REPORT.

[ t February 1987 l MONTH j WR# DATE -EQUIPMENT MALFUNCTION CORRECTIVE ACTION 6395 01/28/87 Boric Acid Heat Trace Test switch broken  ! Replaced broken switch

. Circuit 4 Pane? 33A 6559 02/02/37 Condensate Storage Tank Transmitter capsule failed Replaced transmitter

Level Indicator LI-1128A 6653 02/10/37 Primary Water Storage Tank -Indicator reads down-scale Replaced' amplifier and Level Indicator, LI-1131 calibrated-i 6570 02/11/87 Reactor Coolant System, Faulty capacitors Replaced three capacitors-i Pressurizer Modulating 9

Heater Transformer ,

j 6650 02/12/87 Reactor Coolant System. Power supply breaker tripped Replaced transformer. ,

Pressurizer Modulating 4

Heater Transformer 6682 02/12/87 #33 Static Inverter Low Output Voltage during Replaced transformer,

, extended load test resistors,' fuses and diodes 6684 02/12/87 Radiation Monitoring System, Detector failed Replaced G-M tube ' !-

Containment Gas Monitor, R-12

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MONTHLY MAINTENANCE CATEGORY I REPORT ','

February 1987-MONTH WR# DATE EQUIPMENT MALFUNCTION CORRECTIVE ACTION 9841 02/10/87 Reactor Coolant System Blowdown valve leaks by Installed caps on the Loop Flow Indicator, FI-435 blowdown of FI-435 9864 02/11/87 Reactor Coolant System Loop Blowdown valve leaks by Replaced blowdown valve Flow Indicator, FI-446 9870 02/11/87 Penetration and Liner Weld Solenoid valve coil failed Replaced coil-Joint Channel Pressurization System, Zone 4 Weld Channel, Solenoid valve SOV-1197 9867 02/12/87 #34 Fan Cooler Unit Motor Inlet and outlet water Replaced inlet and outlet Cooler hoses leak water hoses 9876 02/12/87 Radiation Monitoring System, Pump trips Replaced pump assembly Containment Air Particulate /

Gas Monitor R-11/12 9868 02/12/87 Steam Generator Blowdown, Valve leaks by Repaired leak with sealant J

Blowdown Valve BD-1 9815 02/19/87 Chemical and Volume Control . Seal leak on pump Repacked cylinder j System, #33 Charging-Pump 9861 02/20/87 Fuel Storage Building ' Fan belts worn Replaced belts and lubricated Exhaust Fan fan and motor 1

i 1

SUMMARY

OF OPERATING EXPERIENCE FEBRUARY 1987 Indian Point Unit #3 was synchronized to the bus for a total of 591.80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />,

-producing a gross generation of 534,360 MWe for this reporting period.

On January 31, 1987, a reactor trip and subsequent turbine trip were initiated automatically by low steam generator (SG) water level. Investigation determined that foreign matter had accumulated in the multiple orifice and check valve assembly in the control oil system for No. 32 Main Boiler Feed Water Pump (MBFP), causing the pump to trip. The resultant decrease in feedwater system flow caused SG 1evels to decrease to the reactor trip setpoint, thus, causing a reactor trip. To prevent recurrence, the control oil system components were cleaned and reinstalled and the high pressure oil filter was replaced on No. 32 MBFP. The control oil system for No. 31 MBFP was similarly inspected and found to be clean. As a precautionary measure, the oil in the common control oil system for both pumps was replaced with clean oil. The unit was returned to service on February 2, at 0928 hours0.0107 days <br />0.258 hours <br />0.00153 weeks <br />3.53104e-4 months <br />.

On February ll, at 0828 hours0.00958 days <br />0.23 hours <br />0.00137 weeks <br />3.15054e-4 months <br />, No. 34 static inverter tripped due to an overcurrent condition caused by a short-circuited solenoid valve. This resulted in a runback of both main boiler feedpump speed control systems and led to a unit trip caused by a steam flow / feed flow mismatch signal coincident with a low level in steam generator No. 34. To prevent recurrence, the design of No. 34 static inverter was improved by removing the instantaneous output breaker trip.

This change will not alter the thermal overload protection but will allow isolation of a single branch circuit (rather than the stat 1c inverter) if a short circuit develops. The failed solenoid valve coil was replaced with a coil of a higher temperature design. As a precautionary measure the other three identical solenoid valve coils in the Penetration and Liner Weld Joint Pressurization System were similarly replaced. Other affected systems were verified to be functioning normally before start-up.

The unit was returned to service on February 13, at 0710 hours0.00822 days <br />0.197 hours <br />0.00117 weeks <br />2.70155e-4 months <br /> and continued to produce electricity for the remainder of the reporting period.

. Indian Point 3

. Nuclear Power Plant P.O. Box 215 Buchanan, New Wrk 10511 914 739.8200

1. > NewYorkPbwer 4# Authority March 13,1987 IP3-WAJ-017Z IP3-LMK-059H Docket No. 50-286 License No. DPR-64 Director, Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Dear Sir:

Enclosed you will find the monthly operating report relating to Indian Point 3 Nuclear Power Plant for the month of February, 1987.

Very truly yours, W am A. Josi er esident M na r Indian Po n 3 nuclear Power Plant Lb -

.08 Enclosure cc: U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Dr. Thomas E. Murley, Regional Administrator Region 1 l U.S. Nuclear Regulatory Commission i

631 Park Avenue King of Prussia, Pennsylvania 19406 INPO Records Center Suite 1500 1100 Circle 75 Parkway l Atlanta, Georgia 30339 l

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