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Monthly Operating Rept for Apr 1987
	ML20214E954
Person / Time
Site:	Indian Point
Issue date:	04/30/1987
From:	Josiger W, Kelly L; POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:	; NRC
References
	IP3-LMK-0129H, IP3-LMK-129H, IP3-WAJ-026Z, IP3-WAJ-26Z, NUDOCS 8705220339
	Download: ML20214E954 (7)
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-OPERATING: DATA l REPORT-__. y. '

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.Date

'05-01-87

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DocketiNo.:;50-286 6O.

,',a' Completed (By~.

L. Kelly 4..

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- Telephone 914-736-8340 -

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\\ < GOPERATING2 STATUS \\

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J1.CUnit(Name: nIndian-Point:No. 3 Nuclear Power Plant"

-Notes

'l2.Q R: porting Period:

April 1987 3..

Licensed Thermal' Power.(MWt):

~3025

,4;fNtmeplate;RatingL(Gross-MWe):

1013 5.-iD3 sign Electrical-Ratingl(Net MWe):

965 f6 M Mzximum Dependable Capacity'(Gross ~MWe): 965

7.'TMzximum Dependable Capacity.(Net: MWe):

930-( 8'.s IIf Changes-Occ'urfitil 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.d Reasons for Restrictions,,If Any: 1 33 Low Pressure Turbine was modified by replacing =

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-two rows of blades with baffle assemblies.

a This Month Yr. to Date Cumulative 4

hl'1[.rl Hours!InReporting' Period

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M12, : Number ~of1 Hours' React'or. Was ' Critical.

719#

2,879 93,504 633.42 2,616.52

-56,465.68 f13..."Reac' tor' Reserve. Shutdown Hours' 0

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.0 14? Hours Generatiorf On-Line' 1

619.25-2,587.93 ~ 54,649.46

15. l Unit. Reserve-Shutdown Hours..

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M 16.;, Cross Thermal Energy Generated- (MWH) 1,809,631.89 7,638,285- -146,171,146-

-17MGross; Electrical'EnergyGenerated1(MWH) _

<564,450 2,423,390 45,728,005: >

r18;. Net Electrical. Generated (MWH)i 543,810

2,336,093-43,876,373 119.4 Unit' Service Factor'

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86.1

- 89.9 -

58.5-Y20.,UnitjAvailabilityFactor W.

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58.5:

'21~.f Unit 1CapacityiFactorl(Using MDC, Net)l 81.3-

-87.3 50.63*J

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22.;., Unit _ Capacity Factor (Using. DER Net):.

78.4 84.1-48.6-4 l23. -Unit Forced. Outage Rate'

&3.5 4.2 19.3-

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924.c Shutdowns Scheduled Over Next 6" Months (Type,Date,and DurationLofTEach):~* Weighted Average f Cycle '5/6 Refueling Outage (5/2/87/ thru 7/30/87)'

2b.UIf h$tsDownat_End'ofReportPeriod..EstimatedDateofStartup:

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126;;; Units In' Test Status.(Prior to Commercial _ Operation):

Forecast Achieved.

INITIAL CRITICALITY' a,

INITIAL ELECTRICITY-COMMERCIAL OPERATION f.

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8705220339 870430

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' AVERAGE DAILY UNIT POWER LEVEL

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DOCKET.NO. :50-286-UNIT-IP,

DATE 01 COMPLETED BY

-L. Kelly

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TELEPHONE (914) 736-8340^

s MONTH

' April 1987 DAY

' AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVELE (MWe-Net)

..(MWe-Net) 1 0

17 224 2

'O 18 325' 3

0-19 867' 4

258 20 914 5

857 21 920-

-6 918' 22 918 7

920 23

- 918 8

919 24-919L 9

918 25 920

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10 917 26 916 11 914 27 915 12 913 28 916 13 914 29' 916-14.

912 30 916 15.

915 31 16-914 7

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INSTRUCTIONS:

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-in the reporting month. Compute to the nearest whole megawatt.

On this format, list the average daily unit power level in MWe-Net for each day.

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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

'50-286 UNIT NAME Indian Poi-t 3' 1

DATE- 05-01-87 REPORT MONTH APRIL 1987 TELEPHONE 914-736-R340 m

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wUI Licensee a

Ee Cause & Corrective e$

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Event O 45 E.'8 Action to j$

al jd Report i y0 j "'

Prevent Recurrence

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Date 03 870327 S

77.15 B

1 NA-CB PUMPXX B The unit was taken off the line in a controlled shutdown in order to replace No. 33 Reactor Coolant' Pump Sea]

l Package which had been exhibiting increases in. seal return flow.

i 04 870417 F

22.60 A

3 87-004-00 CJ-CKTBRK A A unit trip oc' curred when No. 32 Reactoi Coolant Pump lower oil reservior magnetrol grounded to its metal cover causing a drop'in voltage on instrument bus No. 33.

This resulted in an automatic reactor trip generated by a steam flow / feed flow mismatch coincident with low steam generator level. The oi]

level switch was repaired.

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F Forced Reason:

Method:

Exhibit F.- Instructions S: tekadulad A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance of Test 2-Manual Scram

. Entry Sheets for Licensee C-Refueling 3-Automatic Scram Event Report-(LER) File (NUREG D-Regulatory Restriction 4-Other (Explain) 0161)

E-Operator Training & License Examination F-A4ministrative G-Operational Error (Explain) 5 N-Other (Explain)

Exhibit H - Same Source

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MONTHIX MAINTENANCE CATECORY I ' REPORT--~

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- "1987?'

.: Ap' hill

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1 MONTH.},J WR#

DATE EQUIPMENT MALFUNCTION-

-CORRECTIVE ACTION-7911 104/02/87f Primary Sampling System,.

LValve does'not stroke open

' Replaced valve' VCT Sample Isolation Valve 265'

' 10181

' 04/02/87 Containment (SuildingPurge

, Valve doec not operate

' Installed plug:.on exhaust Supply Solenoid Valve,.

-port.of'valveL S0V-1277-

' 10142-04/03/87-SteamGeneratorBlowdown,l

' Body t'o bonnet leak-

RepairedIleaku 31 Steam Generator' Blowdown s

Isolation Valve, BD-1

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10020 04/10/87

33 Charging Pump

5 Cyclinder. packing leak'

Repacked' pump-10123 04/13/87

31 Boric Acid-Transfer Pump Ruptured valve diaphram' Replaced compressor assembly.

4 Discharge Pressure Cauge-and diaphram Isolation Valve 10231 04/16/87

31 Boric icid Transfer; Pump. Valve leaks by; Replaced bonnet.

Discharge Pressure Gauge:

Isolation Valve 10228 04/22/87~

31 Boric Acid Transfer:

Pump seals damaged Replaced pump with spare

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.!NONTHLY-I'&LC CATEGORY I.'REPORTL

-' Q' April W 1987?

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MONTH '

WRf DATE

- EQUIPMENT

- MALFUNCTION -

CORRECTIVE-ACTION'

6336, 04/01/87-

33 Reactor; Coolant Pump;

, Corroded RTD block:

'Repl' aced RTD and-rewired?

Seal' Inlet Temperature-,

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-1 Element,.TE-153-t,-.

6849-04/01/87' Reactor. Protection Relay.~-

Relay.does not energize.

JReplaced relay.with' spare.

. P-7-2 Train "A"J

'5652 04/01/87 "j

. #34 Reactor' Coolant' Pump Faulty RTD.

Replaced RTD i

. Seal Water Inlet Temperature;

' 0 7-'.

. Element, TE-152-

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6056 04/03/87

31 and #34 Reactor. Coolant!

31'and #34 RTD's wir'ed

. Repaired wiring.

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Pump Stator Temperature RTD incorrectly.

6846 04/21/87 Reactor Coolant Flow Current to' current (I/I).

Calibrated 2(I/I)

Indicator,'FI-435 isolation out'of calibration.

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6923 04/24/87

' Radiation ~ Monitoring System, ' Monitor: reads.high.

. Replaced and calibrated:

32 Main Steam'Line Monitor,

detector R-62 c

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SUMMARY

.OF OPERATING EXPERIENCE-M

" APRIL 1987; W

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InhianPoint:Nnit #3 was synchronized to the bus for a. total ~of 619.25 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months ,-

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producing ~a gros's generation of'564,450 MWe for this. reporting period.

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On March 27th-~at.1848 hours0.0214 days 0.513 hours 0.00306 weeks 7.03164e-4 months the unit.was taken off the'line-in. order:to repair 7 f.No.'33 Reactor Coolant Pump Se'l Package. In addition, No.;32 RCP Seal ~ Package a

(was replac'ed.a~sfa preventative maintenance effort.t Upon-completion of maintenance'and-testing of-the seal packages, the unit was returned to service--

on April 4th'at 0509 hours0.00589 days 0.141 hours 8.416005e-4 weeks 1.936745e-4 months .-

'On' April 17th at 0555Ihours a unit trip. occurred when No. 32 Reactor Coolant Pump lower oil reservoir magnetrol grounded.to its metal. cover causing. circuit 119 on instrument Bus No. 33 to open.- A drop in voltage on'No.-33 instrument bus w.

occurred res~ulting in an'au'tomatic reactor trip generated by a' steam flow / feed

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flow mismatch. coincident with low steam generator. level. The' failed level-iswitch, which caused the voltage perturbation on -IB No. 33, 'was're' paired.' ;The

= unit was returned.to service on April. 18, 1987 at 0431 hours0.00499 days 0.12 hours 7.126323e-4 weeks 1.639955e-4 months and-continued-to-

' produce-electricity'for'the remainder of=the reporting period.,

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Inden Point 3 Nuclear Power Plant P.O. Box 215 Buchanan, NewWrk 10511 914 739.8200

> NewYorkPbwer-tv Authority May 15, 1987 IP3-WAJ-026Z IP3-LMK-0129H 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 April, 1987.

Very truly yours, O

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'W am A J iger esident a ager Indian P i t 3 nuclear Power Plant sn:3:10 Enclosure cc:

U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.

20555 Dr. Thomas E. Murley, Regional Administrator Region-1 U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pennsylvania 19406 INPO Records Cettter Suite 1500 1100 Circle 75 Parkway Atlanta, Georgia 30339 f

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ML20214E954

Text

SUMMARY

Dear Sir:

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