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Monthly Operating Rept for June 1986
	ML20207C317
Person / Time
Site:	Indian Point
Issue date:	06/30/1986
From:	Krieger K, Otoole J; CONSOLIDATED EDISON CO. OF NEW YORK, INC.
To:	Taylor J; NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
	NUDOCS 8607210336
	Download: ML20207C317 (7)
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OPERATING DATA REPORT 4 .

50-247 . -4 pocg DATE ti ,q o 7_- 8-86 ~~ ~

I' CoMPLETI D liYK. K r 1 eg e r

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TELLI' HONE ( 914 ) 516::5155

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.:. ~. OPER ATING STATUS 7 '. -

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' Indian Point Unit No. 27 =_ Notes ~ ~ i -i--- M- c ~ - - -2.

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.~.~- 3. Licensed Therma! Power (MWI): - 1013 - -- -3 T m__ g 7 F s- --- _.

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.' -~~. - 5. Design Efectrical Rating (Net MWe):y 7 3 ~ ~ 2 - ' -v ~ . T.

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j .- .1 6. Maximum Dependable Capacity (Gross MWe): .

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f 7., Maximum Dependatie Capacity (Net MWe): -

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! 8. If Chan;;es Occu: In Capacity Ratings (Items Number 3 Throu;h 7) Since 1.ast Report. Gid Reasons:' ~"

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, Oc-b . 9. Power LeielTo Which Restricted.lf Any (Net MWe):

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720 A : = m . M 4343 M J:r 105192-1 = -

523.33-- - -- -963.98 3'--" '70133 84- - >

12. Number of Houn Reactor Was Critical l,_ _13. Reactor Resene Shutdown Hours ~--

1 b.b/ ~196.67 n- m 3595.04

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UN- e n - -8 5 7 .-1 1 t- --67993.79 I'f 7' ' 14. Hours Generator on-Line . . _

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~ 15. Unit Resene Shutdown Hours 0 + m 0W= -_: 0 ~ .

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. . 16. Gross Thermal Energy Generated (MWH) 1.141420 2013629. 176839926 _ [..

17. Gioss Electrical Energy Generated (MhH) MU acio/u

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__ b4. Shutdowns Schema! Oict Ne.st 6 Months (Type.Date.and Duration of Each):- m'7fi: E 2 1~; ~ :._.

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[ 26. Units in Test Status (Per io rummercial Operationi: . . . _. .. m . Forecast M 's .. Achieved.

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PDR ADOCK 0D000247 +

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AVERAGE DAILY UNIT POWER LEVEL 50-247 DOCKET NO.

3,,7 I.P. Unft 2 I~ O 0 0 DATE COMPLETED BY K. Krie9er TELEPHONE (914)526-5155 June 1986 ..

MONTH DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net) (MWe-Net)

, 0 737 37 2

0 742 18 0 740 3 19 4 0 ,

20 777 s

0 834 21 0

6 22 832 0

7 23 833 8 0 835 24 172 9 25 423 0 474 to 26 191 33 27 828 12 557 837 28 625 840 13 29 14 261 830 30 15 738 -

31 16 734 INSTRUCTIONS

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On this format, list the average daily unit power levelin MWe Net for each day in the reporting month. Compute to the neares' whole megawatt. .

(9/77)

DOCKET NO.

50-247 -

UNIT SIIUTDOWNS AND POWER REDUCTIONS UNIT NAME I.P. Unit 2 DATE /-6-do COMPLETED RY K. Krieger REPORT MONTil June 1986 TELEPilONE (914)b20-blb5 n.

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, .!? .[ $ Licensee E t, f, Cause & Corrective No. Daie g 3g ,g y 5 g'2 H

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s 5 35c

- g Event Report a mu u

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o Action to Prevent Recurrence O

4 doubdl t 196.63 A 1 N/A HA lurban lurDine t.xciter uearing rrooiem .

5 860609 F 30.48 r 2 86-019 CH Pu,mgXX 21 MBFP Oil Pressure 6 860613 F 8.79 A 3 n/a HA Turbin RubbinD Coupling Guard on Main Turbine Shaft 7 860625 F 15.62 a 3 86-o21 ZZ ZZZZZZ ~ Trip signal from Independent Electrical,0verspeeh protectiori~

circuitry, during testing. (PTM-13EJ

Refer to LER e

4 1 2 3 4 F: Forced Reason: Method: Exhibit G-Instructions S: Scheduled A Equipment Failure (Explain) 1 -Manual for Preparatidn 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) 01611 E Operator Training & License Examination F Administrative 5 G-Operational Error (Explain) Exhibit 1 - Same Source (9/77) Il-Other (Explain)

I MAJOR SAFETY RELATED CORRECTIVE MAINTENANCE ir MWO SYSTEM COMPONENT DATE WORK PERFORMED 25706 CCW 21 CC Pump 5/29/86 Adjusted Seal & Gasket i

20303 PACS FCU 1309-Vlve 5/19/86 Replaced Diaphragm 1

22286 WCPS PCV 1195-Vlve 5/29/86 Replaced Gasket & Valve 25867 CVCS Sample Line 21 BAST 5/9/86 Cleared line 22868 CVCS Sample Line 22 BAST 5/9/86 Cleared line 26124 NVS Seal table lks 5/5/86 Adjusted fittings

, 19-20-27 26219 SIS Hanger-22 SIS Pump 5/28/86 Replaced Hanger 24026 SFPC Seal Leak 22 SF Pump 5/14/86 Overhauled Pump 22310 SW FIC 1176 5/12/86 Replaced 3 XMTR lines 24841 RMS PRM 11-12 5/3/86 Replaced Motor / Compressor 26294 RCS Lift Pump 24 RCP 5/21/86 Replaced Lift Pump i

26707 CCW Seal ik 21 CC Pump 5/13/86 Replaced Seal j 23167 RHR Seal ik RWST Purf. 5/1/86 Replaced Seal j Pump

1 a

4 26626 CCW 21 CC Pump 5/28/86 Rebuilt Pump 26139 RPI P/A Converters 3/29/86 Replaced Converters 21870 RPI Rod Control DC 3/21/86 Refurbished Cabinets

} Hold & Logic Cabinets 27098 RCS TE-422A & 431A 6/11/86 Installed Isolators &

Test Points 27086 SIS Relay SI-A2 6/2/86 Replaced Relay 4 27087 SIS BFD Relays SL-2, 6/2/86 Replaced Relays TR-2 & TR-2X

26293 RPI Bistables H4 & H12 6/2/86 Replaced Bistables 26330 RPI Bistables M8 & DB 6/2/86 Replaced Bistables

O

SUMMARY

OF OPERATION EXPERIENCE June 1986 The month of June began with the unit at hot shutdown. The main unit Number 11 Bearing repairs were completed and the unit wa s on turning gear by 6 June 1986: The six secondary sa fetie s, which had been repaired, were also returned to full operability by this date.

Prior to taking the reactor critical, it wa s detemined that 21 Battery Cha rger was not ope ra ble . This constituted a limiting condition for ope ra tion (L.C.O.) which precluded criticality until repairs to the battery charger returned it to full operability. A second L.C.O. , which precluded criticality at this time, wa s the inoperability of two of three 1

cha rging pumps.

Both L.C.O.s were cleared and the reactor was taken critical by 1555 on 7 June 1986. The unit was synchronized to the bus at 0438 on 9 June 1986, following slight delays caused by Main Boiler Feed Pump Oil System water ontamination. Power escalation continued throughout the day.

Manual Reactor Trip followed by automatic Safety Injection occurred on 9 June 1986. The Reactor Trip was ordered upon trip of the single operating Main Boiler Feed Pump. The Safety Injection was the result of circumstances which the protective circuitry sen sed as a situation requiring safegua rd s actuation. All protective featu re s functioned per design.

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Repairs to Main Boile r Feed Pump Bea ring Oil System were pe rformed to eliminate the root cause of Reactor Trip and the unit was retu rned to service at 0507 hours0.00587 days 0.141 hours 8.382936e-4 weeks 1.929135e-4 months on 11 June 1986. Powe r ascension to 90% wa s commenced subject to applicable fuel soak limitations.

The unit was removed from service at 2229 hours0.0258 days 0.619 hours 0.00369 weeks 8.481345e-4 months on 13 June 1986 due to rubbing between Main Turbine shaft and the coupling guard betw en #22 and 23 LP Turbine. The guard was removed and the unit returned to service at 0715 on 14 June 1986.

The Reactor was brought to 90% power by 0330 hours0.00382 days 0.0917 hours 5.456349e-4 weeks 1.25565e-4 months for final physics testing.

Indian Point 2 attained 100% Reactor Power on 20 June 1986 following physics testing at 90% power.

Reactor power was reduced to 75% when 22 MBFP was removed from service on 25 June 1986. The feedwater regulating valve for #24 Steam Gene rator developed problems which dictated a fu rther load reduction to affect repairs to the valve.

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A Reactor Trip from 45% power on 25 June 1986 was caused by a trip signal f rom the independent electrical overspeed protection circuitry. The unit was returned to service on the morning of 26 June 1986 and attained 100%

power by 1500 that day.

The month ended with the unit at 100% power. Fine tuning of the Main Turbine Genera tor was in progre ss in an attempt to increa se unit efficiency.

f e

e

John D. O'Toole

. . Vce Prssdant Consolidated Edison Company of New York, Inc.

4 trving Place, New York. NY 10003 Telephone (212) 460-2533 July 15, 1986 Re: Indian Point Unit No. 2 Docket No. 50-247 Mr. James N. Taylor, Director Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Wa shington, D. C. 20555 AT7N: Document Control Dett Enclosed a re twelve copies of the Monthly Ope rating Report for Indian Point Unit No. 2 for the month of June 1986.

Ve truly yours, I

'] g_y ff Encl.

cca Dr. Thomas E. Murley, Regional Administrator Region I U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pa . 19406 i Senior Resident Inspector ,

U. S. Nuclear Regulatory Commission l P. O. Box 38 Buchanan, New York 10511 i

6 i I >Ns i i

ML20207C317

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