ML20087L407

Monthly Operating Rept for Feb 1984

ML20087L407
Person / Time
Site:	Indian Point
Issue date:	02/29/1984
From:	Blatt M, Otoole J CONSOLIDATED EDISON CO. OF NEW YORK, INC.
To:	Mcdonald W NRC OFFICE OF ADMINISTRATION (ADM)
References
NUDOCS 8403270186
Download: ML20087L407 (7)

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OPERATING DATA RLl' ORT DOCKET 50.

50-247 DATE 3-6-84 CO3il't.E1ED llY M-B1att TELEl'IlONE f41Ai R26-5127 OPERATING STATUS Notes Indian Point Unit #2

1. Unit Name:

February, 1984

2. Reparting Period:

2758

3. Licensed Thermal Power (alW )-

1013

4. Nameplate Ratin;IGross.\\lWe):

873

5. Design Electrical Rating (Net 31We):

900

6. blaximum Dependable Capacity (Gross SIWE):

864

7. blaximum Dependable Capacity (Net 31We):

8. If Changes Occur in Capacity Ratings (items Number 3 Through 7) Since Last Report. Give Reasons:

None

9. Power Lesel To bliich Restri;ted. If Any (Net SIWE))i -

None None

10. Reasons For Restrictions.If Any:

This $lonth Yr..to-Date Cumub:!ve 696 1440 84745 II. Hours In Reporting Periou

__ 305.63 997.46 56944.68

12. Number Of Hours Reactor has Critical 0

0 2119.73

13. Reactor Resene Shutdown llours 293.77 973.50 55169.20

14. Hours Generator On-Line 0

0 0

15. Unit Reserve Shutdown Hours 772 960 2 599 755 143 640 654

16. Gross Thermal Energy Generated plWH) 238 730 813 190 44 470 766

17. Gross Electrical Energy Generated plWH) 224 033 775 379 42 402 471

18. Net Electrical Energy Generated plWil) 42.4 67.6__

65.1

19. Unit Senice Factor 42.4 67.6 65.1

20. Unit Availability Factor 37.3 62.3 58.2

21. Unit Capacity Factor IUsing 310C Net) 36.9 61.7 57.3

22. Unit Capacity Faetor IUsing DER Nett 57.8 32.4 9.8

23. Unit Forced Outage Rate

'24. Shutdowns Seheduled Oser Next ti alonths IType. Date.and Duration of Eacht:

20 Year In Service Insnection/Refuelino Outaae Scheduled to begi,3_

June 3, 1984.

25. If Shut Down At Ehd Of Report Period.Estimaird Date of Startup:

Forecast Achiesed

26. Units in Test Status (Prior to Commercial Operation):

N/h N/A INITITL CRITICTLITY INITI \\l. FI l'CTRICI TY a

CO%l\\ll'RCITL OPI'RAIION 8403270186 840229 PDR ADOCK 05000247 R

PDR 19/77) s

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AVERAGE DAILY UNIT POWER LEVEL 50-247 DOCKET NO.

UNIT IP - _ fin i t No. 2 DATE 3-6-84 1att COMPLETED BY TELEPllONE (914) 526-5127 Pebruary, 1984 MO TH C'AY AVElbtGE DAILY PbWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net)

(Mwe. Net) 3 832 0-g7 829 0

2 g,

827 0

3 19 4

821 0

20 819 0

21 6

919 22 0

7 835 0

23 814 0

g 24

'9 606 25 0

10

• O 0

26 534 165 11.._

3 12 0

28 804 13 O

831 29 0

34 30

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'15 0

3g 16 0

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INSTRUCTIONS.

On this format, list the average daily unit power level in MWe. Net for each day in the reporting month. Compute o the nearest whole tregawait.

(9/77)

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UNITSHUIDOWNS AND POWER REDUCTIONS DOCKET NO.

Mn_947

- a UNIT NAME JP Unie n?-

DATE 3 4,.84._

COMPLETED ay M.

Blatt REPORI' MONTil Pehritary, 1984 TELEPHONE (914) 526_5127 l

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3 jY5 Licemee E r, K

Cause & Corrective No.

D.ite E'

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.pi j 5 Event s?

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Acti.n to S

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3 g =!

Repsut #

<N 0

$0 Present Recurrence e

o 6

Control 2

2/9/84 P

27.72 D

1 IB Instru.

Rod Position Indicator Repair 9

84-003 r

3 2/11/84 P

374.52 A

1 CC HT Exch Steam Generator Tube Leak P

1 i,

1 t

2 3

4 l'

Feet ed Rea>on:

Method:

Exinbn G Instructions S: S heduled A li uipment Failure (Esplain) 1-Manual for Preparation of Data l

B-Maintenance of Test 2-Manual Scram.

Entr> Sheets fur Licensee C-Refueling 3-Automatic Scram.

Event Report (LERI File tNUREG-D Regulatory Restriction 4-Other IExplain) 016li E-Operator Training & License Fxamination F-Administrative 5

G-Operational Error (Explain)

Exhibit I Same Source t!77 )

Il4hher(Explain) 1

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Summary of Operating Exper3ence Februaty 1984 Unit-2 was at 100% reactor power at the beginning of the report period.

On February 8, reactor power was briefly reduced to 86% to investigate low instrument air pressure.

The cause of this was determined to be excessive leakage at a branch connection fitting inside the vapor containment building.

Instrument air prassure returned to normal after the connection was isolated, and the unit was returned to 100% power.

On Feburary 9, digital Voltmeter readings indicated two (2) control rod position indications in one bank to be out of specification.

The reactor was brought to hot shutdown and all rod position indicators were recalibrated.. At 2257 on February 10, the unit -was synchronized to the bus and a gradual return to 1004 power initiated.

On February 11, a reactor shutdown was initiated to repair a primary to secondary leak in number 22 steam generator.

The reactor reached cold shutdown conditions by February 12.

A single tube leak in the steam generator was identified and mechanically plugged.

Eddy current testing indicated the leak was on the hot leg, at or near the secondary face of the tube sheet.

Thirteen (13) surrounding tubes were similarly tested in the. same general area and no significant. indications were found.

Other major work accomplished during this outage included preventive maintenance on number 22 reactor coolant pump seal package, inspection and cleaning of all fan cooler unit cooling coils, changeout of number 22 RHR pump and the blanking off of valve FCV 1173 in the conta'nment purge

- ex.aust line.

The containment exhaust valve was blanked due to em:essive weld channel air leakage.

This valve is scheduled to be repaind during the upcoming refueling outage.

On February 24, a successful -hydrostatic test was performed on the reactor coolant system. On February 26, plant heatup was initiated. The reactor was made critical and synchronized to the bus at 1010 on February 27; it was returned to 100% power that same day.

On February 27, reactor power was reduced to 91% while the hand speed changer on number 21 main boiler feed pump was adjusted.

The. reactor was returned to 100% power and remained there for the rest of the month.

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MAJOR SAFETY RELATED C0RRECTIVE MAINTENANCE MNR NO.

DATE COMPOi!ENT SYSTTM CORRECTIVE ACTION

- 2450 11/7/83 R13/R14 RM Replaced pump 5875 11/22/83 25 FCU

- SW Replaced elbow

- 5975 11/27/83 765A Gate Valve ACS Replaced gate 6401 11/15/83 22 SG Blowdown SGB Repaired piping leak

-n?665-11/17/83 Pump 0031-010 SW Overhauled pump 9721'-

_11/4g83~

~ MG Set 22 Rod Drive ELEC Repaired MG set

- 10274

.11/9/83 21 SW Pump' SW Tightened flange Discharge Flange' 10524 11/10/83 22 Charging Pump CVCS Repacked pump

-11212' 11/23/83 Heat Trace Circuit ELEC Replaced heater e

46B 11216 11/26/83 21'MBFP Discharge FW Replace 1 operator valve 1236 12/6/83 21 RCP Jib Crane CM Installed Crane 6201 12/18/83 25 FCU HVAC Repaired Fan Boot-9436

'12/5/83 Pump 0031-005 SW Overhauled Pump

~10440

'12/22/83 Valve PW-383 PMW Repaired Leak 11199 12/29/83-Valve PCV 1189 AEW Adjust ed Limit Switch

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MAJOR SAFETY RELATED CORRECTIVE MAINTENANCE MWR NO.

DATE COMPONENT SYJTEM CORRECTIVE ACTION 11358 12/9/83 30' EL Air Iock VC Test Operated Door Door 3,.

11422 12/13/84 23 Cherging CVCS Rebuilt Seals Pump 11384 12/15/83 22 Charging Pump 'CVCS Replaced Packing 11446 12/29/83 VA-8 CVOS Replaced Diaphragm 11457 12/19/83 21 SWP Check SW Open/ Adjusted Valve Valve 11466 12/20/83 21 SW Pump SW Replaced Pump 11619 12/20/83 SOV 1280 WCCP Replaced Coil l

11662 12/23/03 21 SWP Chcck SW Repaired Valve l

Valve 11679 12/27/83 23 SWP Check SW Repaired Valve Valve e

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John D. O'Toch Oce Prescerg Consondated Edison Company of New York. Inc 4 Irv:ng Piace, New York, NY 10003 Telephone (212) 460-2533 March 15, 1984 Ret Indian Point Unit No. 2 Docket No. 50-247 Mr. William G. Mcdonald, Director Office of Management Infonnation and Program Control c/o Distribution Services Branch, DDC, ADM washington, D. C. 20555 Dear Mr. Mcdonald Enclosed you will find two copies of the Monthly Operating Report for 4

Indian Point Unit No. 2 for the month of February 1984.

Ve truly yours, e

l L

j (L-Encl.

cc:

Mr.. Richard DeYoung, Director (40 copies)

Office of Inspection and Enforcement c/o Distribution Services Branch, DDC, ADM U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Dr. Thomas E. Murley, Regional Administrator Region I U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pa.

19406 Mr. Thomas Foley, Senior Resident Inspector U. S. Nuclear Regulatory Commission P. O. Box 38 Buchanan, New York 10511

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