ML20069B326

Monthly Operating Rept for Nov 1981

ML20069B326
Person / Time
Site:	Indian Point
Issue date:	12/04/1981
From:	Eich E CONSOLIDATED EDISON CO. OF NEW YORK, INC.
To:
Shared Package
ML20069B323	List: ML20069B319 ML20069B326
References
NUDOCS 8112240175
Download: ML20069B326 (5)

Text

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e OPERATING DATA REPORT DOCKET NO. 50-747 DATE 12-4-91 CO5!PLETED BY r e nich TELEPl!ONE "014-526-5155 OPERATING STATUS

!. Unit Name: Indian Point Station Unit No. 2 Not'5 November, 1981

2. Reporting Period:

3. Licensed Thermal Power (51W ):

2758 I;one

4. Namep!ste Rating (Gross 51We):

1013 873

5. Design Electric =1 Rating (Net 51We):

900

6. 51sximum Dependable Capacity (Gross S!We):

7. S!sximum Dependable Capacity (Net 51We):

8. If Changes Occurin Capacity Ratings (Items Number 3 Through 7)Since Last Report Give Re. sons:

nin

9. Power Level To Which Restricted. lf Any (Net S!We):

"nMr

10. Reasons For Restrictions. If Any:

M/A

,I l

This 5fonth Yr..to.Date Cumutstive

[

11. Hours In Reporting Period 720 8016 65041 l

12. Number Of Hours Reactor Was Critics!

432.95 3413.62 41577.53 L.

13. Reactor Reserve Shutdown Hours 0

54.64 1527.43 c

426.77 3206.62 40367.00

14. Hours Generator On-Line

15. Unit Reserve Shutdown Hours 0

0 0

16. Gross Therms! Energy Generated (51WII) 1145536 8467303 104275731 365330 2561170 32181216

17. Gross Electrical Energy Generated (51WH) 347791 2422312 30651636

18. Net Electrical Energy Generated (51WH)

19. Unit Service Factor 59.3 41.0 62.1

20. Unit Availability Factor 59.3 41.0 62.1

{

21. Unit Capacity Factor (Using SIDC Net) 55.9 35.3 54.8 55.3 34.6 54.O I

22. Unit Capacity Factor (Using DER Net 1

23. Unit Forced Outage Rate

24. Shutdowns Scheduled Over Next 6 Stunths (Type.Date.and Duration of Esch1:

nnnn

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

"/"

i

25. Units In Test Status (Prior o Commercial Operation):

Forecast Achiesed

=

INITIA L CRITICALITY INITIA L ELECTRICITY CON!stERCIA L OITR ATION N/A 8112240175 811215

(

PDR ADOCK 05000247

ggf77, R

PDR

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-247 _

UNIT IugIA" POT"? STATION DATE nit-..

U No. 2 AI./ 4 / o A i

COMPLETED BY E.P.

Eich 1

TELEPIIONE 91 A M M-91 sq MO$Tl!

November 1981

- DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL

~

(MWe Net)

(MWe. Net) 1.

R91 37 0

776 0

2 j

18 b l 3

_ 653 0

19

{.

4

'Ad4 20 0

I w

5 847 21 0

i; H!

6 330 22-n 7

450 23 0

~

8 845 2g 556 l

9 850 25 857 10 949 26 855 I

1.

. ! lV 11 734 27 851

.J 13 O

858

.l-12 0

857 2S

~

29 t

14 n

30 859 0

15 -

33 d

l 16 e

I J e t

l INSTRUCTIONS.

j On this format. fist the average daily unit power Icve! In MWe. Net for each day in the reporting month. Compute to

.the ricarest whole megsws:t.

.i 1

-d (9/77)

I' l

l l

i 1

\\

i f

i L.

DOCKETNO.

50-2'?

UNITSilUTDOWNS AND POWER REDUCI10NS UNIT NAME

.r.

" nit "o.2 REPORT MONTil NOVEMBER 1981 CbMPLETED BY F,

TELEPilONE a.'-5205155 e.

.! E 3

Ak Licensee

Hat,

~,,

Cause & Correvive No.

. Date g

3g i

jg5 Event g "L2 os Action o H

5 Ji gg g Report #

wU

$U Present Recurrence u

O 12 11/11/81 F

290.47 A

2 81-030 CB PumpXX Repair No. 23 reactor coolant (For info).

X.

Pump Scal.

~

13

,11/24/81 F

2.76 A

3 r!J

!!TEXCII N/A 2 2 Steam Generator !!i Loved.

p T

/

I 2

3 4

F: Forced Reason:

Method:

Exhibit G-Instructions

- S Scheduled A Equipment Failure (Explain) 1-Manual for Preparation of Dass B Maintenance of Test

'2 ManualScram.

Entry Shests for Licensee C Refueling 3-Automatic Scram.

Event Report ILER) File INUREG-D-Regulatory Restriction 4-Other(Explain) 0161)

E-Operator Training & License Examination F Administrative '-

5 G-Operational Error (Explain)

E.shibit I Same Source 19/77)

Il-Other (Explain)

+

SUMMARY

OF OPERATING EXPERIENCE November, 1981 Docket No.

50-247 Late:

12/8/81 Completed Dy:

J. Curry Telephone: (914) 52G-5235 November started with Indian Point No. 2 operating at 100% reactor power.

On November 2, 198L the load was reduced briefly to repair a leak in the cross under piping to No. 21A moisture separator reheater. Unit No. 2 operated at full load until Wednesday evening, November 11, when a failure of the No I coal on No. 23 reactor coolant pump required a plant chutdown. After reaching cold shutdown conditions on Friday, November 13, Unit No. 2 reactor coolant system was depressurized and drained :;or repairs to the controlled leakage coals

)

on No. 23 reactor coolant pump.

Repairs to the seals w?re completed and during reactor coolant heatup to the hydrostatic test temperatt:re on Thursday, November 19, one of the pressuri cr code safety valve (PCV-464) lifted pre-maturely at approximately 2350 psig. The system was brot ght to the cold shut-down condition and the valve reset to the correct lifting pressure After the conduct of a successful reactor coolant system hydrostatic test and replacement of No. 22 high head safety injection pump with a spare, Unit f

No. 2 was returned to service on Monday, November 23, but tripped automatically I

approximately forty-five minutes later due to high drum icvel in No. 22 steam generator. The unit was again returned to service on Tuesday, November 24 and the load raised to the 100% reactor power level and remained at this level for the remainder of the month.

l

~

~

MECHANICAL AND ELECTRICAL MAINTENANCE Docket No. 50-247' Indian Point Unit No. 2 November, 1981 Date Component MWR Malfunction Corrective Action 11/19/81 No. 23 Reactor Coolant 2NS-6151 tb. 1 Seal Failure Replaced ceals Punp 11/22/81 No. 22 High Head Safety 00042 Pump Seized Replaced with spare punp Injection Pump O

t.

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