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

- - ,

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 Not'5

!. Unit Name: Indian Point Station Unit No. 2 -

2. Reporting Period:

November, 1981

3. Licensed Thermal Power (51W ): 2758 I;one

4. Namep!ste Rating (Gross 51We): 1013

5. Design Electric =1 Rating (Net 51We): 873

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

900

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 -

14. Hours Generator On-Line 426.77 3206.62 40367.00

15. Unit Reserve Shutdown Hours 0 0 0

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

17. Gross Electrical Energy Generated (51WH) 365330 _,

2561170 32181216

18. Net Electrical Energy Generated (51WH) 347791 2422312 30651636

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  !

22. Unit Capacity Factor (Using DER Net 1 55.3 34.6 54.O I

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 l U

DATE nit- .

AI./ 4 / o A

. No. 2 i

COMPLETED BY E.P. Eich 1

TELEPIIONE 91 A M M-91 sq MO$Tl! November 1981 .

, . l

- DAY AVERAGE DAILY POWER LEVEL DAY

~ AVERAGE DAILY POWER LEVEL l (MWe Net) (MWe. Net)  !

1. R91 37 0 776 0 j 2 18 .

bl 3 _ 653 .

19 0 ,

{.

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.

!. 11 734 851 * .

27 . ! lV .J 0 857 12 2S . .

" .l-

~

13 O -

858 .

29 _

t 14 n 859  !:

30 ,-

15 - 0 d 33 _

l -

! 16 e .,-

I l

t J e -

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 I'

(9/77) 1 -

-d l -

l l l

\

1 i

% i f

! i L.

UNITSilUTDOWNS AND POWER REDUCI10NS , '

DOCKETNO. 50-2'?

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 wU u$U

$ :,,, Ji gg g Report # Present Recurrence 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 p 2 2 Steam Generator !!i Loved.

T -

/

I 2 3 4 F: Forced Reason: Method:

- S Scheduled Exhibit G-Instructions 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  !

approximately forty-five minutes later due to high drum icvel in No. 22 steam I 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

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