ML20029C780

Monthly Operating Rept for Mar 1994 for Indian Point Unit 1. W/940415 Ltr

ML20029C780
Person / Time
Site:	Indian Point
Issue date:	03/31/1994
From:	Bram S, Reed A CONSOLIDATED EDISON CO. OF NEW YORK, INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9404290156
Download: ML20029C780 (6)

Text

-

St: phen B.Cr m

.A- , Vce Pretkient M I Consolidated Edison Company of New York, Inc.  ;

I Indian Point Station Broadv/ay & Bleakley Avenue April 15, 1994 Buchanan, NY 10511

• Telephone (914) 734 5340 Re: Indian Point Station Docket No. 50-247 Director, Office of Resource Management US Nuclear Regulatory Commission Washington, DC 20555 Dear Sirs Enclosed are twelve copies of the Monthly Operating Report for Indian Point Unit No. 2 for the month of March, 1994.

Very truly yours, l l' i / \

V~

Enclosure cc Document Control Desk US Nuclear Regulatory Commission Mail Station Pl-137 Washington, DC 20555 Mr. Thomas T. Martin Regional Administrator - Region I US Nuclear Regulatory Congnission 475 Allendale Road King of Prussia, PA 19406 Senior Resident Inspector US Nuclear Regulatory Commission PO Box 38 Buchanan, NY 10511 P

f' 9404290156 940331 7 DR ADOCK 0500 l

.i

,, , ~.. - - _ ~, .

SUMMARY

OF OPERATING EXPERIENCE

~ tiarch. 1994 The unit operated at 100% reactor power for the entire month of March with the following exceptions:

Reactor power was reduced to approximately 89% at 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br /> on March 16th to perform the periodic stop valve test.

Reactor power was returned to 100% at 0200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> on March 17th.

I Reactor power was reduced to a low of approximately 34% at 0500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> on March 23rd due to a primary to secondary leakago in Steam Generator N24. Power was leveled off and held at 36%.at 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br /> on the same day. The 36% power level was held until 1800 hours0.0208 days <br />0.5 hours <br />0.00298 weeks <br />6.849e-4 months <br /> on March 23rd when the reactor power was raised to 40% and held. Reactor powar was raised to 50% at 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br /> on March 24th and held until 0130 hours0.0015 days <br />0.0361 hours <br />2.149471e-4 weeks <br />4.9465e-5 months <br /> when the level was raised to 60% and held. The unit was raised to 70% reactor power at 1530 hours0.0177 days <br />0.425 hours <br />0.00253 weeks <br />5.82165e-4 months <br /> on March 24th.

This power level was held until 1730 hours0.02 days <br />0.481 hours <br />0.00286 weeks <br />6.58265e-4 months <br />, when the level was raised to 80% and held. At 2230 hours0.0258 days <br />0.619 hours <br />0.00369 weeks <br />8.48515e-4 months <br /> on March 24th the reactor power level was raised to a high of approximately 92%. At this power level, the tube leak in Steam Generator

1. 24 became more evident. 'I he unit's power was then reduced to approximately 90% at 030t hours. At this level, the leak again became slight and 1ower was held there for the ,

remainder of the month. l

\

l l

1 J

- + , *

,L s g.

d -

OPERATING DATA REPORT DOCKET NO. 50-247 l DATE 4/07/94 COMPLETED BY A. Reed TELEPHONE (914) 734 5155 OPERATING STATUS l

1. Unit Name: Indian Point Unit #2 Notes l

2. Reporting Period: March.1994 1

3. Licensed Thermal Power (MWt): 3071.4 l

4. Nameplate Rating (Gross MWe): 1310 l

5. Design Electrier! Rating (Net MWe): 986 G. Maximum Dependable Capacity (Gross MWe): 985 l

7. Maximum Dependable Capacity (Not MWe): 951

8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7 smee Last neport, vive neasons:

9. Power Level To Which Restricted, If Any(Net MWe):

10. Reasons For Restrictions, If Any:

This Month Yr..to-Date Cumulative

11. Hours In Reporting Period 744 2160 173137

12. Number Of Hours Reactor Was Critical 744 2160 121734.86

13. Reactor Reserve Shutdown Houra 0 0 4118.52 -l

14. Hours Generator On-Line 744 2160 118709.34 l

15. Unit Reserve Shutdown Hours 0 0 0  !

10. Gross Thermal Energy Generated (MWID 2168728 6497050 327679974

l

17. Gross Electrical Energy Generated (MWH) 697241 2088572 100481155

18. Net Electrical Energy Generated (MWH) 673356 2019190 96169420

19. Unit Service Factor 100.0 100.0 68 6 h Unit Availability Factor 100.0 100.0 68.6 :i '

21. Unit Capacity Factor (Using MDC Net) 95.2 98 3 63.6

22. Unit Capacity Factor (Using DER Net) 91.8 94.8 62.0

23. Unit Forced Outage Rate 0 0 68

24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each)-

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

26. Units In Test Status (Prior to Commercial Operationh Forecast Achieved INITIAL CRITICALITY N/A N/A.

INITIA.L ELECTRICITY N/A -N/A COMMERCIAL OPERATIO.N N/A N/A

. (9/77)

1

. i AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-247

. UNIT I.P. Unit #2 DATE 04/07/94 l COMPLETED BY A. Reed TELEPHONE (914) 734 5155 MONTII March,1994 -

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

1 953 17 953 .

2 957 18 958 2

3 955 19 961 4 960 20 964 5 959 21 958 6 956 22 958 7 955 23 364 8 956 24 655 9 955 25 852 10 955 26 846 11 955 27 843 j 12 957 28 860 13 955 29 868 14 955 30 . , _ _ ,

868 15 957 31 8't 1 16 940 INSTRUCTIONS On this format, list the average daily unit power leve: in 'MWe Net for each day in the reporting month.

Compute to the nearest whole megawatt. (9/77) -

UNIT SHUTDOWNS AND POWER REDUCTIONS .

DOCKET NO. 50-247 - c ,

UNIT I.P. Unit #2 DATE 04/07/94 -

COMPLETED BY A. Reed ,

REPORT MONTH March,1994 TELEPHONE (914) 734-5155 2

No? Dats . Type' Duration . Reason JMethod ofa iLicensee System Componenti: Cause &. Corrective Actiosto Prevent 4 5

(Hoursh

- Sh'utting ; [Eventi  : Code'^ i. Code ~ *Rneuheneet-

~14

fDown;  ! RepM #' . . _

. ;Reactch '

N/A 940320 i F 0 A 4 CH HTEXCH #24 Steam Generator Tube Leak Rx.

Remmned Critical t

1 2 3 4 F: Forced Reason: Method: Exhibit G - Instructions .

S: Scheduled A - Equipment Failure (Explain) 1 - Manual for Preparation of Data "

B - Maintenance or Test 2 - Manual Scram. Entry Sheets of Licensee C - Refueling 3 - Automatic Scram. Event Report (LER) File (hTREG- i D - Regulatory Restriction 4 - Other (Explain) 0161)

E - Operator Training & Licensee Examination F- Administrative G - Operational Error (Explain) 5 (9/77) H - Other (Explain) Exhibit 1 - Same Source

, -. , , . - - ,- . . . . ~ - _ . = . - - = . . . ,. . - . _ . . . . . . . __

l.

-8

, .,-a

. . t MAJOR SAFETY-RELATED CORRECTIVE MAINTENANCE f"

Date IfdQ System comoonent Comoleted Work Performed

-None i

4

. ,)

I i

l I

1 l

l 1

,. _ _ . . _ . .. . .