ML20029C780

From kanterella
Jump to navigation Jump to search
Monthly Operating Rept for Mar 1994 for Indian Point Unit 1
ML20029C780
Person / Time
Site: Indian Point Entergy icon.png
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 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'

/

\\

V~

i 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 f'

P 9404290156 940331 l

DR ADOCK 0500 7

.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.

\\

1 J

+

,L s

g.

d OPERATING DATA REPORT DOCKET NO.

50-247 DATE 4/07/94 COMPLETED BY A. Reed TELEPHONE (914) 734 5155 OPERATING STATUS l

1. Unit Name:

Indian Point Unit #2 Notes

2. Reporting Period:

March.1994

3. Licensed Thermal Power (MWt):

3071.4 l

4. Nameplate Rating (Gross MWe):

1310

5. Design Electrier! Rating (Net MWe):

986 G. Maximum Dependable Capacity (Gross MWe):

985

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
15. Unit Reserve Shutdown Hours 0

0 0

10. Gross Thermal Energy Generated (MWID 2168728 6497050 327679974
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 No?

Dats.

Type' Duration

. Reason JMethod ofa iLicensee System Componenti:

Cause &. Corrective Actiosto Prevent 4 2

(Hoursh
- Sh'utting ;

[Eventi

Code'^
i. Code ~
  • Rneuheneet- ~14 5
fDown;

! RepM #'

Reactch N/A 940320 i F

0 A

4 CH HTEXCH

  1. 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 1

..