NL-03-143, August 2003 Monthly Operating Report for Indian Point Unit 2

August 2003 Monthly Operating Report for Indian Point Unit 2

ML032600566
Person / Time
Site:	Indian Point
Issue date:	09/12/2003
From:	Dacimo F Entergy Nuclear Northeast
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-03-143
Download: ML032600566 (6)

Text

-%En-tergy Entergy Nuclear Northeast Indian Point Energy Center 295 Broadway, Suite 1 PO. Box 249 Buchanan, NY 10511-0249 Tel 914 734 5340 Fax 914 734 5718

~~~~~~~~~~~~~~~~~~~~~Fred Dacimo Vice President, Operations September 12, 2003 Re:

Indian Point, Unit No. 2 Docket No. 50-247 NL-03-1 43 Document Control Desk U.S. Nuclear Regulatory Commission Mail Stop O-P1 -17 Washington, DC 20555-0001

Subject:

Monthly Operating Report for August 2003

Dear Sir:

This letter provides the Monthly Operating Report for Indian Point 2 for the month of August 2003, in accordance with Technical Specification 6.9.1.7. There are no commitments contained In this correspondence.

Should you or your staff have any questions regarding this matter, please contact Mr. John McCann, Manager, Licensing, Indian Point Energy Center at (914) 734-5074.

Sincerely,

(

Fred R. Dacimo Vice President, Operations Indian Point Energy Center

NL-03-143 Page 2 of 2 Attachments cc:

Mr. Hubert J. Miller Regional Administrator - Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1498 Mr. Patrick D. Milano, Project Manager Project Directorate I Division of Reactor Projects I/Il U.S. Nuclear Regulatory Commission Mail Stop O-8-C2 Washington, DC 20555-0001 Senior Resident Inspector U.S. Nuclear Regulatory Commission Indian Point Unit 2 P.O. Box 38 Buchanan, NY 10511-0038 Senior Resident Inspector U.S. Nuclear Regulatory Commission Indian Point Unit 3 P.O. Box 337 Buchanan, NY 10511-0337 Mr. Paul Eddy State of New York Department of Public Service 3 Empire Plaza Albany, NY 12223

NL-03-143 Monthly Operating Rport Page 1 of 4 OPERATING DATA REPORT DOCKET NO.

50-247 DATE September 5, 2003 COMPLETED BY S. Smith TELEPHONE (914)736-8304 OPERAThINGSTATUS 1.

2.

3.

4.

5.

6.

7.

8.

Unit Name:

INDIAN POINT UNIT No. 2 Notes Reporting Period:

August-2003 Licensed Thermal Power ( MWt):

3114.4 Nameplate Rating (Gross Mwe ):

1008 Design Electrical Rating ( Net Mwe):

993 Maximum Dependable Capacity ( Gross Mwe):

988 Maximum Dependable Capacity ( Net Mwe ):

956 If Changes Occur in Capacity Ratings ( Items Number 3 Through 7 ) Since Last Report, Give Reasons:

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

12. Number Of Hours Reactor Was Critical 682.18

13. Reactor Reserve Shutdown Hours 0

14. Hours Generator On-Line 627.87

15. Unit Reserve Shutdown Hours 0

16. Gross Thermal Energy Generated ( MWH) 1,907,956

17. Gross Electrical Energy Generated ( MWH) 602,034

18. Net Electrical Energy Generated ( MWH) 577,360

19. Unit Service Factor 84.4

20. Unit Availability Factor 84.4

21. Unit Capacity Factor ( Using MDC Net) 81.2

22. Unit Capacity Factor ( Using DER Net) 78.1

23. Unit Forced Outage Rate 15.6 5,831 5,735.86 0

5,669.65 0

17,410,014 5,684,767 5,490,600 97.2 97.2 99.2 95.2 2.8 255,696 180,237.48 4,566.64 176,241.95 0

497,853,133 155,763,123 149,270,072 68.9 68.9 65.3 63.1 13.5

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 Operation ):

Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION N/A N/A N/A N/A N/A N/A (9177)

NL-03-143 Monthly Operating Rport Page 2 of 4 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-247 UNIT I.P. Unit #2 DATE September 5,2003 COMPLETED BY S. Smith TELEPHONE (914)736-8304 August-2003 MONTH DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1 960 2

959 3

161 4

0 5

28 6

882 7

957 8

957 9

957 10 957 11 959 12 958 13 957 14 643 15 0

16 0

DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 414 953 953 955 953 952 956 959 958 959 957 958 959 959 959 INSTRUCTIONS On this format, list the average daily unit power level in Mwe-Net for each day in the reporting month. Compute to the nearest whole megawatt.

(9f77)

NL-03-143 Monthly Operating Report Page 3 of 4 UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT MONTH August-2003 DOCKET NO.

50-247 UNIT I.P. Unit #2 DATE September 5, 2003 COMPLETED BY S. Smith TELEPHONE (914)736-8304

.~~~~~~~~~~~

CLicensee 7

No.

Date l

Event l

Cause & Corrective Action to Prevent Recurrence U

'n Report#

I~~~~~~~~~~

_)

xxxxxx Reactor trip initiated by a turbine trip (Ti) on auto stop oil. The TT was caused 2

030803 F

59.47 H

3 2003-004 XX by a generator trip on over-fiequency due to a loss of electrical load as a result of a lightning strike on the tower of 345 kV feeder W93.

Reactor trip (Ri') on low Reactor Coolant Pump (RCP) loop flow due to trip of a 3

030814 F

56.67 H

3 2003-005 XX RCP breaker as a result of under-frequency due to an unstable power transmission grid. RT initiated a turbine trip.

_m=

I F: Forced S: Scheduled 2

3 Reason:

A - Equipment Failure ( Explain)

B - Maintenance or Test C - Refueling D - Regulatory Restriction E - Operator Training & License Examination F - Administrative G - Operational Error ( Explain)

H - Other ( Explain)

Method:

I - Manual 2 - Manual Scram 3 - Automatic Scram 4 - Other ( Explain )

4 Exibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report ( LER ) File ( NUREG-0161 )

5 Exibit I - Same Source (9/77)

NL-03-143 Monthly Operating Report Page 4 of 4 Docket No. 50-247 Unit: Indian Point 2 Date: September 5, 2003 Completed By: S. Smith Telephone: (914) 736-8304

SUMMARY

OF OPERATING EXPERIENCE August 2003 Indian Point Unit No. 2 Nuclear Power Plant was synchronized to the bus for a total of 627.87 hours0.00101 days <br />0.0242 hours <br />1.438492e-4 weeks <br />3.31035e-5 months <br />, producing a gross electrical generation of 602,034 MWH.

On August 3, 2003, at approximately 0430 hours0.00498 days <br />0.119 hours <br />7.109788e-4 weeks <br />1.63615e-4 months <br />, an automatic reactor trip was Initiated by a turbine auto stop oil. The turbine trip was caused by a generator trip on over-frequency due to a loss of electrical load as a result of a lightning strike on the tower of 345 kV feeder W93.

Following the reactor trip, the resultant cooldown caused letdown flow to isolate when pressurizer level reached approximately 18% as designed. Since charging flow remained in service, the subsequent increase in pressurizer level and pressure caused the Pressurizer Power Operated Relief Valve (PORV) 455C to actuate automatically to control the pressure transient. The charging/level mismatch after letdown isolation caused a total of ten (10) PORV actuations from 0514 hours0.00595 days <br />0.143 hours <br />8.498677e-4 weeks <br />1.95577e-4 months <br /> to 0526 hours0.00609 days <br />0.146 hours <br />8.69709e-4 weeks <br />2.00143e-4 months <br />. After letdown was restored, pressurizer level was stabilized and the PORV actuations terminated. The unit was stabilized in the hot shutdown condition.

The reactor was brought critical on August 4, 2003, at 0813 hours0.00941 days <br />0.226 hours <br />0.00134 weeks <br />3.093465e-4 months <br />, and the unit synchronized to the bus on August 5, 2003, at 1558 hours0.018 days <br />0.433 hours <br />0.00258 weeks <br />5.92819e-4 months <br />, with full power achieved at 1230 hours0.0142 days <br />0.342 hours <br />0.00203 weeks <br />4.68015e-4 months <br />, on August 6, 2003.

On August 14, at approximately 1612 hours0.0187 days <br />0.448 hours <br />0.00267 weeks <br />6.13366e-4 months <br />, an automatic reactor trip was initiated on low reactor coolant pump (RCP) loop flow. Low RCP loop flow was caused by the trip of a RCP supply breaker as a result of 6.9 kV bus underfrequency due to an unstable power transmission grid. The grid disturbance was associated with a blackout which affected much of the northeastern United States. The unit was stabilized in the hot shutdown condition.

The reactor was brought critical on August 16, 2003, at 0218 hours0.00252 days <br />0.0606 hours <br />3.604497e-4 weeks <br />8.2949e-5 months <br />, and the unit synchronized to the bus on August 17, 2003, at 0052 hours6.018519e-4 days <br />0.0144 hours <br />8.597884e-5 weeks <br />1.9786e-5 months <br />, with full power achieved at 2235 hours0.0259 days <br />0.621 hours <br />0.0037 weeks <br />8.504175e-4 months <br /> on August 17, 2003. The unit remained on line at full power for the remainder of the reporting period.