NL-03-082, April 2003 Monthly Operating Report for Indian Point Unit 2

April 2003 Monthly Operating Report for Indian Point Unit 2

ML031390020
Person / Time
Site:	Indian Point
Issue date:	05/15/2003
From:	Dacimo F Entergy Nuclear Northeast
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-03-082
Download: ML031390020 (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 May 15, 2003 NL-03-082 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station O-P1-17 Washington, DC 20555-0001

Subject:

Indian Point Unit No. 2 Docket No. 50-247 License No. DPR-26 Monthly Operating Report for April 2003

Dear Sir:

Enclosed is the Monthly Operating Report for Indian Point 2 for the month of April 2003 that is being submitted in accordance with Technical Specification 6.9.1.7.

Entergy is making no commitments in this letter. Should you have any questions regarding this submittal, please contact Mr. John McCann, Manager, Licensing, Indian Point Energy Center at (914) 734-5074.

Siqpyel yours, Fred R. Dacimo Vice President, Operations Indian Point Energy Center cc: see next page

'r-, -z"-4

Docket No. 50-247 NL-03-082 Page 2 of 2 Attachment cc:

Mr. Hubert J. Miller Regional Administrator - Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1498 Resident Inspector U.S. Nuclear Regulatory Commission Indian Point 2 P.O. Box 38 Buchanan, NY 10511 INPO Records Center 700 Galleria Parkway Atlanta, Georgia 30339-5957 Mr. Paul Eddy State of New York Department of Public Service 3 Empire Plaza Albany, NY 12223

NL-03-082 Attachment Page 1 of 4 OPERATING DATA REPORT DOCKET NO.

DATE COMPLETED BY TELEPHONE 50-247 May 6, 2003 M. Walther (914)734-5728 OPERATING STATUS 1.

2.

3.

4.

5.

6.

7.

8.

Unit Name:

INDIAN POINT UNIT No. 2 Notes Reporting Period:

April-2003 Licensed Thermal Power ( MWt ):

3071.4 Nameplate Rating ( Gross Mwe ) :

1008 Design Electrical Rating ( Net Mwe ):

986 Maximum Dependable Capacity (Gross Mwe ):

965*

Maximum Dependable Capacity (Net Mwe ):

931*

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

• The above changes reflect summer ratings effective April 6, 2003.

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

10. Reasons For Restrictions, If Any:

This Month Yr.-to-Date

11. Hours In Reporting Period 719 2,879

12. Number Of Hours Reactor Was Critical 685.68 2,845.68

13. Reactor Reserve Shutdown Hours 0

0

14. Hours Generator On-Line 673.78 2,833.78

15. Unit Reserve Shutdown Hours 0

0

16. Gross Thermal Energy Generated ( MWH) 2,050,270 8,658,399

17. Gross Electrical Energy Generated ( MWH) 674,651 2,854,572

18. Net Electrical Energy Generated (MWH) 651,080 2,761,489

19. Unit Service Factor 93.7 98.4

20. Unit Availability Factor 93.7 98.4

21. Unit Capacity Factor (Using MDC Net) 96.9 101.3

22. Unit Capacity Factor (Using DER Net) 91.8 97.3

23. Unit Forced Outage Rate 6.3 1.6

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 ):

INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION Forecast N/A N/A N/A Cumulative 252,744 177,347.30 4,566.64 173,406.08 0

489,101,518 152,932,928 146,540,961 68.6 68.6 64.9 62.7 13.7 Achieved N/A N/A N/A (9/77)

NL-03-082 Attachment Page 2 of 4 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-247 UNIT I.P. Unit #2 DATE May 6, 2003 COMPLETED BY M. Walther TELEPHONE (914)734-5728 April-2003 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1 980 2

981 3

978 4

979 5

979 6

979 7

980 8

979 9

980 10 980 11 979 12 979 13 980 14 980 15 979 16 978 DAY AVERAGE DAILY POWER LEVEL (MWC-Net) 17 979 18 979 19 978 20 980 21 978 22 978 23 980 24 979 25 978 26 981 27 982 28 681 29 0

30 75 31 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.

(9177)

MONTH

NL-03-082 Attcilment' Page3of4 Page ? e UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT MONTH DOCKET NO.

50-247 UNIT I.P. Unit #2 DATE May 6,2003 COMPLETED BY M. Walther TELEPHONE (914)734-5728 April-2003 2

F: Forced S: Scheduled 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) 3 Method:

1 - 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 (9l77)

Cause & Corrective Action to Prevent Recurrence Reactor trip due to turbine-generator trip as a result of a main generator over-frequency trip caused by loss of offsite load.

1

Docket No. 50-247 NL-03-082 Attachment Page 4 of 4 Summary Of Operatinc Experience April 2003 Indian Point Unit No. 2 was synchronized to the bus for a total of 673.78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br />, producing a gross electrical generation of 674,651 MWH.

On April 28,2003, at 1645 hours0.019 days <br />0.457 hours <br />0.00272 weeks <br />6.259225e-4 months <br />, an automatic reactor scram occurred due to a turbine-generator trip as a result of a loss of offsite load. The plant trip was initiated by a main generator over-frequency trip. All required safety systems functioned as designed. Fast bus transfer from supply by the unit auxiliary transformer to supply by the station auxiliary transformer was blocked per design by the over-frequency transfer interrupt circuit. The blocked power transfer de-energized four of six 6.9 Kv buses (1, 2, 3, and 4) and two of four associated 480 volt buses (2A and 3A). All four-reactor coolant pumps and 4 out of 6 circulating water pumps were de-energized due to the loss of the 6.9 Kv buses. Per plant design all three Emergency Diesel Generators (EDG) started but did not automatically load their assigned buses. EDG 22 was manually loaded to energize Buses 2A and 3A. 6.9 Kv buses 5 and 6 remained energized throughout the event. In response to the transient, Pressurizer PORV 455C lifted for a short duration and reseated with no leakage. Initially motor driven auxiliary feed water pump 21 did not start due to the de-energization of its assigned bus 3A. The plant was stabilized and in natural circulation. After a post trip assessment, the reactor was brought critical at 0204 hours0.00236 days <br />0.0567 hours <br />3.373016e-4 weeks <br />7.7622e-5 months <br /> on April 30,2003, with unit synchronization at 1358 hours0.0157 days <br />0.377 hours <br />0.00225 weeks <br />5.16719e-4 months <br />. Power ascension commenced with full power being achieved on May 1,2003, at 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br />.