NL-03-010, December 2002 Monthly Operating Report for Indian Point Unit 2

December 2002 Monthly Operating Report for Indian Point Unit 2

ML030160197
Person / Time
Site:	Indian Point
Issue date:	01/15/2003
From:	Dacimo F Entergy Nuclear Northeast
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-03-010
Download: ML030160197 (6)

Text

A SEntergy Entergy Nuclear Northeast Entergy Nuclear Operations, Inc Indian Point Energy Center 295 Broadway, Suite 1 PO Box 249 Buchanan, NY 10511-0249 January 15, 2003 NL-03-01 0 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station O-Pl-17 Washington, DC 20555-0001

Subject:

Indian Point Unit No. 2 Docket No. 50-247 License No. DPR-26 Monthly Operating Report for December 2002

Dear Sir:

Enclosed is the Monthly Operating Report for Indian Point 2 for the month of December 2002 that is being submitted in accordance with Technical Specification 6.9.1.7. There are no commitments contained in this letter.

If there are any questions regarding this matter, please contact Mr. John McCann, Manager, Licensing, Indian Point Energy Center at (914) 734-5074.

Sincerely, Fred Dacimo Vice President Indian Point Entergy Center cc: see next page

Docket No. 50-247 NL-03-010 Page 2 of 2

Enclosure:

Monthly Operating Report for December 2002 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 Mr. Paul Eddy State of New York Department of Public Service 3 Empire Plaza Albany, NY 12223

NL-03-010 Attachment Page 1 of 4 OPERATING DATA REPORT DOCKET NO.

50-247 DATE January 9, 2003 COMPLETED BY M. Walther TELEPHONE (914)734-5728 OPERATING STATUS

1.

2.

3.

4.

5.

6.

7.

8.

Unit Name:

INDIAN POINT UNIT No. 2 Notes Reporting Period:

December-2002 Licensed Thermal Power (MWt):

3071.4 Nameplate Rating (Gross Mwe ) :

1008 Design Electrical Rating ( Net Mwe):

986 Maximum Dependable Capacity ( Gross Mwe):

985 Maximum Dependable Capacity (Net Mwe ):

951 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

11. Hours In Reporting Period 744 8,760

12. Number Of Hours Reactor Was Critical 744 8,000 87

13. Reactor Reserve Shutdown Hours 0

0

14. Hours Generator On-Line 744 7,931.25

15. Unit Reserve Shutdown Hours 0

0

16. Gross Thermal Energy Generated (MWH) 2,184,429 23,930,716

17. Gross Electrical Energy Generated (MWH) 714,160 7,831,466 18 Net Electrical Energy Generated ( MWH) 690,355 7,556,550

19. Unit Service Factor 100 0 90 5

20. Unit Availability Factor 100 0 90 5

21. Unit Capacity Factor ( Using MDC Net) 97.6 91 8 22 Unit Capacity Factor (Using DER Net) 94.1 87 5

23. Unit Forced Outage Rate 0

0 24 Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration Of Each):

Cumulative 249,865 174,501.62 4,56664 170,572 30 0

480,443,119 150,078,356 143,779,472 68.3 68.3 64.4 62.3 13.8 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 Achieved N/A N/A N/A N/A N/A N/A

NL-03-010 Attachment Page 2 of 4 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-247 UNIT I.P. Unit #2 DATE January 9, 2003 COMPLETED BY M. Walther TELEPHONE (914)734-5728 December-2002 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1 616 2

617 3

621 4

795 5

844 6

883 7

974 8

979 9

978 10 979 11 979 12 979 13 976 14 976 15 973 16 950 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 17 975 18 972 19 976 20 977 21 978 22 979 23 979 24 978 25 976 26 966 27 971 28 983 29 979 30 977 31 980 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.

MONTH

NL-03-010 Attachment Page 3 of 4 UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT MONTH December-2002 DOCKET NO.

50-247 UNIT I.P. Unit #2 DATE January 9, 2003 COMPLETED BY M. Walther TELEPHONE (914)734-5728 1

F: Forced S : Scheduled 2

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 (9/77)

4.

0 0

• 0

= ---,*

o

• Licensee o

Event D 4 o

Cause & Corrective Action to Prevent Recurrence N

Report#

0o 0

U PUMPXX N/A 021201 F

0.00 A

4 CHI 75% Hold due to 21 Main Boiler Feed Pump oil leak.

B N/A 2121 F

0.00 A

4CIIPUMPXX NIA 021201 F

0.00 A

4 CH PAdditional reduction in power to effect repairs on 21 Main Boiler Feed Pump.

B

Docket No. 50-247 Indian Point 2 NL-03-010 Attachment Page 4 of 4 Summary Of Operating Experience December 2002 Indian Point Unit No. 2 started the month of December in the power ascension mode following a scheduled refueling outage. On December 1, at approximately 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br />, reactor power was held at 75% and then reduced to approximately 65% in order to remove 21 Main Boiler Feed Pump from service due to an oil leak. Following repairs, power ascension commenced. On December 4, at 1730 hours0.02 days <br />0.481 hours <br />0.00286 weeks <br />6.58265e-4 months <br />, power ascension was held at 90% power in order to conduct physics and power range testing. Testing was completed on December 6, at 1157 hours0.0134 days <br />0.321 hours <br />0.00191 weeks <br />4.402385e-4 months <br />, and power ascension continued. Reactor power was held at 97% power on December 6, at 1730 hours0.02 days <br />0.481 hours <br />0.00286 weeks <br />6.58265e-4 months <br />, for additional testing and thermal power calculations. At 2301 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.755305e-4 months <br />, on December 6, power was increased with full power being achieved by December 7, 2002, at 0230 hours0.00266 days <br />0.0639 hours <br />3.80291e-4 weeks <br />8.7515e-5 months <br />.

The unit continued to run at full power until December 15, 2002, when reactor power was reduced to approximately 97%, to conduct 21 Auxiliary Boiler Feed Pump recirculation valve testing. The unit returned to full power and continued to run at full power through remainder of the reporting period.