NL-03-083, April 2003 Monthly Operating Report for Indian Point 3
| ML031390019 | |
| 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-03-083 | |
| Download: ML031390019 (6) | |
Text
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En tergy Entergy Nuclear Northeast Indian Point Energy Center 295 Broadway, Suite 1 RO. Box 249 Buchanan, NY 10511-0249 Tel 914 734 5340 Fax 914 734 5718 Fred Dacimo Vice President, Operations May 15, 2003 NL-03-083 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop O-Pl -17 Washington, D.C. 20555-0001
Subject:
Indian Point 3 Nuclear Power Plant Docket No. 50-286 License No. DPR-64 Monthly Operating Report for April 2003
Dear Sir:
The attached monthly operating report, for the month of April 2003, is hereby submitted in accordance with Indian Point 3 Nuclear Power Plant Technical Specification 5.6.4.
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 Entergy Center at (914) 734-5074.
Sinc e
- urs, d
R. Dacimo Vice President, Operations Indian Point Energy Center cc: See next page
<(, WA,
Docket No. 50-286 NL-03-083 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, Pennsylvania 19406-1415 Resident Inspector's Office U.S. Nuclear Regulatory Commission Indian Point 3 Nuclear Power Plant P.O. Box 337 Buchanan, NY 10511-0337 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
DOCKET NO.
UNIT:
DATE:
COMPLETED BY:
TELEPHONE NO:
LETTER NO:
50-286 Indian Point 3 5-05-03 T. Orlando (914) 736-8340 NL-03-083 ATTACHMENT PAGE 1 of 4 OPERATING DATA REPORT OPERATING STATUS
- 1.
Unit Name:
Indian Point No. 3 Nuclear Power Plant
- 2.
Reporting Period:
April 2003
- 3.
Licensed Thermal Power (MWt):
3067.4
- 4.
Nameplate Rating (Gross MWe):
1013
- 5.
Design Electrical Rating (Net MWe):
979
- 6.
Maximum Dependable Capacity (Gross MWe):
1014
- 7.
Maximum Dependable Capacity (Net MWe):
979
- 8.
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:
- Hours In Reporting Period Number Of Hours Reactor Was Critical
-Reactor Reserve Shutdown Hours Hours Generator On-Line i Unit Reserve Shutdown Hours tGioss Thermal Energy Generated (MWH) b Ix a
.t,Gross Electrical Energy Generated (MWH)
Net Electrical Energy Generated (MWH)
---Unit Service Factor
'Upit Availability Factor Unit Capacity factor (Using MDC Net)
Unit Capacity Factor (Using DER Net)
Unit Forced Outage Rate This Month 719 193.1 0
111.97 0
146,312 40,628 37,423 15.6 15.6 5.3 5.3 35.5 Yr-to-Date 2,879 2,255.97 0
2,169.12 0
6,438,221 2,150,573 2,082,115 75.3 75.3 73.8 73.8 4.1 Shutdowns Scheduled Over Next 6 Months (Type, Date and Duration of Each):
If Shut Down At End Of Report Period. Estimated Date of Startup:
Units In Test Status (Prior to Commercial Operation):
Forecast Ach INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION Weighted averages Cumulative 234,160 148,494.13 0
145,576.97 0
419,163,105 134,750,746 130,118,989 62.2 62.2 58.3*
57.9*
22.7 leved 11.
12.
iS.
24.
45.
~6.
0.
457.
as.
~t 8.
19.
9.
-21.
-22.
23.
I I.
,2.
24.
25_
261..
5.
21.
2.
)1.
DOCKET NO.
UNIT:
DATE:
COMPLETED BY:
TELEPHONE NO:
LETTER NO:
AVERAGE DAILY UNIT POWER LEVEL 50-286 Indian Point 3 5-05-03 T. Orlando (914) 736-8340 NL-03-083 ATTACHMENT PAGE 2 of 4 MONTH Aril 2003 AVERAGE DAILY POWER 0
0 0
0 0
0 0
0 0
0 0
0 0
0 DAY 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 AVERAGE DAILY POWER LEVEL (MWe-Net) 0 0
0 0
0 0
211 183 181 0
246 486 73 317 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.
DAY 1.
2 3
4 5
6 7.
8 9.-
10 L'-1 V' 12 13 14 15 16
- '¢ DOCKET NO.
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-,-' UNIT:
DATE:
COMPLETED BY:
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LETTER NO:
UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT MONTH Aril 2003 50-286
- Indian Point 3 5-05:03 T. Orlando (914) 736-8340 NL-03-083 ATTACHMENT PAGE 3 of 4 (1) Type F: Forced S: Scheduled (2) Reason:
(3) Method:
A-Equipment 1-Manual B-Maintenance or Test 2-Manual Scram C-Refueling 3-Automatic Scram D-Regulatory Restriction 4-Other (Explain)
E-Operator Training & Licensee Examination F-Administrative G-Operational Error H-Other (Explain)
(4) Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG - 0161)
(5) Exhibit 1 -
Same Source V
METHOD OF NO.
DATE TYPE DURATION REASON SHUTTING LICENSEE SYSTEM COMPONENT CAUSE & CORRECTIVE ACTION TO 1
(HUROS) 2 DSOW N EVENT CSODE CODE CAUS E N C RECTE A NEC ET REACTOR 3 REPORT#
4 5
2 030329 S
542.57 C
2 N/A N/A N/A Manually scrammed the reactor to commence scheduled refueling outage 3R12.
3 030424 S
2.76 B
N/A N/A N/A N/A Manually secured the main turbine generator in order to facilitate the performance of surveillance test 3PT-V21, Turbine Generator Overspeed Trip Test.
4 030425 F
33.15 A
N/A N/A HA VALVE XX Manually secured the main turbine generator in order to facilitate repairs to main turbine control valve #34.
5 030429 F
28.55 A
2 2003-002-00 HA TURBIN Manually scrammed the reactor due to indication of a fire at high-pressure turbine bearing #2.
t Ir I
DOCKET NO.
50-286 UNIT:
Indian Point 3 DATE:
5-05-03 COMPLETED BY:
T. Orlando TELEPHONE NO.:
(914) 736-8340 LETTER NO.
NL-03-083 ATTACHMENT PAGE 4of4
SUMMARY
OF OPERATING EXPERIENCE April 2003 The Indian Point Unit No. 3 Nuclear Power Plant was synchronized to the bus for a total of 111.97 hours0.00112 days <br />0.0269 hours <br />1.603836e-4 weeks <br />3.69085e-5 months <br />, producing a gross electrical energy generation of 40,628 MWH.
On March 28, 2003, at 0301 hours0.00348 days <br />0.0836 hours <br />4.976852e-4 weeks <br />1.145305e-4 months <br />, a load reduction commenced to support a controlled unit shutdown for a scheduled refueling outage (3R12). On March 29, at 0003 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />, the reactor was manually scrammed and 3R12 commenced.
On April 19, at 2252 hours0.0261 days <br />0.626 hours <br />0.00372 weeks <br />8.56886e-4 months <br />, the unit entered Mode 4 (hot shutdown). On April 20, at 1925 hours0.0223 days <br />0.535 hours <br />0.00318 weeks <br />7.324625e-4 months <br />, the unit entered Mode 3 (hot standby). On April 21, at 0230 hours0.00266 days <br />0.0639 hours <br />3.80291e-4 weeks <br />8.7515e-5 months <br />, the unit reached Mode 2, normal operating temperature and reached normal operating pressure at 0635 hours0.00735 days <br />0.176 hours <br />0.00105 weeks <br />2.416175e-4 months <br />.
On April 22, at 0414 hours0.00479 days <br />0.115 hours <br />6.845238e-4 weeks <br />1.57527e-4 months <br />, the reactor was brought critical. The unit was synchronized to the bus on April 23, at 1534 hours0.0178 days <br />0.426 hours <br />0.00254 weeks <br />5.83687e-4 months <br />, ending 3R12 and starting fuel cycle 13. The unit was stabilized at 30% reactor power at 2010 hours0.0233 days <br />0.558 hours <br />0.00332 weeks <br />7.64805e-4 months <br />.
On April 24, at 0145 hours0.00168 days <br />0.0403 hours <br />2.397487e-4 weeks <br />5.51725e-5 months <br />, a scheduled load reduction commenced in order to remove the unit from service. This was necessary in order to facilitate the performance of surveillance test 3PT-V21, Turbine Generator Overspeed Trip Test. The unit was removed from service at 0316 hours0.00366 days <br />0.0878 hours <br />5.224868e-4 weeks <br />1.20238e-4 months <br />, by manually securing the main turbine generator. Following successful performance of 3PT-V21, the unit was synchronized to the bus at 0612 hours0.00708 days <br />0.17 hours <br />0.00101 weeks <br />2.32866e-4 months <br />. Also on April 24, at 2155 hours0.0249 days <br />0.599 hours <br />0.00356 weeks <br />8.199775e-4 months <br />, unit load was reduced to 200 MWe from 250 MWe, in order to facilitate repairs to main feedwater regulating valve air line BFD-FCV-447. Following successful repairs, unit load was increased to 250 MWe.
On April 25, at 2003 hours0.0232 days <br />0.556 hours <br />0.00331 weeks <br />7.621415e-4 months <br />, the main turbine generator was manually secured in order to facilitate repairs to main turbine control valve #34 (34 CV) and the power range detector (N-44).
The unit was stabilized in Mode 2 at 2010 hours0.0233 days <br />0.558 hours <br />0.00332 weeks <br />7.64805e-4 months <br />. Following successful repairs, on April 26, at 0740 hours0.00856 days <br />0.206 hours <br />0.00122 weeks <br />2.8157e-4 months <br />, the unit entered Mode 1 and the unit was synchronized to the bus on April 27, at 0512 hours0.00593 days <br />0.142 hours <br />8.465608e-4 weeks <br />1.94816e-4 months <br />.
On April 29, at 0303 hours0.00351 days <br />0.0842 hours <br />5.009921e-4 weeks <br />1.152915e-4 months <br />, the reactor was manually scrammed due to an indication of a fire at high pressure turbine bearing #2 lower casing. The fire was successfully extinguished by the plant Fire Brigade. An investigation revealed that insulation had absorbed oil from a leak at a vertical joint at the #2 oil seal bracket. Following successful repairs, the reactor was brought critical at 2143 hours0.0248 days <br />0.595 hours <br />0.00354 weeks <br />8.154115e-4 months <br /> and the unit was synchronized to the bus on April 30, at 0736 hours0.00852 days <br />0.204 hours <br />0.00122 weeks <br />2.80048e-4 months <br />. Unit load was stabilized at 70% reactor power for reactor engineering testing. Unit load ascension recommenced at 2220 hours0.0257 days <br />0.617 hours <br />0.00367 weeks <br />8.4471e-4 months <br />, and the unit remained on line for the remainder of the reporting period.