ML030230710
| ML030230710 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 01/10/2003 |
| From: | Hopkins L Constellation Nuclear |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NMPIL 1707 | |
| Download: ML030230710 (4) | |
Text
PG Box 63 P O Box 63 Lycoming, New York 13093 Constellation
\\3Nuclear Nine Mile Point Nuclear Station January 10, 2003 A Member of the
, 17 Constellation Energy Group NMP1L 1707 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
Subject:
Nine Mile Point Unit 1 Docket No. 50-220 DPR-63 Monthly Operating Report for December 2002 Gentlemen:
Submitted herewith are the Operating Data Report, Unit Shutdowns, and a Narrative of Operating Experience for December 2002 for the Nine Mile Point Nuclear Station Unit 1.
Submittal of this information complies with Section 6.9.1.c of the Unit 1 Technical Specifications.
Very truly yours, Lawrence A. Hopkins Plant General Manager LAH/BE/jm Attachments cc:
Mr. H. J. Miller, NRC Regional Administrator, Region I Mr. G. K. Hunegs, NRC Senior Resident Inspector
ATTACHMENT A OPERATING DATA REPORT DOCKET NO: 50-220 DATE: 1/03/03 PREPARED BY: B. L. Eastman TELEPHONE: (315) 349-2559 OPERATING STATUS Unit Name: Nine Mile Point Unit #1 Reporting Penod: December 2002 1
Design Electrical Rating: (Net MWe) 2 Maximum Dependable Capacity: (Net MWe) 613 565 3
Critical Hours 4
Hours Generator On-Line 5
Unit Reserve Shutdown Hours 6
Net Electrical Energy Generated (MWH)
This Month 319.0 281.1 0.0 161,094 0 Yr-to-Date 8,264.7 8,194.1 0.0 4,904,562.0 Cumulative 205,286 8 200,862.3 20.4 111,935,381.0
ATTACHMENT B UNIT SHUTDOWNS REPORTING PERIOD - DECEMBER 2002 DOCKET NO: 50-220 UNIT NAME: NMP1 DATE: 1/03/03 PREPARED BY: B. L. Eastman TELEPHONE: (315) 349-2559 TYPE NO.*
DATE F: FORCED DURATION REASONS' METHOD OF SHUTTING CAUSE & CORRECTIVE ACTIONS S: SCHEDULED (HOURS)
DOWN2 COMMENTS 3
021205 F
462.9 A
2 The unit was shutdown due to drywell leakage. Repairs were made to Reactor Building Closed Loop Cooling piping.
(1)
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)
- NOTE Sequential numbering used.
(2)
Method
- 1.
Manual
- 2.
Manual Trip/Scram 3
Automatic Trip/Scram 4
Continuation 5
Other (Explain)
ATTACHMENT C NARRATIVE OF OPERATING EXPERIENCE DOCKET NO: 50-220 DATE: 01/10/03 PREPARED BY: P.M. Amway TELEPHONE: (315) 349-7911 Nine Mile Point Unit 1 operated during the month of December 2002 with a Net Electrical Design capacity factor of 35.3 percent.
On December 5, 2002, at 1040 hours0.012 days <br />0.289 hours <br />0.00172 weeks <br />3.9572e-4 months <br />, Unit 1 commenced a planned shutdown because of elevated unidentified drywell leakage. Unidentified drywell leakage remained below the Technical Specification limit of five (5) GPM during the shutdown and cooldown to cold shutdown. The main turbine was removed from service at 1724 hours0.02 days <br />0.479 hours <br />0.00285 weeks <br />6.55982e-4 months <br /> and the reactor mode switch was placed in shutdown at 1729 hours0.02 days <br />0.48 hours <br />0.00286 weeks <br />6.578845e-4 months <br /> the same day. The source of the elevated drywell leakage was from various threaded connections in the Reactor Building Closed Loop Cooling (RBCLC) system. While shutdown, the identified sources of leakage were corrected and other planned maintenance activities that require the plant to be either shutdown or at reduced power were completed.
After completing planned maintenance, the reactor was brought critical at 1035 hours0.012 days <br />0.288 hours <br />0.00171 weeks <br />3.938175e-4 months <br /> on December 11, 2002. During plant heatup, leakage past electromatic relief valve 111 pilot valve required the plant to be shutdown for repair of the valve. The shutdown was completed with all control rods fully inserted at 1537 hours0.0178 days <br />0.427 hours <br />0.00254 weeks <br />5.848285e-4 months <br /> the same day. After completing repair of the relief valve, the reactor was brought critical at 1512 hours0.0175 days <br />0.42 hours <br />0.0025 weeks <br />5.75316e-4 months <br /> on December 12, 2002.
On December 12, 2002, at 2350 hours0.0272 days <br />0.653 hours <br />0.00389 weeks <br />8.94175e-4 months <br />, during the 900 PSIG inspection of the drywell, leakage was observed from a Reactor Building Closed Loop Cooling (RBCLC) threaded connection. An orderly plant shutdown was commenced at 0325 hours0.00376 days <br />0.0903 hours <br />5.373677e-4 weeks <br />1.236625e-4 months <br /> on December 13. All control rods were fully inserted at 0827 hours0.00957 days <br />0.23 hours <br />0.00137 weeks <br />3.146735e-4 months <br /> the same day. Extensive testing and piping replacement was performed on the RBCLC system during the outage. After completing repairs, the reactor was brought critical at 0416 hours0.00481 days <br />0.116 hours <br />6.878307e-4 weeks <br />1.58288e-4 months <br /> on December 24. The main turbine was placed in service at 0019 hours2.199074e-4 days <br />0.00528 hours <br />3.141534e-5 weeks <br />7.2295e-6 months <br /> on December 25, with full power operation achieved by 0809 hours0.00936 days <br />0.225 hours <br />0.00134 weeks <br />3.078245e-4 months <br /> on December 26, 2002.
On December 26, 2002, at 2016 hours0.0233 days <br />0.56 hours <br />0.00333 weeks <br />7.67088e-4 months <br />, reactor power was reduced to 90 percent to perform a control rod pattern adjustment. Reactor power was returned to rated conditions by 2315 hours0.0268 days <br />0.643 hours <br />0.00383 weeks <br />8.808575e-4 months <br /> the same day.
There were no challenges to the electromatic relief valves or safety valves during this reporting period.