ML041070242

March 2004 Monthly Operating Report for Davis-Besse Nuclear Power Station Unit 1

ML041070242
Person / Time
Site:	Davis Besse
Issue date:	04/14/2004
From:	Bezilla M FirstEnergy Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
3047
Download: ML041070242 (6)

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FENOC 5501 North State Route 2 FirstEnergy Nuclear Operating Company Oak Harbor. Ohio 43449 Mark B. Bezilla 419-321-7676 Vice President - Nuclear Fax: 419-321-7582 Docket No. 50-346 License No. NPF-3 Serial 3047 April 14, 2004 Document Control Desk U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 Ladies and Gentlemen:

Monthly Operating Report, March 2004 Davis-Besse Nuclear Power Station Unit I Enclosed is a copy of the Monthly Operating Report for the Davis-Besse Nuclear Power Station for the month of March 2004.

Please direct questions to Brian D. Boles, Manager - Plant Engineering at (419) 321-7302.

Very truly yours, I

/ 1' W~

AWB/s Enclosures cc: DB-1 NRC/NRR Senior Project Manager DB-I Senior Resident Inspector NRC Region III Administrator 11-'

Docket No. 50-346 License No. NPF-3 Serial 3047 Distribution bcc: B. S. Allen, DB-2101 A. W. Bless - DB Compliance, DB 3065 B. D. Boles, DB-1056 D. R. Converse, DB-3310 J. J. Grabnar, DB-3210 F. Heizer, PUCO L. J. Kovach, DB-1056 B. Lewis, Utility Data Institute, Inc.

M. E. O'Reilly, GO-18 R. Prijatel, Fuel Accounting, GO-6 R. Runo, A-GO16A R. Schomaker, Framatome D. R. Wuokko, Supervisor - DB Licensing, DB-3065 M. D. Zawacki, DB-1056 American Nuclear Insurers CNRB Administrator, DB-3344 INPO Records Center Ohio EPA - DERR Compliance Utility Radiological Safety Board

Docket Number 50-346 License Number NPF-3 Serial 3047 Page 1 of 1 COMMITMENT LIST The following list identifies those actions committed to by the FirstEnergy Nuclear Operating Company (FENOC), Davis-Besse Nuclear Power Station in this document.

Any other actions discussed in the submittal represent intended or planned actions by FENOC. They are described only as information and are not regulatory commitments.

Please notify the Manager - Regulatory Affairs (419-321-8450) at Davis-Besse of any questions regarding this document or associated regulatory commitments.

Commitments Due Date None N/A

OPERATING DATA REPORT DOCKET NO. 50-0346 UNIT NAME Davis-Besse Unit 1 DATE 04/01/04 COMPLETED BY A. R. Miller TELEPHONE 419-321-7824 REPORTING PERIOD March, 2004 YEAR TO MONTH DATE CUMULATIVE 1 Design Electrical Rating (MWe-Net). 906 The nominal net electrical output of the unit specified by the utility and used for the purpose of plant design.

2 Maximum Dependable Capacity (MWe-Net). 882 The gross electrical output as measured at the output terminals of the turbine-generator during the most restrictive seasonal conditions minus the normal station service loads.

3 Number of Hours the Reactor Was Critical. 287.3 287.3 147,921.6 The total number of hours during the gross hours of the reporting period that the reactor was critical.

4 Number of Hours the Generator Was On Line. 135.1 135.1 145,172.2 (Also called Service Hours). The total number of hours during the gross hours of the reporting period that the unit operated with breakers closed to the station bus.

The sum of the hours the generator was on line plus the total outage hours should equal the gross hours In the reporting period.

5 Unit Reserve Shutdown Hours. 0.0 0.0 5,532.0 The total number of hours during the gross hours of the reporting period that the unit was removed from service for economic or similar reasons but was available for operation.

6 Net Electrical Energy (MWH). 48,988 48,988 119,180,786 The gross electrical output of the unit measured at the output terminals of the turbine-generator minus the normal station service loads during the gross hours of the reporting period, expressed in mega-watt hours. Negative quantities should not be used.

UNIT SHUTDOWNS DOCKET NO. 50-346 UNIT NAME Davis-Besse #1 DATE 4106104 COMPLETED BY A.R. Miller REPORTING PERIOD: March, 2004 TELEPHONE (419) 321-7824 NO. DATE TYPE DURATION REASON (1) METHOD OF CAUSE/CORRECTIVE ACTIONS F: FORCED (HOURS) SHUTTING S: SCHEDULED DOWN (2) COMMENTS 2/16102 S: SCHEDULED 365.5 C. H 1,4 13 RFO work on the reactor vessel pressure retaining head revealed degradation and corrosion. As a result, the reactor vessel pressure retaining head was replaced. The plant remained shutdown due to various modifications which included (but not limited to): the Decay Heat Valve Tank, the Emergency Sump, Containment Air Coolers and HPI Pumps.

Additional activities are being completed, such as: Operations improvements, restart readiness reviews, and certain calculations.

2 3117104 F: FORCED 243.4 A 1 Shutdown reactor due to sodium concentration in Main Feedwater.

Performed repair on Main Feedwater Control Isolation Valve to #1 Steam Generator. Performed Main Turbine Overspeed Trip Test while shutting down the reactor.

SUMMARY

The reactor was shutdown on February 16, 2002 to begin the 13th refueling outage. Reactor criticality was achieved on March 11, 2004 at 13:42. The Main Generator was synchronized to the grid on March 16, 2004 at 05:27. The Main Turbine was tripped off-line to perform the Main Turbine Overspeed Trip Test on March 17, 2004 at 02:25. Following the Main Turbine Overspeed Trip Test, Mode 3 was entered on March 17, 2004 at 17:56 (1) Reason: (2) Method:

A-Equipment Failure (Explain) 1-Manual B-Maintenance or Test 2-Manual Trip/Scram C-Refueling 3-Automatic TriplScram D-Regulatory Restriction 4-Continuation E-Operator Training &License Exam 5-Other (Explain)

F-Administrative G-Operational Error (Explain)

H-Other (Explain)

" I UNIT SHUTDOWNS due to sodium concentration in Main Feedwater and to perform maintenance on Main Feedwater Control Isolation Valve to #1 Steam Generator.

Reactor criticality was again achieved on March 26, 2004 at 04:56. The Main Generator was synchronized to the grid on March 27, 2004 at 05:51.

(1) Reason: (2) Method:

A-Equipment Failure (Explain) 1-Manual B-Maintenance or Test 2-Manual Trip/Scram C-Refueling 3-Automatic Trip/Scram D-Regulatory Restriction 4-Continuation E-Operator Training & License Exam 5-Other (Explain)

F-Administrative G-Operational Error (Explain)

H-Other (Explain)