ML20247J909

Monthly Operating Repts for Apr 1998 for Byron Nuclear Power Station,Units 1 & 2

ML20247J909
Person / Time
Site:	Byron
Issue date:	04/30/1998
From:	Kofron K, Vogl J COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BYRON-98-0149, BYRON-98-149, NUDOCS 9805210441
Download: ML20247J909 (8)

Text

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Commonweahh Edison Company

-.-  !!)ron Generating Station 4450 North German Church Road ll} ron. IL (ilOlO-979 s Tcl H 15-2.4 4-51 il

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,O May 10,1998 LTR: BYRON 98-0149 FILE: 2.7.200 U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 l

ATTENTION: Document Control Desk j t

SUBJECT:

Monthly Operating Report I Byron Nuclear Power Station, Units 1 and 2 NRC Docket Numbers: 50: 454 and 455 Gentlemen:

Enclosed for your information is the Monthly Operating Report covering Byron Nuclear Power Station for the period April 1 through April 30,1998.

Sincerely, i

K. L. Kofron Station Manager Byron Nuclear Power Station KLK/JV/rp cc: A.B. Beach, Regional Administrator - Rlll Byron Project Manager - NRR Senior Resident inspector - Byron Office of Nuclear Safety - IDNS INPO Records Center

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i B. Lewis, McGraw - Hill Nuclear Publications Dept.

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L t e BYRON NUCLEAR POWER STATION UNIT 1 AND UNIT 2 MONTHLY PERFORMANCE REPORT COMMONWEALTH EDISON COMPANY NRC DOCKET NO. 050-454 NRC DOCKET NO. 050-455 LICENSE NO. NPF-37 LICENSE NO. NPF-66  ;

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, OPERATING DATA REPORT UNIT ONE DOCKET NO. 050-454 UNIT NAME Byron One DATE 05/10/98 COMPLETED BY J. Voal TELEPHONE (815) 234-5441 x2282 REPORTING PERIOD April,1998 (Month / Year)

MONTH YEAR TO DATE CUMULATIVE

1. Design Electrical Rating (MWe-Net).

The nominal net electrical output of the unit specified by the utility and used for the purpose of plant design. 1,120 N/A N/A

2. Maximum Dependable Capacity (MWe-Net).

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. 1,105 N/A N/A

3. Number of Hours the Reactor Was Critical.

The total numbcr of hours during the gross hours of the reporting period that the reactor was critical. 719 1, 293.1 89,973.4

4. Number of Hours the Generator Was On Line.

(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. 719 1,264.9 89,093.4

5. Unit Reserve Shutdown Hours.

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. 0 0 0

6. Net Electrical Energy (MWH). l The gross electrical output of the unit measured at the i

, output terminals of the turbine-generator minus the  !

I normal station service loads during the gross hours of the reporting period, expressed in megawatt hours. j Negative quantities should not be used. 814,538 1,217,394 88,274,902 l l

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UNIQUE REPORTING REQUIREMENTS (UNIT 1) l , ,

for the month of April,1998 l

1. Safety / Relief valve operations for Unit One. This information is provided pursuant to the reporting requirements contained in Technical Specification 6.9.1.8.

VALVES NO & TYPE PLANT DESCRIPTION DATE ACTUATED ACTUATION CONDITION OF EVENT-None

2. Licensee generated changes to ODCM.

None

3. Indications of failed fuel.

No. Fuel Reliability Indicator: FRI = 3.51 E-5 pCi/cc

4. Licensee Event Reports The following is a tabular summary of all Licensee Event Reports for Byron Nuclear Power Station, Unit One, occurring during the reporting period, April 1,1998 through April 30,1998.

This information is provided pursuant to the reportable occurrence reporting requirements as set forth in 10CFR 50.73.

Occurrence Licensee Event Report Number Date Title of Occurrence 454: 98-011 04/09/98 Integral Attachment Welds not inspected in Accordance with ASME Code due to Deficient ISI Program Plan.

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., . OPERATING DATA REPORT UNIT TWO DOCKET NO, 050-455 ,

UNIT NAME Byron Two DATE 05/10/98 COMPLETED BY J. Voal TELEPHONE (815) 234-5441 x2282 l

1 REPORTING PERIOD April,1998 '

(Monthh6ar) l MONTH YEAR TO DATE CUMULATIVE

1. Design Electrical Rating (MWe-Net).

The nominal net electrical output of the unit specified by the utility and used for the purpose of plant design. 1,120 N/A N/A

2. Maximum Dependable Capacity (MWe-Net).

The gross electrical output as measured at the outpt.t terminals of the turbine-generator during the most restrictive seasonal conditions minus the normal station service loads. 1.W N/A N/A

3. Number of Hours the Reactor Was Critical.

The total number of hours during the gross hours of the reporting period that the reactor was critical. 240.5 2,400.5 82,298.2

4. Number of Hours the Generator Was On Line. l (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. 239.1 2,399.1 81,590.4

5. Unit Reserve Shutdown Hours. _

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. 0 0 0

6. Net Electrical Energy (MWH).

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 megawatt hours.

Negative quantities should not be used. 193,504 2,524,511 80,919,373

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UNIQUE REPORTING REQUIREMENTS (UNIT 2)

, , for the month of April,1998

1. Safety / Relief valve operations for Unit Two. This information is provided pursuant to the reporting requirements contained in Technical Specification 6.9.1.8.

VALVES NO & TYPE PLANT DESCRIPTION DATE ACTUATED ACTUATION CONDITION OF EVENT None

2. Licensee generated changes to ODCM.

None

3. Indications of failed fuel.

No. Fuel Reliability Indicator: FRI = 1.67E-05 pCi/cc

4. Licensee Event Reports The following is a tabular summary of all Licensee Event Reports for Byron Nuclear Power Station, Unit Two, occurring during the reporting period, April 1,1998 through April 30,1998.

This information is provided pursuant to the reportable occurrence reporting requirements as set forth in 10CFR 50.73.

Occurrence Licensee Event Report Number Date Title of Occurrence 455: 98-003 04/16/98 Procedure Not Corrected By OPEX Program Causes ESF Actuation.

455: 98-004 04/19/98 FHB Rad Monitor ESF Actuation Due to High Dose Water in Fuel Transfer Canal.

455: 98-005 04/20/98 Failure to Provide Pre-Job Brief Resultu inTechnical Specification Deviation.

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