ML20209H371

Monthly Operating Repts for June 1999 for Byron Station, Units 1 & 2.With

ML20209H371
Person / Time
Site:	Byron
Issue date:	06/30/1999
From:	Colglazier R, Lopriore R COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BYRON-99-0096, BYRON-99-96, NUDOCS 9907200201
Download: ML20209H371 (8)

Text

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- 4 113 run,11. 61010 <>7t> j Tel HI42M S 6 61 July 12,1999 LTR: BYRON 99-0096 FILE: 2.7.200 U. S. Nuclear Regulatory Commission i ATTN: Document Control Desk l Washington, D.C. 20555-0001 Byron Station, Units 1 and 2 Facility Operating License Nos. NPF-37 and NPF-66 NRC Docket Nos. STN 50-454 and STN 50-455 J

Subject:

Monthly Operating Report In accordance with Technical Specification 5.6.4, " Monthly Operating Reports," we are submitting the l Monthly Operating Report for Byron Station, Units 1 and 2. This report covers the period June 1,1999, to June 30,1999.

If you have any questions regarding this report, please contact Mr. B. J. Adams, Regulatory Assurance  ;

Manager, at (815) 234-5441 extension 2280.

Respectfully, Rici r P. LoprDre 2Or Station Manager Byron Station RPL/RC/dpk cc: Regional Administrator- NRC Region til I NRC Senior Resident inspector- Byron Station -

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BYRON STATION UNIT 1 AND UNIT 2 MONTHLY OPERATING REPORT COMMONWEALTH EDISON COMPANY i

FACILITY OPERATING LICENSE NOS. NPF-37 AND NPF-66 NRC DOCKET NOS. STN 050-454 AND STN 050-455 1

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' 1 OPERATING DATA REPORT I UNIT ONE

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I DOCKET NO. 50-454 UNIT NAME Byron One DATE 07/07/99 COMPLETED BY R. Colalazier TELEPHONE (815)234-5441 X2609 REPORTING PERIOD: June.1999 1 (Month / Year)

MONTH YEAR TO DATE CUMULATIVE l

1. Design Electrical Rating (Mwe-Net). 1,120 N/A N/A The nominal net electrical output of the )

unit specified by the utility and used for the purpose of plant design. j

2. Maximum Dependable Capacity (Mwe-Net). 1,105 N/A N/A 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.

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3. Number of Hours the Reactor was Critical. 720 3,557.63 99,412.03 The total number of hours during the gross I hours of the reporting period that the reactor was critical.

4. Nur..ber of Hours the Generator was On Line. 720 3,528.82 98,503.22 (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 38 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). 838,603 3,961,273 98,809,609 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.

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UNIQUE REPORTING REQUIREMENTS (UNIT 1) for the month of June,1999 i

1. Safety / Relief valve operations for Unit One. This information is provided pursuant to the reporting requirements contained in Technical Specification 5.6.4.

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

2. Licensee generated changes to ODCM.

On June 24,1999, Byron Station implemented Revision 2, of the Off-Site Dose Calculation Manual (ODCM) dated April 1999. The ODCM has been revised to reflect the common methodology used at Commonwealth Edison (Comed) Company for determining the Total Effective Dose Equivalent (TEDE) to the public.

These common methodologies are reflected in Chapters 1 through 7 and Appendices A through C of this revision. Previously, these methodologies are stated in Chapters 1 through 9 and Appendices A through E. This revision edits the text for clarity by removing redundant information, site-specific criteria, and combining chapters, appendices and tables. Two criteria were added for the station to evaluate the effect of dose to the public. These are the dredging of rivers and storage of radioactive material on site.

The Army Corp of Engineers dredges rivers for navigation purposes and disposes of the soil on non-Comed sites. The dredging activity is not applicable to Byron Station because the Rock River is not navigable and when dredged the materialis disposed of on Comed property. The second ,

evaluation has already been implemented at Byron Station. During the Steam Generator i Replacement Project, completed during refuel outage B1R08, an additional Thermoluminescent l Detector and surveillance was added to the Radiological Effluents Technical Specifications (RETS) and Radiological Effluent Monitoring Program (REMP). The surveillance monitors the exterior dose rate of the Old Steam Generator Facility and accumulation of liquids from inside the building.

The implementation does not change past requirements of the RETS and REMP programs. All surveillance criteria remain the same.

3. Indications of failed fuel.

None. Fuel Reliability Indicator FRI = 5.49 E-06 pCi/cc.

4. Licensee Event Reports The following is a tabular summary of all Licensee Event Reports for Byron Station, Unit One, occurring during the reporting period, June 1,1999 through June 30,1999. 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 None I p:'99byttr:1990096 doc I

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OPERATING DATA REPORT

, . UNIT TWO I

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UNIT NAME Byron Two DATE 07/07/99 COMPLETED BY R. Colalazier TELEPHONE (815)234-5441 X2609 REPORTING PERIOD: June.1999 (Month / Year)

MONTH YEAR TO DATE CUMULATIVE

1. Design Electrical Rating (Mwe-Net). 1,120 N/A N/A j 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). 1,105 N/A N/A The gross electrical output as measured at the output terminals of the turbine-generator during the most restictive seasonal conditions minus the normal station service loads.

3. Number of Hours the Reactor was Critical. 720 4,343 92,112.4 ,

The total number of hours during the gross hours of the reporting period that reactor was critical.

4. Number of Hours the Generator was On Line. 720 4,343 91,389.9 (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 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.

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6. Net Elactrical Energy (MWH). 833,121 4,939,746 91,927,529 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.

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. .o UNIQUE REPORTING REQUIREMENTS (UNIT 2)

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1. Safety / Relief valve operations for Unit Two. This information is provided pursuant to the reporting requirements contained in Technical Specification 5.6.4.

VALVES NO & TYPE PLANT DESCRIPTION l DATE ACTUATED ACTUATION CONDITION OF EVENT j t

None

2. Licensee generated changes to ODCM.

On June 24,1999, Byron Station implemented Revision 2, of the Off-Site Dose Calculation Manual (ODCM) dated April 1999. The ODCM has been revised to reflect the common methodology used at Commonwealth Edison (Comed) Nuclear Stations for determining the Total Effective Dose Equivalent (TEDE) to the public.

These common methodologies are reflected in Chapters 1 through 7 and Appendices A through C of this revision. Previously, these methodologies are stated in Chapters 1 through 9 and Appendices A through E. This revision edits the text for clarity by removing redundant information, site-specific criteria, and combining chapters, appendices and tables. Two criteria were added for the station to evaluate the effect of dose to the public. These are the dredging of rivers and storage of radioactive material on site.

The Army Corp of Engineers dredges rivers for navigation purposes and disposes of the soil on non-Comed sites. The dredging activity is not applicable to Byron Station because the Rock River is not navigable and when dredged the materialis disposed of on Comed property. The second evaluation ,

has already been implemented at Byron Station. During the Steam Generator Replacement Project, l completed during refuel outage B1R08, an additional Thermoluminescent Detector and surveillance was added to the Radiological Effluents Technical Specifications (RETS) and Radiological Effluent Monitoring Program (REMP). The surveillance monitors the exterior dose rate of the Old Steam Generator Facility and accumulation of liquids from inside the building.

The implementation does not change past requirements of the RETS and REMP programs. All surveillance criteria remain the same.

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3. Indications of failed fuel.

None. Fuel Reliability Indicator: FRI = 3.97 E-06 pCi/cc

-4. Licensee Event Reports The fohuwing is a tabular summary of all Licensee Event Reports for Byron Station, Unit Two, occurring during the reporting period, June 1,1999 through June 30,1999. 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 None pa99hyhrs\990096 doc