ML20195F832

Monthly Operating Repts for Oct 1998 for Byron Nuclear Power Station,Units 1 & 2.With

ML20195F832
Person / Time
Site:	Byron
Issue date:	10/31/1998
From:	Colglazier R, Levis W COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BYRON-98-0301, BYRON-98-301, NUDOCS 9811200099
Download: ML20195F832 (10)

Text

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Commonsvealt h Illison Company

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• Ily ttn1 Generating Station l . 4450 North German Church Road l liyron, IL 610109791 Tel H15-231514 I l

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l November 11,1998 I LTR: BYRON 98-0301 1 FILE: 2.7.200 1

U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 ATTENTION: Document Control Desk

SUBJECT:

Monthly Operating Report 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 October 1 through October 31,1998.

Sincerely, f nn-

.A.)Ak-.

William Levis Station Manager Byron Nuclear Power Station WURC/rp cc: NRC Regional Administrator - Region Ill NRC Senior Resident inspector - Byron Station

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BYRON NUCLEAR POWER STATION

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UNIT 1 AND UNIT 2 l

MONTHLY PERFORMANCE REPORT f i COMMONWEALTH EDISON COMPANY 1

I NRC DOCKET NO. 050-454 l- NRC DOCKET NO. 050-455 l

LICENSE NO. NPF-37

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,- OPERATING DATA REPORT UNIT ONE DOCKET NO. 050-454 UNIT NAME Byron One DATE 11/10/98 COMPLETED BY R. Colalazier TELEPHONE (815) 234-5441 x2609 REPORTING PERIOD October 1988 (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 number of hours during the gross hours of the reporting period that the reactor was critical. 745 5,710.1 94,390.4

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. 745 5,681.9 93,510.4

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. 844,524 6,151,706 93,209,214 (p \98byrltrs\980301.wpf-4)

UNIT SHUTDOWNS DOCKET NO. 050-454 ,

UNIT NAME. Byron One ,

DATE 11/10 S8 -

COMPLETED BY R. Colalazier TELEPHONE (8151234-5441 x2609 REPORTING PERIOD: October,1998 (Month / Year)

NO. DATE TYPE DURATION REASON METHOD OF CAUSE/ CORRECTIVE ACTIONS F: FORCED (HOURS) (1) SHUTTING S: SCHEDULED DOWN (2) COMMENTS 2

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SUMMARY

Unit One Ran Steady During the Month of October.

(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 Examination 5 - Other (Explain)

F - Administrative G - Operational Error (Explain)

H - Other (Explain)

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UNIQUE REPORTING REQUIREMENTS (UNIT 1) ,

for the month of October,1998 '

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

VALVES NO & TYPE PLANT DESCRIPTION DATE ACTUATED- ACTUATION CONDITION OF EVENT '

None l

2. Licensee generated changes to ODCM.

ODCM Chapter 10, Revision 1.4 Summary of Changes Pace # Revision

Description:

10-1 New Revision Number 10-li Updated Page Number References.

10-lil- Updated Page Number References. )

! '10-3 Removed Component Cooling Water Monitor Description from Section 10.1.2 Airborne Process Radiation Monitors.

7 A.dded Component Cooling Water Monitor Description to Section 10.2, Liquid Process Radiation Monitors. i 10-9 Added dual reference to applicable Technical Requirements Manual and Administrative Technical Requirements Table. '

ODCM Chapter 11, Revision 1.6 l Summary of Changes Paae # Revision

Description:

11-1 . New Revision Number 11 2 8 Miscollaneous Format Changes to maintain consistency throughout the Chs,ntci.

, 11-7 Removed Dairy BY-27 from REMP Sampling Program. The dairy is no longer active, and no samples can be obtained.

13 Deleted BY-27 from Figure 11-4, " Ingestion and Waterborne Exposure Pathway Sample Locations".

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.,. 3. Indications of ffled fuil.  !

No. Fuel Reliability Indicator: FRI = 1.82 E-5 pCl/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, October 1,1998 through October 31,1998. 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 None.

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=,. OPERATING DATA REPORT 1 UNIT TWO

. DOCKET NO. 050-455 g UNIT NAME Byron Two L DATE 11/10/98 COMPLETED BY R. Colalazier TELEPHONE (815) 234-5441

. x2609 o4 l

REPORTING PERIOD October.1998 (Month / Year)

J j MONTH YEAR TO DATE CUMULATIVE l

' 1'.

Design Electrical Rating (MWe-Net).

' The nominal not electrical output of the unit specified i

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 electical_ 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.

l The total number of hours during the gross hours of

' the reporting period that the reactor was critical. 745 6,407.7 86,305.4

4. Number of Hours the Generator Was On Line, j i

(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. 745 6,391.6 85,582.9

5. Unit Reserve Shutdown Hours.

The total number of hours during the gross hours of l

.the reporting period that the unit was removed from i

~ service for economic or similar reasons but was l available for operation.. 0 0 0 l

!- 6. Net Electrical Energy (MWH).

l The gross electrical output of the unit measured at the L .. 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. 843,329 6,912,362 85,307,224 I

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UNIT SHUTDOWNS DOCKET NO. 050-455 UNIT NAME. Byron Two DATE. 11/10/98 -

COMPLETED BY R. Colatazier TELEPHONE (8151234 5.441 x2609 REPORTING PERIOD: October.1998 (Month / Year)

NO. DATE TYPE DURATION REASON METHOD OF CAUSE/ CORRECTIVE ACTIONS F: FORCED (HOURS) (1) SHUTTING S: SCHEDULED DOWN (2) COMMENTS

SUMMARY

Unit Two Ran Steady During the Month of October.

(1) Reason (2) Method A - Equipment Failure (Explain) 1 - Manual B - Maintenance or Test 2 - Manual Trip / Scram C - Refueling 3 - Automatic Trip /Scrr.m ,

D - Regulatory Restriction 4 - Continuation E - Operator Training / License Examination 5 - Other (Explain)

F - Administrative G - Operational Error (Explain)

H - Other (Explain)

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UNIQUE REPORTING REQUIREMENTS (UNIT M

.. . for the month of October,1998

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

-VALVES NO & TYPE PLANT DESCRIPTION DATE ACTUATED' ACTUATION CONDITION OF EVENT

)

None i

2. Licensee generated changes to ODCM.

ODCM Chapter 10, Revision 1.4

. Summary of Changes Pace # Revision

Description:

i 10-1 New Revision Number 10-il - Updated Page Number References. i 1

10-lil . Updated Page Number References.

L..

l- 10-3 Removed Component Cooling Water Monitor Descripte from Section 10.1.2 Airborne Process Radiation Monitors.

' 10-7 Added Component Cooling Water Monitor Description to Sechan 10.2, Liquid Process Radiation Monitors.  ;

10-9 Added dual reference to applicable Technical Requirements Manual and Administrative Technical Requirements Table.  !

ODCM Chapter 11, Revision 1.6 i Summary of Changes j Pace # Revision

Description:

11-1 New Rev:sion Number i 11 11-8 Miscellaneous Format unanges to maintain consistency throughout l the Chapter.

4 i .11 Removed Dairy BY-27 from REMP Sampling Program. The dairy is no longer active,' and no samples can be obtained.

11-13 Deleted BY-27 from Figure 11-4, " Ingestion and Waterborne Exposure

~ Pathway Sample Locations".

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.,. ; 3. Indications of failed fuel.

1, No. Fuel Reliability udicator: FRI = 5.97 E-5 pCl/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, October 1,1998 through' October 31,1998. 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 None (pt\9Ebyt1*rs\980301.wpf-11) d

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