ML20197F120

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Monthly Operating Repts for Nov 1997 for Byron Nuclear Power Station,Units 1 & 2
ML20197F120
Person / Time
Site: Byron  Constellation icon.png
Issue date: 11/30/1997
From: Kofron K, Vogl J
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BYRON-97-0302, BYRON-97-302, NUDOCS 9712300137
Download: ML20197F120 (8)


Text

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e December 11,1997 LTR: BYRON 97-0302 FILE: 2.7.200 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 tne Monthly Operating Report covering Byron Nuclear Power Station for the period November 1 through November 30,1997.

Sincerely, K.yL, Kof n J

Station Man er

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Byron Nuclear Power Station , ,

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cc: A.B. Beach, riegional Administrator - Rill 1 G. Dick, Byron Project Manager - NRR  ! j Senior Resident inspector - Byron Office of Nuclear Safety lDNS INPO Records Center B. Lewis, McGraw - Hill Nuclear Publications Dept.

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-i 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 .

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UNIT ONE

. DOCKET NO, 0504 54 UNIT NAME Byron One DATE 12/11/97 COMPLETED BY J. Voal TELEPHONE (815) 234-5441 x2282 REPORTING PERIOD November.1997 (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 1,120 N/A N/A design.

2. Maximum Dependable Capacity (MWe-Net).

The gross electrical output as measureo at tne output terminals of the turbine-generator during the most testrictive 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. 145.2 6,794.8 88,680.3

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 tha' 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 s groes hours in the reporting period. 144.5 6,740.5 87,828.5 >

5 Unit Reserve Shutdown Hours.

The total number of hours during the gross hours of 1

the reporting period that the unit was removed from tervice for economic or similar reasons but was available for operation. 0 0 0

6. Net Electrical Energy (MVM).

Tha 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 ti,e reporting period, expressed in megawatt hours.1 Negative quantities should not be used. 145,989 7,161,725 87,066,480

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s UNIT SHUTDOWNS DOCKET NO. 050-454 y.  ;,-

UNIT MAME. Byron One -

DATE 12/11/97 ,

COMPLETED BY - ' J. Voal -

TELEPHONE (8151234-5441 x2282 i REPOl4 TING ' PERIOD: November; 1997

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(Month / Year)

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

a 8- 11/07/97- s 575.5 c 1 Began Unit One Refuenng Outage' BIR08 .

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SUMMARY

Unit One Began its Refueling Outage and Steam Generator Replacement.

(1) Reason (2) Method A - Eqt ipment Failure (Explain) 1 - Manual 3 B - Ma rdenance or Test 2 - Manual Trip / Scram C - Ra fueling 3 - Automate Trip / Scram D - Re gulatory Restriction 4 - Continuation E - Operator Training /Ucense Examination 5 - Other (Explain)

F - Adtranistrative G - Operational Error (Explain) .;

H - Other (Explain) -

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,_ UNIQUE REPORTING REQUIRE"ENTS (UNIT 1) for the month of November,1997

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 = 4.46 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, November 1,1997 through November 30,1997. This information is provided pursuant to the reportable -

occurrence reporting requirements as set forth in 10CFR 50.73.

Licensee Event Occurrence Renort Number Date Title of Occurrence 4

454: 97-022 11/14/97 SSPS Logic Testing Not Performed Due To inadequate Testing Design.

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OPERATING DATA REPORT

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. UNIT TWO

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DOCKET NO.- 050-455 UNIT NAME Byron Two DATE 12/11/97 COMPLETED BY -J Vool TELEPHONE (815) 234-5441 x2282 )

, REPORTING P. .RIOD November.1997 i

(Month / Year)

MONTH YEAR TO DATE CUMULATIVE

1. Design Electrical Rating (MWe-Net).

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

3 Maximum Dependable Capacity (MWe-Net).

>i 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. 720 7,631 79,153.7

4. Number of Hours the Generator Was On Line.

(Also called Service Hours). The tntal 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. 720 7,600.7 78.447.3

- 5. Unit Reserve Shutdown Hours.

The total number of hours during the gross hours of the report;ng period that the unit was removed from service for econorr : or similar reasons but was available for operaoun. 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. 804,354 8,264,714 77,556,685 (pr\9?byritrs\970302.wpf 6)

' UNIT- SHUTDOWNS:. ~

DOCMET NO. 05(M55 " .. t.

UNIT MAME. ' Byron Two. '" +

DATE 12/11/97 .

~ COMPLETED BY J. Voal " -

TELEPHONE, (8151234-5441 x2282 .

REPOPWs PERIOD: November,1997 (Month / Year)

' I NO. DATE TYPE DURATION . REASON (1) METHOD OF ( ' CAUSE/ CORRECTIVE ' ACTIONS'-

F: FORCED (HOURS) SHUTTING S:- SCHEDULED DOWN (2) COMMENTS 1

SUMMARY

No Shutdowns for Unit lwo in November.

(1) Reason (2) Method A - Equgxnent Fadure (Explain) 1 - Manual B - Maintenance or Test 2 - Manual Trip / Scram C - Refuenng 3- Automate Trip / Scram D - Regulatory Restriction 4 - Continuation E - Operator Traininglicense Examination 5 - Other (Explain)

F - Administrative G - Operational Error (Explain)

H - Other (Explain)

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. , UNIQUE REPORTING REQUIREMENTS (UNIT 2) for the month of November,1997 L1. 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 DESCRIPT!ON DATE ACTUATi2 ACTUATION - CONDITION OF EVENT None-

2. Licensee generated changes to ODCM.

None i 3. Indications of failed fuel. ,

No. Fuel Reliability Indicator: FRI = 4.30 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 Two, occurring during the reporting period, November 1,1997 4

through November 30,1997. 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: 97-004 9/12/97 Reverse Functioning Control Switch Due to improper Actuator installation and Failure to Recognize Reportability of the issue (p \97byrlt;rs\970302.wpf-8) .

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