ML20206R699

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

ML20206R699
Person / Time
Site:	Byron
Issue date:	04/30/1999
From:	Colglazier R, Lopriore R COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BYRON-99-0082, BYRON-99-82, NUDOCS 9905200183
Download: ML20206R699 (9)

Text

Commonweahh I. demo Company b) ron (icarrating Mation 1450 North (irrman < hurth Road

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• llyron, IL 61010179 i Tel 815 2.41-5 e il May 11,1999 LTR: BYRON 99-0082 FILE: 2.7.200 i

l U. S. Nuclear Regulatory Commission I ATTN: Document Control Desk Washington, D.C. 20555-0001 i

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

Subject:

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

to April 30,1999.

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

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

l Respectfully,

'O Richard Loprio e Station Manager Byron Station RURC/rp cc: Regional Administrator- NRC Region lli ,

NRC Senior Resident inspector- Byron Station D

9905200183 990430 -

PDR ADOCK 05000454 '

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l BYRON STATION UNIT 1 AND UNIT 2 MONTHLY OPERATING REPORT COMMONWEALTH EDISON COMPANY FACILITY OPERATING LICENSE NOS. NPF-37 AND NPF-66 NRC DOCKET NOS. STN 050-454 AND STN 050-455 l

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OPERATING DATA REPORT UNIT ONE DOCKET NO. 50-454 UNIT NAME Byron One DATE 05/03/99 COMPLETED BY R. Colalazier TELEPHONE (815)234-5441 X2609 REPORTING PERIOD: Aoril.1999 (Month / Year)

MONTH YEAR TO DATE CUMULATIVE

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.

2. Maximum Dependab:e 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.

3. Number of Hours the Reactor was Critical. 158.98 2,201.43 98,055.83 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. 139.92 2,181.32 97,155.72 (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 tc*al 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 n n available for operation,

6. Net Electrical Energy (MWH). 103,642 2,421,065 97,269,401 The gross electrical output of the unit measured at the output terminals of the turbine-generato,r minus the normal station service loads during the gross hours of the reporting period, expressed in megawatt hours. Negative quantres should not be used.

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UNIQUE REPORTING REQU;REMENTS (UNIT 1) for tha month of April,1999

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' 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 EVEET 4/23/99 1RY455A 1 Spurious Mode 3 See Attacned

2. Licensee generated changes to ODCM.

None

3. Indications of failed fuel.

None. Fuel Reliability Indicator: FRI = N/A, Plant startup on 4/24. No steady state data available.

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, April 1,1999 through April 30,1999. This information is 1 provided pursuant to the reportable occurrence reporting requirements as set forth in 10CFR 50.73.

i Occurrence Licensee Event Report Number Date Title of Occurrence j 454: 99-002 4/23/99 Feedwater Reset Pushbuttons Depressed to Prevent Feedwater Isolation when opening Reactor Trip Breakers i

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I SAFETY RELIEF VALVE OPERATIONS FOR UNIT ONE l The unit was at 2235 psig,540 degrees F waiting for personnel to perform the Mode 3 Walk down ,

and additional testing.

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At 00:48:00 on 4/23/99, all 4 Pressurizer pressure channels indicated normal pressure (2232 psig). {

At 00:48:03, a control deviation high alarm came in, followed 1 second later by the 1RY455A power operated relief valve (PORV) open alarm. Looking at the point history data for all four Pressurizer pressure channels, PT455 dropped to 1839 psig sometime between 00:48:00 and 00:48:05, remained at 1839 psig until 00:48:10, then increased back to 2160 psig. The other three channels of Pressurizer pressure decreased to 2160 over this span of time and remained unaffected by the spike in channel PT455. In all cases, the Master Pressurizer Pressure Controller, the Spray Valve Controllers and 1RY455A valve responded correctly to the event. The 1RY455A valve did not open due to a high pressure event, rather due to the rate sensitive feature of the Master Controller and .

the indicated rapid increase in pressure sensed from channel PT455. 1 The cause of the spike in channel PT455 is not certain. The spike showed up in the l&C portion of channel PT455 but not in the SSPS portion of that same loop as indicated by the absence of a 'LO PZR PRESS RX Trip Alert alarm 1839 psig is lower than the 1885 psig reactor trip sotpoint, so SSPS should have seen the pressure transient had it originated in the transmitter.

Therefore, the likely cause to this event is either a spurious signal from the control loop or some sort of RF interference close to the cabinets. The latter can not be verified at this time based on the available information. There were no adverse consequences as a result of this event.

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OPERATING DATA REPORT UNIT TWO DOCKET NO. 50-455 UNIT NAME Byron Two DATE 05/03/99 COMPLETED BY R. Colalazier TELEPHONE (8151234-5441 X2609 REPORTING PERIOD: April.1999 l (Month / Year)

MONTH YEAR TO DATE CUMULATIVE

1. Design Electrical Rating (Mwe-Net). 1,120 N/A N/A The nominal net electrical output of the unit i specified by the utility and used for the purpose  !

of plant design. l

2. Maximum Dependable Capacity (Mwe-Net). 1,105 N/A N/A The gross electrical output as measured at the l 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. 719 2,879 90,648.4 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. 719 2,879 89,925.9 (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.

6. Net Electrical Energy (MWH). 791,158 3,263,007 90,250,790 The gross electrical output of the unit measJred 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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. l UNIQUE REPORTING REQUIREMENTS (UNIT 2) for the month of April,1999

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 DATE ACTUATED ACTUATION CONDITION OF EVENT None

2. Licensee generated changes to ODCM.

None l

3. Indications of failed fuel.

I None. Fuel Reliability Indicator: FRI = 3.04 E-6 pCi/cc I

4. Licensee Event Reports i The following is a tabular summary of all Licensee Event Reports for Byron Station, Unit Two, occurring during the reporting period, April 1,1999 through April 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 l

None i

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