ML20066D908

Monthly Operating Repts for Braidwood Nuclear Power Station for Dec 1990

ML20066D908
Person / Time
Site:	Braidwood
Issue date:	12/31/1990
From:	Dundek K COMMONWEALTH EDISON CO.
To:
Shared Package
ML20066D888	List: ML20066D886 ML20066D908 ML20066D912
References
NUDOCS 9101170103
Download: ML20066D908 (13)

Text

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BRAIDWOOD NUCLEAR POWER STATION UNIT 1 AND UNIT 2 MONTHLY PERFORMANCE REPORT COMMONWEALTH EDISON COMPANY NRC. DOCKET NO. 050-456, LICENSE NO. NPP-72 NkC DOCKET NO. 050-457, LICENSE NO. NPF-77 l

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I 9101170103 910110 PDR ADOCK 05000456 PDR R

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Monthly Report for Braidwood Unit 1 A.

Summary of Operating Expgnigggg s

Unit 1: entered the month of December-at.approximately-99.2% power. On December.1, 1990-the unit tripped on low steam generator level resulting f rom the' loss -of a main-

'feedwator pump. The pump was repaired and the unit returned to power operation on December:3, 1990. On December 4,-1990 the. generator was taken off-line to replace the seal ollivapor extractor motor.- After the j

motor replacement, the generator was-synchronized to the grid ~and the. unit-performed routinely until December 30, 1990 when it tripped due to a main generator neutral' ground.overcurrent. The unit remained off-line through'the remainder of the report period.

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DEX. RATING DATA REPQRI DOCKET NO.:

50-456 UNIT Braidwood 1 DATE: 01/10/91 COMPILED BY:

K. M. Dundek TELEPHONE:

(815)458-2801 ext. 2480 OPERATING STATUS 1.

Reporting Period: December, 1990 Gross Hours:

744 2.

Currently Authorized Power Level (MWt):

3411 Design Electrical Rating (MWe-gross):

1175 Design Electrical Rating (MWe-net):

1120 Max Dependable Capacity (MWe-gross):

1175 Max Dependable Capacity (MWe-net):

1120 3.

Power level to which restricted (If Any):

None 4.

Reasons for restriction (If-Any):

None IHIS MONTH YR TO DATE CUMULATIVE 5.

Report period Hours:

744 8760 21249 6.

Hours Reactor Critical:

655.2 7830.1 16927.3 7.

RX Reserve Shutdown Hours:

0.Q_

0.0 0. 0..

8.

Hours Gonerator on Line 640.4 7781.3 16630.9 l

9.

Unit Reserve Shutdown Hours:

0.0 0.0 0.0 10.

Gross Thermal Energy (MWH):

2058699 21849862 49653070 11.

Gross Elec. Energy (MWH):

710492 8600574 17080641 12.

Net Elec. Energy (MWH):

680782'

_3264585 If321756 13.

Reactor Service Factor 88.1 89.4 79.7 14.-

Reactor Availability Factor:

88.1 69 1 79.7 15.

Unit Service Factor 86.1 88 1 78.3 2

16.

Unit Availability Factor 86.1 88.8 78.3 17.

Unit Capacity Factor (MDC net):

81.7 84.2 68.6 18.

Unit Capacity Factor (DER not):

81.7 84.2 68 1_

19.

Unit Forced Outage Rate 13.9 11.2 8.2 20.

Unit Forced Outage Hours:

103.9 979 1479.3 21.

Shutdowns Scheduled Over Next 6 Months: Refueling Outage - March, 1991 22.

If Shutdown at End of Report Period, Estimated Date of Startup:

Februarv 6, 1991_

(227/ZD85G)4

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AVERAGE DAILY UNIT NET' POWER LEVEL LOG.

DOCKET No. 456 UNITI-Braidwood 1

}

-DATE:

01/10/91' COMPILED BY K. M. Dundek TELEPHONE:

(815)458-2801-ext. 2480 MONTH:

December, 1990

< 1..

786 17.

• 1129 L

2.

-15 18.-

• 1128 3.

-3 19.:

• 1128 4.

116 20.

'*1128

'u.

5.

691 21.

• 1128-6.

1068 22.

• 1127 i

7, 1069 23.

• 1128 8..

1069

-24.

• 1128 9.

1070 25.

• 1124 10, 1071 26.

• 1126 11..

1070

27. -

~ *1126 ^

12..

1068 28.

• 1126 13, 1071 29.

1118 1070

- 3 0.

308 15.

1086 31.

-14

?16.

-*1129 i

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' INSTRUCTIONS.

On this form list the average daily unit power level in MWe-Het for each

day in the reporting month. LCompute to the

nearest'whole megawatt.

?These figures > will; be used to plot a graph for cach reporting. month.

Note that-when. maximum dependable capacity is used:for the net electrical

-rating of the: unit there'may be-occasions when1the daily average power.

level exceeds the 100% line (or the restricted power: level line).- InL

-such cases the average-daily unit power output sheet should be footnoted to explain the apparent anomaly.

• Due to. Condenser Efficiencies (227/ZD85G)5

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UNIT SHUTDOWNS / REDUCTIONS DOCKET NO.: 50-456 UNIT: Braidwood l~

DATE: 01/10/91 COMPILED BY: K. M. Dundek-TELEPHONE: (815)458-2801 ext. 2480 REPORT PERIOD: December, 1990 No DATE TYPE HQURE REASON METHOD LER NUMBER SYSTEM COMPONENT CAUSE & CORRECTIVE ACTION TO PREVENT RECURRENCE 5

901201 F 53.7 A

3 90-021 EW N/A The IB Feedwater Pump tripped due to low oil pressure.

'It is believed that the suction of the high pressure oil pump became partially plugged. A portable centrifuge has been connected to the pump oil reservoir to remove water and debris from the oil system. Other methods to minimize potential water intrusion into the oil system are being evaluated.

6 901230 F 39.6 A

3 90-023-TG GEN Neutral ground overcurrent trip of main generator. Problem isolated to stator with exact.cause being investigated for appropriate corrective action.

SUMMARY

TYPE REASON METHOD SYSTEM & COMPONENT F-Forced A-Equ.ipment _ Failure Maint or Test 1 - Manual Exhibit F & H S-Scheduled

'B-Maint or Test 2 - Manual Scram Instructions for Preparation of C-Refueling-3 - Auto Scram Data Entry Sheet D-Regulatory Restriction 4 - Continued Licensee Event Report E-Operator Training & License Examination 5 - Reduced Load (LER)' File (NUREG-Ol61)

F-Administration 9 - Other G-Oper Error H-Other.

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UNIOUE REPORTING REOUIREMENTS - Unit 1

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1.

Safety / Relief ' valve operations.

VALVES NO & TYPE-PLANT DESCRIPTION s

DATE ACTUATED ACTUATION CONDITION JF EVENT NOME 2.

Licensee generated changes to ODCM.

See Attachment k

(227/ZD85G)7

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.klCERSEE EVENT REPORTS - UNIT l' i

r The_-following isLa tabular summary of'all Licensee Event Reports i

I submitted ~during the reporting _ period, December 1 through December 31, 1990. This information is provided. pursuant to the reportable ocettrence reporting requirements as set forth in 10 CFR 50.73.

Licensee Event Report Eleport Numbet Rafa Title of Occurrence 90-020-12-21-90 Spurious start of the Auxiliary Building Inaccessible Filter Plenum

-l A Charcoal Booster Fan OB due to component failure.90-021 12-31-90 Reactor trip as a result _.of a Feedwater Pump trip due to low oil pressure.-

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Monthly Report for Braidwood Unit 2 A.

Summary of Operating Experience Braidwood Unit 2 operated routinely in December with no outages or significant power reductions caused by equipment problems.

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- B.l QPERATING DATA REPOEI DOCKET NO. J 50-457 UNIT:

Braidwood 2 DATE 01/10/91' COMPILED BY:

K. M. Dundek TELEPHONE:

(815)458-2801 ext. 2480 OPERATING STATUS l

1. -

Reporting Period December, 1990 Gross Hourst 744 2.

Currently Authorized Power Level _(Mh't):

3411 Design. Electrical Rating _(MWe-gross):

1175 Design Electrical Rating (MWe-net):

1120 Max Dependable Capacity (MWe-gross):

1175 i

Max Dependable Capacity (MWe-net):

1120 3.-

Power leve11to which' restricted (If Any): None

-4.

Reasons for restriction (If Any): None.

THIS M0dTH yjLIQ_DATE CUMULATIVE r

5.

Report period Hours:

744 8760 19331

-6.-

Hours Reactor-Critical

'744

-6904.2 16039.5 7.

RX Reserve Shutdown Hours:

'0.0 0.0 0.0 8.~

-Hours Generator-on Lines 744 6850.4

,___15911.2 9.'

Unit Reserve Shutdown Hours:

0.0 0.0

'0.0 10.

Gross Thermal Energy (MWH):

2397002 19469070 45310028

11. -. Cross Elec. Energy (>941) _

.8E1383 6643385-15534773 12.~ -. Net Elec.-Energy (MWH):

797837 6334505 14827480 13.

Reactor Service. Factors 100.0 78.8

'83.0 14.

Reactor;Avellability Factort-100.0 78 a 83.0-t 15.

Unit Service Factor:

100.0_

78.2 82.3 L 16. _

Unit Availability Factor:

100.0 78.2 82.3 Eli.

Unit Capacity.-Factor (MDC net):

95.7 64.6 68.5 o

18.

Unit Capacity Factor (DER net):

95.7 64.6 68.5' 119. -- -Unit: Forced Outage Rate:

0.0 2.1 3.7 l

20.

Unit Forced-Outage Hours L 0.0 147 2 613.6-i

_21.

. Shutdowns Scheduled Over Next 6 Months: None i

22.

Il[ Shutdown at End of Report Period, Estimated Date'of Startup L

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DOCKET.NO.s. 50-457

'I C..

- AVERAGE DAILY UNIT NET POWER LEVEL LOG UNITi~ Braidwood 2 DATE:

01/10/91-COMPILED BY -

K. M. Dundek TELEPHONES- (815)458-2801 ext. 2480-

]

MONTH

-December, 1990

-!q l'

1107 17.

1118 2.

1003 18.

• 1129 3.

1054 19.

• 1129 I

4.

1102 20.

• 1129 5.

• 113L-21, 1108' 6.

• 1133 2 2.-

1097 1

-7.

• 1133

'2 3.

1047

j 8.

'1091 24, 1043

'j 9.

887 25.

880

- 10.

1043 26.

1086 f:

11.

1032 27.

'1109' 12..

1021 28.

1073 13.

1J04'-

29.

1020 1

14, 1110 30.

1036 i

= 15.1 1032 31, 1114 16, 1116 p

INSTRUCTIONS

'On;this-form list the-average-daily unit. power level--in MWe-Net for each~

day.in the reporting month. Compute to-the: nearest whole megawatt.'

These figures will be used to plot a graph for each reporting month.

? Note.that when maximum' dependable' capacity is used for the net electrical-

-rating of.theltnit there may be occasions when the daily.' average power lovel exceeds the 100% line (or the> restricted power level line).,In p

such cases the average daily unit power output sheet should be footnoted to explain the; apparent anomaly.

• Due to Condenser Efficiencies.

-(227/ZD85G)11

m DOCKET NO.: 50-457 D.

UNIT SHUTDOWNS / REDUCTIONS UNIT: Braidwood 2 DATE: 01/10/91 l

COMPILED BY: K. M. Dundek TELEPHONE: (815)458-2801 ext. 2480 REPORT PERIOD: December, 1990 No p_A_TE TXP_E HQURS REASON METHQD RR_LPRfIlE_R SYSTEM COMPONENT CAUSE & CQRR_ECTIVE ACTION TO PREVENT l

NONE co***************

SUMMARY

oo***************

METHOD SYSTEM & lOMPONENT TYPE REASON 1 - Manual Exhibit F & H j

F-Forced A-Equipment Failure Maint or Test Instructions for Preparation of 2 - Manual Scram S-Scheduled B-Maint or Test l

3 - Auto Scram Data Entry Sheet C-Refueling 4 - Continued Licensee Event Report D-Regulatory Restriction E-Operator Training & License Examination 5 - Reduced Load (LER) File (NUREG-0161)

F-Administration 9 - Other G-Oper Error H-Other (227/ZD85G)12

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TJNIOUE REPORTING REOUIREMENTS -' UNIT 2 1.

Safety / Relief valve operations.

VALVES NO & TYPE PLANT DESCRIPTION DATE ACTUATED ACTUATION CONDITION

.__OF EVENT None 2.

Licensee generated changes to ODCM.

See Attachment i

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LICENSEE EVENT REPORTS - UNIT 2--

The following is a-tabular summary of all Licensee Event Reports.

--submitted'during the reporting period, December-I through

. December 31) 1990, This-information is provided pursuant to-the

, reportable' occurrence reporting requirements as set forth in 13 CFR 50,73, Licensee' Event Report i

~

Report Number Date

-Iltle of Occurreng.g

- {

90-012-12-18-90

. Containment Ventilation isolation'

-signal due to a failed Radiation Detector.

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