ML20043F411

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Monthly Operating Repts for May 1990 for Braidwood Nuclear Power Station
ML20043F411
Person / Time
Site: Braidwood  Constellation icon.png
Issue date: 05/31/1990
From: Peterson M, Querio R
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BW-90-0608, BW-90-608, NUDOCS 9006140503
Download: ML20043F411 (14)


Text

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Commsnwoalth Edison Braidwood Nuclear Power St1 tion Route #1, Box 64

. Braceville, Illinois 60407 Telephone 815/458 2801 June 8,1990 BW/90-0608 Director, Office of Resource Management United States Nuclear Regulatory Commission Washington, D.C. 20555 ATTN: Doc"mt Control Desk Gentlemen:

Enclosed for your information is the Monthly Performance Report

- covering Braidwood Nuclear Power Station for the period May 1 through May 31,1990.

Very truly yours, W

w d R. E. Queri F Station Manager Braidwood Nuclear Station REQ /EWC/jfe (4957z)

Attachments cc: - A. B. Davis, NRC, Region III NRC Resident inspector Braidwood 111. Dept. of Nuclear Safety T. J. Malman K. L. Graesser T. J. Kovach Nuclear Fuel Services, PWR Plant Support INPO Records Center Performance Monitoring Group, Tech Staff Braidwood Station Nuclear Group, Tech Staff Braidwood Station S. Sands - USNRC S. C. Hunsader D.R. Eggett-Nuclear Engineering Department

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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. NPF-72 NRC DOCKET NO.- 050-457, LICENSE NO. NPF-77 I

.I.

Monthly Report for Braidwood Unit 1 A.

SLmmarv of Ooeratina Exoerienta Braidwood Unit 1 operated routinely in May with no outages or significant power reductions.

(4957z/3)

l S.-

' OPERATING DATA REPORI DOCKET NO.:

50-456 UNIT: - Braidwood 1 DATE:

06/10/90 i

COMPILED BY:

M. H. Peterson TELEPHONE:

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

Reporting Period: May, 1990 Gross Hours: 744 2.-

Currently Authorized Power Level-(MHt):

3411 Design Electrical Rating (MWe-gross):

1175 Design Electrical Rating (MHe-net):

1120

(

Max Dependable Capacity (MHe-gross):

1175 Max Dependable Capacity (MHe-net):

1120 3.

Power level to which restricted (If Any):

None 4.

Reasons for restriction (If Any):

None THIS MONTH YR TO DATE CUMULATIVE 5.

Report period Hours:

744 3623 16112 6.

Hours Reactor Critical:

744 3599.6 12696.8 7..

RX Reserve Shutdown Hours:

0.0 0.0 0.0 8.

Hours Generator on Line:

744 3587.7 12437.3 i

9.

Unit Reserve Shutdown Hours:

0.0 0.0 0.0 10.

Gross Thermal Energy (MHH):

2401030 11694528 36497736 11.

Gross Elec. Energy (MHH):

_B37287 4076196 12556263 12.

Net Elec. Energy (MHH):

806043 3932959 11990130 13.

Reactor Service Factor:

100 99.4 78.8 14.

Reactor Availability Factor:

100 99.4 78.8 15.

Unit Service Factor:

100 99.0 77.2 16.

Unit Availability Factor:

100 99.0 77.2 17.

Unit Capacity Factor (MDC net):

96.7 96.9 66.4 18.

Unit Capacity Factor (DER net):

96.7 96.9 66.4 19.

Unit Forced Outage Rate:

0.0 1.0 4.1 20.

Unit forced Outage Hours:

0.0 35.3 535.6 21.

Shutdowns Scheduled Over Next 6 Months: None l

22.

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

1 1'

l I'

l l

(4957z/4) l

C..

AVERAGE DAILY UNIT NET POWER LEVEL LOG DOCKET NO.:

50-456 UNIT:

Braidwood 1 DATE: 06/10/90 COMPILED BY:

M. W. Peterson TELEPHONE:

(815)458-2801 ext. 2480

, MONTH: May, 1990 I

1.

1102 17, 1089 l

2.

  • 1121 18, 1089 j

I 3,

1096 19, 1082 4.

  • 1129 20.

1069 i

5.

1093 21.

1076 i

6.

973 22, 1054 7,

1070 23, 1051

,l 8,

1120 24, 1072 9.

  • 1121 25.

1065 10..

'1100 26.

1068 i

11.

1116 27, 1029 12.

1081 28.

1041 l

13.

1070 29.

1052 1

14.

1096 30, 1082 15.

  • 1127 31.

1102 16.

  • 1136 INSTRUCTIONS On this form list the average daily unit power level in HWe-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 the unit there may be occasies when the daily average power level exceeds the'1007, line (or the restricted power level line).

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

  • 0ue to Condenser Efficiencies (49572/5)

~

D.

UNIT SHUTDOWNS / REDUCTIONS DOCKET NO.: 50-456 UNIT: Braidwood 1 DATE: 06/10/90 COMPILED BY: M. W. Peterson TELEPHONE: (815)458-2801 ext. 2480 REPORT PERIOD: May, 1990 No DATE TY_PE HOURS REASON METHOD LER NUMBER SYSTEM COMPONENT CAUSE & CORRECTIVE ACTION TO PREVENT RECURRENCE None

SUMMARY

TYPE REASON METHOD SYSTEM & COMPONENT F-Forced A-Equipment 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-0161)

F-Administration 9 - Other G-Oper Error H-Other (4957z/6)

E.-

UNIOUE REPORTING REOUIREMENTS - Unit-1 1.

Safety / Relief valve operations.

VALVES NO & TYPE PLANT DESCRIPTION DATE ACTUATED ACTUATION CONDITION OF EVENT None 2.

Licensee generated changes to ODCM..

None l

l l

I l

(4957z/7) l L

. =

4

--G Ff LICENSEE EVENT REPORTS - UNIT 1 The following is a tabular summary of all Licensee Event Reports submitted during the reporting period, May 1 through May 31, 1990. This information is provided pursuant to the reportable occurrence reporting requirements as set forth in 10 CFR 50.73.

Licensee Event Report Reoort Number Qaig Title of Occurrence 90-005 05-11-90 Unnecessary entry into limiting conditions for Operation Action Requirement 3.0.3 due to unclear main steamline isolation valve operability requirements.90-006 05-16-90 Diesel Generator slow start from crisscrossed starting airlines due to programmatic deficiency.

(4957z/8)

F1

?

4 l

4 I.-

Monthly Report for Braidwood Unit 2.

A.-

Summary of Ooerating Exnerience Braidwood Unit 2 was in its first refueling outage for the first 27 days of the month. =The unit was brought on line on May 28, 1990.

The unit was taken off-line later that day to perform the turbine overspeed' trip test and then i

brought back on line to perform 30% power testing.

The unit remained there through the end of the month.

e I

t L

t 1

(4957z/9) i

OPERATING DATA REPORT DOCKET NO.:

50-457 jL -

~c UNIT:

Braidwood 2 DATE:

06/10/90-COMPILED BY:

M. H. Peterson TELEPHONE:

(615)458-2801 ext. 2480 OPERATING STATUS-1.

Reporting Period: May, 1990 Gross Hours:

744 2.

Currently Authorized Power Level (HHt):

3411 Design Electrical Rating (MHe-gross):

1175 Design Electrical Rating (MHe-net):

1120-Max Dependable Capacity (MHe-gross):

1175 Max Dependable Capacity (MHe-net):

1120 3.

Power level to which restricted (If Any):

30% (352 Mwe-gross) 4.

Reasons for restriction (If Any);

Flux Mapping THIS MONTH YR TO DATE CUMULATIVE 5.

Report period Hours:

744 3623 14194 6.

Hours Reactor Critical:

157.1 1934.3 11069.6 7.

RX Reserve Shutdown Hours:

0.0 0.0 0.0-8.

Hours Generator on Line:

84.6 1861.3 10922.1 9.

Unit Reserve Shutdown Hours:

0.0 0.0 0.0 10.

Gross Thermal Energy (MHH):

85374 3835611 29676569 11.

Gross Elec. Energy (MHH):

19546 1264659 10156047 12.

Net Elec. Energy (MHH):

7276 1174744 9667719 13.

. Reactor Service Factor:

21.1 53.4 78.0 14.

Reactor Availability Factor:

21.1 53.4 78.0 15.

Unit Service Factor:

11.4 51.4 76.9 16.

Unit Availability Factor:

11.4 51.4 76.9 17.

Unit CapacityrFactor (MDC net):

0.9 29.0 60.8 18.

Unit Capacity Factor (DER net):

0.9 29.0 60.8 19.

Unit Forced Outage Rate:

0.0 0.0 4.1 20.

Unit Forced Outage Hours:

0.0 0.10 465.7 21.

Shutdowns Scheduled Over Next 6 Months: None 22.

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

(4957z/10)

C.

AVERAGE DAILY UNIT NET POWER LEVEL LOG DOCKET NO.:

50-457 UNIT:

Sraidwood 2 DATE: 06/10/90-COMPILED BY:

M. H.-Peterson TELEPHONE:

(815)458-2801 ext. 2480 MONTH: May, 1990 1.

-13 17.

-14 2.

-13 18.

-14 3.

-13 19.

-14 4.

-13 20.

-14 5.

-13 21.

-14 6.

-14 22.

-15 7.

-14 23.

-15 8.

-14 24.

-15 9.

-13 25.

-15 10.

-13 26.

-15 11.

-13 27.

-15 12.

-13 28, 37 13.

-13 29.

172 14.

-13 30, 214 15.

' -13 31, 260 16.

-13 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 the unit there may be occasions when the daily average power level exceeds the 100% line (or the restricted power level line).

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

(4957z/ll) l l

,c

.. = -i.,

i

. DOCKET NO.: 50-457

'D.

UtilT SHUTD0HNS/ REDUCTIONS.

UNIT: Braidwood 2 DATE:=06/10/90 COMPILED BY: M. H. Peterion TELEPHONE: (815)458-2801--

ext. 2480 REPORT PERIOD: May, 1990 No DATE TYPE HOURS REASON METHOD LER NUMBER SYSTEM COMPONENT CAUSE & CORRECTIVE ACTION TO PRE 1

900316 S 656.3 C

4 NA NA NA Concluded Bradwood Unit 2 first refuel outage.

2 900528 S 3.1 B

1 NA NA NA Unit 2 taken off line for turbine overspeed trip test.

AAAAAAAAAAAAAAAAA

SUMMARY

            • AAAA444*AA&

TYPE REASON METHOD SYSTEM & COMP 0NEP C -

F-Forced A-Equipment failure Maint or Test 1 - Manual Exhibit F & H S-Scheduled B-Maint or Test 2 - Manual Scram Instructions for Preparation of 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 (4957z/12) i-

E.

'UNIOUE 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 ODCH.

None (4957z/13)

J..

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--<r r

.r

Y e '1

.4 -.y x

, l.

-k F.

LICENSEE EVENT REPORTS - UNIT 2 The following is a tabular summary of all Licensee Event Reports submitted during the reporting period, May l'through May 31, 1990..This information is provided pursuant to the reportable occurrence reporting requirements as set forth in 10 CFR 50.73.

Licensee Event Report Reoort Number DAtt -

Title of_0ccurrence 90-003 05-03-90 Inadvertent train B safety injection due to programmatic deficiency.90-004 05-14-90 2A Diesel Generator speed oscillations due to a defective resistor.90-005 05-25-90 2A Diesel Generator starting air valves 6L and 9L crossed, (4957z/14)

.