ML20154D996
| ML20154D996 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 04/30/1988 |
| From: | Peterson M, Querio R COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| BW-88-345, NUDOCS 8805200054 | |
| Download: ML20154D996 (14) | |
Text
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BRAIDHOOD NUCLEAR P0HER STATION UNIT 1 AND UNIT 2 MONTHLY PERFORMANCE REPORT COMMONHEALTH EDISON COMPANY NRC DOCKET NO. 050-456, LICENSE NO. NPF-72 NRC DOCKET NO. 050-457, LICENSE NO. NPF-75 8805200054 880430 DR ADOCK 0500 6
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Monthly Report for Braidwood Unit 1 A.
Summary of Ooeratina Exoerience The unit entered the month of April in Mode 5.
On April 25, the unit was brought on line and taken up to 50%
reactor power.
By April 28, the unit's power was reduced to approximately 25% due to problems with two feedwater isolation valves.
The unit remained at approximately 25%
power through the end of the month.
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(4957z/3)
B.
OPERATING DATA REPORT DOCKET NO.:
50-456 UNIT:
Braidwood 1 DATE: 05/10/88 COMPILED BY:
H. H. Peterson TELEPHONE:
(815)458-2801 ext. 2480 OPERATING STATUS 1.
Reporting Period: April, 1988 Gross Hours:
719.0 2.
Currently Authorized Power Level (MHt):
3411 Design Electrical Rating (HHe-gross):
1175 Design Electrical Rating (HHe-net):
1120 Max Dependable Capacity (HHe-gross):
1175 Hax Dependable Capacity (HHe-net):
1120 3.
Power level to which restricted (If Any): None 4.
Reasons for restriction (If Any): None THIS HONTH YR TO DATE CUMULATIVE 5.
Report period Hours:
719.0 2903.0 k 7056.0 6.
Hours Reactor Critical:
163.1 249.0 3308.7 7.
RX Reserve Shutdown Hours:
0.0 0.0 0.0 8.
Hours Generator on Line:
140.6 213.2
_2823.9 9.
Unit Reserve Shutdown Hours:
0.0 0.0 0.0 10.
Gross Thermal Energy (HHH):
154593,__
250909 5266583 11.
Gross Elec. Energy (HHH):
49032 79586 1684190 12.
Net Elec. Energy (HHH):
42025 58136 1514787 13.
Reactor Service Factor:
N/A N/A N/A 14.
Reactor Availabilit.y factor:
N/A N/A N/A 15.
Unit Service Factor:
N/A -
N/A N/A 16.
Unit Availability Factor:
N/A._
N/A N/A 17.
Unit Cspacity Factor (MDC net):
N/A N/A N/A 18.
Unit Capacity Factor (DER net):
N/A N/A N/A 19.
Unit Forced Outage Rate:
N/A N/A N/A 20.
Unit Forced Outage Hours:
578.4 733.4 1655.6*
21.
Shutdowns Scheduled Over Next 6 Honths:
1 22.
If Shutdown at End of Report Period, Estimated Date of Startup:
23.
Units in Test Status (Prior to Comercial Operation):
FORECAST 6.W.VED Initial Criticality 05/23/87 E. 29/87 Initial Electricity 07/11/87 07/12/87 Comercial Operation 05/10/88
- Adjusted Figure (4957z/4)
C.
AVERAGE DAILY UNIT NET POWER LEVEL LOG DOCKET N0.:
50-456 UNIT:
Braidwood 1 DATE:
05/10/88 COMPILED BY:
H. H. Peterson TELEPHONE:
(815)458-2801 ext. 2480 HONTH: April, 1988 1.
0 17.
0 2.
0 18.
O 3.
0 19.
0 4.
0 20.
0 5.
0 21.
0 6.
0 22.
0 7.
0 23.
0 8.
0 24.
0 9.
0 25.
240 10.
0 26.
514 11.
0 27.
421 12.
0 28.
201 l
13.
0 29, 200 14.
0 30.
233 15.
0 16.
O INSTRUCTIONS On this form list the average daily unit power level in MWe-Net for each j
day in the reporting month. Compute to the nearest whole megawatt.
These figures will be used to plot a graph for each reporting month.
4 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/5)
/
D.
UNIT SHUTDONNS/ REDUCTIONS DOCKET NO.: 50-456
't UNIT: Braidwood 1 DATE: 05/10/88 COMPILED BY: M. W. Peterson TELEPHONE: (815)458-2801 ext. 2480 REPORT PERIOD: April, 1988
]NQ_- [MIE Iy_P_E HOURS REASON METHOD LER NUMBER SYSTEM COMPONENT CAUSE & CORRECTIVE ACTION TO PREVENT RECURRENCE P
02 880323 F 578.4 H
4 N/A N/A N/A Unit shut down due to environmental qualification concerns with Limitorque valve operator grease. Grease was enanged as required.
SUMMARY
TYPE REASON METHOD SYSTEM & CG1PONENT F-Forced A-Equipment Failure 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 j
D-Regulatory Restriction 4 - Continued Licensee Event Report E-Operator Training & License Examination 5 - Reduced Load (LER) File (NUREG-1022; F-Administration 9 - Other G-Oper Error l
H-Other (4957z/6)
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F.
LICENSEE EVENT REPORTS - UNIT I The following is a tabular summary of all Licensee Event Reports submitted during the reporting period, April 1 through April 30, 1988.
This information is provided pursuant to the reportable occurrence reporting requirements as set forth in 10 CFR 50.73.
Licensee Event Recort Rgoort Number QA11 Title of Occurrence 87-031-02 03/30/88 Control room ventilation shift to emergency makeup mode as a result of spurious actuation of a radiation monitor due to design deficiency.
88-004-00 04/04/88 Hanual reactor trip due to digital rod position indication system component failure.
88-006-00 04/06/88 Partial loss of auxiliary building non accessible filter plenum position indication due to an administrative and management deficiency.
88-008-00 04/25/88 Reactor coolant system leakage due to broken relief valve disc pin.
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II. Monthly Report for Braidwood Unit 2 A.
Summary of Operating Exoerience The unit entered the month of April in Mode 5.
The unit remained in Mode 5 through the end of the month due to Limitorque valve operator grease concerns.
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(4957z/9)
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B.
OPERATING DATA REPORT DOCKET NO.: 50-457 UNIT:
Braidwood 2 DATE: 05/10/88 COMPILED BY:
H. H. Peterson TELEPHONE:
(815)458-2801 ext. 2480 OPERATING STATUS 1.
Reporting Period: April, 1988 Gross Hours:
N/A 2.
Currently Authorized Power Level (HHt):
170 Design Electrical Rating (HWe-gross):
1175 Design Electrical Rating (HHe-net):
1120 Hax Dependable Capacity (HHe-gross):
0 Max Dependable Capacity (HHe-net):
0 3.
Power level to which restricted (If Any):
5%
4.
Reasons for restriction (If Any): Terms of Braidwood Station's Facility Optrating License.
THIS HONTH YR TO DATE CUMULATIVE 5.
Report period Hours:
N/A 6.
Hours Reactor Critical:
N/A 7.
RX Reserve Shutdown Hours:
N/A 8.
Hours Generator on Line:
N/A 9.
Unit Reserve Shutdown Hours:
N/A 10.
Gross Thermal Energy (HHH):
N/A 11.
Gross Elec. Energy (HHH):
N/A 12.
Net Elec. Energy (HHH):
N/A 13.
Reactor Service Factor:
N/A 14.
Reactor Availability Factor:
N/A 15.
Unit Service Factor:
N/A 16.
Unit Availability Factor:
N/A 17.
Unit Capacity Factor (MDC net):
N/A 18.
Unit Capacity Factor (DER net):
N/A 19.
Unit Forced Outage Rate:
N/A 20.
Unit Forced Outage Hours:
N/A 21.
Shutdowns Scheduled Over Next 6 Honths:
22.
If Shutdown at End of Report Period, Estimated Date of Startup:
23.
Units in Test Status (Prior to Commercial Operation):
FORECAST ACHIEVED Initial Criticality 02/29/88 03/08/88 Initial Electricity 03/28/88 Commercial Operation 07/25/88 (4957z/10)
C.
AVERAGE DAILY UNIT NET POHER LEVEL LOG DOCKET NO.:
50-457 UNIT:
Braidwood 2 DATE: 05/10/88 COMPILED BY:
M. W. Peterson TELEPHONE:
(815)458-2801 ext. 2480 MONTH: April, 1988 1.
N/A 17.
N/A 2.
N/A 18.
N/A 3.
N/A 19.
N/A 4.
N/A 20.
N/A 5.
N/A 21.
N/A 6.
N/A 22.
N/A 7.
N/A 23.
N/A 8.
N/A 24.
N/A 9.
N/A 25.
N/A 10.
N/A 26.
N/A 11.
N/A 27.
N/A 12.
N/A 28.
N/A 13.
N/A 29.
N/A 14.
N/A 30.
N/A
'?.
N/A 16.
N/A INSTRUCTIONS On this form list the average daily unit power level in HHe-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 1001 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)
____-____________________J
~
D.
UNIT SHUTDONNS/ REDUCTIONS DOCKET NO.: 50-457 UNIT: Braidwood 2 DATE: 05/10/88 COMPILED BY: M. M. Peterson TELEPHONE: (815)458-2801 ext. 2480 REPORT PERIOD: April, 1988 No DAIE 11EE HOURS REASON METHOD LER NUMBER SYSTEM COMPONENT CAUSE & CORRECTIVE ACTION TO PREVENT RECURRENCE N/A
SUMMARY
.3...............
TYPE REASON METHOD SYSTEM & COMPONENT F-Forced A-Equipment Failure 1 - Manual Exhibit F & H S-Scheduled 8-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-1022)
F-Administration 9 - Other G-Oper Error H-Other (4957z/12)
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UNIOVE REPORTING REQUIREMENTS - UNIT 2 1.
Safety / Relief valve operations.
VALVES NO & TYPE PLANT DESCRIPTION DATI ACTUATED ACTUATION CONDITION OF EVENT None 2.
Licensee generated changes to 00CM.
None (4957z/13)
F.
LICENSEE EVENT REPORTS - UNIT 2 The following is a tabular summary of all Licensee Event Reports submitted during the reporting period, April 1 through April 30, 1988.
This information is provided pursuant to the reportable occurrence reporting requirements as set forth in 10 CFR 50.73.
Licensee Event Reoort Recort Number Qaig Title of Occurrence 88-001-00 04/07/88 Safety injection pump discharge valve locked closed due to operator miscommunication.
88-005-00 04/21/88 Component cooling water surge tank level instrumentation discrepancies due to a design error.
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f Commonwealth Edison
' _ _ IU r.;.
Braidwood Nuclzr Pow:r Station
)
Rout) #1, Box 84 v'
Braceville, Illinois 60407
. Telephone 815/458-2801 BH/88-345 i
May 10, 1988 Director, Office of Resource Management United States Nuclear Regulatory Commission Hashington, D.C.
20555 ATTN:
Document Control Desk Gentlemen:
Enclosed for your information is the Monthly Performance Report j
l covering Braidwood Nuclear Power Station for the period April 1 through April 30, 1988.
i Very truly yours, i
R. E. Querto Station Manager Braidwood Nuclear Station REQ /RCB/ jab (4957z) f Attachments cc:
A. B. Davis, NRC, Region III NRC Resident Inspector Braidwood Gary Wright, Ill. Dept. of Nuclear Safety T. J. Maiman i
K. L. Graesser H. E. Bliss Nuclear Fuel Services, PHR Plant Support INPO Records Center l
Performance Monitoring Group, Tech Staff Braidwood Station Nuclear Group, Tech Staff Braidwood Station S. Sands - USNRC l
P. L. Barnes p
S)
I i
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