ML20154E981
| ML20154E981 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 08/31/1988 |
| From: | Peterson M, Querio R COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| BW-88-1078, NUDOCS 8809190208 | |
| Download: ML20154E981 (14) | |
Text
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BRAIDH000 NUCLEAR POWER STATION UNIT 1 AND UNIT 2 MONTHLY PERFORMANCE REPORT en i
COMMONHEALTH E0ISON COMPANY NRC DOCKET NO. 050-456, LICENSE NO. NPF-72 i
l NRC DOCKET NO. 050-457, LICENSE NO. NPF-77 i
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8009190200 880831 i'
PDR ADOCK 05000456 i
R PDC (495/2/4) i I
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Monthly Report for Braidwood Unit 1 A.
Summary of Ooeratina Experience The unit entered the month of August at 99% reactor power. On August 11, a reactor trip occurred while replacing a fuse on the Rod Control System.
The unit was returned to service on August 12. On August 21 power was reduced to less than 50% to evaluate the Quadrant Power Tilt Ratio following load swings ordered by the Load Dispatcher.
The unit was returned to 98% reactor power on August 22 and remained at that level through the end of the month, r.
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(4957z/3)
j OPhRATING DATA RF2Qft1 B
DOCKET NO.:
50-456 UNIT:
Braidwood 1 DATE: 09/09/88 COMPILED 8Y:
K. W. Peterson TELEPHONE:
(815)458-2801 ext. 2480 OPERATING STATUS 1.
Reporting Period: August, 1988 Gross Hours:
744.0 2.
Currently Auth4d 2ed Power Level (HHt):
3411 Design ElectHcal Rating (HH9-gross):
1175 Desic' Electrir.1 Rating (HHr-net):.
1120 Hax Dependebie Japacity (HHe-g*csO :
1175 Max Opi.1dela Capacit) (HHe-net);
1120 3.
Power level to (Mch restricted (If Any):
None h
4.
Re.';v.s for ref *rictic t (If.\\ fry): None 1111S HONTH YR TO 04TE' CUMULATIVE
- 5.
Report period Hours:
744.0_.
800.3 800.3 6.
Sours Reactor Critical:
727.3 783.6 783.6 7.
RX R9 serve Shutdown Hours:
0.0 0.0 0.0 8.
Hours Generator on Line:
716.3 772.6 772.6 9.
Unit Reserve Shutdown Hours:
0.0 0.0 0.0 10.
Gross Thermal Energy (HHH):
2172541 2355623 2355623 11.
Gross Elec. Energy (HHH):
735674 798364
__2983fL_._
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12.
Net Elec. Energy (HHH):
704408 764448 764448 -
13.
Reactor Service Factor:
97.8 97.9 97.9 14.
Reactor Availability Factor:
97.8
- 97. 9_,
97.9 15.
Unit Service Factor:
96.3 96.5 96.5 16.
Unit Availability Factor:
96.3 96.5 96.5 17.
Unit Capacity Factor (HDC net):
84.5_
85.3 85.3 i
18.
Unit Capacity Factor (OER net):
84.5 85.3 85.3 l
19.
Unit Forced Outage Rate:
0.04 0.03 0.03 20.
Unit Forced Outage Hours:
27.7 27.7_
27.7 21.
Shutdowns Scheduled Over Next 6 Honths:
1 22.
If Shutdown at End of Repert Period, Estimated Date of Startup:
23.
Units in Test Status (Prior to N
i comercial Operation):
4, FORECAST ACHIEVED.
0H29182/\\y7 Initial Criticality 05123182 rx Initial Electricity 07/11/82 0ZI12182 '/ '\\s Comercial Operation 07/15LBB 01/_29L88
- Numbers re-zerced due to comercial operation i
(4957z/4)
.. - ~ - - -,,,,
n-----..,--.n,--,-------_-,n,.__-,
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C.
AVERAGE DAILY UNIT NET POWER LEVEL LOG DOCKET NO.:
50-456 l
UNIT:
Braidwood 1 DATE: 09/09/88 COMPILED BY:
M. H. Peterson 1
TELEPHONE:
(815)458-2801 ext. 2480 HONTH: August, 1988 1,
1106 17.
1096 2.
1094 18.
1097
[
3.
1062 19, 1084 4.
1108 20.
1087 j
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1035 21.
550 i
j 6.
1033 22.
874 7.
1012 23, 1073 J
8.
1094 24.
988 9,
1094 25.
995 l
l 10, 1095 26.
999 l
l 11.
530 27, 1012 12.
11 28.
974 4
13.
285 29.
991 l
14.
787 30.
998 f
1 15, 1087 31.
1009 16.
1076 i
I INSTRUCTIONS
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On this form list the average daily unit power level in HHe-Net for each l
l day in the reporting month. Compute to the nearest whole megawatt.
j 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 a
such cases the average daily unit power output sheet should be footnoted i
to explain the apparent anomaly, i
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(49572/5)
D.
W IT SHUTDOWNS /REDUCTIG"S DOCKET NO.: 50-456 UNIT: Braidwood 1 DATE: 09/09/88 COMPILED BY: M. H. Peterson TELEPHONE: (815)458-2801 ext. 2480 REPORT PERIOD: August, 1988
_!80_ Q&5 11P_E HOURS PEASON METHOD LER NUMBER SYSTEM COMPONENT CAUSE & CORRECTIVE ACTION TO PREVENT RECURRENCE 01 880811 F 27.7 G
3 88-016 N/A N/A Reactor trip due to negative rate trip.
02 88C321 F 0
F 1
N/A N/A N/A Load reduction to evaluate the Quadrant Power Tilt Ratio following a load swing ordered by the load dispatcher.
SUMMARY
TYPE REASON METHOD SYSTEM & COMPONENT l
F-Forced A-Equipment Failure 1 - Manual Exhibit F & H l
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-1022)
F-Administration 9 - Other G-Oper Error H-Other (4957zl6)
t E.
UNIOUE REPORTING REOUIREMENTS-UNIT I 1.
Safety / Relief valve operations.
VALVES NO & TYPE PLANT DESCRIPTION DA_TE ACTUATED ACTUATION CONDITION OF EVENT None 2.
Licensee generated changes to 00CH.
None (4957z/7)
F.
LICENSEE EVENT REPORTS - UNIT I The following is a tabular summary of all Licensee Event Reports submitted during the reporting period. August 1 through August 31, 1988.
This information is provided pursuant to the reportable occurrence reporting requirements as set forth in 10 CFp 50.73.
Licensee Event Repar_t Egoort Number-QAlg Title of Occurrence 88-015-00 07/25/88 Control room ventilation isolation due to inadvertent switch mispositioning.
88-017-00 08/17/88 Hissed technical specification composite samples due to failure to implement required changes.
88-018-00 08/17/88 Inoperable valves to 1H001CB containment chiller IB as a result of out of service procedural deficiency.
86 t,9-00 08/19/88 Train A and B control room ventilation switchover due to i
radiation monitors OPR31J thru 34J l
experiencing a momentary loss of l
power from 345 KV line loss.
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(4957I/8)
II. Monthly Report for Braidwood Unit 2 A.
Summarv of Ooeratina Exoerience The unit entered the month of August at 74% reactor power. On August 7, power was reduced to below 50% to facilitate Feedwater Pump startup testing.
Following this testir.g the unit 'vas returned to 74% reactor power on August 8.
1he unit was again reduced below 50% reactor power on August 13 to facilitate Feedwater Pump testing.
On August 15, the unit was returned to 70% reactor power.
On August 17, the 75% startup test sequence was completed and the unit was increased to 90% reactor power. On August 23, power was reduced t 26% as a result of a nitrogen leak on a Feedwater Isolation Valve. Upon completion of repairs, the unit was increased to 90%
reactor power. On August 31, the 90% startup test sequence was completed and the unit was increased to 100%
reactor power.
.+
(4957z/9)
B.
.0PERATING DATA REPORT DOCKET NO.:
50-457 UNIT:
Braidcood 2 DATE: 09/09/88 COMPILED BY:
M. H. Peterson TELEPHONE:
(815)458-2801 l
ext. 2480 OPERATING STATUS 1.
Reporting Period: August, 1988 Gross Hours: 744.0 2.
Currently Authorized Power Level (MHt):
3411 Design Electrical Rating (MHe-gross):
1175 Design Electrical Rating (MHe-net):
1120 Max Dependable Capacity (MHe-gross):
1175 Max Depe'deble Capacity (MHe-net):
1120 3.
Power level to which restricted (If Any):
None 4.
Reatons for restriction (If Any): None f
THIS HONTH YR TO DATE CUMULATIVE 5.
Report period Hours:
744.0 2355.4
_1355.4 6.
Hours Reactor Critical:
744.0 2111.7 2111.7 7.
RX Reserve Shutdown Hours:
0.0 0. 0._
0.0 q
8.
Hours Generator on Line:
744.0 1951.6 1951.6 9.
Unit Reserve Shutdown Hours:
0.0 0.0 0.0 10.
Gross Thermal Energy (MHH):
1916252 3734970 3734970 11.
Gross Elec. Energy (MHH):
639092 1157854 1157854 12.
Net Elec. Energy (MHH):
60837.0_.
1031199.
._1091199 13.
Reactor Service Factor:
N/A N/A N/A 14.
Reactor Availability Factor:
N/A N/A N/A 15.
Unit Serv'ce Factor:
N/A N/A N/A 16.
Unit Availability Factor:
N/A N/A N/A 17.
Unit Capacity 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:
0.0
_204.1 204.1 21.
Shutdowns Scheduled Over Next 6 Months:
22.
If Shutdown at End of Report Period.
Estimated Date of Str.rtup:
23.
Units in Test Status (Prior to Comercial Operation):
FORECAST ACHIEVED Initial Criticality 02129188 03L08/88 Initial Electricity 03L28L88 05L25LB8 Comercial Operation 10Llllfl8 (4957z/10)
C.
AVERAGE DAILY UNIT NET POWER LEVEL LOG DOCKET NO.:
50-457 UNIT: Braidwood 2 DATE: 09/09/88 COMPILED BY:
M. H. Peterson TELEPHONE:
(815)458-2801 ext. 2480 MONTH: August, 1988 1.
806 17.
823 2.
810 18.
987 3.
802 19, 996 4.
794 20.
998 5.
802 21.
994 6.
803 22.
1000 7.
527 23.
603 8.
716 24.
229 l
9.
796 25.
638-l 10.
.795 26.
1042 11.
787 27, 1110 12.
777 23.
1116 13.
533 29.
1017 14.
516 30.
902 15.
748 31.
1052 16.
_815 INSTRUCTIONS On this form list the average daily unit power level in HHe-Net for each day in the veporting month. Compute to the nearest whole megawatt.
These figures will be used to plot a graph for each reporting inonth.
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.
(49572/11)
D.
UNIT SHLITDOWNS/ REDUCTIONS DOCKET NO.: 50-45/
UNIT: Braidwood 2 DATE: 09/09/88 COMPILED BY: M. W. Peterson TELEPHONE: (815)458-2801 -
ext. 2480
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REPORT PERIOD: August 1988
_No_ D81E Illi HOURS REASON METHOD LER NUMBER SYSTEM COMPONENT fMISE & CORRECTIVE ACTION TO PREVENT RECURRENCE 10 880807 5 0
B 5
N/A N/A N/A Load reduction to facilitate startup testing of the Feedwater System.
11 880813 S O
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N/A N/A N/A Load reduction to facilitate startcp testing of the Feedw?.2er System.
12 880823 F 0
A 5
N/A N/A N/A Load reduction due to a nitrogen leak while perform' g a Feedwater System surveillance.
Leak was repaired.
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SUMMARY
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TYPE REASON METHOD SYSTEM & COMPONENT l
F-Forced A-Equipment Failure 1 - Manual Exhibit F & H S-Scheduled B-Maint or Test 2 - Manual Scram Instructions for Preparation of I
C-Refueling 3 - Auto Scram Data Entry Sheet
~(
D--Regulatory Restriction 4 - Continued Licensee Event Report i
E-Operator Training & License Examin1 tion 5 - Reduced Load (LER) File (NUREG-1022)
F-Administration 9 - Other i
G-Oper Error l
H-Other g
(4957z/12)
E.
UNIOUE REPORTING REOUIREMENTS - UNIT 2 1.
Safety / Relief valve operations.
VALVES NO & TYPE PUWT DESCRIPTION MTI ACTUATED ACTUATION CONDITION
.OF EVENT None 2.
Licensee generated changes to 00CM.
None
+
(4957z/13)
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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 August 1 through Augurt 31, 1988.
4 This information is provided pursuant to the reportable occurrence reporting requirements as set forth in 10 CFR 50.73.
4 Licensee Event Rinori Etport Number DAll Title of Occurrence
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88-019-00 08/19/88 Manual reactor trip due to approaching low low steam generator levels as a result of instrument air valve mispositioning by person i
or persons unknown.
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(4957z/14)
Commonwealth Edison Braidwood Nuclear P.wcr Station Route C1, Box 84 Braceville, Illinois 6o407 Telephone 815/458-2801 BH/88-1078 September 9, 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 covering Braidwood Nuclear Power Station fcr the period August I through August 31, 1988.
Very truly yours.
WA O R. E. Querto Station Manager Braidwood Nuclear Station REQ /RCB/ jab (49572)
Attachments cc:
A. B. Davis, NRC, Region III NRC Resident Inspector Braidwood Gary Hright, Ill. Dept. of Nuclear Safety T. J. Maiman K. L. Graesser H. E. Bliss Nuclear Fuel Services, PHR Plant Support INPO Records Center Performance Munitoring Group, Tech Staff Braidwood Station Nuclear Group, Tech Staff Braidwood Station S. Sands - USNRC N
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