ML20076B188
| ML20076B188 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 06/30/1991 |
| From: | Kofron K, Pershey C COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| BW-91-0586, BW-91-586, NUDOCS 9107110080 | |
| Download: ML20076B188 (17) | |
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/ Braidwood Nucicar Power Station -
I Route #1, Box 84 -
.( O '
Braceville, Illinois 60407 Telephone 815/458-2801 -
July 10, 1991 BW/91-0586 Director, Office of Resource Management United States Nuclear Regulatory Commission Washington, D.C.
20555 ATTN Document Control Desk Gentlement Enclosed for your information is the Monthly Performance Report covering Braidwood Nuclear Power Station for the period June 1 through June 30, 1991.
Very truly yours, A
K.
. Kofron &
Station Manager Braldwood Nuclear Station KLK/ ENC /cif (227/ZD85G)
Attachments cc A. B. Davis, NRC, Region III NRC Resident Inspector Braidwood Ill. Dept. of Nuclear Safety.
M. J. Wallace K. L. Graesser T. J. Kovach Nuclear Fuel Services, PWR Plant Support INFO Records Center Performance Monitoring Group, Tech Staff Braidwood Station Nuclear Group, Tech Staff Braidwood Station R.
Pulsifer - USNRC A.
R. Checca D.
R.
Eggett - Nuclear Engineering Department 910711oC30 910630 PDR f4 DOCK 05000 66 fj.
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DRAIDWOOD NUCLEAR POWER STATION 4
UNIT 1 AND UNIT 2 MONTHLY PERFORMANCE REPORT 1
COMMONWEALTH EDISON COMPANY-NRC DOCKET NO. 050-456, LICENSE NO. NPF-72 NRC DOCKET NO. 050-457,- LICENSE NO. _ WPF-77 9
a h
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.I 1.-
Monthly Report for Braidwood Unit 1
<A.
S.umAIy_nL_QPMAting_ExpeI.12nCB Braidwood Unit 1 operated routinely from June 1 through June 18, 1991 when the unit reduced power to inspect a condenser water box for tube leaks.
After completion of repairs on June 20, 1991 the unit returned to normal operation until June 22, 1991 when power was again reduced to inspect and repair tubes in another condenser water box.
The unit returned to full power on June 24, 1991 and operated routinely for the remainder of the month.
(227/ZD8'1)3
i B.
OPIRATING. DATA EEEORT
- DOCKET NO.
'50-456 I
UNIT:..Braidwood 1 DATEt 07/10/91 COMPILED BY:
C..E. Pershey TELEPHONE:
(815)458-2001 ext. 2173 OPERATING STATUS 1.
Reporting Period: June, 1991.
Gross Hours:
720 2.
Currently Authorized Power-Level (MWt):
3411 Design'Elt
-ical 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 T111E_MQtiTli IILTQ_DATE _CUMULATIYL
-5.
Report period Hours:
720.0 4343 233.9.2 6.
Hours Reactor Critical:
720,9 1011d 18000 (_
7.
RK Reserve Shutdown Hours:
OJ
..020
- 0.. o 8.
Hours Generator on Lines 72020 10&LS _ _17671.8 9.
Unit Reserve Shutdown Hours:
0.0 0.0 0.0 10.
Gross Thermal Energy.(MWH):
2237555 2773396 12_(16_{66 i
11.
Gross Elec. Energy (MWH):
766498
_911140 11011S11
-12.
Net Elec. Energy (MWH):
736434
_jiQlli
.111]1140 13.
Reactor Service Factor 100,9 24,1 701L
.14.
Reactor Availability Factor:
100J 21,2 70.3 15.
Unit Service factor:
100J 24.0 69.1 16.
Unit-Availability Factor:
100.0 24.Q 61 1 17.-
~~ Unit Capacity Factor (MDC net):
91.1 17.5 59.9 1
18.
Un't Capacity Factor (DER net):
91.3 17.5 59.9 19.
Unit Forced Outage Rate:
__Q1Q 57.6 11 1 20.
U u t Forced Outage Hours:
0Q 1416.0 2R951Q_
1 21.
Shutdowns Scheduled Over Next 6 Months: -None 22.
If Shutdown at End of Report Period, Estimated Date of Startup:
b (227/ZD85G)4
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e C.
AURAGI_EAILX_lMIT NET POWER LEYE W DOCKET NO.1-50-456 UNIT:
Draidwood 1 DATE 07/10/91-COMPILED BY C. E. Pershey TELEPHCHE :
(815)458-2001 ext.' 2173 MONTH:
Juno, 1991.
1, 1033 17.
191L 2.
128.5 18.
076 3.
1084 19.
750 __
4.
1091 20.
776 5.
10.95 21.
_,_1035 6.
1034 22.
73 0-7.-
1080 23, 776 8.
1018 24.
1Q21 9.
1016 25, 1067 10.
1051 26, 1050
- 11..
1090 27, 1090 12.-
1103 28.
1933 13.
1111 29, 1Q5E 14.
1112 3 0..
1043 15.
1057 16.
ID6B INSTRUCTIONS On this form list the average delly 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 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.
(227/ZD85G)5
1 D.
LTII_ SHUTDOWNS / REDUCTIONS DOCKET NO.: 50-456-UNIT: Braidwood 1}
DATE: 07/10/91-COMPILED BY: C. E. Pershey TELEPHONE:'(815)458-2801 ext. 2173 REPORT PERIOD:
June,.1991 No DATE TIEE HOURS REASON HEIHQD 'LER NUMBER SXHIEM* COMPONENT CAUSE & CORRECTIVE ACTION TO PREVEIC EECURRENIX' 2
910618 F 50 B
5 N/A' KE-COND Power reduction to inspect condenser water box for tube leaks. Leaks were identified and tubes plugged.
3 910622 F 52 B
5 N/A KE COND Power reduction to inspect condenser water box for tube leaks. Leaks were identified and tubes plugged.
- e***************
SUMMARY
- +****
TYPE REASON METHOD SYSTEM A 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 4L 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 (227/ZD85G)6
E 3-E.
UNICUE REPORTING REOUIREMENTS - Unit 1-1.
Safety / Relief valve operations.
VALVES NO & TYPE PLANT DESCRIPTION.
DATE ACTUATED ACTUATION CONDITION
_QF EVENT NONE
.I T
2.
Licensee generated changes to ODCM.
[
See Attachment 4
2 h
=
i
(
(227/ZD85G)7
~. _ -.. -..
'4 g -
4 F.
LICERSEE_ EVENT REPORT!i;- URlT_1 The following is a tabular _ summary of-all' Licensee Event Reports submitted during the reporting period, June 1 through June 30, 1991.
-This information is provided_ pursuant to the reportable occurrence
' reporting requirements as set forth in 10 CFR 50.73.
Licensee Event Report Rep.pJt Numben Qats 71 tic _Qi_QcnnLtcate None
(.
(227/ZD85G)8
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I.-
Monthly Report for Braldwood. Unit 2-A.-
- Sxmmary_oLOperating.Expct1once Braidwoc.d Unit 2 operated routinely from June 1 through June 22, 1991_'when the unit reduced power to remove the generator from service for repalrc to the turbine I:lectrohydraulle Control System.
The reactor remained critical during this time.
Following repairs, the generator was returned to service and the unit performed routinely the remainder of the month.
I (227/ZD85G)9
B.
OPIRATING._ DATA _REEORT DOCKET NO.:
50-457 UNIT:
Braidwood 2 DATE:
07/10/91 COMPILED BY
-C.
E. Pershey TELEPHONE:
(815)458-2801 ext.-2173 OPERATING STATUS
'1.
Reporting Period:
June, 1991 Gross Hours:
720 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 shich restricted (If Any): Nene 4.
Reasons for restriction (If Any): None IlllE_MONIll IILTQ_DATE CUMULATLVI 5.
Report period Hours:
7201Q 43Al2D 23611__
6.
Hours Reactor Critical:
720,R
_4133,4 _ 2011121 7.
RX Reserve Shutdown Hours:
0,R 0,0 O0 t
8.
Ilours Generator on Lines 71E,1 411LoS 2004221 9.
Unit Reserve Shutdown Hours:
00 0.2D 0,9 4
10.
Gross Thermal Energy (MWH):
_2J15130._ 132fDha6_ 5351D114 _
11.
Gross Elec. Energy (MWH):
__112211__ _4114967. 20Dh27A0__
12.
Net Elec. Energy (MWH):
__111372
_4325222__. 1R291102_
13.
Reactor Service Feetor:
10Q2D_
9115 E5 3
-14.
Reactor Availability Factor:
1DD1D_
9115 85,2 15.
' Unit Service Factor:
99.l_
95.1 84 1 t
16.
Unit Availability Factors.
1912_
95.1 aitl 17.
Unit Capacity Factor (MDC net):
Bats _
_B323 7 24A 18 Unit Capacity Factor (DER net):
032 1.
E319 72 4 19.
Unit Forced Outage Rate:
O ol_
4,3 42D 20.
Unit-Forced Outage Hours:
419._
211,5 Bli,1 21.
Shutdowns Scheduled Over Next 6 Months:
September 1991 - Refuel Outage 22.
If Shutdown at End of Report Period, Estimated Date of Startups.
(227/ZD85G)10
~ ~.
C.
AYIBAGIJAILLUEIT NFT P.QWEILLLYEh_LQQ DOCKET NO.:
50-457 UNIT:
Braidwood 2 DATE:
07/10/91 COMPILED BY:
C.
E. Pershey TELEPHONE:
(815)458-2801 ext. 2173 MONTH: June, 1991 1.
1Q92_
17, 995 2.
9.B Q 18.
1R43 3.
LQ20 19.
1051 4,
1Q19 20, 1023 5.
1030 21.
10jlft 6.
1Q12.
22.
31D_
7.
1Q92 23.
iQ3 8.
L0]9 24.
701_
9.
_1091 25.
1023 10.
_1Q93 26.
1Q9.Q 11.
1Q12 27.
1.QBQ 12.
1036 28.
lQ28 13.
1002 29.
lD95 14.
10El 30.
J Q91 15.
1Q42 16.
950 I'ISTRUCTIONS 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.
(227/ZD85G)1
4 D.
UNIT SHUTDOWNSLEEDUCTIONS DOCKET NO.: 50-457 UNIT: Braidwood 2 DATE: 07/10/91 COMPILED BY: C. E. Pershey TELEPHONE: (815)458-2801 e x '.. 2173 REPORT PERIOD:
June, 1991 4
_Ilg._
DATI TYPE HOUES REASON METHOD LER NUMBER SISTEM COMPONENT CAUSE & CORRECTIVE ACTION TO PREVENT' RECURRENCE 5
910622 F 4.9 A
1 N/A JJ SEAL A power reduction along with the' turbine being taken off line occurred to perform maintenance on a degrading *O*
ring on the Electrohydraulic Control System. The
'O' ring was replaced.
i I
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b o*oo*************
o
SUMMARY
i oooo*************
I TYPE REASON METHOD SYSTEM & COMPONENT
=i F-Forced A-Equipment Failute Maint or Test 1 - Manual Exhibit F & H S-Scheduled B-Maint or Test 2 - Manual Scram Instructions for Preparation of r
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-ACninistration 9 - Other G-Oper Error H-Other.
(227/ZD85G)12
E.
UNIOUE REPORTING REOUIREMENTS'- UNIT:2' 1.
' Safety / Relief valve operations.
' VALVES NO & TYPE.
PLANT DESCRIPTION k
DATE ACTUATED' ACTUATION
-CONDITION-OF EVENT None
. j.
l 2.
Licensee generated changes'to ODCM.
1 See Attached.
1 4
I
+
S (227/ZD85G)13 i
a.,
F..
LICENSIElVIRLREPORIS. - UruL2 The following is a tabular-summary of all Licensee Event Reports submitted during the reporting period, June 1 through June 30, 1991.
This-information is provided pursuant to the reportable occurrence reporting requirements as set forth in 10 CFR 50.73.
Licensee Event Report Rep _ ort Nunther_
Daic T111g_pLDcsungnce 91-002 06-07-91 Reactor shutdown caused by excessive containment purge valve leakage discovered during local leak rate' testing.
i (227/ZD85G)14
ATTACHMENT Revision to the Offsite Dose Calculation Manual (ODCM)
Revisions to the Offsite Dose Calculation Manual (ODCM) are reportable to the NRC in accordance with Braidwood Station's Technical Specificaticns.
Braidwood Station's Radio; ogical Environmental Monitoring Program (REMP) has been updated to identify a new surface water sampling location, sample point BD-25, Enkakee River upstream of discharge 9.6 mi E of t%
station. This sample point was added to eliminate the posotbility of the upstream sample being influenced by Braidwood Station discharge water.
The change does not reduce the accuracy and reliability of the aetroint determination or model methodology, l
l 1
l
DwAP 1205-371 Revisies 3
~
Broldwood On-sito R3vloer cnd Inv36tightlos Paport OSR Numbert 7/~O5 Y Date:
9^'
1 Subject Reviews _.fr co den d %hs can 4, a =
l's'.. oO w Mfkht Requested by l
Discip1 Anes pequirede F A Huclear Power Plant Technology E8 Reector Operations OC Reactor Engineering CD Chemistry FE Radiation Protection UT Instrumentation and Control OG Hechanical and Electrical Systems
Participants:
T51 Kfs OSR Hom* rship Approved [
d* Nd -e[
Y38f(
TechnicalStaffSuperv[sor
/
Date 10CTR50.59 Screening and/or Safety 9 u untion is Required? - - - Y/N.\\/
I If yes, attach completed documer.cacion in accordance with BwAP 1205-6.
ll Concurrence Required by Offsite Review? (per Section C.6) - - - Y/H
\\/
/
Findings and Recommendations:
Correc 4ed it zuphaa \\ ergt Added M v a R. A.c._h m
@D 2's, h pmtM) c : n u A 4c 4 L au rst !_ k bu,ppara.c sv4 o
._.an A-ee
$ 6.. f e l
j tei m m t.1 0 h s o m n,(
L{ [ N iv annennenenseen****nneeneanaennennennaeannemanaemenneneneanaanneaemeneennemanas.
OQte Rev$ew Cononitteet Signature indicates concurrence with rindings and Q
Recommendations and 10CFR50.59 Safety Evaluation.
M 11gnaturaa D11ci31. int.ls.).
DAlt MTJtAA4 'A AAda Y u rf n; hildhdW
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Y-30-91 te H
7i C3 ms
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APPROVtv Approved by:
STAIIdH MANAGER DATE MAR 1.i 091 (rinal) 130(032191) 1 A7.$fLUd$
ZWB'4AP
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8RAIDM000 REV1210N 0.D MAY 1991*
Table 11-1 (Cont'd)
Sampling or Type and Frequency' Exposure Pathway Collection Freauency of Analysis and/or Samole Samolino or Monitorino Locationia 2.
Direct Radiation Controls (Cont'd)
Two sets of TLDs at each of the air-borne pathway control locations
.specified in Part 1 of this table.
Minimum of 2 TLDs per set.
3.
Haterbornee a.
Public Mattr 80-22. M11mington 5.0 mi NME (8.0 km B)-
Heekly Gross beta and gamma isotopic analyses monthly composite.
Tritium analysts on quarterly composite.
b.
Surface B0-07. Kankakee River upstream of Meekly Gamma isotopic discharge. 5.4 mi E (8.4 km E) analysis on monthly composite from each 80-10. Kankakee River downstream of location. Ti'11um discharge. 5.0 mi ENE (8.0 km D) analysis on qe rterly composite from each 80-25. Kankakee River upstream of discharge.
location.
9.6 mi E (15.4 km E) f Gross beta and gamma c.
Ground /Mell 80-13. Braldwood City Hall Well.
81 weekly 1.7 al NME (2.7 km B) isotopic analysts on monthly ccaposite.
Tritium analysis on quarterly composite.
1-131 analysis biweekly when the dose calculated for consumption is greater than I areelyr.
11-6
_ - _.