ML20101P909

Monthly Operating Repts for June 1992 for Braidwood Nuclear Power Station,Units 1 & 2

ML20101P909
Person / Time
Site:	Braidwood
Issue date:	06/30/1992
From:	Kofron K, Pershey C COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BW-92-0360, BW-92-360, NUDOCS 9207140082
Download: ML20101P909 (14)

Text

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" . C:mm:nwotith Edis:n O Braidwood Nuclear Powcr Etation l

" ,< Route #1. Bon 84

. Bracevillo. Illiriols 60407 Telephono 815/455 2801

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July 10, 1992 ,

, SH/92-0360 l

l Director, Office of Resource Hanagement United States Nuclear Regulatory Commission Hashington, D.C. 20555 l

ATTN: Document Control Desk i

Gentlemen:

Enclosed for your information is the Monthly Performance Report covering Braldwood Nuclear Power Station for the period June I through June 30, 1992.

/k K.L.Kofronf~

Station Manager Braliiwood Nuclear Station i KLK/JL/dla l (590/Z085G) .

Attachments

! cc: A. B. Davis, NRC, Region III l NRC Resident I1spector Braldwood l Ill. Dept. of Nuclear Safety l

M. J. Wallace E. D. Eenigenburg T. J. Kovach

l. Nuclear Fuel Services, PHR.' Plant Support L

INPO Records Center l  : Performance Monitoring Group, Tech Staff Braidwood Station-Nuclear Grosp, Tech Staff Braidwood Station

.R. Pulsifer -'USHRC T. H. Simpkin D. R.'Eggett - Nuclear Engineering Department I-L [

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}i 9207140082 920630 l PDR .ADOCK 0500045u R

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BRAIDWOOD NUCLEAR POWER STATION i

t UNIT 1 AND tlHIT 2 '

! MONTHLY PERFORMANCE REPORT 1

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COMHONWEALTH EDISON COMPANY l

} NRC DOCKET NO. 050-456, LICENSE NO. NPF-72 i

NRC DOCKET NO. 050-457, LICENSE NO. NPF-77 i

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1 I. Monthly Report for Braldwood Unit 1 '

i A. S unmary_of.Dp.gr Lting_.faeLifn c e

. Braidwood Unit 1 entered the month of June, 1992 at I approximately 99.5% reattor power. The unit operated ,

i routinely untti June 7 when power was reduced to allow a containment entry, Power was reduced on June 19 to make a i second containment entry. On June 20, reduced power was

maintained to improve steam generator feedwater chemistry.

< Power was increased once chemistry was within specifications, and the unit operated routinely through the j end of the month.

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e 4 B. OEERillHG DATA REPORT DOCKET NO.: 50-456 UNIT: Braldwoot< 1 DATE: 07/10/92 COMPILED BY: C. E. Pershey TELEPHONE: (815)458-2801 ext. 2173 OPERATING STATUS

1. Reporting Period: June, 1992 Gross Hours: 720

2. Currently Authorized Power Level (HWt): 3411 Design Electrical Rating (HWe-gross): 1175 Design Electrical Rating (HWe-net): 1120 Mak Dependable Capacity (HWe-gross): 1175 Hex Dependable Capacity (HWe-net): 1120

3. Power level to which restricted (If Any): None

4. Reasons for restriction (If Any): None Iji13_HQNIll YR TO 0 ATE _CUMULMiyL -

5. Peport period Hours: _. 72DJ 436LQ 34376.0

6. Hours Reactor Critical: 720.0 410LI 26581.9

7. RX Reserve Shutdown Hours: _0 ._0 _DJ '0.0

8. Hours Generator on Line: __ ___lifaQ __42.aL5. 28114.5

9. Unit Reserve Shutdown Hours: O0t __0J OJ ,

10. Gross Thermal Energy (HHH): _.lM6107 11635.65.l_. 18 H illI_

/ 11. Gross Elec. Energy (HWH): _f42075 .4667500_._ 26989692_.

12. Net Elec. Energy (HWH): _6_52.343 _14814B5_ ,_%5169_40D_

13. Reactor Service Factor:' 98,5

.1010 77.3

14. P.eactor Availability Factor: __ 100.0' 98.5 77.3

15. Unit Service factor: 100.0 9L1 76.0

16. Unit Availability Factor: 100.& 98.1 76.D 17 Unit Capacity Factor (MDC net): 8DJ._ 91.7 67 0 18 Unit Capacity Factor (DER net): 80J 91_.1 67_._ Q

19. Unit Forced Outage Rate:- 0.0 _ id 11 0

20. Unit Forced Outage Hours: 0.0 _dLS 3236 3 21; Shutdowns Scheduled Over Next 6 Months: Rerueling Outage - September,- 1992

22. -If Shutdown at End of Report Period, Estimated Date of Startup-r (574ZD85G)4

C. AVERAGLO&lLLuti1LtlELEOREILLEVEL LOG 00CKET NO.: 50-456  %

UNil: Braidwood 1 DATE: 07/10/92 COMPILED BY: C. E. Pershey TELEPHONE: (815)458-2801 ext.-2173 HONTH: May, 1992

1. 1.036 17. ._.1D.9 2

2. 1093 18. 1050

3. _

1033 19. 1023

4. 1097 20. _._, 230 ._

5, 1.059 21, 236 .

6. 1085 __ 22. . _ __ 237

7. 423 23. _ 23L

8. BE9 24. .l0.4 9, 1091 __ 25. 1104

10. 1091 26. J.101

11. 1092 27. 81.8 ,_

12. _1082 28, 801 _

13. 1034 _ . _

29, 993

14. 1079 30. 1095-

15. 1951 31. .

16. 1090 INSTRUCTIONS On this form list the average daily unit 3ower level in HWe-Net '.ir each day in the reporting month. Compute to tie 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 untt power output sheet should-be footnoted -

to explain the apparent anomaly.

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D. UNIT SHUTDOWNS / REDUCTIONS DOCKET NO. 50-456 UNIT: Brald'scod 1

'}i 1 DATE: 07/10/92 CCHPILED BY: C. E Pershey TELEPHONE: (315)c58-2801 ext. 2173  !

REPORT PERIOD: June, 1992 j No DATE TYPE HOURS REASON METHOD .LER NUMBER 51$TJ.M COMPONENT CAUEE & CORRECTIVE ACTION TO PREVENT P.ECURRENCE  !

3 920607 S 22.2 B 5 FH ISV Reduced load and made a containment entry to f stop leakage on the steam generator level wide i range lower isolation valve. Radiation levels at this power level prohibited the planned corrective maintenance. The valve was

0 backseated, but the leakage did not stop l completely.  !

t 4 920619 S 23.8 6 5 FH ISV Reduced load and made a containment entry to i stop leakage on the steam generator level wide  !

range lower. isolation. Leakage was stopped.  !

Power was increased to 307. and maintained for I a chemi:,try hold.  ;

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5 920620 5 78.7 F 4 RC SG Maintained reduced load to improve steam  !

l- generator feedwater chemistry. Once chemistry I was within specification, load was increased. f

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SUMMARY

TYPF REASON METHOD SYSTEM & COMPONENT a

- F-Forced A-Equipment Failure Maird or Test 1 - Method Exhibit F & H  !

i S-Scheduled B-Maint or Test 2 - Manual Scram Instructions for Preparation of l 4

C-Tsefueling 3 - Auto Scram Data Entry Sheet

D-Regulatory Restriction 4 - Continued Licensee Event Report i E-Operator Training & License Examination 5 - Reduced Load (LER) File (NUREG-0161)

• F-Administration 9 - Other G-Oper Error i

H-Other i (574ZD85G111 i  !

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- E.- 'UNIGUE REDORTING RE00fREMENTS - i

'1. Safety / Relief valve operations.

. VALyFO NG & TYPE PLANT DESCRIPTION

.DATE ACTUATED ACTUATION CONDITION _OF EVENT l None 3;

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'2. Licensee generated changes to 00CH.

None i

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f. LIILESELEVENT REPORll- UNIT I 1

I The following is 6 tabular summary of all Licensee Event Repcrts l submitted during the reporting period, June I through June 30, 1992. ,

l This information is provided pursuant to the' reportable occurrence r i reporting requirements as set forth in 10 CFR 50,73.'  ;

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! Licensee Event Report Re.patLNumbeL Di.te H tle_of Octurrence i  !

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l. I. Monthly Report for Braidwood Unit 2 1

i A. SutearlpL0nen. ting _.Exnerient.e -

9 Braldwood Unit 2 entered the nonth of June,1992 in a forced outage which continued from Hay, 1992. The forced outage j ended on June 2. Full power operation was achieved on June 5 i

, after holding at 75% reactor power to repair'a main condenser ,

l tube leak. The unit operated routinely through the end of

! the month.

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I B. OPERATING _DAIA R P.0AI DOCKET NO.: 50-457 [

i UNIT: Praidwood 2 i DATE: 07/10/92 3 COMPIt.ED BY: C. E. Pershey i TELEPHONE: (815)458-2801 i ext. 2173 .

OPERATING STATUS l

j 1. Reporting Period: June, 1992 Gross Hours: 720 l '

i 2. Currently Authorized Power level (HHt): 3411 l Design Electrical Rating (HHe-gross): 1175 Design Electrical Rating (HHe-net): 1120 Har. Dependable Capacity (HHe-gross): 1175 l

HaF Dependable Capacity (HHe-n9t): 1120 ,

3. Power level to which restricted (If Any): None

4. Reasons for restriction (If Any): None 1

l IlilS30RUi YR.10_DAII SUBULAILVI-

5. Report period Hours: 720J 433LD __314E0-l l

6 Honrs Reactor Critical: 7E5 . .4010 2 267E0_.

7. RX Reserve Shutdown Hours: 0.0 00 0.0-

! 8. Hours Generator on Line: 684 3 . _ . 39E3 _EE53L3_ '

l 9. Unit Reserve Shutdown Hours: ._, 0.0 0.0 0.0

10. Gross Thermal Energy (MHH): _E144813 J27.53151 .18109412 l

11. Gross Elec. Energy (HHH): __lE4143 _. _43.11026_._ 26136466 i

< 12. Het Elec. Energy (HHH): __.11514L __4201E58 25512.553

13. Reactor Service factor: 98.1 9L3 82.6 l 14. Reactor Availabil1ty Factor: .__ 98.J 92.3 8LL

15. Unit Service factor: EQ .R5 ._Bh8_

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16. Unit Availability Factor: ED _ 15 81.L l 17. Unit Capacity Factor (MDC net): 86.3 85J 70.l .

18. Unit Capacity Factor (DER net): 85.3 El 70. L

19. Unit Forced Outage Rate: ._5J 8.5 4J . .;

L 20. Unit-Forced Outage Hours: 3L.1 371.7 1319.5

21. Shutdowns Scheduled Over  ;

j Next 6 Honths: None l

22. If Shutdown at End of Heport Period, L Estimated Date of Startup: _

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! C. AYBA.GE_DAllLIMILhELf0liEILLERLLOG DOCKET No.: 50-457 UNIT: Braidwood 2 '

i DATE: 07/10/92 COMPILED BY: C. E. Pershey 1 TELEPHONE: (815)458-2801 i ext. 2173 i H0 NTH: June, 1992  ;

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- 15 17. Il0L ._ ,

2. 122 18. 984

. 3. 82 5 19. _1985 1

i 4. 82.6 20. 938 ,

i l S. . 889 21. _816 _.

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7. _ _.10A5 23. _. _lDB1  ;

l 8. 1096 24. 101L.,

! 9. 992 25. ._1055

10. . . 1020. 26. 1018

11. 1111 27. _ 1057 U:. 1106 28. 985

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l 13. _1102 29. 1015 i

14. 1081 30. ~1104 .. _ __

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) INSTRUCTIONS On this forra list the e.verage daily unit power level in MWe-Net for each r day in the reporting month. Compute to the nearest whole-megawatt.

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

L Hote that when maximum dependable capacity is used for the net electrical

rating of the unit there may be occasions-when the daily average pcNer level exceeds the 100% line (or the restricted power level line)._ In such cases the average ually unit power output sheet should be footnoted to explain the apparent anomaly.

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i D. UNIT SHUTDOHHS/ REDUCTIONS DOCKET M9.: 50-457 UNIT: Braidwood 2 .

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- DATE: 07/10/92 [

COMPILED BY: C. E. Pershey  ;

1 TELEPHONE: (815)458-2801 l i REPORT PERIOD: June, 1992 ext. 2173  !

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_No_ DATE TYPE EQUES REASON M_EILLOD LER.. NUMBER SYSTEM COMPONENT CAUSE &_ CORRECTIVE ACTION TO PREVENT RECURRENCE  !

[ 10 920601 F 35.7 A 4- 92004 RD EI Completed repairs following the B motor

, generator set trip on 920531. The equipment

tested satisfactorily and has operated l routinely since unit restart.

I j 11 920602 S 76.3 B 4 KE TBG- A main condenser waterbox was removed from  !

! service while increasing power following the l 920523 shutdown. One condenser tube was i plugged and the waterbox was restored.

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SUMMARY

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TYPE REASON METHOD SYSTEM & COMPONENT  !

j' F-Forced A-Equipment Failure Maint or Test I - Method Exhibit F & H 2' 2 - Manual Scram S-Scheduled 3-Maint or. Test Instructions for Preparation of j C-Re#ueling 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)  ;

i F-Administration 9 - Other  :

[ G-Oper Error i H-Other i

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- l F. LICEtGILEGLREEORIS - UMLL2 The following is a tabular sumary of all Licensee Event Reports I submitted during the reporting period, June I through June 30, 1992.

This information is provided pursuant to the reportable occurrence reporting requirements as set forth in 10 CFR 50.73.

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Licensee Event Report j RecorLMumbeL Dde ittie of 0.cturn ate '

!92-003 06/25/92 2A Essential Service Water

!; Pump Automatic Start Due to Procedural Deficiency.

1 j 92-004 06/30/92 Reactor Trip Due to Loss

! of Both Motor Generator Sets, i

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