ML20077M254

Monthly Operating Repts for Jul 1991 for Braidwood Nuclear Power Station Units 1 & 2

ML20077M254
Person / Time
Site:	Braidwood
Issue date:	07/31/1991
From:	Kofron K, Pershey C COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BW-91-0660, BW-91-660, NUDOCS 9108130247
Download: ML20077M254 (14)

Text

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C:mm:nwealth Edis:n Braidwood Nuclear Power Station O Telephone 815/458-2801-a Route 01. Box 84 Braceville, lilinois 60407 August 9, 1991 BW/91-0660 Director, Office of Resource Management United States Nuclear Regulatory Commission Washington, D.C. 20555 ATTN: Document Control Desk Ger. tlemen t Enclosed for your information is the Monthly Performance Report covering Braidwood Nuclear Power Station for the period July 1 through July 31, 1991.

Very truly yours,

,CK_ % q, K. L. Ko f ron ['2 -

Station Manager Braidwood Nuclear Station KLK/EWC/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 INPO 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 k

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9108130247 910731 \

PDR (4 DOCK 05000456 R FDR

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BRAIDWOOD NUCLEAR POWER STATION l

UNIT 1 AND UNIT 2 MONTHLY PERFORMANCE REPORT COMMONWEALTH FDISON COMPANY NRC DOCKET NO. 050-456, LICENSE NO. NPF-72 NRC DOCKET NO. 050-457, LICENSE NO. NPF-77 e

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I. Monthly Report for Braidwood Unit 1 i

A. Slumnu.y_pl_ Ope r a t i ng._IKpfI1RDER Braidwood Unit 1 entered the month of July at reduced power to accommodate condenser weter box inspections. On July 5th the unit returned to full power and operated routinely until July 13th when the unit reduced load for repairs associated with a governor valve. Following repairs the unit returned to full power until July 17th when a failure in the rod control drive controls forced the unit to begin a controlled shutdown.

Before the unit could shutdown the rod control drive system was repaired and the unit returned to full power. The unit remained critical curing this event. On July 23rd the unit reduced power to make repairs on the pneumatic solenoid valves associated with the feedwater isolation valves. While still under reduced power on July 27th maintenance was performed on a mainsteam isolation valve. The repairs were completed and the unit completed the mont.h of July performing routinely.

(227/ZD85G)3

l B. OPERATING _ DATA _REPDRT DOCKET NO. 50-456 UNIT: Braidwood 1 DATE: 08/10/91 COMPILED BY: C. E. Parshey TELEPilONE: (815)458-2801 ext. 2173 OPERATING STATUS

1. Reporting Period: July, 1991 Gross Hours: 744

2. Currently Authorized Power Level (MWt): 3411 Design Electrical Rating (MWe-gross): 1175 Deslyn Electrical Rating (MWe-net): 1120 Max Dependable Capacity (MWe-gross): 1175 adax Dependable Capacity (MWe-net): 1120

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

4. Reasonc for restriction (If Any): None Ill1S_HONTil IR_.T0JATE ._EUMULATIVE_

5. Report period Hours: 741D 5082__ 16316

6. Hours Reactor Critical 111.Q 1817.1 _ _18110 4

7. RX Reserve Shutdown Hours: OJ 0.0 0.0

8. Hours Generator on Line: Illd 1771J 18101,7

9. Unit Reserve Shutdown Hours: 0.0 0,3 QJ_

10. Gross Thermal Energy (MWH): lag 5D L 1610A17 5A111sB7

11. Gross Elec. Energy (MWH): _131QRD__. 15213AD _ lEli2SHL

12. Net Elec. Energy (MWH): _6D6486 1457220 12]lD31$__

13. Reactor Service Factor: 1QL3 3L1 11.1

14. Reactor Availability Factor: 10DJ 3hl 71,L

15. Unit Service Factor 10d MJ 6hl_

16. Unit Availability Factor 9&d 33 .0 6 9 d_

17. Unit Capacity Factor (MDC not): 72.8 2L1 _ 6Qal_

18. Unit Capacity Factor (DER net): 72J , IL1 QD.1

19. Unit Forced Outege Rate: _ LL 4h1 13 1

20. Unit Forced Outage Hours: _12.a _ li21d 2 9D1d_

21. Shutdowns Scheduled Over Nm t 6 Months: None

22. If Shutdown et End of Report Period, Estimated Date of Startup:

(227/ZD85G)4

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C. AYIEAQE DAILY UNIT _ NET POWER __ LEVEL LOG DOCKET NO.:- 50-456 UNIT: Braidwood 1 DATE: 08/10/91 COMPILED BY: C. E. Pernhey TELEPHONER. (815)458-2801 e x t' . 2173 j HONTH: . July, 1991

1. 960 17. 65.4 )

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-- 2 . 816 18. .791 l I

3. 765 19. 792 j 4, 674 20. Ell _

5. 933 21. 1082 ,

6. 1076 22. 1115 >

7, 951 23. 728 .

8. 1065 24. 258

9. 1114 25. 26D

'10, 1009 26. 174

11. 1047 27, 179 12.- 1109 28.- 373

13. 803 29. 871

14. 890 30. 919

15. _

986 31. 952 16 1033 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.

-(227/ZD85G)5

NDCKET NO.: 50-456 D. UNIT SHUTDCWNS/REDUCTICNS UNIT: Braidwood 1 DATE: 08/10/91 -

COMPILED BY: C. E. Pershey TELEPr10fiE: (815)458-2801

• ext. 2173 REPORT PERIOD: July, 1991 No DATI 2"ll'I HQUES RIASOH METHQD LER NUMBER SYSTEM COMPONElG CAUSE & CORRECTIVE ACTIO1L 5 N/A TG XT Power was reduced to replace a failed linear 4 910713 F 0.0 A variable differential transformer on the number 2 governor valve.

0.0 A 5 91-007 AA OSL A controlled shutdown was initiated due to 5 910717 F failed rod control drive firing card on Bank 1A of the control rod drive mechanism. The card was replaced before the unit was required to complete shutdown.

5 N/A SJ SOL Power was reduced to repair / replace failed 6 910723 F 0.0 A pneumatic solenoids on IFWOO9A, B and D.

A 5 N/A SJ SOL Continuation of power reduction to repair 7 910724 F 0.0 solenoids on IFWOO9A, B and D.

N/A SB TC Generator taken off line to repair leak on the 8 910726 F 12.1 A 1 IB MSIV *F* flow control valve caused by 'O' ring not being properly compressed. Machined the proper dimension in the *F' valve cartridge which enabled the 'O' ring to compress properly.

SUMMARY

METHCD SISTER 4 & COMPftLENT ._

TYPE REASON 1 - Manual Exhibit F & H F-Forced A-Equipment Failure Instructions for Preparation of 2 - Manual Scram S-Scheduled B-Maint or Test 3 - Auto Scram Data Entry Sheet C-Refueling Licensee Event Report 4 - Continued D-Regulatory Restriction (LER) File (NUREC-0161)

E-Operator Training & License Examination 5 - Reduced Load 9 - Other F-Administration G-Oper Error H-Other  !

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j E. UNIOUE REPORTING RECUIREMENTS-- Unit'1 ' '

1. ' Safety / Relief valve operations..

1 ,

VALVES NO & TYPE PLANT DESCRIPTION

, DATE -ACTUATED ACTUATIC?{ CONDITION- OF EVENT l NONE i i

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2. Licensee generated changes to ODCM. .

None  !

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-1 (227/ZD85G)7  ;

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F. LICItiSEE_fiD1TlEf0RTS 1I101_1 The following is a tabular summary of all Licensee Event Reports submitted during the reporting period, July 1 through July 31, 1991.

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

Licensee Event Report EcpoLLilwobeL Dats IllittoLorcurrence None (227/ZD85G)B

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1. Monthly Report for Braidwood Unit 2 A. Siman t y_.3r LDpe r atint.Expe rie nc e Braidwood Unit 2 operated routinely from July 1 through July 14, 1991 when the unit reduced power to inspect a condenser water box for tube leaks. After completion of repairs the unit returned to normal operation until July 20, 1991 ws.cn power was again reduced to inspect and repair tubes in a condenser water box. On July 24, 1991 the unit began coasting down inr the second refueling outage scheduled to begin in September, 1991.

(227/ZDB5G)9

-~ -. . -- . .- - - - _ ~ . . ~. _ - - , _.

-- B. , OPERATING _. DATA _REEORT DOCKET NO.: 50 457 UNIT: Braidwood 2 DATE: 08/10/91 COMPILED BY: C. E. Pershey.

TELEPilONE (815)458-2801 ext. 2173 OPERATING' STATUS

1. Reporting Period: July, 1991- Gross Hours: 744 2.= 'Cuttently Authorized Power Level-(MWt): 3411 Design Electrical Rating (MWe-gross)4 1175

. Design Electrical Rating (MWe-net): 1120 Max Dependable Capacity (MWe-gross): 1175 l Max Dependable' Capacity (MWe-net) -- 1120

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

1

4. Reasons for restriction (If Any): None IlilS_liOHTl! YlLT0_DATE CUMULATlYE

5. . Report period flours: 14410 5 QED _ 21418.__

6. ilours Reactor Critical: . 7 4b.0 4 elf __ 2M91Qal

7. RX Reserve Shutdown llours: 0.R OJ LD

8. Cours Generator on Lines 74bD 4315 5 2015L1 1

9. Unit Rc. serve Shutdown flours: D.D .L D LD

10. Gross Thermal-Energy (MWII): _214355A_ _ 1550.4214 _ 509L4272_ _ .-

13 . - Gross Elec. Energy (MWH): _ 7I1816 _. 5120191._ '2DB55551 _

12. Net. Elec. Energy (;1W11): _.211553 _ _.5129175 . 199.51255 -

13. deactor Service Factor: laQd_ %1 8521

14. Reactor Availability Factor: 1QO20 _hl- ALl

15. Unit Service Factor: 100.Q_ 95.8 El

16. Unit Availability Fhetor _ _100.0 9La 85.1

17. . Unit Capacity Factor (MDC net): _J 0. 6 .LR 73.A

18. Unit Capacity Factor (DER net): E 1. ED _mD

19. Unit Forced Outage Rato OA _. .b2 3d

20. Unit Forced Outage Ilours: 01 211.5 . 82hl

21. Shutdowns Scheduled Over Next 5 Months: September 1991 _ Refuel Outage

22. If Shutdown at End of Report Perlod, Estimated Date of Startup

-(227/ZD85G)10

C. AVIRAGE_DAILLUNILNELPONER LEVIL_ LOG DOCKET NO. 50-457 UNIT: Braldwood 2 DATCt 08/10/91 COMPILED BY: C. E. Pers. hey TELEPHONE: (815)458-2801 ext. 2173 MONT11: July, 1991

1. 1003 17. ___ 1989

2. lab 1 18. 1QB3 _ _ _ _ _

3. __10BA_ __ 19. 1013

4. 1015 70. Dal 5, 1Rab 21. __ Bih_

6. 1083 22. E18

7. 1R83 23. 913

8. lqa1 24. _1072

9. 10.B3. _

25. 1Q47 _

10, 1087 26. 1Q34

11. 10a6 27. 1024

12. lQED 28. 1003 13, 1057 29. 985

14. BQ1 30. 912

15. 796 31. _9_11 16, 935 INSTRUCTIONS On this form list the aver'qo 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 dally unit power output sheet should be footnoted to explain the apparent anomaly.

(227/ZD850)11

DOCKET NO.: 50-457 D. UNIT SHDTDCWNS/REDUCTICNS UNIT: Braidwood 2 DATE: 08/10/91 COMPILED BY: C. E. Pershey TELEPHONE: (815)458-2801 ext. 2173 i

REPORT PERIOD: July, 1991 l l

__HQ_. DATE IIEE liCURS REASCH MEIliCD LER__HUMBER SYSTEM CCMPONENT CAUEE & CORRECTIVE ACTION TO 5 N/A KE COND Power was reduced to inspect the condenser 6 910?I4 F 0.0 B waterbox for tube leaks. Leaks were identified and the tubes were plugged.

5 N/A KE COND Power was reduced to inspect the condenser 7 910720 F 0.0 B waterbox for tube leaks. Leaks were identified and the tubes were plugged.

SUMMARY

METHOD SYSTEM & CCNPCl.ENT TYPE REASON 1 - Manual Exhibit F & H F-Forced A-Equipment Failure Instructions for Preparation of 2 - Manual Scram S-Scheduled B-Maint or Test 3 - Auto Scram Data Entry Sheet C-Refueling Licensee Event Report D-Regulatory Restriction 4 - Continued 5 - Reduced Load (LER) File (NUREG-0161)

E-Operator Training & License Examination F-Administration 9 - Other G-Oper Error H-Other (227/ZD85G)12 3

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mm E. UNIOUE REPORTING REOUIREMENTS - UNIT 2-

1. Safety / Relief valve operations.

NO & TYPE PLANT DESCRIPTICN VALVES CORDITION CF EVENT DA2'E ACTsIATED ACTUATION None I

2. Licensee generated changes to ODCM.

None 1

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=-4. '; .

r. LICENSEE _IVENLEEPfRTS - UNIL2 The following is a tabular summary of all Licensee Event Reports submitted during the reporting period, July 1 through July 30, 1991.

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

Licensee Event Report Repart Num12RL DAtt 11110-Qf Occutte21gn None l

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(227/ZD85G)l4