ML20207N220

Monthly Operating Repts for Sept 1988 for Braidwood Nuclear Station,Units 1 & 2

ML20207N220
Person / Time
Site:	Braidwood
Issue date:	09/30/1988
From:	Peterson M, Querio R COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
BW-88-1228, NUDOCS 8810190033
Download: ML20207N220 (14)

Text

, _ _ _ _ _ _ - _ _ _ _ - _ _ - . _ _ _ .__ ___

BRAIDH000 NUCLEAR POWER STATION UNIT 1 AND UNIT 2 MONTHLY PERFORMANCE REPORT COM40NNEALTH EDISON COMPANY NRC DOCKET NO. 050-456 LICENSE NO. NPF-72 NRC DOCKET NO. 050-457- LICENSE NO. NPF-77 8910190033 880930 PDR ADOCK 05000456 R PDC (4957zl2)

N A- t l

I. Monthly Report for Braidwood Unit 1 -

A. Summary of Ogerating Exoerience Unit One entered the month of September at 96% reactor '

power. On September 15, the unit was taken off line due to out of tolerance secondary water chemistry. On September 16, the reactor was shutdown and the Reactor .

Coolant System was cooled down to 545'F per chemistry requirements. Following cleanup of secondary water chemistry the unit was brought critical on September 20 and synchronized to the grid on September 21. By  !

September 22 the unit was at 97% reactor power where it !

remained through the end of the month, i

I i

l I

L k

I I

t (4957z/3)

~ ' '

B. OPERATING DATA REPORT LCKET NO.: 50-456 UNIT: Braidwood 1 DATE: 10/07/88 COMPILED BY: M. H. Peterson TELEPHONE: (815)458-2801 ext. 2480 OPERATING STATUS

1. Reporting Period: September, 1988 Gross Hours: 720.0

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 Dependable Capacity (MWe-net): 1120

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

4. Reasons for restriction (If Any): None THIS MONTH YR TO DATE* CUHULATIVE'

5. Report period Hours: 720.0 1520.3 1520.3

6. Hours Reactor Critical: 618.7 1402.3 1420.3

7. RX Reserve Shutdown Hours: 0.0 0.0 0.0

8. Hours Generator on Line: 577.4 1350.0 _1350.0

9. Unit Reserve Shutdown Hours: 0.0 0.0 0.0

10. Gross Thermal Energy (MHH): 1728640 4084263 4084263__

11. Gross Elec. Energy (MHH): 595068 1393432 1393432

12. Net Elec. Energy (MHH): 562563 1327011 1327011

13. Reactor Service Factor: 85.9 92.2 92.2_

14. Reactor Availability Factor: 85.9 92.2 92.2

15. Unit Service Factor: 80.2 88.8 88 8

16. Unit Availability Factor: 80.2 88.8 88.8

17. Unit Capacity Factor (MDC net): 69.8 77.9 77.9

16. Unit Capacity Factor (DER net): 69.8 77.9 _ 77.9

19. Unit Forced Outage Rate: 0.20 0.11 0.11

20. Unit Forced Outage Hours: 142.6 170.3 170.3

21. Shutd w ns Scheduled Over Next 6 Montns: Scheduled Surveilliance Outage beginning 02/20/89.

Secheduled Restart. 04/01/89.

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

23. Urits in Test Status (Prior to Commercial Operation):

FORECAST ACHIEVED Initial Criticality 05/23/87 Q5/29/81 Initial Electricity 07/11/87 07/12/87 Commercial Operation 07/15/8e 07/29/88

• Numbers re-zeroed due to commerical operation (4957z/4)

• C. AVERAGE DAILY UNIT NET PONER LEVEL LOG DOCKET NO.: 50-456 UNIT: Braidwood 1 DATE: 10/07/88 COMPILED BY: H. H. Peterson TELEPHONE: (815)458-2801 ext. 2480 HONTH: August, 1988

1. 1070 17. 0

2. 1033 18. 0

3. 1079 19. 0

4. 1014 20. 0

5. 976 21. 257

6. 964 22. 1034

7. 974 23. 1087

8. 920 24, 1077

9. 963 25. 1075 10, 834 26. 1046

11. .858 27. 1017 12, 1003 28. 1054 13, 1051 29. 1046 14, 998 30, 1077

15. 77 31. N/A

16. 0 l 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 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.

l (4957z/5)

~

0. UNIT SHUTD0HNS/ REDUCTIONS DOCKET NO.: S0-456 -

UNIT: Braidwood 1 - -

DATE: 10/07/88 -

COMPILED BY: M. W. Peterson~-

TELEPHONE: (815)458-2801-

• ext. 2480 REPORT PERIOD: September, 1988 No DAIE IIP _E HOURS REASON METH00 LER NUMBER SYSTEM COMPONENT CAUSE & CORRECTIVE ACTION TO PREVENT RECURRENCE 03 880915 F 142.6 G 1 N/A N/A N/A Out of Specification Secondary Chemistry.

• S.UMMARY*

TYPE REASON METHOD SYSTEM & COMPONENT 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 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/6)

w E. UNIOUE REPORTING REOUIREMENTS- UNIT I

1. Safety / Relief valve operations.

VALVES NO & TYPE PLANT DESCRIPTION Q&IE ACTUATED ACTUATION CONDITION OF EVENT ..

.None

2. Licensee generated changes to 00CM. - -

i None t

i

) '

(4957z/7)

)

I i

, - - - , - , , , ,,,~,,---,,,,--,.---,--.-.,e,-- - , - - - , , - - - , , - - , - - - --- -

,,-,.--.-,-,,,,--------r- -

,-r, - - - - ..~ , --- ---- ~ -

F. LICENSEE-EVENT REPORTS - UNIT I The following is a tabular summary of all Licensee Event Reports submitted during the reporting period September 1 through September 30, 1988. This.information is provided pursuant to the reportable occurrence reporting requirements as. set forth in 10 CFR 50.73.

Licensee Event Report Report Number Raig Title of Occurrence 88-003-01 08-31-88 Loss of pulses to Fuel Handling incident montior ORT-AR056 for unknown reasons.

88-011-00 09-02-88 Control Room Ventilation shift to emergency makeup mode due to spurious radiation monitor noise spike.

88-016-00 08-23-88 Reactor trip due to negative rate trip as a result of improper administrative controls.

l (4957z/8) i

II. Monthly Report for Braidwood Unit 2 A. Summary of Ooeratina Exoerience The Unit entered the month at 99% reactor power. On September 4, the Unit was manually tripped due to Low Steam Generator Water level caused by a failed open heater drain valve. The Unit was brought critical and synchronized to the grid on September 5. Reactor power was increased to 99% on September 8. The 50% Load Reject Startup Test was completed on September 10 and reactor power was increased again to 99.5% on September 12. The Turbine was taken off line on September 15 due to secondary water chemistry problems and reactor power was reduced below 5% to support maximum Steam Generator blowdown. On September 19, while at 3% reactor power, the Unit tripped on source range high flux when the source range was inadvertently re-energized as a result of a loose wire. The Unit was again brought critical on September 21, and on September 23 completed the 100% Load Reject Startup Test. The reactor was brought critical on September 28 and synchronized to the grid, but tripped on September 29 due to a High-High Steam Generator Hater level initiated while troubleshooting in rector protection cabinets. The reactor was again brought critical later that day. The unit was synchronized to the grid briefly on September 30, but the generator was again taken off line due to out of tolerance secondary water chemistry.

Reactor power remained at less than 5% through the end of the month supporting maximum Steam Generator blowdown.

(4957z/9)

= s B. OPERATING DATA REPORT DOCKET NO.: 50-457 UNIT: Braidwood 2 DATE: 10/07/88 COMPILED BY: H. H. Peterson TELEPHONE: (815)458-2801 ext. 2480 OPERATING STATUS

1. Reporting Period: September, 1988 Gross Hours: 720.0

2. Currently Authorized Power Level (HHt): 3411 Design Electrical Rating (HHe-gross): 1175 Design Electrical Rating (HHe-net): 1120 Max Dependable Capacity (HHe-gross): 1175 Max 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: 720.0 3075.4 3075.4

6. Hours Reactor Critical: 544.3 2656.0 2656.0

7. RX Reserve Shutdown Hours: 0.0 0.0 0.0

8. Hours Generator on Line: 385.2 2336.8 2336.8

9. Unit Reserve Shutdown Hours: 0.0 0.0 0.0

10. Gross Thermal Energy (HHH): 984844 4719814 4719814

11. Gross Elec. Energy (HHH): 324334 1482188 _1481 LEE __

12. Net Elec. Energy (HHH): 301811 1393010 1393010

13. Reactor Service Factor: N/A N/A N/A

14. Reactor Availability 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 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: 218.6 422.7 422.7

21. Shutdowns Scheduled Over Next 6 Honths: Scheduled Surveillance Outage 12/03/88 Scheduled Startup 01/02/89

22. I Shutdown at End of Report Period, Es?imated Date of Startup:

23. Units in Test Status (Prior to Commercial Operation):

FORECAST ACHIEVED Initial Criticality Q2/29/88 03/08/83 Initial Electricity 03/28/88 05/25/88 Commercial Operation 10/17/88 l

(4957z/10)

- CJ. AVERAGE DAILY UNIT NET POWER LEVEL LOG DOCKET NO.: 50-457 UNIT: Braidwood 2 DATE: 10/07/88 COMPILED BY: M. H. Peterson TELEPHONE: (815)458-2801~

ext. 2480 HONTH: September, 1988

1. 1123* 17. 0 ,

.2. 1120 18. 0

3. 1088 19. 0

4. 93 20. 0

5. 95 21. 0

6. 323 22. 250

7. 852 23. 512

8. 1036 24. 0

9. 1011 25. 0

10. 873 26. 0

11. 821 27. 0

12. 1007 28. 73 4

13. 1113 _ _ . 29. 91 1

14. 1117 30. 45

15. 156 31. N/A

16. O INSTRUCTIONS On this form iii. the average daily unit power level in MHe-Net for each day in the reporting r.<cth. rompute to the nearest whole megawatt.

These figures will be usea tv plot a graph for each reporting month.

l 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.

l

• Due to Condenser Efficiencies i

1 (4957z/11) i

D. UNIT SHUJDOWNS/REDUCTICS DOCi'ET NO.: 50-457 UNIT: Braidwood 2 -

~

DATE: 10/07/88 -

COMPILED BY: M. H. Peterson*'

TELEPHONE: (815)458-2801 -

• ext. 2480 REPORT PERIOD: September, 1988

_ N_p_ DALE IyPE HOURS REASON METHOD LER NUMBER SYSTEM COMPONENT CAUSE & CORRECTIVE ACTION TO PREVENT RECURRENCE 13 880904 F 33.1 A 2 88-020 SI V Low Steam Generator Level Due to failed Open Heater Drain Valve 14 880915 F 159.9 G 1 N/A N/A N/A Secondary Chemistry Out of Specification 15 880923 S 116.2 8 3 N/A N/A N/A Startup Test - Full Power Trip 16 880929 F 14.4 G 3 88-026 AA N/A Reactor Trip Due to High Steam Generator level Initiated by Instrument Hechanic in Instrument Rack 17 880930 F 11.2 F 1 N/A N/A N/A Secondary Chemistry Out of Specification

SUMMARY

TYPE REASON METHOD SYSTEM & COMPONENT 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 Date. 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)

E. UNIOUE REPORTING REOUIREMENTS - UNIT 2

1. Safety / Relief valve operations.

VALVES NO & TYPE PLANT DESCRIPTION QALE ACTUATED ACTUATION CONDITION OF EVENT None

2. Licensee generated changes to 00CH.

None (4957z/13)

1

+

F. LICENSEE EVENT REPORTS - UNIT 2 The following is a tabular summary of all Licensee Event Reports submitted during the reporting period, September 1 through ,

September 30, 1988. This information is provided pursuant to the reportable occurrence reporting requirements as set forth in 10 CFR 50.73.

Licensee Event Renort Rgoort Number (Lita Title of Occurrence 88-012-00 08/24/88 Reactor Trip Due to Phase 8 Overturrent Protective Relay C0-7 Defective Current Switch.

88-014-00 08/24/88 Unit 2 Reactor Trip Due to Low  !

water level Caused by Erratic Operation of main Regulating Valves 88-020-00 09/08/88 Hanual Reactor Trip Due to Approaching Low Low S/G Levels as a Result of failed Open Heater Drain Valve (4957z/14)

l

' l

< Commonwealth Edison

. Br ldwood Nucl=r Pow;r St tion ,

Route #1. Box 84 Braceville, Illinois 60407 Telephone 815/458-2&'1 BH/88-1228 October 7, 1988 Director, Office of Resource Hanagement United States Nuclear Regulatory Commission Washington, D.C. 20555 ATTN: Document Control Desk Gentlemen:

Enclosed for your information is the Monthly Performance Report cf/ering Braidwood Nuclear Power Station for the period September 1 through September 30, 1988.

Very truly yours,

[ WO R. E. Querio Station Hanager Braidwood Nuclear Station REQ /RCB/ jab (4957z)

Attachments cc: A. B. Davis, NRC, Region III NRC Resident Inspector Braidwood Gary Wright, Ill. Dept. of Nuclear Safety T. J. Maiman K. L. Graesser li. E. Bliss Nuclear fuel Services, PHR Plant Support INPO Records Center Performance Monitoring Group, Tech Staff Braidwood Station Nuclear Group, Tech Staff Braidwood Station S. Sands - USNRC ff,Y I 1