ML20150B914

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Monthly Operating Repts for Feb 1988
ML20150B914
Person / Time
Site: Braidwood  Constellation icon.png
Issue date: 02/29/1988
From: Peterson M, Querio R
COMMONWEALTH EDISON CO.
To:
NRC, NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
REQ-88-020, REQ-88-20, NUDOCS 8803170184
Download: ML20150B914 (14)
v • d • e


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l BRAIDH000 NUCLEAR P0HER STATION UNIT 1 AND UNIT 2 MONTHLY PERFORMANCE REPORT COMMONHEALTH EDIS0N COMPANY NRC DOCKET NO. 050-456, LICENSE NO. NPF-72 NRC DOCKET NO. 050-457, LICENSE NO. NPF-75

.qgzy (4957z/2) _

8803170184 880229 PDR ADOCK 05000456

@ - DCD_ _ __ ___ _ _ _ ____ _ _____ _ _ __________

I. Monthly Report for Braidwood Unit 1 A. Summary of Ooeratina Exoerience The unit entered the month of February in Mode 5 as surveillance outage activities were being completed. On February 20 the unit entered Mode 3, however, due to an accumulator fill line leak the unit was returned to Mode 4 on February 23. On February 24, the unit entered Mode 3, however, due to an excessive reactor coolant system leakage rate the unit entered Mode 5 on February 27. The unit remained in Mode 5 through the end of the month.

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(4957z/3) t

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B. OPERATING DATA REPORT DOCKET N0.: 50-456

. . UNIT: Braidwood 1 DATE: 03/10/88 COMPILED BY: M. H. Peterson TELEPHONE: (815)458-2801 ext. 2480 OPERATING STATUS

1. Reporting Period: February, 1988 Gross Hours: 696.0
2. Currently Authorized Power Level (MHt): 3411 Design Electrical Rating (MWe-gross): 1175 Design Electrical Rating (MWe-net): 1120 Max Dependable Capacity (MHe-gross): 1175 Max Dependable Capacity (HWe-net): 1120
3. Power level to which restricted (If Any): None
4. Reasons for restriction (If Any): None THIS MONTH YR TO DATE CUMULATIVE
5. Report period Hours: 696.0 1440.0 5593.0
6. Hours Reactor Critical: 0.0 14.5 3074.2
7. RX Reserve Shutdown Hours: 0.0 0.0 0.0
8. Hours Generator on Line: 0.0 14.5 2625.2
9. Unit Reserve Shutdown Hours: 0.0 0.0 0.0
10. Gross Thermal Energy (MHH): 0.0 47283 5062957
11. Gross Elec. Energy (MHH): 0.0 17056 1621660
12. Net Elec. Energy (HWH): 0.0 16111 1472762
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 l
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 l

l 20. Unit forced Outage Hours: 0.0 0.0 1322.3

21. Shutdowns Scheduled Over Next 6 Months:
22. If Shutdown at End of Report Period, Estimated Date of Startup:
23. Units in Test Sts.tus (Prior to Comercial Operation):

FORECAST ACHIEVED Initial Criticality 05/23/87 05/29/87 Initial Electricity 07/11/87 07/12/87 Comercial Operation 04/23/88 l

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C. AVERAGE DAILY UNIT NET POWER LEVEL LOG DOCKET NO.: 50-456 UNIT: Braidwood 1 DATE: 03/10/88 COMPILED BY: H. H. Peterson TELEPHONE: (815)458-2801 ext. 2480 HONTH: February, 1988

1. 0 17. 0
2. 0 18. 0
3. 0 19. O __

l 4. 0 20. 0

5. 0 21. 0
6. 0 22. 0 l
7. 0 23. O
8. 0 24. 0 i

l 9. 0 25. O

10. 0 26. 0
11. 0 27. 0

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12. 0 28. 0 l
13. 0 29. 0 1
14. 0 l 15. 0
16. 0 j INSTRUCTIONS l

l On this form list the average daily unit power level in MWe-Net for each day in the reporting mor.th. Compute to the nearest whole megawatt.

l 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 1001. line (or the restricted power level line). In such cases the average daily unit power output sheet should be footnoted l

to explain the apparent anomaly.

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(4957z/5)

D. UNIT SHUTDOWNS /REDilCTIONS DOCKET NO.: 50-456 UNIT: Braidwood l'  :

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DATE: 03/10/88 COMPILED BY: M. H. Peters'o,n TELEPHONE: (815)458-2801 ext. 2480 REPORT PERIOD: February, 1988 No DAIL Iyf_E HOURS REASON METHOD LER NUMBER SlSIFE COMPONENT CAUSE & CORRECTIVE ACTION TO PREVENT RECURRENCE 01 880101 S 696.0 H 4 N/A N/A N/A Continuance of 6 week surveillance outage.

Subsequent RCS leakage caused the unit to remain down. Reactor coolant pump seals were replaced.

AAAAAAAAAAAAAAAAA

SUMMARY

AAAAAAAAAAAAAAAAA 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)

E. UNIOUE REPORTING RE0VIREMENTS- UNIT I ',

1. Safety / Relief valve operations.

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

2. Licensee generated changes to 00CM. .

None (4957z/7)

, e-F. LICENSEE EVENT REPORTS - UNIT I The following is a tabular summary of all Licensee Event Reports submitted during the reporting period, February 1 through February 29, 1988. This information is provided pursuant to the reportable o:currence reporting requirements as set forth in 10 CFR 50.73.

Licensee Event Reoort Eeoort Number DAtt Title of Occurrenca 88-001-00 02/02/88 Control room ESF actuation for unknown reasons.

(4957z/8)

II.. Monthly Report for Braidwood Unit 2 A. Summary of Ooeratina Exoerience The unit entered the month cf February in Mode 5.

On February 6, at approximately 0058 hours6.712963e-4 days <br />0.0161 hours <br />9.589947e-5 weeks <br />2.2069e-5 months <br />, the Reactor Coolant System (RCS) was water solid at 131*F and 360 psig. The train B Hanual Safety Injection Initiation Surveillance 2Bw0S 3.2.1.1.a-2 was in progress. Per this procedure, the Charging Pump to Cold Leg Injection Valve 2SI8801B was opened to demonstrate that the thermal overloads were properly replaced. The procedure specifically cautions to minimize the amount of time the valve is open since cycling the valve with the RCS water solid may cause a pressure transient. Upon opening 2SI8801B, the RCS pressure rose from approximately 360 psig to 500 psig causing Power Operated Relief Valve (PORV) 2RY455A to open. Both PORVs were in the Arm Lo Temp Cold Overpressure Protection Mode. Valve 2SI88018 was then closed per procedure. The PORV closed after two seconds and RCS pressure stabilized at approximately 360 psig. It is presumed that the Residual Heat Removal (RHR)

Suction Relief Valve 2RH8708A and 2RH8708B also lifted during the pressure transient.

On February 9, the unit entered Mode 4 and on February 13, entered Mode 3.

On February 28, the unit was at normal operating temperature and pressure with Start-up Test BwSU RC-72 in progress. At 1706 hours0.0197 days <br />0.474 hours <br />0.00282 weeks <br />6.49133e-4 months <br />, all four Reactor Coolant Pumps (RCP) were tripped in accordance with the test. At 1727 hours0.02 days <br />0.48 hours <br />0.00286 weeks <br />6.571235e-4 months <br />, the 20, 2C, and 2A RCPs were started as required by BwSU RC-72 system restoration steps. Five minutes later, the 2A RCP was stopped due to No. 1 seal leak-off concerns, and at 1802 hours0.0209 days <br />0.501 hours <br />0.00298 weeks <br />6.85661e-4 months <br />, the other running RCPs were secured. After troubleshooting the 2A RCP, the 2D RCP was restarted at 1859 hours0.0215 days <br />0.516 hours <br />0.00307 weeks <br />7.073495e-4 months <br />. Aproximately 42 seconds after start, pressurizer PORV 2RY455A opened for four seconds.

The cause of the PORV opening was a pressure spike caused by the heat up of the RCS by warmer water on the secondary side of the four Steam Generators. When the ID RCP 1

started, it swept the colder RCS water into the Steam Generator where it was heated, which resulted in a pressure spike. The Nuclear Station Operator opened spray valve 2RY455B to provide additional pressure control. The opening of the PORV terminated the transient and returned system pressure to stable conditions at approximately 2235 psig.

The unit remained in mode 3 through the end of the month.

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(4957z/9) l

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B. OPERATING DATA REPORT DOCKET N0.: 50-457 UNIT: Braidwood 2 DATE. 03/10/88 COMPILED BY: M. H. Peterson TELEPHONE: (815)458-2801 ext. 2480 OPERATING STATUS

1. Reporting Period: February, 1988 Gross Hours: N/A
2. Currently Authorized Power Level (MWt): 0 Design Electrical Rating (MWe-gross): 1175 Design Electrical Rating (MWe-net): 1120 Max Dependable Capacity (MWe-gross): 0 Max Dependable Capacity (MWe-net): 0
3. Powet 'evel to which restricted (If Any): 5%
4. Reasons for restriction (If Any): Terms of Braidwood Station's Facility Operating License.

THIS HONTH YR TO DATE CUMULATIVE

5. Report period Hours: N/A -- --
6. Hours Reactor Critical: N/A -- --
7. RX Reserve Shutdown Hours: N/A -- --
8. Hours Generator on Line: N/A -- --
9. Unit Reserve Shutdown Hours: N/A -- --
10. Gross Thermal Energy (MWH): N/A -- --
11. Gross Elec. Energy (MWH): .

N/A -- --

12. Net Elec. Energy (MWH): N/A -- --
13. Reactor Service Factor: N/A -- --
14. Reactor Availability Factor: N/A .
15. Unit Service Factor: N/A -- --
16. Unit Availability Factor: N/A -- --
17. Unit Capacity Factor (MDC net): N/A -- --
18. Unit Capacity Factor (DER net): N/A -- --
19. Unit Forced Outage Rate: N/A -- --
20. Unit Forced Outage Hours: N/A -- --

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21. Shutdowns Scheduled Over Next 6 Months:
22. If Shutdown at End of Report Period, Estimated Date of Startup:

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

FORECAST ACHIEVED Initial Criticality 02/29/88 03/08/88 Initial Electricity 03/28/88 Commercial Operation 07/25/88 (4957z/10)

C. AVERAGE DAILY UNIT NET POWER LEVEL LOG DOCKET N0.: 50-457 UNIT: Braidwood 2 DATE: 03/10/88 COMPILED BY: H. H. Peterson TELEPHONE: (815)458-2801 ext. 2480 MONTH: February, 1988

1. N/A 17. N/A
2. N/A 18. N/A
3. N/A 19. N/A
4. N/A 20. N/A
5. N/A 21. N/A
6. N/A 22. N/A
7. N/A 23. N/A
8. N/A 24. N/A
9. N/A 25. N/A
10. N/A 26. N/A
11. N/A 27. N/A
12. N/A 28. N/A
13. N/A 29. N/A
14. N/A
15. N/A
16. N/A 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.

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(4957z/11) i

D. UNIT SHUTDOWNS / REDUCTIONS DOCKET NO.: 50-457 UNIT: Braidwood 2' .

DATE: 03/10/88 COMPILED BY: M. H. Peterson TELEPHONE: (815)45r-2801 ext. 2480 REPORT PERIOD: February, 1988 No DAIE IyfE (( QUES REASON METHOD LER NUMBER SYSTEM COMPONENT CAUSE & CORRECTIVE ACTION TO PREVENT RECURRENCE N/A Precritical Period AAAAAAAAAAAAAAAAA

SUMMARY

AAAAAAAAAAAAAAAAA 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/12)

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E. UNIOUE REPORTING REOUIREMENTS - UNIT 2 ,

1. Safety / Relief valve operations.

VALVES NO & TYPE PLANT DESCRIPTION DATE ACTUATED ACTUATION CONDITION OF EVENT 880206 2RY455A Pzr PORV Mode RCS water solid. Per an operating 2RH8708A RHR Suction RCS Temp 121*F surveillance, valve 2SI8801B was 2R.98708B Relief Valves RCS Press 360 psig opened. Upon opening this valve the RCS pressure rose from approximately 360 psig to approximately 500 psig causing the PORV, and presumably the RHR Suction Relief Valves to lift.

> The valves functioned as expected.

880228 2RY455A Pzr PORV Mode 3 During the performance of a startup RCS Temp 557'F test all four reactor coolant pumps RCS Pres 2235 psig were secured due to a seal leak-off concern on the 1A pump. Upon restart of the 2D pump a pressure spike occurred causing the PORV to lift. The valve functioned as expected.

2. Licensee generated changes to 00CM.

None (4957z/13)

F. LICENSEE EVENT REPORTS - UNIT 2 The following is a tabular summary of all Licensee Event Reports submitted during the reporting period, February 1 through February 29, 1968. This information is provided pursuant to the reportable occurrence reporting requirements as set forth in 10 CFR 50.73.

Licensee Event Reoort Reoort Number QAlf Title of Occurrence 88-002-00 02/16/88 Containment ventilation isolation from loss of pulses to rad monitor 1RT-AR0ll due to low background radiation.

88-003-00 02/29/88 Inadvertent loss of power to instrument bus 212 resulting in a reactor trip due to personnel error.

88-004-00 02/25/88 Undervoltage start of the 2A diesel generator due to operator error.

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Braceville, Illinois 60407 Telephone 815/458-2801 REQ /88-020 March 10, 1988 Director, Office of Resource Management United States Nuclear Regulatory Commission Washington, D.C. 20555 ATTN: Document Control Desk Gentlemen:

Enclosed for your information is the Monthly Performance Report covering Braidwood Nuclear Power Station for the period February 1 through February 29, 1988.

Very truly yours, R. E. u rio

[StationManager 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 L. D. Butterfield Nuclear Fuel Services, PHR Plant Support L. Anastasia, Station Nuclear Engineering INPO Records Center Performance Monitoring Group, Tech Staff Braidwood Station Nuclear Group, Tech Staff Braidwood Station 4 %N S. Sands - USNRC P. L. Barnes i

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