ML20206E552

Monthly Operating Repts for Oct 1988 for Braidwood Nuclear Power Station Units 1 & 2

ML20206E552
Person / Time
Site:	Braidwood
Issue date:	10/31/1988
From:	Peterson M, Querio R COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
BW-88-1410, NUDOCS 8811180112
Download: ML20206E552 (14)

Text

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i BRAIDWOOD NUCLEAR F04ER STATION UNIT 1 AND UNIT 2 MONTHLY PF.RFORMANCE REPORT COMMONWEALTH EDISON COMPANY NRC COCKET NO. 050-456, LICENSE NO NPF-72 NRC DOCKET NO. 050-457, LICENSE NO. NPF-77 8911180112 081031 ADOCK 050 46

{s>R (4957z/2) f6:)Y lll

• I. Monthly Report for Braidwood Unit 1 A. Summary of Ooerating Exoerience The unit entered the _..sth of October at 95.7 percent reactor power and 1136 megawatts electric gross generation. On October 16, 1988, a loss of our Davis Creek line, due to a lightning strike, was followed by a pole disagreement on a 345 KV yard breaker in the Braidwood switchyard. This resulted in a loss of the system auxiliary transformer. A blocked relay associated with the IC reactor coolant pump allowed it to trip on overcurrent during the bus transfer. The unit was brought critical age.in on October 19, 1988, and the turbine

. synchronizec~to the grid on October 20, 1988. The unit continued power operation thru the end of the month.

(4957z/3)

./ B. OPERATING DATA REPORT DOCKET NO.: 50-456 UNIT: Braidwood 1 OATE: 11/09/88 COMPILED BY: H. H. Peterson TELEPHONE: (815)458-2801 ext. 2480 OPERATING STATUS l

i. Reporting Period: October, 1988 Gross Hours: 745.0

2. Currently Authorized Power Level (HHt): 3411 Design Electrical Rating (HHe-gross): 1175 Design Electrical Rating (HHe 'st): 1120 Max Dependable Capacity (HHe-gross): 1175 Hax Dependabic Capacity (HHe-rut): 1120

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

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

5. Report period Hours: 745.0 2265.3 _2265.3

6. Hours Reactor Critical: 676.6__ 2078.9 2078.9

7. RX Reserve Shutdown Hours: 0 . Q_ _ __ 0.0 0.0

8. Hours Generator on Line: 657.b 2007.5 2007.5

9. Unit Reserve Shutdown Hours: 0.0 0.0_ 0.0

10. Gross Thermal Energy (HHH): _1012005 _ _6096268 _EOSf21B_.

11. Gross Elec. Energy (HHH): _61Baa0_ _2092312 2092312

12. Net Elec. Energy (HHH): 665968_ 1992979 1992973_.

13. Reactor Service Factor: 90.8 91.8 91.8

14. Reactor Availability Factor: _ 90.8 91.8 91.8

15. Unit Service Factor: 88.3 88.6 88 5 _

16. bait Availability Factor: 88.3 88.6 88.6  ;

17. Unit Capacity Factor (MDC net): ___. 79.8 78. 6.. . 7L6_

18. Unit Capacity Factor (DER net): 79.8 78.6 78.6.

19. Unit forced Outage Rate: 11.7 11.4 11.4 i

20. Unit Forced Outage Hours: 87.5 257.B__ 257.8 >

21. Shutdowns Scheduled Over Next 6 Honths: Scheduled Surve1111ance Outage beginning 02/20/89.

Scheduled Restart. 04/01/89.

22. If Shutdown at End of Report Period, 4 Estimated Date of Startup:

23. Units in rest Status (Prior to Comercial Operation):

FORECAST AGIEVED Initial Criticality 05/23/87 05/29/87 Initial Electricity 07/11/87 07/12/87 Commercial Operation 07/15/83 Q2123/_83

• Numbers re-zerced due to comerical operation (4957z/4)

C. AVERAGE DAILY UNIT NET POWER LEVEL LQG DOCKET NO.: 50-456 UNIT: Braldsood 1 DATE: 11/09/88 COMPILEO BY: H. H. Peterson TELEPHONE: (815)458-2801 ext. 2480 HONTH: October, 1988

1. 994 __ 17. 0

2. 1004 18. 0

3. 969 19. 0

4. __ 1053 20. 123

5. _ 1071 21. 473

6. 1032 22. 1053

7. 1087 23. 1113

8. 1078 24, 1098

9. 1032 25, 1120

10. 1047 26, 1108 3

11. 1010 27, 1110 12, 1120 28. 1097

13. 985 29. 1068 14, 986 30, 1069

15. 1043 31. 1022 16, 886 INSTRUCTIONS On this form list the average daily unit power level in FWe*Ntt for each j day in the reporting month. Compute to the nearest who19 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 anor.aly.

(4957z/5) .

D. UNIl_SHUlQQWNSIREWCIII)NS DOCKET NO.: 50-456 UNIT: Braidwood 1 .

DATE: 11/09/88 -

COMPILED BY: M. H. Peterson TELEPHONE: (815)458-2801 ext. 2480 REPORT PERIOD: October, 1988

_EQ_ Dalf 11PL [fQURS REA50ff tiEIH@ LER_ NUMBER SYSTEM COMPONENT CAUSE & CORRECTIVE. ACTION TO PREVENT RECURRENff 04 881016 F 87.6 A 3 88-022 EA L2002 A loss of the Davis Creek transmission line followed by a pole disagreement on a 345 KV yard breaker resulted in a loss of the System Auxiliary Transformer. A blocked relay associated with the IC Reactor Coolant Pump allowed it to trip on overcurrent during the bus transfer. The 345 KV yard breaker pole disagreement has been adjusted and the relay block was removed. . The other 4 KV and 6.9 KV buses on Unit I have been inspected to ensure that no relay blocks are installed.

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 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 (49572/6)

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F. ' LICENSEE EVENT REPORTS - UNIT 1 The following is a tabular summary of all Licensee Event Reports ,

submitted during the reporting period, October 1 through  :

October 31, 1988. This information is provided pursuant to the reportable oc;urrence reporting requirements as set forth in 10 CFR 50.73.

Liclasee Evertt Repor.1 Report Number- QAlt Title of Occurrence 08-020 10/05/88 Control Room ventilation switchover due to spurious noise.88-021 10/24/88 Axial flux difference monthly surveillance missed due to error in tracking due date.

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II. Monthly Report for Braidwood Unit 2 A. Summary of Optrating Exoerience The unit entered the month of October shut down. This was the result of the out of specification secondary water chemistry which was experienced in September. On October 5, 1988,'the reactor was brougnt critical and the turbine was synchronized to the grid. The 100 hour0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> warranty run was completed on October 15, 1988, and the unit was declared in commercial service on October 17, 19s3. A lightr.ing induced voltage transient caused a reactor trip on October 17, 1988. On October 18, 1988, the reactor was broug.. critical and the turbine was synchronized to the grid. The reactor was manually tripped on October 25, 1988, as a result of a clogged condensate pump suction strainer. On October 30, 1988, the reactor was again brought critical and the turbine was synchronized to the l grid. The unit continued power operation thru the end of the month.

I (4957z/9)

. ,. B . OPERATING DATA REPORT DOCKET NO.: 50-457

.l. UNIT: Braidwood 2 DATE: 11/09/88 COMPILED BY: H. H. Peterson TELEPHONE: (815)458-2801 ext. 2480 OPERATING STATUS

1. Reporting Period: October, 1908 Gross Hours: 347.0

2. Currently Authortred Power Level (HHt): 3411 besign Electrical Rating (HHe-gross): 1175 Design Electrical Rating (HHa-net): 1120 Max Dependable Capacity (HWe-gross): 1175 Mar Dependable Capacity (HWe-nat): 1120

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

4. Reasons for restriction (If Any): None IHIS H0!418 YL,[Q_D&II* (UMULATLVI*

5. Report period Hours: __147.0 _ 347.t_ , _ 347.0_ _

6. Hours Reactor Critical: _2EQ__ _210__ _215.0

7. RX Reserve Shutdown Hours: .020. _ 0.0 0.0

8. Hours Generator on Line: ..198.5._. 198.5 198.5

9. Unit Reserve Shutdown Hours: _ 0.0 0 . 0 . __ 0.0

10. Gross Thermal Energy (HHH): 498112__ 498112 EallL__.

11. Gross Elec. Energy (HHH): ._ .16 92.5 Q__ 169750 1f3250

12. Net Elec. Energy (HHH): 158477 158477 ._158477'

13. Reactor Service Factor: 6 L2__ 62.2 __ 62.2

14. Reactor Availability Factor: 62.2 6 2. 2. .. . _ 62.2

15. Valt Service Factor: 57.2 57.2 57.2

16. Unit Availability Factor: 57,2_ _ 57.2 57.2

17. Unft Capacity Factor (MDC net): 4Qd._ 4QJL._ _ 40.8

18. Unit Capacity Factor (DER net): 40.8 _ 40.8 40.8

19. Unit Forced Outage Rate: 4 2 . 8.__ 42_.a 42.8

20. Unit Forced Outt.ge Hours: 148.5 148.5 148.5

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

22. If Shutdown at End of Report Period.

Estimated Date of Startup:

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

FORECAST ACHIEVED Initial Criticality 02/2.91AS 03108188 Initial Electricity 0312 ALES 05125188 Comercial Operation 10/17/88 10/17/83

• Numbers re-Zerced due to comercial operation.

(4957z/10)

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• C. AVERAGE DAILY ORLTJEIf0HER.11YLLLQG DOCKET NO.: 50-457 i

,e UNIT: Braidwood 2  :

DATE: 11/09/88

, COMPILED BY: M. H. Peterscre {

TELEPHONE: (815)458-2801  ;

ext. 2480 i MONTH: October, 1988 i

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5. . NA_ . 21. 973 6 NA 22. 975

7. NA 23, 1004

8. NA 24. 1017

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! 15. NA 31. 668

16. NA INSTRUCTIONS On this form list the average daily unit power level in MWe-Net for each t day in the reporting month. Compute to the alarest whole megawatt.

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

Note-that when maximum orpendable capacity is used for the net electrical rating of the unit there may be occasions when the dal',y 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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I (4957z/11) i

D. {JNIT SHUTDQMNS/REDUCTI(DS DGCKET NO.: 50-457 '

tmIT: Braidwood 2 / '

DATE: 11/09/88 00MPILED BY: M. W. Peterson TELEPHONE: (815)458-2801 ext. 2480 REPORT PERIOD: October, 1988

~

J2- DAIE JIP_E LFERS REASM METHOD LER NUMBER SYSIf3 COTONENT CAUSE & CORRECTIVE ACTION TO PREVENT RECURRENCE 01 881017 F 29.1 A 3 88-027 AA 59 A lightning strike induced a voltage tran-sient which caused rod drive overvoltage devices to actuate which resulted in the control rods being inserted into the reactor core. The overvoltage devices were reset on the Rod Control System, and damaged equipment was replaced / repaired.

Engineering is performing a review of the grounding system.

02 881025 F 119.4 A 2 88-029 SD STR Clogging of the Condensate Pump Suction Strainers resulted in low pump discharge pressure and decreasing Steam Generatt.

Water Level. A Manual Reactor Trip was performed when Condensate Pump Discharge Pressure could not be maintained. The clogged strainers were cleaned and selected strainers in the 3 eater Drain Pump System, Condensate Pump system and the Feedwater pump Systems before restarting the unit.

SUMMARY

TYPE REASON METH00 SYSTEM & COMPONENT F-Forced A-Equipment Failure 1 - Manual Exhibit F & H S-Scheduled 8-Maint or Test 2 - Manual Scram Instructions for Preparation of i

C-Refueling 3 - Auto Scram Data Entry Sheet l D-Regulatory Restriction 4 - Ccntinued Licensee Event Report l E-Operator Training & License Examination 5 - Reduced Load (LER) Flie (NUREG-1022)

F-Administration 9 - Other G-Oper Error l H-Other l

(4957z/12)

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F. LICENSEE EVENT REPORTS - UNIT 2 The following is a tabular summary of all Licensee Event Reports '

submitted during the reporting period October I thrcugh October 31, 1988. This information is provided pursuant to the reportable o:currence reporting requirements as set forth in 10 CFR 50.73.

Licensee Event Esport Rep. ort Number ___ Qalg Title of Occurigatt '

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88-021-00 10/14/88 Steam Genertor hi ht level due to feedwater regulating bypass valve  !

positioner calibration drift.

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88-022-00 10/14/88 Reactor trip due to loose

, connections in 2PH05J (source range hi flux).

88-023-00 10/18/68 Both RHR trains declared inoperbie

, due to a procedural deficiency. -

88-024-00 10l18/88 Steam Generator hl hl level due to incorrect operation of High

, Pressure Cleanup Loop as a result .

of a design deficiency in the Hat.-Machine Interface.

88-025-00 10/24/88 Technical Specification surveillance interval exceeded due

to mislogging burnup of previous '

surveillance performed.  !

88-026-00 10/27/88 Turbine trip caused by hi hl Steam I

Generator level.

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(49572/14)

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. . Commonwealth Edison

• Braldwood Nuclear Power Station

. Route #1. Box 64 Braceville. Illinois 60407 Telephona 815/458-28ot November 9, 1988 BH/88-1410 Olrector, Office of Resource Management United States Nuclear Regulatory Comission Washington, D.C. 2055S ATTN: Document Control Desk Gentlemen:

Enclosed for your information is the Monthly Performance Report covering Braidwood Nuclear Power Station for the period October I through October 31, 1988.

Very truly yours, d? ~

dR.E.Que o l' Station Manager Braidwood Nuclear Station REQ /RC8/ jab (49572)

Attachments cc: A. B. Davis, NRC, Region !!!

NRC Resident Inspector Braidwood Gary Wright, Ill. Dept. of Nuclear Safety T. J. Halman K. L. Graesser H. E. Bliss Nur. lear Fuel Services, PWR Plant Support INPO Records Center Performance Monitoring Group, Tech Staff Braidwood Station Nuclear Group, Tech Staff Braidwood Station S. Sands - USNRC ff

)

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