ML20212F907

Monthly Operating Rept for Jan 1987

ML20212F907
Person / Time
Site:	Braidwood
Issue date:	01/31/1987
From:	Fitzpatrick E, Peacock B COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
EEF-87-165, NUDOCS 8703050210
Download: ML20212F907 (8)

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BRAIDWOCD PUCLEAR POWER STATION UNIT 1 M0lm!LY PERFORPWICE REPORT C0tECPMEALTil EDIS0tl COMPAtti flRC DOCKET NO. 050-456 LICENSE NO. NPF-59 f*

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(4491a)

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l I. Monthly Report for Braidwood Unit 1 f

A. Sumary of Operatin2 Expe rienc_e The unit remained in Mode 5 throughout the month of January, 1987.

Pre-operational testing continued.

On January 6, 1987, at 0023 hours2.662037e-4 days <br />0.00639 hours <br />3.80291e-5 weeks <br />8.7515e-6 months <br />, the Reactor Coolant System (RCS) was water solid at 380 psig and 125*F with all four Reactor Coolant Pumps (RCP's) stopped. The Residual Heat Removal (RHR) Train 1B was running in the shutdown cooling mode. Both Pressuriger (Pze) Power Operator Relief Valves (PORV's) were in the cold overpressure l protection mode, in which PORV 1RY455A has a setpont of 470 psig at l 125'F. The IC RCP was started and, approximately 46 seconds later, the 1RY455A PORV lifted for two seconds.

This pressure transient was induced by a rapid increase of RCS temperature when the 1C RCP was started and the 125'r RCS water was swept through the steam generator tubes with the secondary coolant temperature at approximately 150*F. The letdown pressure control valve, ICV 131, was being controlled in manual at the time the IC RCP was started and could not be opened quickly enough to mitigate the resulting pressure transient. The maximum RCS pressure reached was approximately 480 psig. The PORV functioned as expected and j terminated the pressure transient.  !

On January 12, 1987, at approximately 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> a steam bubble was formed in the pressurizer. This steam bubble supplies a surge volume to the RCS which can absorb pressure transients due to RCS water temperature increase. Additionally, an RCP has been run intermittently since the incident occurred to help maintain RCS temperature equal to secondary steam generator temperature. These actions should prevent recurrence of this event.

(4491a)

B.

OPERATING DATA REPORT DOCKET NO.: 50-456 UNITt Broidwood 1 DATE: 02/05/87 COMPILED BY: B. M. Peacock TELEPHONE: (815)458-2801 ext. 2480 OPERATING STATUS

1. Reporting Period: January 1987 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. Power level to which restricted (If Any): 0 (MWe-gross)

4. Reasons for restriction (If Any): Low power testing license has not been received yet.

TIIIS MONTH YR TO DATE CUMULATIVE

5. Report period flours: N/A -- --

6. liours Reactor Critical: N/A -- --

7. RX Reserve Shutdown flours: N/A -- --

8. Ilours Generator on Line: N/A -- --

9. Unit Reserve Shutdown Hours: N/A -- --

10. Gross Thermal Energy (MWil): N/A -- --

11. Gross Elec. Energy (MWil): N/A -- --

12. Net Elec. Energy (MWil): 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 not): N/A --

18. Unit Capacity Factor (DER net): N/A -- --

19. Unit Forced Outage Rate N/A -- --

20. Unit Forced Outage llours: N/A -- --

21. Shutdowns Scheduled Over Next 6 Months:

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

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

FORECAST ACllIEVED Initial Criticality 03/13/87 Initial Electricity 04/20/87 Commercial Operation 07/19/87 (4491s)

C. AVERAGE DAILY UNIT NET POWER LEVEL LOG DOCKET NO.: 456-UNIT: Braidwood 1 DATE: 02/05/87

, COMPILED BY: B. M. Peacock TELEPHONE: (815)458-2801 l ext. 2480 MONTH: January, 1987 j 1. N/A 17. - N/A _

2. N/A 18. N/A

3. N/A 19. N/A

4. N/A 20. Ng

5. N/A 21. N/A l 6. N/A _

22. N/A l

l 7. N/A 23. N/A l

8. N/A 24. N/A j 9. N/A 25. N/A

10. N/A 26. N/A

11. N/A 27. N/A l

l 12. N/A 28. N/A l

13. N/A 29. N/A

14. N/A 30. N/A

15. N/A 31. 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.

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

Note that when maximum dependable capacity is used for the not electrical rating of the unit there may be occasions when the daily average power l 1evel exceeds the 100% line (or the restricted power level line). In l such cases the average daily unit power output sheet should be footnoted I

l to explain the apparent anomaly.

l l

t l (4491a)

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I D. IEfIT SERITDOBEES/REDUCTIOBES . DOCKET NO.: 50-456- -

UNIT: Braidwood 1 DATE: 02/05/87 COMPILED BY: B. M. Peacock l TELEPHONE:-(815)458-2801-ext. 2480 REPORT PERIOD: January 1987 No DATE TYPE HOURS REASON METHOD LER NIDEBER SYSTEM COMPONENT CAUSE & CORRECTIVE ACTION TO PREVENT RECURRENCE N/A FRIERITICAL PERIOD i

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SUMMARY

Coceeeeeeeeeeeeet TYPE REASON METIIOD SYSTEM A COMPONENT F-Forced A-Equipment Failure Maint or Test 1 - Method Exhibit F 5. H-S-Scheduled C-Refueling 2 - Manual Scram Instructions for Preparation of D-Regulatory Restriction 3 - Auto Scram Cata Entry Sheet E-Operator Training & License Examination 4 - Continued Licensee Event Report F-Administration 5 - Reduced Load (LER) File (NUREG-0161)

G-Oper Error 9 - Other H-Other (4491 ) .

W=-

E.- UNIQUE REPORTING REQUIREMENTS

1. Safety / Relief valve' operations.

VALVES NO & TYPE PLANT DESCRIPTION-DATE ACTUATED ACTUATION . CONDITION OF EVENT 01/06/87 1RY455A Pzr PORV Mode 5 Pzr solid. PORV in cold overpressure RCS Temp.125*F- protection mode. Starting IC RCP-RCS Pres 380.psig induced a pressure transient causing the PORV to lift. PORV functioned as expected.

2. Licensee generated changes to ODCM.

None (4491z)

3: s l

. F.- . LICENSEE EVENT REPORTS The following'is a tabular summary of all Licensee Event Reports 4 submitted during the reporting period, January 1 through-January 31,11987. This _.information is provided pursuant to the reportable occurrence reporting requirements as set forth in 10 CFR 50.73.

Licensee Event-Report Number Date- Title of Occurrence 86-008-00 01/09/87 Failure to Comply With Technical

. Specification Action Statement Due to Cognitive Personnel Errors 86-009-00 01/13/87 Diesel Generators declared inoperable due to incorrect. design of Emergency Mode circuitry 86-010-00 01/09/87 Reactor Trip -caused by damage to Source Range Cable due to personnel error 86-011-00 01/26/87 Containment Ventilation Isolation Due to Spurious Signal 87-001 01/23/87 Failure to take^ required gas sample with H2 and O2 Analyzer Inoperable due to personnel error e

9 (4491z)J

Commonwealth Edison hvo h -

Br _idwood Nuclear Power Sttion

' RoutX1. Box 84 Braceville, Illino'3 60407 Telephone 815/458-2801 EEF/87-165 File: AGNC-14 February 10, 1987 Director, Office of Resource Management United States Nuclear Regulatory Commission Washin3Luu, L.v. zubbo w ATTN: Document Control De '

Gentlemen:

Enclosed for your information is the Monthly Performance Report covering

m. Braidwood Nuclear Power Station for the period January 1 through January 31, 1987.

Very truly yours,

(( 7K2/,/r7 E. E. Fitzpatrick Station Manager Braidwood Nuclear Power Station EEF/HDP/mjv (4491z)

Attachments cc: J. G. Keppler, NRC, Region III NRC Resident Inspector Braidwood Gary Wright, Ill. Dept. of Nuclear Safety D. P. Galle T. J. Maiman D. L. Farrar Nuclear Fuel Services, PWR Plant Support L. Anastasia, Station Nuclear Engineering INPO Records Center Performance Monitoring Group, Tech Staff Braidwood Station Nuclear Group, Tech Staff Braidwood Station J. Stevens - USNRC P. L. Barnes