ML20212P159

Monthly Operating Rept for Dec 1986

ML20212P159
Person / Time
Site:	La Crosse File:Dairyland Power Cooperative icon.png
Issue date:	12/31/1986
From:	Goodman L, Malin L, Taylor J DAIRYLAND POWER COOPERATIVE
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
LAC-12036, NUDOCS 8703160009
Download: ML20212P159 (7)

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NARRATIVE SIM4ARY OF OPERATING EXPERIENCE DECEMBER 1986

-At'the onset of the December 1986 reporting period,' power generation continued at approximately 96% Reactor Thermal Power (48 MWe-net).

At 2230 on December 9, 1986, the reactor automatically shut down when a scram solenoid on lower Control. Rod Drive Mechanism No. 18 burned out. During the shutdown the o-ring was replaced at the flange of upper Control Rod Drive Mechanism No.18. The reactor was taken critical at 2106 on December 13. The

. turbine-generator was synchronized to the DPC grid at 1947 on December 14.

Power escalation continued until December 21, when 96% Rated Thermal Power (48 MWe-net) was reached. Power generation continued at approximately this ,

level for the remainder of the reporting period. l Other safety-related maintenance performed during December included replacement of one of the IB High Pressure Service Water Diesel starting batteries.

During the month of December, Type B leakage tests were performed on the electrical penetrations and personnel airlock with satisfactory results. The leakage rate measured during the airlock test completed on December 8 was 3.38 SCFH.

4 The leakage rates measured during the electrical penetration tests were as follows:

TEST LEAKAGE (SCFH)

Electrical Penetrations ID IE, 2-6:

ID 0.028 IE O

. 2A 0 i 2B 0.074 2C 0 2D 0 4 2E O-3 0 4 0.206 5 0 i 6 0 i Electrical Penetrations IB:

! 1A 0 IB 0.0011 1C 0.0011 1D 0 8703160009 861231 lDR ADOCK 05000409 PDR PCI-15 W4 ih

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-TEST LEAKAGE (SCFH) 1E 0.0011 2A 0.0016 2B 'O.0011 2C 0.0005 2D- 0 2E 0.0049

. 2F 0.0011

-Electrical Penetrations-IB 1 0 2 0.0009 3 0.006 4 0.0025 5 0 L 6 0.0038 7 0.0033 8 0.0016 9 0.00055 10 0.0022

. Electrical Penetrations IC 1 0.00056 2 0.0023 3 0.0011

, 4 0.0011 5 0.0011 6 0.014 7 0.002 8 0.0017 9 0.0011 10 0.0017 11 0.002 12 0.0006 13 0.0011 14 0.002 15 0.0028 16 0.002 17 0.0011 18 0.0017 19 0.00056 20 0.00056

, 21 0.0011 22 0.0017 23 0.002 24 0.0011 25 0.002 i

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4 TESTS LEAKAGE (SCFH)

Electrical Penetrations IA 3 0.00065 4 0 5 0 PCI-IS

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-OPERATING' DATA REPORT -

DOCKET N0'.'50-409 DATE 01/07/87-COMPLETED BY L. Malin TELEPHONE , 608-689-2331 OPERATING STATUS

-1. Unit Name: La Crosse Boiling Water Reactor-

2. Report Period: 0000.'12/01/86 to 2400. 12/31/86

'3.

Licensed Thermal Power (Mit ): 165 4.- ' Nameplate rating (Gross MW.): 65.3

5. Design Electrical Rating (Net Mt.): 50 6.~ -

. Maximum Dependable Capacity.(Gross MW.): 50

7. Maximum Dependable Capacity (Net MW.): 48

8. If Changes Occur in Capacity Ratings (Items 3 Through 8 ) Since Last Report, Give Reasons:

9. ' Power Level to Which Restricted, If Any (Net MW.):

10. . Reasons for -Restrictions, If Any:

This Month Year-to-Date Cumulative

11. - Hours In Reporting Period 744 8.760 150.483 12.. Number of Hours Reactor Was Critical 649.4 4.401.2 100.482.1

13. Reactor Reserve Shutdown Hours 0 39.2 517.2

14. Hours Generator On-Line 626.7 3.998.1 93.499.0

15. Unit Reserve Shutdown Hours 0 41.5 120.5

16. Gross' Thermal Energy Generated (MWH) 93.061.2 558.258.5 13.017.221.I

17. Gross Electrical Energy Generated (MWH) 29.025 171.282 3.910.491

18. Net Electrical Energy Generated (MWH) 27.357 157,179 3.625.924

19. Unit Service Factor 84.2 45.6 62.1

20. Unit Availability Factor 84.2 46.1 62.2

21. Unit capacity Factor (Using MDC Net) 76.6 37.4 50.0

22. Unit Capacity Factor (Using DER Net) 73.5 35.9 48.2

23. Unit Forced Outage Rate 15.8 43.3 11.9

24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

25. If Shut Down At End Of Report Period, Estimated Date of Startup: N/A

26. Units In Test Status (Prior to Commercial Operation): Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COP 9tERCIAL OPERATION PCI- 15

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-409 UNIT LACBWR DATE 01/07/87 COMPLETED BY L. S. Goodman TELEPHONE 608-689-2331 MONTH December DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 48 _

17 30 2 48 18 34 3 48 19 38 4 48 20 43 5 48 21 46 6 48 22 48 7 48 23 48 8 48 24 47 9 46 25 48 10 0 26 48 11 0 27 48 -

12 0 28 48 13 0 29 47 14 1 30 48 15 19 31 48 16 27 Instruction On this format, list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.

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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-409 UNIT NAME LACBWR DATE 01/07/87 REPORT MONTH DECEMBER 1986 COMPLETED BY L.S. Goodman TELEPHONE 608-689-2331

:  :  :  :  : Method of : Licensee :  :  : Cause & Corrective  :

:  :  : Duration :  : Shutting Down: Event  : System : Component: Action to  :

No. : Date : Typel : (Hours)  : Reason 2 : Reactor 3 : Report # : Code 4 : Code 5  : Prevent Recurrence  :

86-25:12/09/86: F  : 117.3  : A  : 3  : 86-36  : RB  : CRDRVE  : Reactor automatically shut down'

:  :  :  :  :  :  :  :  : when one of the scram solenoids l'

:  :  :  :  :  :  :  :  : on lower Control Rod Drive  :

:  :  :  :  :  :  :  :  : Mechanism (CRDM) No. 18 burned :

:  :  :  :  :  :  :  :  : out. During the shutdown, the :

:  :  :  :  :  :  :  :  : o-ring was replaced at the

:  :  :  :  :  :  :  :  : flange of Upper CRDM No. 18. It:

:  :  :  :  :  :  :  :  : could not be determined whether :

:  :  :  :  :  :  :  :  : the solenoid failure was due to :

:  :  :  :  :  :  :  :  : water. Replacement of the scram:

:  :  :  :  :  :  :  :  : solenoids was added to the  :

:  :  :  :  :  :  :  : Preventive Maintenance program. :

1 2 3 4 Reason Method Exhibit G-Instrustionse for F: Forced A-Equipment Failure (Explain) 1-Manual Preparation of Data Entry Sheets S: Scheduled B-Maintenance or Test 2-Manual Scram for Licensee Event Report (LER)

C-Refueling 3-Automatic Scram File (NUREG-0161)

D-Regulatory Restriction 4-Other (Explain)

E-Operator Training & License Examination F-Administrative 5 G-Operational Error (Explain) Exhibit 1 - Same Source H-Other (Explain)

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D DA/RYLAND hhh[ COOPERATlVE . P.O. box 817

• 2615 EAST AVE SO LA CRO (608) 788-4000

\ . JAMES W. TAYLOR General Manager January 7, 19 In reply, please refer to LAC-12036 DOCKET NO. 50-409 Office of Management Information and Program Control U.-S. Nuclear Regulatory Commission Washington, DC 20555

SUBJECT:

DAIRYLAND POWER COOPERATIVE LA CROSSE BOILING WATER REACTOR (LACBWR)

PROVISIONAL OPERATING LICENSE No. DPR-45 MONTHLY OPERATING DATA FOR DECEMBER 1986

REFERENCES:

1) NRC Letter, Reid to Madgett, dated September 19, 1977.

2) NRC Letter, Reid to Madgett, dated December 29, 1977.

Gentlemen:

In accordance with instructions contained in Reference (1) and Technical Specification Amendments contained in Reference (2), we are submitting information concerning operability and availability of the Ln Crosse Boiling Water Reactor (LACBWR) for the Month of December 1986.

Please contact us if there are any questions concerning this report.

incerely, JWT: LSG:sks cc: J. G. Keppler, Regional Administrator, NRC-DRO-III Roby Bevan, LACBWR Project Manager NRC Resident Inspector D. Sherman (ANI Library)

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