ML20207B991

Monthly Operating Rept for Apr 1986

ML20207B991
Person / Time
Site:	La Crosse File:Dairyland Power Cooperative icon.png
Issue date:	04/30/1986
From:	Goodman L, Malin L, Taylor J DAIRYLAND POWER COOPERATIVE
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
LAC-11579, NUDOCS 8607210045
Download: ML20207B991 (6)

Text

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1' NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE April 1986 l

During the month of April 1986, the refueling outage which commenced March 7, 1986 continued.

1 Major safety-related work performed during the month included refueling the reactor, installation of the core spray bundle and the reactor vessel head, i

and performance of hydrostatic tests. The inboard Alternate Core Spray Valve i

was disassembled and manually lifted for the Inservice Inspection Test. The 4

Alternate Core Spray Valves then did not pass their Type C leakage test. Both valves were disassembled, cleaned and lapped. See table below for the leak rates measured. The Retention Tank Pump Discharge Valve was replaced as planned. Prior to removal of the old valve, a leak test was performed for information purposes. Excessive leakage was measured.

j Other major work performed included replacement of the IC Static Inverter and j

Generator Plant Battery and Charger. A portion of the Shutdown Condensor vent line was upgraded. Two lines were relocated from the High Pressure Core Spray suction line from the Overhead Storage Tank to the Containment Building Spray line. The High Pressure Core Spray Pumps suction and discharge valves were replaced. Work was performed on Upper Control Rod Drive Mechanism No. 2 due to flange leakage during the first hydrostatic test. Work was also performed

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on lower Control Rod Drive Mechanisms. A plugged oil filter was replaced on the IB High Pressure Service Water (HPSW) Diesel and the fuel oil was filtered. The starting batteries for 1B HPSW Diesel were moved, as an Appendix R modification. Preventive maintenance, calibrations, and testing I

continued during the month of April.

Type B and C leakage tests conducted during April 1985 were as follows:

4 Penetration Leakage (SCFH) 4 Personnel Airlock 4.36 a

Main Steam Penetration 0.036 Feedwater Penetration 0.022

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Heating Steam & Condensate Penetration 0.02 1

Freight Door 0.015 Vacuum Breaker 1 0.01 Vacuum Breaker 2 0.012 Containment Spray Handwheel 0.001-Ventilation Discharge Dampers 0.231 Ventilation Inlet Dampers 0.136 Reactor Vent Header Valve 0.0 i

Heating Steam Check Valve 0.0 Heating Steam Condensate Return Valve 0.0 Station Air Valve 0.0 Main Steam Isolation & Bypass Valve 0.22 Feedwater Check Valve 0.125 i

Decay Heat Blowdown Valve 0.026 8607210045 860430 DR ADOCK 0500 9

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Penetration Leakage (SCFH)

Shutdown Condenser Vent to Offgas 0.0 Primary Purification Resin Sluice Valves 0.0 Alternate Core Spray Check Valves

> 48 3.67 11.0 15.0

> 48 11.0 11.0 1.31 Reactor Coolant Sample Supply Valve 0.0 Containment Building Drain Valve 0.0 Demineralized Water Valve 0.240 Seal Inject Makeup Valve 0.04 Control Air Valve 0.0 HPSW Containment Isolation' Valve 0.799 FESW Ion Exchanger Resin Sluice Line 0.0 Containment Isolation Valves Retention Tank Pump Valve

> 48 0.0 Reactor Cavity Purge Air Valve 5.08 0.096 Containment Atmosphere Sampling 0.006 System Suction Containment Atmosphere Sampling 0.06 System Discharge Reactor Coolant Sample System Suction 1.

Isolation Valve 84-25-002 0.0 2.

Suction Line Penetration 0.002 Reactor Coolant Sample System Discharge 1.

Check Valve 84-26-004 0.0 2.

Isolation Valve 84-25-007 0.023

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a OPERATING DATA REPORT DOCKET NO.

50-409 DATE 05/07/86 COMPLETED BY Loree Malin TELEPHONE 608-689-2331 OPERATING STATUS NOTES:

1. Unit Name: La Crosse Boiling Water Reactor

2. Reporting Period: -0000, 04/01/86 to 2400, 04/30/86

3. Licensed Thermal Power (MW ):

165 t

4. Nameplate Rating (Gross MW ):

65.3 e

5. Design Electrical Rating (Net MW ):

50 e

6. Maximum Dependable Capacity (Gross MW ):

50 e

7. Maximum Dependable Capacity (Net MW ):

48 e

8. If Char ges Occur in Capacity Ratings (Items 3 Through 7) Since Last Report, Give Reasons :

9. Power Level To Which Restricted, If Any (Net MW ):e

10. Reasons for Restrictions, If Any:

l This Month Yr.-to-Date Cumulative 3

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11. Hours In Reporting Period 719 2,879 144,602

12. Number Of Hours Reactor Was Critical 0

1,340.8 97,421.7

13. Reacto r Reserve Shutdown Hours 0

0 478

14. Hours denerator On-Line 0

1,289.9 90,790.8

15. Unit Reserve Shutdown Hours 0

0 79

16. Gross Thermal Energy Generated (MWH) 0 176,225.5 12,635,188.1

17. Gross Electrical Energy Generated (MWH) 0 54,826 3,794,035

18. Net Electrical Energy Generated (MWH)

- 615 50,339 3,519,084

19. Unit Service Factor 0

44.8 62.f-

20. Unit Availability Factor 0

44.8 62.8

21. Unit Capacity Factor (Using MDC Net) 0 36.4 50.7

22. Unit Capacity Factor (Using DER Net) 0 35.0 48.7 l

23. Unit Forced Outage Rate 0

18.5 9.8

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

None

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

May 6, 1986

26. Units In. Test Status (Prior to Commercial Operation):

Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION 1

l WP-6.8 i

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.., _,, _ _ _. _,.... _...,..... _., _.. - _.... ~,... - -..., _. _ -.,., -... _.-.. -

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-409 UNIT LACBWR a

DATE 05/07/86 COMPLETED BY L.S. Goodman TELEPHONE 608-689-2331 MONTH April 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 0

17 0

2 0

18 0

3 0

19 0

4 4

0 20 0

5 0

21 0

6 0

22 0

7 0

23 0

8 0

24 0

9 0

25 0

10 0

26 0

11 0

27 0

12 0

28 0

13 0

29 0

14 0

30 0

15 0

31 NA 16 0

INSTRUCTIONS 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.

WP-6.8 j

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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-409 UNIT NAME LACBWR DATE 05/07/86 REPORT MONTH April 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 Type (Hours)

Reason 2 Reactor 3 Report #

Code 4 Code 5 Prevent Recurrence l

86-04 03-07-86 S

719.0 C

3 86-06 EB CKTBRK Refer to March 1986 report for the discussion of the scram which occurred during the shutdown for this re-fueling outge. The refueling outage continued.during the month of April.

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1 2

3 4

Reason:

Method:

Exhibit G-Instructionse F: Forced A-Equipment Failure (Explain) 1-Manual for Preparation of Data St Scheduled B-Maintenance or Test 2-Manual Scram Entry Sheets for Licensee C-Refueling 3-Automatic Scram Event Report (LER) File D-Regulatory Restriction 4-Other (Explain)

(NUREG-0161)

E-Operator Training & License Examination F-Administrative 5

G-Operational Error (Explain)

Exhibit 1 - Same Source H-Other (Explain)

O' D DA/RYLAND h

[k COOPERAT/VE. pO Box 817 2615 EAST AV SOUTH LA CROSSE. WISCONSIN 54601 (608) 788 4 000 May 7, 1986 In reply, please refer to LAC-11579 DOCKET NO. 50-409 Office of Management Information and Program Control U. S. Nuclear Regulatory Commission Washington, D. C.

20555

SUBJECT:

DAIRYLAND POWER COOPERATIVE LA CROSSE BOILING WATER REACTOR (LACBWR)

PROVISIONAL OPERATING LICENSE NO. DPR-45 MONTHLY OPERATING DATA REPORT FOR APRIL 1986

Reference:

(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 availsbility of the La Crosse Boiling Water Reactor (LACBWR) for the Month of April 1986.

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

Very truly yours, DAIRYLAND POWER COOPERATIVE

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James W. Taylor, General Manager JWT:LSG:sks cc:

J. G. Keppler, Regional Administrator, ;aC-DRO III John Stang, LACBWR Project Manager NRC Resident Inspector D. Sherman (ANI Library)

INPO Y y

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