ML20203E125

Monthly Operating Rept for Jan 1986

ML20203E125
Person / Time
Site:	La Crosse File:Dairyland Power Cooperative icon.png
Issue date:	01/31/1986
From:	Malin L, Taylor J DAIRYLAND POWER COOPERATIVE
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
LAC-11400, NUDOCS 8604240116
Download: ML20203E125 (8)

Text

I OPERATING DATA REPORT DOCKET NO. 50-409 DATE 02/06/86 COMPLETED BY Loree Malin TELEPHONE 608-689-2331 OPERATING STATUS

1. Unit Name: La Crosse Boiling Water Reactor

2. Reporting Period: 0000, 01/01/86 to 2400, 01/31/86

3. Licensed Thermal Power (MWe ): 165 4.' Nameplate Rating (Gross MW,): 65.3

5. Design Electrical Rating (Net MWe): 50 6.' Maximum Dependable Capacity (Gross MWe ): 50

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

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

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

10. Reasons for Restrictions, If Any:

This Month Yr.-to-Date Cumulative

11. Hours In Reporting Period 744 744 142,467

12. Number Of Hours Reactor Was Critical 503.0 503.0 96,583.9

13. Reactor Reserve Shutdown Hours 0 0 478

14. Hours Generator On-Line 452.1 452.1 89,953.0

15. Unit. Reserve Shutdown Hours 0 0 79

16. Gross Thermal Energy Generated (MWH) 58,069.0 58,069.0 12,517,031.5

17. Cross Electrical Energy Generated (MWH) 18,195 18,195 3,757,404

18. Net Electrical Energy Generated (MWH) 16,812 16,812 3,485,557

19. Unit Service Factor 69.8 60.8 63.1

20. Unit Availability Factor 60.8 60.8 63.2

21. Unit Capacity Factor (Using HDC Net) 47.1 47.1 51.0 22.' Unit Capacity Factor (Using DER Net) 45.2 45.2 48.9

23. Unit Forced Outage Rate 39.2 39.2 9.9

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

Refueling, March 2, 1986, 5-6 weeks

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

26. Units In Test Status (Prior to Commercial Operation): Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION WP-6.8 R

w ___ _._ - _____-_- _ __ __ -_ - _-_ - _ _- __ - __ ___ _ _ ____ __________-____-_ --_- _ __- _ _____ _____ _ __ - ___ __-__ - _____ __- _____

( ,_ _ _ _. _. . _ _ _ _ _ _ _ - _ _ _ _ _ _ _ - _ _ _ - _ _ _ _ _ _ _ - _

t l AVERAGE DAILY UNIT POWER LEVEL .

DOCKET NO. 50-409 UNIT LACBWR DATE 02/06/86 COMPLETED BY L.S. Goodman TELEPHONE 608-689-2331

' MONTH January 1986 DAY AVERACE DAILY POWER LEVEL DAY AVERACE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 46- 17 40 i

2 47 18 44 3 47 19 47 4 42 20 46 5 4 21 46 6 0 22 46 7 0 23 46 8 0 24 40 9 0 25 0 10 0 '26 0 11 0 27 0 12 0 28 0 13 19 29 1 14 28 30 24 15 32 31 29 16 36 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.

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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.- 50-409-UNIT NAME LACBWR DATE 02/06/86 REPORT MONTH January 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 l (Hours) Reason 2 Reactor 3 Report i Code 4 Code 5 Prevent Recurrence 86-01 01-04-86 F 0 A 4 NA CJ PIPEXX A manual reactor shutdown was started when a fitting in the seal inject supply line to Control Rod Drive Mechanism No. 2 separated. The shut-down was terminated at 30%

powe r. The line was iso-lated and repaired.

86-02 01-05-86 F 180.9 A 1 NA RB CRDRVE Plant was shutdown to repair the mechanical seal on Upper Control Rod Drive Mechanism (UCRDM) No. 2, which was leaking seal inject water..

During shutdown, work was I performed on lower control i rod drive mechanisms, the Main Steam Isolation Valve and its bypass valve, facility

changes and Shutdown Con-i denser Valves.

(Continued on next page)

I 1 2 3 4 Reason: Method: Exhibit G-Instructionse F: Forced A-Equipment Failure (Explain) 1-Manual for Preparation of Data S: 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 Examinstion F-Administrative 5 G-Operational Error (Explain) Exhibit 1 - Same Source

. H-Other (Explain)

UNIT SHUTDOWNS AND POWER. REDUCTIONS-DOCKET No, 50-409 UNIT'NAME LACBWR -"'

DATE 02/06/86 REPORT MONTH January 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 86-03 01-25-86 F 111.0 A 1 NA RB- CRDRVE Plant was shutdown to repa'ir the mechanical seal on UCRDM No. 13, which was leaking seal inject water.

I 2 3 4 l Reason: Method: Exhibit G-Instructionse l

F: Forced A-Equipment Failure (Explain) 1-Manual for Preparation of Data S: 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-Administracive 5 G-Operational Error (Explain) Exhibit 1 - Same Source H-Other (Explain) l

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REFUELI_NG INFORMATION REQUEST

1. Name of Facility La Crosse Boiling Water Reactor (LACBWR)

2. Scheduled Date for Next Refueling Shutdown The tentative date for the next refueling shutdoun iEOC-IX) is March 2, 1986.

3. Scheduled Date for Restart Following Refueling The tentatively scheduled date for subsequent reactor startup is approximately April 7, 1986

4. Will Refueling or Resumption of Operation Thereafter Require a Technical Specification Change or Other License Amendment?

If answer is yes, what, in general, will these be?

If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Committee to determine whether any unreviewed safety questions are associated with the core reload Reference 10 CFR Section 50.597 If no such review has taken place, when is it scheduled?

A License amendment vill be needed for the neu control rode which vill be installed.

5. Scheduled Date(s) for Submitting Proposed Licensing Action and Supporting Information.

December 1985

6. Important Licensing Considerations Associated with Refueling, e.g.,

New or Different Fuel Design or Supplies, Unreviewed Design or Performance Analysis Methods, Significant Changes in Fuel Design, New Operating Procedure Some neu control rode vill be utilized.

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' REFUELING INFORMATION REQUEST - (Continued) l-

7. The Number of Fuel Assemblies (a) in the Core and (b)'in the Spent Fuel Pool.

? Core Loading: 72 Fuel Assemblies

• Spent Fuel Storage Pool Loading: 237 Irradiated Fuel Assemblies

8. The Present Licensed Spent Fuel Pool Storage Capacity and the Size of any ,

increase in Licensed Storage Capacity that has been Requested or is i Planned, in Number of Fuel Assemblies 440 Fuel Assemblies

9. The Projected Date of the Last Refueling that can be Discharged to the Spent Fuel Pool Assuming the Present Licensed Capacity L,

1992 i'

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WP-6.8 .-. _ - _ _ _ _ _ _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ - _ - _ _ - _ _ _ _ _ _ - , . _ _ _ _ _ _ _ _ _ _ _ - _ - _ _ - - _ _ _ _

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D COOPERAT/VE

• PO BOX 817

• 2615 EAST AV SOUTH

• LA CROSSE. WISCONSIN 54601 (608) 788 4 000 February 6, 1986 In reply, please refer to LAC-Il400 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 JANUARY 1986

Reference:

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

(2) NRC Letter, Reid to Madgett, dated December 29, 1977 Centlemen:

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

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

Very truly yours, DAIRYLAND POWER COOPERATIVE

,fif fe'ft /h'k James W. Taylor, General Manager l

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

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NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE January 1986 At the onset of the January 1986 reporting period, power generation continued at approximately 94% Reactor Rated Thermal Power (47 MWe-net). The plant is slowly coasting down towards the March 1986 refueling outage.

At 2059 on January 4, a manual reactor shutdown was started when a fitting in the seal inject supply line to Control Rod Drive Mechanism (CRDM) No. 2 separated.

The shutdown was terminated at 30% power. The line was isolated and the fitting replaced. Power was reduced below 25% while control rods were being returned to their operating program. On January 5, the plant was shutdown to repair the mechanical seal on CRDM No.2 due to increased seal water leakage.

On January 6, a Type C leakage test was performed on the Reactor Building Main Steam Isolation Valve (MSIV) and its bypass. The leakage measured varied f rom approximately 40 SCFH to greater than 48 SCFH, which is the top end of the rotameter scale. This leakage rate was above the acceptance criteria. The bypass valve was rebuilt. The MSIV was cycled and greased and its seating adjustments were adjusted. A test with acceptable results was conducted on January 9,1986.

The measured leakage was 14 SCFH. The cumulative Type B and C tests leakage rate was 18.65 SCFH, well within the acceptance criteria of less than 30 SCFH.

During the shutdown, work was also performed on lower CRDMs, facility changes, the IB Shutdown Condenser Condensate Valve, and the 1A Forced Circulation Pump Discharge Valve.

The reactor was taken critical at 1200 on January 11. At 0051 on January 12, the reactor was shutdown due to a short on CRDM No. 6. The lower mechanism was replaced with the spare. At 0537 the reactor was returned to criticality. At 1107, the reactor automatically shutdown when the seal inject supply valve at CRDM No. 2 was being opeued. The seal inject tubing came into contact with a terminal block, blowing 2 fuses, and causing a scram. The fuses were replaced.

The reactor was taken critical at 1420. At 0200 on January 13, the turbine-generator was connected to the DPC grid. A steady state power level of 93% (46 MWe-net) was reached on January 19.

On January 24, a manual reactor shutdown commenced due to seal water leakage f rom C RDM No . 13. The generator was taken off-line at 0310 on January 15, and the reactor was shutdown at 0318. During the shutdown, the mechanical seal on CRDM No. 13 was reworked and work was performed on the lA Shutdown Condenser Steam Inlet Valve and Nuclear Instrumentation Channel 2. The reactor was taken critical at 2129 on January 28.

At 1811 on January 29, the turbine-generator was synchronized to the DPC grid. A reactor power level of 68% (31 MWe-net) was achieved by the end of the reporting period.

t l Significant safety-related maintenance performed during January, in addition to l the outage items mentioned, included replacement of a hose on the 1A High j Pressure Service Water / Alternate Cnre Spray Diesel, the transmitter amplifier for l Safety System Water Level Channel 1, and the drawer for Nuclear Instrumentation Channel 6.

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