ML20141F279

Monthly Operating Rept for Oct 1985

ML20141F279
Person / Time
Site:	La Crosse File:Dairyland Power Cooperative icon.png
Issue date:	10/31/1985
From:	Goodman L, Malin L, Taylor J DAIRYLAND POWER COOPERATIVE
To:	NRC
References
CON-LAC-11231 NUDOCS 8601090116
Download: ML20141F279 (8)

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NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE OCTOBER 1985 At the onset of the October reporting period, power generation continued at approximately 97% Rated Thermal Power (48 MWe-net)

At 2030 on October 7, a power de-escalation to approximately 55% power was commenced to allow cleaning of the main condenser tubes. Following condenser cleaning, power was escalated with 97% power being achieved on October 12.

At 0956 on October 22, 1985, the reactor automatically shutdown due to a loss of load transient when a breaker in the switchyard tripped open during maintenance.

The reactor was returned to critical at 0253 on October 23. At 0507 an apparent malfunction of the reactor protective system occurred and the reactor was manually shutdown. Troubleshooting determined the problem was in the oscillator circuit in the trip unit portion of the Nuclear Instrumentation Channel 6 and that there was no malfunction of the reactor protection system. During the shutdown the 1A Fcreed Circulation Pump flow transmitter to Safety System Channel 2 was reworked.

At 1908 on October 24, the reactor was taken critical. The turbine-generator was connected to the DPC. grid at 1245 on October 25. At 2125 on October 26, the reactor automatically shutdown due to a momentary short in the control rod drive gas pressure circuit, believed to be caused by water leaking from the mechanical seal on Upper Control Rod Drive Mechanism No. 2. Seal water to CRDM No. 2 is being carefully controlled to limit leakage to the normal leakoff pathway.

At 0410 on October 27, the reactor was taken critical. At 1750, the turbine-generator was synchronized to the DPC grid. A power level of 97% was achieved by the end of the reporting period.

A Type B test was performed with satisfactory results on the emergency airlock on October 14, 1985. The measured leakage was 0.259 SCFH.

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8601090116 851031 PDR ADOCK 05000409 h

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OPERATING DATA REPORT DOCKET No. 50-409 DATE 11/07/85 COMPLETED BY Loree Malin TELEPHONE 608-689-2331 OPERATING STATUS NOTES:

1. Unit Name: La Crosse Boiling Water Reactor

2. Reporting Period: 0000, 10/01/85 to 2400, 10/31/85

3. Licensed Thermal Power (MWt ): 165

4. Nameplate Rating (Gross MWe ): 65.3

5. Design Electrical Rating (Net MW e): 50

6. Maximum Dependable Capacity (Gross MWe ): 50

7. Maximum Dependable Capacity (Net MWe )* 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 MW ):e

10. Reasons for Restrictions, If Any:

This Month Yr.-to-Date Cumulative

11. Hours In Reporting Period 745 7,296 140,259

12. Number Of Hours Reactor Was Critical 682.2 6,293.2 94,616.9 13.' Reactor Reserve Shutdown Hours 0 0 478

14. Hours Generator On-Line 648.8 6,133.6 88,036.9

15. Unit Reserve Shutdown Hours 0 0 79

16. Gross Thermal Energy Generated (MWH) 94,151.8 885,510.0 12,232,911.9

17. Gross Electrical Energy Generated (MWH) 29,187 272,589 3,668,200

18. Net Electrical Energy Generated (MWH) 27,408 255,719 3,401,555

19. Unit Service Factor 87.1 84.1 62.8

20. Unit Availability Factor 87.1 84.1 62.8

21. Unit Capacity Factor (Using MDC Net) 76.6 73.0 50.5

22. Unit Capacity Factor (Using DER Net) 73.6 70.1 48.5

23. Unit Forced Outage Rate 12.9 3.8 9.8

25. 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 GPERATION WP-6.8

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-409 UNIT LACBWR DATE 11/07/85 COMPLETED BY L.S. Goodman TELEPHONE 608-689-2331 MONTH October 1985 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 48 17 49 2 48 18 49 3 48 19 49 4 48 20 49 5 48 21 48 6 48 22 20 7 47 23 0 8 26 24 0 9 27 25 6 10 28 26 24 l 11 37 27 2 12 46 28 27 13 48 29 37 14 48 30 46 15 49 31 48 16 49 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

UNIT SHUTDOWNS AND POWER REDUCTICNS DOCKET NO. 50-409 ,

UNIT NAME LACBWR DATE 11/07/85 REPORT MONTH October 1985 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 # Code 4 Code 5 Prevent Recurrence 85-10 10-07-85 S 0 H 4 NA HC HTEXCH Power was reduced to allow cleaning of condenser tubes.

85-11 10-22-85 F 74.8 G 3 85-17 EA CKTBRK Reactor automatically shut-down during loss of load transient caused when a switchyard worker bumped the emergency trip level on the 69 kv tie line breaker during maintenance. The trip lever was removed. During the i reactor startup on 10/23/85 an apparent malfunction of the reactor protective system occurred and the reactor was manually shutdown. Trouble-shooting determined the

, problem was in the oscillator circuit in the trip unit por-tion of Nuclear Instrumenta-tion Ch. 6 and that there was no man 1 function of the 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 Examination F-Administrative 5 G-Operational Error (Explain) Exhibit 1 - Same Source H-Other (Explain)

7 UNIT SHUTDOWNS'AND POWER REDUCTIONS' l DOCKET Noi 50-409 l

UNIT NAME LACBWR DATE 11/07/85 REPORT MONTH October 1985 COMPLETED BY L.S. Goodman TELEPHONE 608-689-2331 l

Method of Licensee Cause & Corrective

, Juration Shutting Down Event System Component Action to No. Date Type l (Hours) Reason 2 Reactor 3 Report # Code 4 Code 5 Prevent Recurrence 1

85-11 10-22-85 F 74.8 G 3 85-17 EA CKTBRK reactor' protective system.

, (CONTINUED) During the shutdown, work was also performed on the 1A Forced Circulation flow

! transmitter to Safety System Ch. 2.-

l 85-12 10-?6-85 F 21.4 A 3 85-19 RB CRDRVE Reactor automatically shut-

! down due to a momentary short l in the control rod drive (CRD) gas pressure circuit I

believed to. be caused by water leaking from the mechanical seal on upper CRD mechanism No. 2. Seal water to CRDM No. 2 is being carefully controlled to limit leakage to the normal leakoff pathway.

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 Examination F-Administrative 5 G-Operational Error (Explain) Exhibit 1 - Same Source

( H-Other (Explain) l l

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REFUELING IN10 ,R$ TION REQUESJ

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 (EOC-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 Thereaf ter Require a Technical Specification Change ~ or Other License Amendment?

If answer is yes, what, in reneral, 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 50.59?

If no such review has taken place, when is it scheduled?

A License' amendment vitt be needed for the neu control rode which vitt be instatted.

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

November 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 new control rode ulti be utilized.

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REFUELING INFORMATION REQUEST - (Continued) l .7. The Number of Fuel Assemblies j .-

(a) in the Core and l;

(b) in the Spent Fuel Pool.

Core Loading: 72 Fuel Assemblies Spent Fuel Storage Pool Loading: 237 Irradiated Fuel Assemblies l

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l 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 Planned, in Number'of Fuel Assemblies j 440 Fuel Assemblies l

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

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D DA/RYLAND h [k COOPERAT/VE P.o box 817 26is EAST AV SOUTH . LA CROSSE WISCONSIN 54601 November 7, 1985 (608) 788 4 000 In reply, please

. refer to LAC-11231 DOCKET NO. 50-409 Office of Maaagement 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 OCTOBER 1985

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 availability of the La Crosse Boiling Water Reactor (LACBWR) for the Month of October 1985.

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

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Very truly yours,

DAIRYLAND POWER COOPERATIVE l

j s James W. Taylor, General Manager 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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