ML20154S575

Monthly Operating Rept for Dec 1985

ML20154S575
Person / Time
Site:	La Crosse File:Dairyland Power Cooperative icon.png
Issue date:	12/31/1985
From:	Malin L, Taylor J DAIRYLAND POWER COOPERATIVE
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
LAC-11340, NUDOCS 8604010325
Download: ML20154S575 (9)

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NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE DECEMBER 1985 At the onset of the December 1985 reporting period, power generation continued at approximately 98% Reactor Rated Thermal Power (49 MWe-net).

On about December 11, the slow coastdown towards the March 1986 refueling outage commenced.

At 0605 on December 14, 1985, the l A Forced Circulation Pump Discharge Valve closed. Reactor power was decreased to approximately 30% power and the valve waa reopened at 0637. Power escalation then began and continued until December 17, when approximately 97% power (47 MWe-net) was reached. Power coasted down for the remainder of the month, with 94% power (46 MWe-net) being produced on December 31.

During 1985, a new LACBWR record was set for annual electrical generation. The i

net electrical energy generated for 1985 was 322,909 MWH, the gross was 343,598 MWH.

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 Decemeber 9 was 5.63 SCFE. Following adjustment of the inner door upper handwheel shaf t mechanical seal, a second test was completed on December 16, with a leakage rate of 2.33 SCFH.

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

Test Leakage (SCFH)

Electrical Penetrations ID, IE, 2-6:

ID 0.055 IE 0.028 2A 0.009 2B 0

2C 0.009 2D 0

2E 0

3

'0.029 4

0.206 5

0 6

0 Electrical Penetrations IB:

lA 0.0022 IB 0.0011 1C 0.0027 ID 0.0011 IE 0.0016 2A 0.0027 1

2B 0.0022 2C 0.0055 8604010325 B51231 y

PDR ADOCK 05000409 1/g R

PDR I

r NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE - CONTINUED

-Test Leakage (SCFH) 2D 0.0006 2E 0.0016 2F-0.C022 Electrical Penetrations 1B:

1 0.0070 2

0 3

0.0074 4

0.0025 5

0 6

0 7

0.0016 8

0.0022 9

0 10 0.0006 Electrical Penetrations 1C:

1 0.0028 2

0 3

0.0006 4

0.0017 5

0.0011

~6 0.0006 7

0.0034 8

0.0023 9

0.0006 10 0.0006 11 0.0011 12 0.0011-13 0

14 0.0023 15 0.0011 16 0

17 0

18 0.0017 19 0.0006 20 0.0051 21 0.0006 22 0.0011 23 0.0011 24 0.0011 25 0.0023 Electrical Penetrations 1A:

l l

3 0.00098 l_

4 0

l 5

0.0016 l

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o NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE - CONTINUED On December 31, the l A High Pressure Service Water / Alternate Core Spray Diesel Pump malfunctioned. Its fuel transfer pump was replaced and a satisfactory test performed. The positive high voltage power supply for Nuclear Instrumentation Channel No. 3 failed on December' 22.

The drawer was replaced and a surveillance test performed. No other major safety-related maintenance was performed during the month of December 1985.

OPERATING DATA REPORT DOCKET No. 50-409 DATE 01/07/86 COMPLETED BY Loree Malin TELEPHONE 608-689-2331 OPERATING STATUS NOTES:

1. Unit Name: La Crosse Boiling Water Reactor

2. Reporting Period: 0000, 12/01/85 to 2400, 12/31/85

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 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.-t o-Da t e Cumulative

11. Hours In Reporting Period 744 8,760 141,723

12. Number Of Hours Reactor Was Critical 744 7,757.2 96,080.9

13. Reactor Reserve Shutdown Hours 0

0 478

14. Hours Generator On-Line 744 7,597.6 89,500.9

15. Unit Reserve Shutdown Hours 0

0 79

16. Gross Thermal Energy Generated (MWH) 115,521.6 1,111,560.7 12,458,962.6

17. Gross Electrical Energy Generated (MWH) 36,271 343,598 3,739,209

18. Net Electrical Energy Generated (MWH) 34,350 322,909 3,468,745

19. Unit Service Factor 100.0 86.7 63.2

20. Unit Availability Factor 100.0 86.7 63.2

21. Unit Capacity Factor (Using MDC Net) 96.2 76.8 51.0

22. Unit Capacity Factor (Using DER Net) 92.3 73.7 49.0

23. Unit Forced Outage Rate 0

3.1 9.7

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 1: ate of Startup:

NA

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

Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION WP-6.8

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-409 UNIT LACBWR DATE 01/07/86 COMPLETED BY L.S. Goodman TELEPHONE 608-689-2331 MONTH ^

December 1985' DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 49 17' 47 2

48 18 47 3

48 19 47 4

49 20 47 5

49 21 46 6

49 22 46 7

49 23 47 8'

49 24 47 9

49 25

~47 10 49 26 47 11 49 27 47 12 48 28 46 l

13 48 29 46 l

14 27 30 46 i

15 32 31 46 16 41 INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the reporting month.

Compute to the netrest whole megawatt.

WP-6.8

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO..

50-409-UNIT NAME LACBWR DATE 'O1/07/86 REPORT. MONTH December'1091 COMPLETED BY L.S. Goodman -

TELEPHONE 608-689-2331 Method of Licensee Cause & Corrective Duration Shutting Down Event.

System Com ponent Action to No.

Date Ty pel (Hours)

Reason 2 Reactor 3 Re port ' # '

Code 4 Code 5 Prevent Recurrence 85-15 12-14-85 F

0 A

4 NA CB INSTRU

' Power decreased when the 1A Forced Circulation Pump Dis-charge Valve closed.

I 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-Admi nistrative 5

G-Operational Error (Explain)

Exhibit 1 - Same Source H-Other (Explain)

REFUELING 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 (ECC-IX) is March 2, 1986.

3.

Scheduled Date for Restart Following Refueling The tentatively scheduled dace for subsequent reactor startup is apyroximately 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 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 50.59?

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

A license amendment vill be needed for the neu control rode uhich vill be installed.

-5.

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

December 1985 6.

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

New or Dif ferent Fuel Design or Supplies, Unreviewed Design or Performan::e Analysis Methods, Significant Changes in Fuel Design, New Operating Procedure Some neo control rode vill be utilized.

WP-6.8 - -

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e.

REFUELING INFORMATION REQUEST - (Continued) j 7.

The' Number of Fuel Assemblies T

~

(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 Planned, in Number of Fuel Assemblies 440 Fuel Assemblies i

9.

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

'1992

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4 1

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P WP-6.8 i

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[k COOPERAT/VE

• PO box 817 2615 EAST AV SOUTH. LA CROSSE. WISCONSIN 64601 January 7, 1986 (608) 78540cc In reply, please refer to LAC-11340 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 DECEMBER 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 December 1985.

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

Very truly yours, DAIRYLAND POWER COOPERATIVE

/W 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)

INPO I