ML20207F782
| ML20207F782 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 09/30/1986 |
| From: | Malin L, Taylor J DAIRYLAND POWER COOPERATIVE |
| To: | NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| LAC-11874, NUDOCS 8701060227 | |
| Download: ML20207F782 (10) | |
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OPERATING DATA REPORT DOCKET NO. 50-409 DATE 10/08/86 COMPLETED BY Loree Malin TELEPHONE 608-689-2331 OPERATING STATUS NOTES:
- 1. Unit Name: L3 Crosse Boiling Water Reactor
- 2. Reporting PE iod: 0000, 09/01/86 to 2400, 09/30/86
- 3. Licensed Thansal 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 MWe ):
- 10. Reasons for Restrictions, if Any:
This Month Yr.-to-Date Cumulative
- 11. Hours In Reporting Period 720 6.551 148,274
- 12. Number Of Hours Reactor Was Critical 244.8 3.110.9 99,191.8
- 13. Reactor Reserve Shutdown Hours 39.2 39.2 517.2
- 14. Hours Generator On-Line 182.6 2,773.8 92,274.7
- 15. Unit Reserve Shutdown Hours 41.5 41.5 120.5
- 16. Gross Thermal Energy Generated (MWH) 18,864.5 377,460.2 12,836,422.8
- 17. Gross Electrical Energy Generated (MWH) 5,322 115,110 3,854,319
- 18. Net Electrical Energy Generated (MWH) 4,389 104,790 3,573,535
- 19. Unit Service Factor 25.4 42.3 62.2
- 20. Unit Availability Factor 31.1 43.0 62.3
- 21. Unit Capacity Factor (Using MDC Net) 12.7 33.3 50.2
, 22. Unit Capacity Factor (Using DER Net) 12.2 32.0 48.2
- 23. Unit Forced Outage Rate 73.1 42.8 11.2 l 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
Refueling Outage, March 15, 1987, 6 weeks
- 25. If Shut Down At End Of Report Period, Estimated Date of Startup: October 9,1986 i
- 26. Units In Test Status (Prior to Commercial Operation): Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION ,.
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! WP6.8 8701060227 E60930 /
PDR R
ADOCK 05000409 I ll i PDR 1
E AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-409 UNIT IACBWR DATE 10/08/86 s
CGtPLETED BY ' L.S. Goodman TELEPHONE ~ 608-689-2331 MONTH Septenber 1986~
- D AY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 0 17 33' 2 0 18 7 3- 0 19 0
'4 0 20 0 5 0 21 16 6 0 22 30 7 0 23 37 8 0 24 27 9 0 25 0 10 0 26 0 11 0 27 0 12 0 28 0 13 0 29 0 14 6 30 0 15 20 31 NA 16 29 INSTRUCTIONS On this format, list the average daily unit power level in HWe-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 10/08/86 REPORT MONTH SEPTEMBER 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 # Code 4 Code 5 Prevent Recurrence 1
86-21 07/16/86 F 322.8 A 3 86-21/ ED GENERA The outage which began 86-22 07/16/86 continued. Refer to the July 1986 report for a discussion of the cause.
Major activities performed during September included installing the reactor vessel head, performing hydrostatic and other Technical Specifi-cation tests, tightening water level probe connections, setting Forced Circulation Pumps speeds, reinstalling lower control rod drive mechanisms, work on Nuclear Instrumentation and replace-ment of the Manual Depressurization System valves nitrogen supply regulator.
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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 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-Ol61)
E-Operator Training & License Examination "
5 4 F-Administrative ..-
Exaibit'l - Same Source G-Operational Error 1(Explain)
H-Other (Explain) -f C '
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53.3 UNIT SHUTDOWNS AND POWER REDUCTION- [
- ' . DOCKET NO, 50-409 UNIT. NAME LACBWR .
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DATE- 10/08/86 REPORT MONTH SEPTEHBER 1986 CQ4PLETED BY L.S. Goodman TELEPHONE 608-689-2331
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Method of Licensee -
Cause & Corrective Duration Shutting Dcwn Event System Cenpouent Action to No. Date Type l ,(Hours) Reason 2 Reactor 3 Report # Code 4 Codc5 Prevent Recurrence 86-22 09/18/86 F 69.0 A 3 86-29 CB VALVEX The reactor automatically shut down due to low re-circulation flow when the IB Forced Circulatioa Pump tripped due to loss of seal water when its seal inject supply valve closed. The valve controller was cleaned and overhauled. During this outage work was also performed on Nuclear Instrumentation.
86-23 09/24/86 S/F 145.5 F/B 1 NA RB CRDRVE The plant was manually shutdown because system load demand was low and in pre-paration for performance of maintenance on Upper Control Rod Drive Mechanisms (UCRDM).
UCRDM No. 18 was lowered due to a flange leak. Work was also performed on Nuclear 1 2 3 4 Reason: Method: Exhibit G-Instructionse F: Forced A-Equipment Failure (Explein) 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)
y UNIT SHUTDOWNS AND POWER REDUCTIONS .
DOCKET No. 50-409 UNIT'NAME LACBWR ,
-DATE 10/08/86 REPORT MONTH SEPTEMBER-1986 COMPLETED BY L.S. Goodman TELEPHONE 608-689-2331 Method'of Licensee Cause &' Corrective Duration Down, Event System Component Action to Shutting ~3-No. Date -
Type l (Hours) Reason2 , Reactor Report # Code 4 Code 5 Prevent Recurrence
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e 86-23 , 09/24/86 S/F 145.5 F/B - 1 - NA .RB CRDRVE Instrumentation, the main continued , ,
3 generator and 5o.'I water level probe.
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1 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 (Explaf n)
REFUELIriG INFORMATION REOUEST
- 1. Name of Facility La Crosse Boiling Water Reactor (LACBWR)
- 2. Scheduled Date for Next Refueling Shutdown The tentative date for the next refueting shutdown (EOC-X) is March 15, 1987.
- 3. Scheduled Date for Restart Following Refueling l
The tentatively scheduled date for subsequent reactor startup is approximately April 26, 1987
- 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?
No license amendment vitt be needed for refueling.
The retaod plan will be reviewed by the Safety Review Committee prior to refueting.
- 5. Scheduled Date(s) for Submitting Proposed Licensing Action and Supporting Information.
NA
- 6. Important Licensing Considerations Associated with Refueling, e.g. ,
New or Dif ferent Fuel Design or Supplies, Unreviewed Design or Performance Analysis Methods, Significant Changes in Fuel Design, New Operating Procedure None 1
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REFUELING INFORMATION REQUEST - (Continued)
- 7. The Number of Fuel Assemblies 1 (a) in the Core and (b) in the Spent Fuel Pool.
Core Loading: 72 Fuel Assemblies Spent Fuel Storage Pool Loading: 261 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
- 9. The Projected Date of the Last Refueling that can be Discharged to the Spent Fuel Pool Assuming the Present Licensed Capacity 1993 l
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D DA/RYLAND hh[M[ COOPERATIVE P O BOX 817 2615 EAST AVE SO
- LA CROSSE.
(608) 788 4 000 JAMES W. TAYLOR October 8, 1986 General Manager In reply, please t refer to LAC-Il874 DOCKET NO. 50-409 l
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 SEPTEMBER 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 n information concerning operability and availability of the La Crosse Boili~ng Water Reactor (LACBWR) for the Month of September 1986.
Please contact us if there are any questions concerning this report.
Sincerel he 1
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 M
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NARRATIVE
SUMMARY
OF OPERATING EXPERIENCE SEPTEMBER 1986 ;
I At the onset of the September 1986 reporting period, the plant was in the pipe repair outage which commenced July 16, 1986.
At 2050 on September 9, the reactor was taken critical. At 1218 on September 10, the reactor was shut down to perform a planned test of Forced Circulation Pump speed at operating temperature. At 1405 on September 10, the reactor was taken critical again. At 1416 a reactor scram occurred due to a spike on wide range Nuclear Instrumentation Channel 5. The range switch was replaced and the instrument drawer balance was adjusted. The reactor was taken critical at 1918 on September 10. At 1925, the reactor scrammed on high flux on wide range Nuclear Instrumentation (N1) Channel 6. At low power, a trip occurs if either Channel 5 or 6 exceeds a set percentage of scale on any power range. The operator's attention was diverted by the failure of NI Channel 2 and Channel 6 reached its trip point before the operator upscaled the range.
Work was performed on the Nuclear Instrumentation. New instrumentation is on order and is planned to be installed during the 1987 refueling outage.
The reactor was taken critical at 0500 on September 13. At 1658, the reactor automatically shut down due to a high water level signal generated due to swell when the turbine stop valve was onened later in the startup procedure than required. The reactor was returned to criticality at 2013 on September 13. At 1050 on September 14, the turbine-generator was connected to the CPC grid.
Power escalation continued until September 15 with approximately 52% power (22 MWe-net) being achieved. Power was then reduced to about 38% (14 MWe-net) for cleaning of the condenser water boxes.- Escalation recommenced on September 15 following the cleaning.
At 0505 on September 18, the reactor automatically shut down from 73.5% power (36 MWe-net) due to low total recirculation flow when the IB Forced Circulation Pump tripped due to lack of seal water when its seal inject supply valve closed. The valve controller was cleaned and overhauled. The reactor was taken critical at 1905 on September 19.
At 2334 on September 19, the reactor was manually shut down from low power. A spike had occurred on N1 Channel 6 which generated a scram alarm, but not a reactor trip. The reactor was shut down to investigate. Work was performed on the Nuclear Instrumentation. It was demonstrated repeatedly that the alarm annunciated at a slightly lower voltage than the scram and that in all cases, the reactor trip occurred below the Technical Specification limit. The drawer was replaced.
At 1305 on September 20, the reactor was taken critical. At 0207 on September 21, the turbine-generator was connected to the DPC grid. Power was escalated until September 23, when approximately 79% power (37 MWe-net) was achieved.
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NARRATIVE
SUMMARY
OF OPERATING EXPERIENCE - CONT'D On September 24, power was decreased to 64% (27 MWe-net) for cleaning of condenser water boxes.
Leakage had been noted from the Upper Control Rod Drive Mechanism flanges in positions 2 and 18. It was decided to commence a plant shutdown on September 24, since the load demand was low and the plant not needed, rather than waiting until September 26 to shut down for maintenance, as otherwise would have been done. The turbine-generator was disconnected from the DPC grid at 2230 on September 24, and the reactor was shut down at 0048 on September 25.
Work commenced on the Upper Control Rod Drive Mechanism on September 29. The plant remained shut down for the rest of the reporting period.
Major safety-related maintenance not already mentioned conducted during September 1986 included installation of the reactor vessel head, work on water level probes, installation and removal of Lower Control Rod Drive Mechanisms, and replacement of the Manual Depressurization System valves nitrogen supply regulator.
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