ML20138B555
| ML20138B555 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 09/30/1985 |
| From: | Malin L, Taylor J DAIRYLAND POWER COOPERATIVE |
| To: | NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| LAC-11173, NUDOCS 8512120330 | |
| Download: ML20138B555 (8) | |
Text
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l NARRATIVE
SUMMARY
OF OPERATING EXPERIENCE SEPTEMBER 1985 Power generation continued at approximately 97% Reactor Rated Thermal Power (46 MWe-net) at the beginning of the September reporting period.
On September 9, 1985 at 0220, reactor power decreased from 96% to 62%, when the 1A Forced Circulation ? ump Discharge Valve closed due to a spurious high differential loop temperature signal. Power was manually reduced below 50%. Two potentiometers were replaced in the differential temperature unit. The discharge valve was reopened and power was escalated, with 96% power being reached on September 12.
At 1555 on September 14, the reactor scrammed from 96% power. During maintenance on a recorder, the technician caused a short which blew Fuse 32-1, which supplies some control room instrumentation. One of the signals de-energized was feedwater flow. This caused the Reactor Water Level control system to increase the Reator Feed Pump speed to increase feedwater flow. The reactor scrammed on high water level. The fuse was replaced.
At 2317 on September 14, the reactor was taken critical. The turbine-generator was connected to the grid at 0945 on September 15. Power was escalated, with approximately 97% power achieved on September 18. Power generation continued at this level for the remainder of the reporting period.
1 8512120330 850930 PDR ADOCK 05000409 R PDR N
'lI
OPERATING DATA REPORT I
DOCKET NO. 50-409 DATE 10/03/85 COMPLETED BY Loree Malin TELEPHONE 608-689-2331 OPERATING STATUS NOTES:
- 1. Unit Name: La Crosse Boiling Water Reactor
' 2. Reporting' Period: 0000, 09/01/85 to 2400, 09/30/85
- 3. Licensed Thermal Power (MWe): 165
- 4. Nameplate Rating-(Gross.MW ): 65.3
- 5. Design Electrical Rating (Net MW,): 50
-6. Maximum Dependable Capacity (Gross MW ): 50 7.; Maximum Dependable . Capacity (Net MW,): 48 I
- 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 6,551 139,514
- 12. Number Of Hours Reactor Was Critical 712.6 5,610.9 93,934.6
- 13. Reactor Reserve' Shutdown Hours 0 0 478 14.' Hours Generator On-Line 702.2 5,484.8 87,388.1
- 15. Unit Reserve Shutdown Hours O. 0= 79
- 16. Gross' Thermal Energy Generated (MWH) 106,305.6 791,358.3 12,138,760.1
-17. Gross-Electrical Energy Generated (MWH). 32,624 243,402 3,639,013
- 18. Net Electrical Energy Generated (MWH) 30,718 228,311 3,374,147
- 19. Unit Service Factor 97.5- 83.7 62.6
- 20. Unit. Availability Factor 97.5 83.7 62.7
'21.-Unit Capacity Factor (Using MDC Net) 88.9 72.6 50.4
- 22. Unit-Capacity Factor (Using DER Net)- 85.3 69.7 48.4
- 23. Unit Forced Outage Rate' 2.5 2.6 9.8 I
'24. Shutdowns Scheduled Over Next. 6. Months (Type, Date, and Duration of Each):
' Refueling, March 2, 1986, 5-6 weeks 1
A.
- 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
. . . _ . ~ . . . . . . - - . _ , - . . - - . . - . -.
W
.> ' AVERAGE DAILY UNIT POWER LEVEL
, DOCKET NO. 50-409 i-
- ~
UNIT LACBWR' DATE 10/03/85 ,
t COMPLETED BY L.S . ' Goodman TELEPHONE 608-689-2331 MONTH: September 1985 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL
, (MWe-Net) (MWe-Net).
i d~
1 46 17 - 40 4
2 14 6 18 46
}
4 3 46- 19 47
[ 4 46 20 47 5- -46 21 47 6 46 22 47 7 46 23 48 L 8- 46 24 48 l-9 22 - 25 48-
- 10 30 26 48 11 41 27 48 12 45 28 48 1-13 47 29. 48
.t 14 31 30 48
}
15 12 31 NA 4 ,
16 29 4
- INSTRUCTIONS 4
On titistformat, list the' average daily unit . power '1evel in MWe-Net for each day in ithe. reporting month.' Compute to the nearest whole megawatt.
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, WP-6.8
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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET No. 50-409
, UNIT NAME LACBWR DATE 10/03/85 REPORT MONTH September 1985 COMPLETED BY L.S. Goodman TELEPHONE 608-689-2331 4
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 85-8 09-09-85 F 0 A 4 NA CB INSTRU Power decreased from 96% to 1
62% when the 1A Forced Cir-culation Pump Discharge Valve closed.when a spurious high differential loop temperature signal occurred. Power was manually reduced below 50%.
Potentiometers were replaced in the differential temper-ature unit.
l 85-9 09-14-85 1 17.8 B 3 85-16 IF INSTRU Reactor automatically shutdown l when a recorder's power
,' supply was shorted out during maintenance. A fuse blew, which de-energized some in-strumentation, including the feedwater flow transmitter. .
The reactor water level con-trol system responded by in-j creasing feedwater pump speed i
I 1 2 3 4 Reason: Method: Exhibit G-Instructionse F: Forced .A-Equipment Failure (Explain) 1-Manual for Preparation of Data i S: Scheduled B-Maintenance or Test 2-Manual Scram Entry Sheets for Licensee i C-Refueling 3-Automatic Scram Event Report (LER) File i /
D-Regulatory Restriction 4-Other (Explain) (NUREG-0161)
, E-Operator Training & License Examination l F-Administrative 5 L -
G-Operational Error (Explain) Exhibit 1 - Same Source H-Other (Explain)
l ,
l UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-409 UNIT NAME LACBWR DATE 10/03/85 REPORT MONTH September 1985 COMPLETED BY L.S. Goodman TELEPHONE 608-689-2331
~
Method of- Licensee Cause'& Corrective r Duration Shutting Down Event System -Component Action to N). Date Type l (Hours) Reason 2 Reactor 3 Report # Code 4 Code 5 Prevent Recurrence L
09 09-14-85 1 17.8 B 3 85-16 IF INSTRU and the plant scrammed on (CONTINUED) high. reactor water level.
l The fuse was replaced.
l i
i i
l t
9-l l
I l
l l
~1 2 3 4 Reason: Method: Exhibit G-Instructionse
, F: Forced A-Equipment Failure (Explain) 1-Manual for Preparation of Data l S: Scheduled B-Maintenance or Test 2-Manual Scram Entry Sheets for Licensee l C-Refueling 3-Automatic Scram Event Report (LER) File D-Regulatory Restriction 4-Other (Explain) (NUREG-0161) l E-Operator Training & License Examination
[
F-Administrative 5 G-Operational Error (Explain) Exhibit 1 - Same Source H-Other (Explain)
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+
... s REFUELING INFORMATION RE0_UESI
- 1. 'Name of Facility La Crosse Doiling Water Reactor (LACBVR)
[2. Sche'duled Date for Next--Refueling Shutdown The tentative date for the next refueling shutdown -(M-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, vnat, 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 whett.er 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 new control rods which vill be installed.
/
5.--Scheduled Date(s) for Submitting Proposed Licensing Action and Supporting Information.
October 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 Operatieg Procedure
.Some new control rais will be utilised.
WP-6.8 .
G. . -
l**
REFUELING INFORMATION REQUEST - (Continued)
- 7. The Number of Fuel Assemblies I
(a) in the Core and (b) in the Spent Fuel Fool.
Core Loading: 72 Fuel Assentblies l Spent Fuel Storage Pool Loading: - 237 Irradiated Fuel Assentblies l-1 i 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 Assentblies l
- 9. The Projected Date of the Last Refueling that can be Discharged to the j Spent Fuel Pool Assuming the- Preeent Licensed Capacity l^
1992 l l
.WP-6.8 --___:___-__-_--_____-________-__-___________-_______--_.
O .
D DA/RYLAND h [k COOPERA TlVE
- P.O BOX 817 2615 EAST AV COUTH . LA CROSSE WISCONSIN 54601 October 3, 1985 (608) 788 4000 In reply, please refer to LAC-lll73 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 SEPTEMBER 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 September 1985.
Please contact us if there are any questions concerning this report.
Very truly yours, DAIRYLAND POWER COOPERATIVE b
if James W. Taylor, General Manager JWr:LSG:sks cc: J. G. Keppler, Regional Administrator, NRC-DRO III
' John Stang, LACBWR Project Manager NRC Resident Inspector D. Sherman (ANI Library)
INPO- ,
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