ML20132E157
| ML20132E157 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 04/30/1985 |
| From: | Linder F, Malin L DAIRYLAND POWER COOPERATIVE |
| To: | NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| LAC-10843, NUDOCS 8507170638 | |
| Download: ML20132E157 (6) | |
Text
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t NARRATIVE
SUMMARY
OF OPERATING EXPERIENCE APRIL 1985 At the onset of the reporting period, the plant was shutdown in a refueling outage which commenced March 10, 1985. At 1822 on April 14, the reactor was taken critical. Startup testing was conducted over the next 2 days. At 1043 on April 17, the turbine-generator was connected to the DPC grid.
At 2052 on April 20, the plant shutdown automatically.from 73% Reactor Rated Thermal Power when a scram solenoid on Control Rod No. 12 burnt out, causing a scram. At 0447 on April 21, the reactor was taken critical. At 1335, a reactor shutdown commenced f rom approximately 0.5% power due to a leak in the Seal Inject System. During the shutdown at 1408, the reactor scrammed due to Nuclear Instrumentation Channel 6 when the operator downscaled its range switch too quickly. Channel 6 is a wide range channel with its trip point set at approximately 77 percent of the selected scale.
At 0010 on April 22, the reactor was returned to critical. At 1809, the turbine-generator was synchronzied to the grid. At 0721 on April 27, the reactor automatically shutdown from 77.5% power due to low water level when the oncoming reactor feedwater pump did not respond properly during a swap of operating feedwater pumps necessitated by the erratic control exhibited by the operating pump.
At 1404 on April 27, the reactor was taken critical. At 2235, the plant was placed on-line. Slow power escalation continued with 79% Reactor Rated Thermal Power being achieved by the end of the month.
Type B and C leakage tests conducted during April 1985 were as follows:
Penetration Leakage (SCFH)
Personnel Airlock 0.376 Personnel Airlock 1.13 Vacuum Breaker 1 0.347 Vacuum Breaker 2 0.010 Containment Spray Handwheel 0.0 Ventilation Discharge Dampers 0.082 Ventilation Inlet Dampers 0.543 (post-maintenance)
Ventilation Inlet Dampers 0.204 Reactor Vent Header Valve 0.171 Heating Steam Check Valve 0.47 Heating Steam Check Valve 0.30 Heating Steam Condensate Return Valve 0.0 J
Station Air Valve 0.0 Main Steam Isolation & Bypass Valves 13.5 Feedwater Check Valve 0.56 Decay Heat Blowdown Valve 0.0 Shutdown Condenser Vent to Offgas 0.0 Primary Purification Resin Sluice Valves 0.0 Alternate Core Spray Check valves 0.0 Reactor Coolant Sample Supply Valve 0.0 Containment Building Drain Valve 0.0 b
71 h
Penetration Leakage (SCFH)
Demineralized water Valve 0.511 Demineralized Water Valve 0.144 Seal Inject Makeup Valve 0.0 Control Air Valve 0.0 HPSW Containment Isolation Valve 0.032 FESW Ion Exchanger Resin Sluice Line Containment Isolation Valves 0.0 Retention Tank Pump Valve 24 Retention Tank Pump Valve 0.0 Reactor Cavity Purge Air Valve 0.052 Containment Atmosphere Sampling System Suction 0.0 Containment Atmosphere Sampling System Discharge 0.01 Reactor Coolant Sample System Suction 1.
Isolation Valve 84-25-002 0.0 2.
Suction Line Penetration 0.00367 Reactor Coolant Sample System Discharge 1.
Check valve 84-26-004 0.0 2.
Isolation Valve 84-25-007 0.0019 During April, many other surveillance tests were performed, as were Inservice Inspections. Major safety-related maintenance included installation of a turbocharger on the IB HPSW diesel, installation of switches to disable the Manual Depressurization system during a remote shutdown, work on the personnel airlock and preventive and corrective maintenance on lower control rod drive mechanisms.
m.,
OPERATING DATA REPORT DOCKET NO.
50-409 DATE 05/08/85 COMPLETED BY Loree Malin TELEPHONE 608-689-2331 OPERATING STATUS NOTES:
- 1. Unit Name: La Crosse Boiling Water Reactor
- 2. Reporting Period: 0000, 04/01/85 to 2400, 04/30/85
- 3. Licensed Thermal Power (MW ):
165 g
- 4. Nameplate Rating (Cross 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.-to-Date Cumulative
- 11. Hours In Reporting Period 719 2879 135,842
- 12. Number Of Hours Reactor Was Critical 344.4 1987.1 90,310.8
- 13. Reactor Reserve Shutdown Houra 0
0 47H
- 14. Hours Generator On-Line 263.8 1.H98.1 83,H01.4
- 15. Unit Reserve Shutdown Hours 0
0 79
- 16. Gross Thermal Energy Generated (MWH) 28,933.4 238,263.6 11,585,665.8
- 17. Gross Electrical Energy Generated (MWil) 8,529 73,525 3,469,136
- 18. Net Electrical Energy Generated (MWH) 7,564 68,235 3,214,071
- 19. Unit Service Factor 36.7 65.9 61.7
- 20. Unit Availability Factor 36.7 65.9 61.8
- 21. Unit Capacity Factor (Using MDC Net) 21.9 49.4 49.3 l
- 22. Unit Capacity Factor (Using DER Net) 21.0 47.4 47.3,,
- 23. Unit Forced Outage Rate 18.7 3.1 10.1
- 24. Shutdowns Scheduled Over Next 6 Months (Type Date, and Duration of Each):
None
- 25. If Shut Down At End Of Report Period, Estimated Date of Startup:
- 26. Units In Test Status (Prior to Commercial Operation):
Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION 4
WP-6.8
= _ -.. -,.. - -..
i AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-409 l
l UNIT LACBWR DATE 05/08/85 COMPLETED BY L.S. Goodman TELEPHONE 608-689-2331 i
I MONTH April 1985 i
f i
DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net)
(
l 1
SD 17 6
{
2 SD 18 26 l
t 3
SD 19 30 f
4 SD 20 28 5
SD 21 0
P 6
SD 22 2
7 SD 23 24 8
SD 24 34 9
SD 25 36
[
10 SD 26 38 11 SD 27 12 12 SD 28 23 13 SD 29 35 14 SD 30-37 l
INSTRUCTIONS i
On this format, list the average daily unit power level in MWe-Net for each day in I
the reporting month. Compute to the. nearest whole megawatt.
WP-6.8 r
UNIT SHUTDOWNS AND POWER REDUCTIONS l
DOCKET NO.
50-409 l
UNIT NAME LACBWR i
DATE 05/08/85 REPORT MONTH April 1985 COMPLETED BY L.S. Goodman TELEPHONE 608-689-2331 l
Method of Licensee Cause & Corrective l
Duration Shutting Down Event System Component Action to l
2 3
4 i
No.
Date Type (Hours)
Reason Reactor Report i Code Code 5 Prevent Recurrence l
l I!
l l
l l 85-01 1 03/10/85 S
394.7 C
1 NA Scheduled refueling shutdown.
l l
85-02 04/20/85 F
45.3 A
3 85-08 RB INSTRU i Automatic shutdown due-to l
l ll failure of I of 2 scram sole-l noids on Control Rod No. 12.
l l
l l
Sparelowercontrolroddrivel l
mechanism was installed.
l l
INSTRU Automatic shutdown due to low l 85-03 ll 04/27/85 F
15.2 A
3 85-11 CH u
l ii l water level when oncoming l
reactor feedwater pump did not respond properly during swap l l
l of operating feedwater pumps l
l l necessitated by the erratic l control exhibited by operating l!
l pump. Adjusted dead band l
l l
l width and gain on IB pump l
controller, installed spare amplified for IA pump con-l L
troller and adjusted Reactor l
l Feedwater Flow Controller 1
l l
' response.
I 1
2 3
4 Reason:
Method:
Exhibit C-Instructionse l
F: Forced A-Equipment Failure (Explaf n) 1-Manual for Preparation of Data S: Scheduled B-Maintenance or Test 2-Manual Scram Entry Sheets for Licensee l
C-Refueling 3-Automatic Scram Event Report (LER) File i
D-Regulatory Restriction 4-Other (Explain)
(NUREG-0161) l E-Operator Training & License Examination l
F-Administrative 5
G-Operational Error (Explain)
Exhibit 1 - Same Source l
H-Other (Explain)
0-D
/RYLAND*
COOPERAT/VE
- PO BOX 817 2615 EAST AV SOUTH
- LA CROSSE WISCONSIN $4601 (608) 788 4000 May 8, 1985 In reply, please refer to LAC-10843 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 APRIL 1985 References (1) NRC Letter, Reid to Madgett, dated September 19, 1977.
(2) NRC Letter, Reid to Madgett, dated December 29, 1977 Gentlemen:
In accordance with instructionr 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) ior the Month of April 1985.
Please contact us if there are any questions concerning this report.
Very truly yours, 4
DAIRYLAND POWER COOPERATIVE i
41' llc /Y Frank Linder, General Manager
}
r, PL LSG ske cc J. G. Keppler, Regional Administrator, NRC-DRO III NRC Resident Inspector i
D. Sherman (ANI Library) j Dick Dudley i
INPO i
I i
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