ML20133H535
| ML20133H535 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 05/31/1985 |
| From: | Linder F, Malin L DAIRYLAND POWER COOPERATIVE |
| To: | NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| LAC-10938, NUDOCS 8508090384 | |
| Download: ML20133H535 (5) | |
Text
a NARRATIVE
SUMMARY
OF OPERATING EXPERIENCE MAY 1985 At the onset of the reporting period, a slow power escalation was continuing f rom the refueling outage which had ended in April.
Reactor power was 79% (38 MWe-net).
The reactor achieved approximately 98% Rated Thermal Power (48 MWe-net) on May 7, 1985.
At 0405 on May 17, the reactor automatically shutdown due to low gas pressure or low oil level in one of the control rod drive mechanisms' accumulators.
Pressure switches were adjusted on 2 mechanisms and a scram solenoid was replaced on another mechanism. The reactor was returned to critical at 2022 on May 17 and the turbine-generator was connected to the DPC grid at 0620 on May 18.
The reactor reached 98% Rated Thermal Power (48 MWe-net) on May 22.
Power generation continued at this level for the remainder of the May reporting period.
8508090384 850531 DR ADOCK 05000409 q$39 PDR
OPERATING DATA REPORT DOCKET NO.
50-409 DATE 06/06/85 COMPLETED BY Loree Malin TELEPHONE 608-689-2331 OPERATING STATUS l
NOTES:
- 1. Unit Name: La Crosse Boiling Water Reactor
- 2. Reporting Period: 0000, 05/01/83 to 2400, 05/31/85
- 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.-to-Date Cumulative
- 11. Hours In Reporting Period 744 3623 136,586
- 12. Number Of Hours Reactor Was Critical 727.7 2714.8 91,038.5
- 13. Reactor Re <erve Shutdown Hours 0
0 478
- 14. Hours Generator On-Line 717.8 2,615.9 84,519.2
- 15. Unit Reserve Shutdown Hours 0
0 79
- 16. Gross Thermal Energy Generated (MWH) 110,906.4 349,170.0 11,696,571.9
- 17. Gross Electrical Energy Generated (MWil) 34,150 107,675 3,503,286
- 18. Net Electrical Energy Generated (MWil) 32,238 100,473 3,246,309
- 19. Unit Service Factor 96.5 72.2 61.9
- 20. Unit Availability Factor 96.5 72.2 61.9
- 21. Unit Capacity Factor (Using MDC Net) 90.1 57.8 49.5
- 22. Unit Capacity Factor (Using DER Net) 86.7 55.5 47.5
- 23. Unit Forced Outage Rate 3.5 3.2 10.1
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
ce 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 WP-6.8
AVERAGE DAILY UNIT POWE:1 LEVEL DOCKET 130.
50-409 UNIT LACBWR 1
DATE 06/06/85 COMPLETED BY L.S. Goodman TELEPHONE 608-689-2331 MONTH May 1985 I
l DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL i
(MWe-Net)
(MWe-Net) i f
1 39 17 7
i 2
41 18 12 3
43 19 26 4
44 20 37 5
46 21 46 6
47 22 48 7
48 23 48 8
48 24 48 9
48 25 48 10 48 26 48 11 47 27 48 12 47 28 48 13 48 29 48 14 48 30 48 15 47 31 48 16 48 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 REDUCTIONS DOCKET NO.
50-409 UNIT NAME LACBWR DATE 06/06/85 REPORT MONTH May 1985 COMPLETED BY L.S. Goodman TELEPHONE 608-689-2331 l
l-l Method of Licensee Cause & Corrective l Duration iShutting Downl Event System Component Action to j
Code 5 Prevent Recurrence No.
Date Type (Hours)
Reason 2 Reactor 3 Report f i Code 4 l
i l
l l
l 85-04 05/17/85 F
26.2 A
3 85-12 RB INSTRU l Reactor automatically shut-
)
I l
l down due to low gas pressure l
l l or low oil level in one of l
l l the control rod drive ll l mechanisms' accumulators.
I I-l l' Pressure switches were l
adjusted on 2 mechanisms and a scram solenoid was replaced.l ll on another mechanism.
ll l
i i
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)
E-Operator Training & License Examination F-Administrative 5
G-Operational Error (Explain)
Exhibit 1 - Same Source H-Other (Explain)
/
S-4 D DA/RYLAND h
[k COOPERAT/VE
June 6, 1985 In reply, please refer to LAC-10938 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 MAY 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 instructiona 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 May 1985.
Please contact us if there are any questions concerning this report.
Very truly yours, DAIRYLAND POWER COOPERATIVE Frank Linder, General Manager FL:LSG:sks J. G. Keppler, Regional Administrator, NRC-DRO III cc:
NRC Resident Inspector D. Sherman ( ANI Library)
Dick Dudley INPO rEL4'lt