ML20077P001
| ML20077P001 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 07/31/1991 |
| From: | Edwards M OMAHA PUBLIC POWER DISTRICT |
| To: | |
| Shared Package | |
| ML20077N998 | List: |
| References | |
| NUDOCS 9108150191 | |
| Download: ML20077P001 (7) | |
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AVERAGE DAILY UNIT POWER LEVEL-DOCKET N0.
50-285 UNIT Fort Calhoun Station DATE August 6, 1991 COMPLETED BY M.L. Edwards TELEPHONE (402)636-2451 MONTH July 1991
'OAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 461 17 463 2
462 18 461 3
464 19 461 4
465 20 461 5
466 21 461 6
465 22 460-7 463 23 461 8
465 24 464 9
467 25-465 10
'470 26 466 11 470 27 467 12 468 28 470 13 467 29 470 14 467 30 470 15 467 31 468 16 466
. INSTRUCTIONS On this form, list the average daily unit power level in MWe-Net for each day in the reporting month. -Compute to the nearest whole megawatt.
9108150193 9.1ggg4
{DR 4 DOCK 05000285 PDR
~, _. _ _..... _ _.. -. _., _... _,.. _. _. -,
0PERATING DATA REPORT DOCKET NO.
50-285-UNIT Fort Calhoun Station DATE August 6,-1991 COMPLETED BY M.L. Edwards TELEPHONE (402)636-245T
'0PERATING STATUS 1.
Unit Name:
Fort Calhoun Station Notes 2.
Reporting Period:
July 1991 3.
Licensed Thermal Power (MWt):
1500 4.
Nameplate Rating (Gross MWe):
53 2 5.
Design Electrical Rating (Net MWe): 478 6.
Maximum Dependable. Capacity (Gross RWe):
502 7.
Maximum Dependable Capacity (Net MWe).
478 8.
If changes occur in Capacity Ratings (Item Numbers 3 through 7) Since Last Report, Give Reasons:
N/A 9.
Power Level to Which Restricted, If Any (Net MWe): N/A 10.
Reasons for Restrictions, If Any: N/A This Month Yr-to-Date Cumulative
- 11. Hours in Reporting Period 744.0 5,087.0 156,457.0 12.
Number of Hours Reactor was Critical 7T4.0
- 4,907.0 121,695.7~
~
- 13. Reactor Reserve Shutdown Hours 0.0 0.0 1,309 T
- 14. Hours Generator On-Line 744.0 4~,896.2 120,326.l~
15.
Unit Reserve Shutdown Hours 0.6-0.0 0.0
- 16. Gross Thermal Energy.Gentrated (MWH) 1,111,316.9 D T6 074.5
_157,269,563.8
- 17. Gross-Electrical Energy Generated (MWH) 363,156.0 1,shf,188.0 51,717,914.2
- 18. Net Electrical Energy Generated (MWH) 346,100.1
.1 860 541.7
__4,9,345,318.0 2
4
- 19.. Unit Service Factor 100.0 9te. 2 76.9
- 20. Unit Availability Factor 100.0 96.2 76.9
- 21. UnitCapacityFactor(UsingMDCNet) 97.3 76.5 68. 3 22.
Unit Capacity Factor.(Using DER Net) 23.
Unit Forced Outage Rate 97.3 76.5 66.8 O.0 D
'73 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.0peration):
Forcast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY N/A COMMERCIAL OPERATION
4 H
Refueling Information Fort Calhoun - Unit No. 1 Report for the month ending July 1291 1._
Scheduled date for next refueling shutdown.
January 31. 1992
'2: Scheduled date for restart following refueling.
May 1. 1992
- 3. _Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?
Yes a.
If answer is yes, what, in general, will these be?
Incorporate specific requirements resulting from reload safety
- analysis, b.
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.
N/A
-_c.
._If no such review has taken place, when is it scheduled?
N/A 4.
Scheduled date(s)_for submitting proposed
-licensing action and support information.
November 1991 5.
Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures.
New fuel supplier Rew LOCA Analysis 6.
The number of fuel assemblies: a) in the core 133 Assemblies b) in the spent fuel pool 427 Assemblies c) spent fuel pool storage capacity 729 Assemblies d) planned spent fuel pool Planned to be increased storage capacity with higher density sper.t
. fuel racks.
7.
The projected date of the last refueling that can-be discharged to the spent fuel pool assuming the present licensed capacity.
1995
- Capability _ of full core offload of 133 assemblies lost O
Prepared by C _ -2J dfd c Date_ E y,-9i
-,~
DOCKET NO.T 50-285-UNIT NAME Fort Calhoun Station DATE August'8. 1991 UNIT SHUTDOWNS AND POWER REDUCTIONS COMPLETED BY M. L. Edwards-TELEPHONE (402) 636-2451 REPORT MONTH
-JULY 1991 No.
, Date
. Type ~
Duration Reason Method of Licensee System Component Cause & Corrective -
(1)
(Hours)-
(2)'
Shutting.l Event Cafe Code (5)
Action to Down Report #
(4)-
Prevent Recurrence Reactor -
(3)
There were rio unit shutdowns or significant reduction in power during the month of July 1991.
I 2'
3 4
F-F:nced Reason:
Method:
Exhibit G - Instructions for Preparation of Data Entry Sheets S-Scheduled A-Equipment Failure (Explain) 1-Manual for Licensee Event Report (LER) File (NUREG-0161)
B-Maintenance or Test 2-Manual Scram C-Refueling 3-Automatic Scram D-Regulatory Restriction 4-Other (Explain)
E-Operator Training & License Examination F-Administrative 5
G-Operational Error.
' Exhibit 1 - Same Source
~ II-Other (Explaia)
[
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OMAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No.1 i
July 1991 Monthly Operating Report I.
OPERA 110NS
SUMMARY
Fort Calhoun Station operated at a nominal 100% power through the month of July 1991.
The following NRC inspections took place in July:
IR 91-10 Training Program IR 91-19 Liquid / Gaseous / Solid Rad Waste & Transportation The following LERs were submitted:
LER-91-10 Auxiliary Steam Piping in Room 57 Outside Design Basis (HELB)
LER-91-11 Pressurizer Pressure Low Signal (PPLS) Setpoints LER-91-12 Emergency Diesel Generator Auto-start Due to Loss of Transformer (TIA-4)
LER-91-13 Diesel Generator Auto-start Due to ST on DG-1 LER-91-14 Radiation Monitor RM-054A Out of Service A.
SAFETY VALVES OR PORV CHALLENGES OR FAILURES WHICH OCCURRED None B.
RESULTS OF LEAK RATE TESTS The results of the Reactor Coolant Leak Rate tests for' July 1991 indicate that the Reactor Coolant System (RCS) and Chemical and Volume Control System (CVCS) are both relatively leak tight. During July, the RCS total leak rate averaged 0.14 gpm.
The month's maximum leak rate was recorded on July 6, when the total leak rate was 0.293 gpm and the unknown leak rate was 0.228 gpm.
Worn packing on-charging pump CH-1B was the apparent cause. Charging pump CH-1B was repacked and the leak rate returned to normal. At the end of July, the leak rate increased again.
Worn packing on charging pump CH-1A is suspected to be the cause of this recent increase in the leak rate.
C.
CHANGES, TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY COMMISSION AUTHORIZATION PURSUANT TO 10 CFR 50.59 Amendment No.
Description None
Monthly Operating Report LIC-91-202R Page 2 D.
SIGNIFICANT SAFETY RELATED MAINTENANCE FOR THE MONTH OF JULY 1991 The 125 VDC battery number one (EE-8A) developed a crack on the corner of cell #15 causing an electrolyte leak. After the crack was temporarily repaired with clear silicone RTV caulk and the cell was filled with distilled water, maintenance was initiated to replace the cell.
Raw water pump AC-10D was removed, a new pump bowl assembly was installed and the pump was reassembled.
The pump internals showed normal wear.
Post maintenance test results were satisfactory and new baseline data was recorded.
During monthly surveillance testing on reactor protective system (RPS) trip unit B/TU-08, the setpoints were found within the acceptance range but close to the upper limit.
The pre-trip and trip setpoints were readjusted and the surveillance test was performed again to verify operability.
The sample pump for containment stack radiation monitor, RM-061, was degrading in performance as indicated by low flow and vacuum readings.
The sample pump was replaced.
Containment stack radiation monitor, RM-050, was cycling from 10,000 to 1,000 to 10,000 cpm. Troubleshooting identified the ratemeter as the cause of the cycling irregularity and it was replaced.
Other maintenance activities on RM-050 included repair of the sample flow fault light and the power available light.
Two fuses were found blown due to a seized solenoid.
Repairs included the replacement of the filter advance switch, filter advance solenoid, the rectifier and diode.
Replaced piping, fittings and hoses on iodine stack monitor RM-060 and installed seismic support for RM-060 flow totalizer.
During monthly testing the radiator exhaust damper would not open on diesel generator number two (DG-2) because the dampers were binding on the outside.
DG-2's dampers were aojusted and a broken roll pin in the linkage mechanism was replaced.
The diesel generator number one (DG-1) radiator exhaust damper was inspected to verify that the damper moved freely.
DG-l's lower right damper blade was damaged and the roll pin was cracked.
Repairs to DG-1 included straightening the edge of the damper and replacement of the roll pin.
Post maintenance testing was performed on each diesel generator and the dampers were cycled to ensure there was no binding.
Each diesel generator was started and operability testing i
verified the dampers opened as required.
The handwheel gear drive key on the inner door of the personnel air lock sheared, causing failure of the inner lock. Repairs included disassembly of the drive mechanism, replacement of the key, reassembly and adjustment of the interlocks. Aging and cycle fatigue is the suspected cause of failure.
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