ML20247H194
| ML20247H194 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 08/31/1989 |
| From: | Morris K, Stice D OMAHA PUBLIC POWER DISTRICT |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| LIC-89-872, NUDOCS 8909190239 | |
| Download: ML20247H194 (26) | |
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l Omaha Public Power District 1623 Harnetj Omaha. Nebraska 68102 2247 402/536-4000 September 14, 1989 LIC-89-872 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station PI-137 Washington, DC 20555
Reference:
Docket No. 50-285 Gentlemen:
SUBJECT:
August Monthly Operating Report Pursuant to Technical Specification Section 5.9.1, and 10 CFR Part 50.4(b)(1),
please find enclosed one copy of the August 1989 Monthly Operating Report for the Fort Calhoun Station Unit No. 1.
If you should have any questions, please contact us.
Sincerely, I
K. J. Morris Division Manager Nuclear Operations KJM/pjc c:
R. D. Martin, NRC Regional Administrator P. H. Harrell, NRC Senior Resident Inspector Office of Management & Program Analysis (2)
R. M. Caruso - Combustion Engineering
%y R. J. Simon - Westinghouse i i Nuclear Safety Analysis Center I
INP0 Records Center American Nuclear Insurers 8909190239 890831 PDR ADOCK 05000285 R
PDC as siz4 i mNuumen t ia oppoininnu
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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-285 UNIT Fort Calhoun Station DATE September 11, 1989 COMPLETED BY D. L. Stice TELEPHONE (402)636-2474 MONTH August 1989 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 447 17 454 2
448 18 455 3
450 19 456 4
449 20 456 5
448 21 455 6
449 22 455 7
452 23 455 8
455 24 453 9
456 25 453 10 455 26 455 11 455 27 456 12 456 28 456 13 456 29 455 14 456 30 454 15 456 31 452 16 454 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.
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OPERATING DATA REPORT DOCKET NO.
50-285 UNIT Fort Calhoun Station DATE September 11, 1989 COMPLETED BY D. L. Stice TELEPHONE (402)636-2474 OPERATING STATUS 1.
Unit Name:
Fort Calhoun Station Notes 2.
Reporting Period:
August 1989 3.
Licensed Thermal Power (MWt):
1500 4.
Nameplate Rating (Gross MWe):
502 5.
Design Electrical Rating (Net MWe): 478 6.
MaximumDependableCapacity(GrossMWe):
502 7.
Maximum Dependable Capacity (Net MWe):
478 8.
If changes occur in Capacity Ratings (Item Numbers 3 through 7) Since Last Report, j
Give Reasons:
i N/A 9.
PowerLeveltoWhichRestricted,IfAny(NetMWe):
N/A
- 10. Reasons for Restrictions, If Any:
N/A This Month Yr-to-Date Cumulative
- 11. Hours in Reporting Period 744.0 5,831.0 139,681.0
- 12. Number of Hours Reactor was Critical 744.0 4,988.8 108,338.6
- 13. Reactor Reserve Shutdown Hours 0.0 0.0 1,309.5
- 14. Hours Generator On-Line 744.0 4,771.3 107,186.6
- 15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
- 16. Gross Thermal Energy Generated (MWH) 1,111,876.3 6,739,930.1 139,628,924.0
- 17. GrossElectricalEnergyGenerated(MWH) 354,530.0 2,174,174.0 45,918,302.2
- 18. Net Electrical Energy Generated (MWH) 337,473. 7 2,067,942.9 43,839,447.7
- 19. Unit Service Factor 100.0 81.8 76.7
- 20. Unit Availability Factor 100.0 81.8 76.7
- 21. UnitCapacityFactor(UsingMDCNet) 94.9 74.2 67.9
- 22. Unit Capacity Factor (Using DER Net) 94.9 74.2 66.2
- 23. Unit Forced Outage Rate 0.0 3.5 2.9 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:
N/A
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?6. Units In Test Status (Prior to Commercial Operation):
Forcast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY N/A COMMERCIAL OPERATION
Refueling Information Fort Calhoun - Unit No. 1 Report for the month ending Auoust 1989 1.
Scheduled date for next refueling shutdown.
February 1990
- 2.. Scheduled date for restart following refueling.
May 1990 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 deter-mine whether any unreviewed safety questions are associated with the core reload.
c.
If no such review has taken place, when is it scheduled?
4.
Scheduleddate(s)forsubmittingproposedlicensing action and support'information.
January 1990 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.
None Planned 6.
The number of fuel assemblies: a in the core 133 assemblies b in the spent fuel pool 437 c spent fuel pool storage capacity 729 d) planned spent fuel pool May be increased storage capacity via fuel pin consolidation or dry cask storage 7.
The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity.
1994*
- Full core offload of 133 assemblies lost.
Prepared by OD C Date September 11, 1989
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OMAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No. 1 August 1989 Monthly Operations Report I.
OPERATIONS
SUMMARY
Fort Calhoun Station operated at a nominal 100% power throughout the month of August 1989.
A major revision to the Emergency Operating Procedures (EOPs) was issued.
This revision introduced the use of a two column format for contingency
-actions. A new E0P for station blackout was also issued.
Modification work has started for installation of a new instrument air dryer. The present air dryer is not functioning per design requirements.
Until the new dryer is functional, a temporary air dryer has been installed to maintain a desi;n dew point temperature of less than -20*F.
The water plant outage for system repair is complete.
Since completion there have been intermittent sulfate intrusion problems.
Investigation and corrective actions are continuing.
Technical Specification Amendment 122 was effective August 31, 1989. This amendment provides definitions of testing frequencies, as well as a generic permissible extension of 25% to testing frequencies.
The Emergency Diesel Generators have a jacket water temperature limit of 208'F. Testing has shown a linear relationship between jacket water temperature and outside ambient air temperature. High ambient air
' temperature could cause the diesels to exceed 208*F jacket water temperature under design loads. Administrative ambient temperature limits have been established at which point a diesel will be declared inoperable, although it will be left in a fully automatic condition to ensure its availability if needed. Further actions are being developed to reduce the limiting effect of ambient air temperature.
The Raw Water / Component Cooling Water heat exchangers have been i
experiencing the common seasonal occurrence of sand plugging on the raw water side.
Recent testing has shown that the restriction in the heat exchangers has reduced the raw water flow rate below that required for the present river temperature and particular combinations of three of the four heat exchangers in service. Air sparging of the heat exchangers was increased, resulting in some improvement in raw water flow rate.
Monitoring of flow rates was also increased. Other methods for reducing the sand plugging are being developed.
Except for testing, all four heat i
exchangers are presently being kept in service.
Work on the Control Room filter modification to meet GDC 19 habitability requirements for operators continues. Construction of the new Chemistry and Radiation Protection (C/RP) locker facility and the Rad Waste building continues.
l 1
Monthly Operation Report Page Two August 1989
.The following NRC inspections took place in August.
IR 89-32 Resident Inspectors' Monthly Inspection
- Not Provided NRC Special Inspection on IN 89-45 (DW-46 A/B Breakers)
The following LER's were submitted.
Date Submitted 89-S06 Failure to Initiate Compensatory Actions August 17, 1989 An enforcement conference was held on August 28, 1989 in Arlington, TX.
The subject of the conference was Security and Inspection Report 89-31.
No safety valves or PORV challenges or failures occurred.
A.
PERFORMANCE CHARACTERISTICS None B.
CHANGES IN OPERATING METHODS None C.
RESULTS OF SURVEILLANCE TESTS AND INSPECTIONS None D.
CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL System Acceptance Committee Packages for August 1989:
Packaae Description / Analysis SP-FW-13 The purpose of this procedure was to calibrate, in place, turbine driven AFW pump FW-10; to cycle the complete speed control loop; and to control the removal and examination of the nullmatic derivative unit and the two mode nu11matic controller.
This procedure did not constitute an unreviewed safety question as defined by 10 CFR 50.59 because at no time was FW-10 in a condition outside of its normal design limits.
The test involved the equivalent of preventive maintenance tests that should be accomplished on a regular basis. The information gathered will be used to generate future preventive maintenance tasks. The required safety functions of FW-10 were not interfered with in any way not covered by previous analysis.
_ _ - _ _ _- __ - _ = - -
L.
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Monthly Operations Report Page Three August 1989 E.
RESULTS OF LEAK RATE TESTS For the month of August, daily testing of the Reactor Coolant System (RCS) leak rate yielded values for Total, Known, and Unknown leakages consistent with Cycle 12 operation. Total leakage rece.,re d varied from a high of.586 gpm on August 29, to a low of.323 gpm on August 19.
Unknown leakages varied from.311 gpm to.045 gpm on the same days as the maximum and minimum total leakages, respectively.
The RCS leakage calculation for August 29 was suspect because 50 gallons of water were added to the RCS during the test. A hand calculation from the test input data was performed with results consistent to the computer values. The RCS leak rate was retested immediately after the original test results came in. Total leakage for the retest was.405 gpm, with.078 gpm being unknown leakage.
F.
CHANGES IN PLANT OPERATING STAFF Four operators were hired during August 1989. One operator was terminated.
G.
TRAINING' During the month 'of August, the testing program for the simulator was revised to improve the probability of shipping the simulator in December. A realistic time for shipping the simulator is from December 1989 to February 1990.
License class training material was forwarded to the NRC, as requested, for their use in preparing for the upcoming Senior Reactor Operator (SRO) license exam. The Reactor Operator (RO) license class completed two weeks of simulator training
.to meet license qualifications.
Licensed and non-licensed operator requalification training continued as scheduled. The Shift Technical Advisor (STA) initial training continued with students going to Combustion Engineering for simulator training. The second phase of System Engineer training began this month and will continue through December.
The draft combination FCS/INPO Accredited Electrical Training Program and Apprenticeship Maintenance Program were submitted for review. The first round of Supervisor Safety Training was completed.
Validation committee meetings were held throughout August in order to design the Emergency Preparedness training. The Safety Audit & Review Committee (SARC) commented favorably on Training.
H.
CHANGES, TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY COMMISSION AUTHORIZATION PURSUANT TO 10CFR50.59 Amendment No.
Description None
Monthly Operations Report Page Four August 1989 II. MAINTENANCE (Significant Safety Related)
See attached printout.
G. R. Peterson Manager-Fort Calhoun Station i
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