ML20077B775
| ML20077B775 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 04/30/1991 |
| From: | Edwards M, Gates W OMAHA PUBLIC POWER DISTRICT |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| LIC-91-159R, NUDOCS 9105150163 | |
| Download: ML20077B775 (7) | |
Text
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Omaha Public Power District 444 South 16th Street Mall Omaha. Nebraska 68102-2247 402/636-2000 May 14, 1991 LIC-91-159R U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station Pl-137 Washington, DC 20555 Referencc:
Docket No. 50-285 Gentlemen:
SUBJECT:
April Monti,1y Operating Report (MOR)
Please find enclosed the April 1991 Monthly Operating Report for the Fort Calhoun Station Unit No. I as required by Technical Specification Section 5.9.1.
If you should have any questions, please contact me.
Sincerely,
- b. N. /Y W. G. Gates Division Manager Nuclear Operations WGG/sel Enclosures l
c:
LeBoeuf, Lamb, Leiby & MacRae R. D. Martin, NRC Regional Administrator, Region IV R. P. Mullikin, NRC Seninr Resident Inspector D. K. Sentell, Combustion Engineering R. J. Simon, Westinghouse l
Office of Management & Program Analysis (2) l INP0 Records Center American Nuclear Insurers 9105150163 910^30 f
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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-285 UNIT Fort Calhoun Station DATE May 4, 1991 1
COMPLETED BY '.L.
Edwards M
TELEPHONE T402)636-2451 MONTH April 1991 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 327-17 325 2
326 18 326 3
326 19 327 4
326 20 327 5
32E 21 327 6
324 22 327 7
310 23 294 8
322 24 138 9
323 25 138 10 324 26 138 11
-326 27 243 12 327 28 340 13 328 29 343 14
-328 30 350 15 328
-16 326 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 May 4, 1991 COMPLETED BY M.L. Edwards TELEPHONE (402)636-2451 OPERATING STATUS 1.
Unit Name:
Fort Calhoun Station Notes 2.
Reporting Period:
April 1991 3.
Licensed Thermal Power (MWt):
1500 4.
Nameplate Ratinn (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, Give Reasons:
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 719.0 2,879.0 154,249.0
- 12. Number of Hours Reactor was Critical 719.0 2,699.0 119,487.7
- 13. Reactor Reserve Shutdown Hours 0.0
-~ 2,688.2 118,118.1 0.0 1,309.5
- 14. Hours Generator On-Line 719.0
- 15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
- 16. Gross-ThermalEnergyGenerated(MWH) 716,092.2 3,124,403.8 154,407,893.1
- 17. Gross Electrical Energy Generated (MWH) 234,356.0 1,036,646.0 50,786,772.2
- 18. Net Electrical Energy Genecated (MWH)
-219,323.0 978,599.2 48,463,375.5
- 19. Unit Service Factor 100.0-93.4 76.6
=20.
Unit Availability Factor 100.0 93.4 76.6
- 21. UnitCapacityFactor(UsingMDCNet)
-63.8 71.1 68.1
- 22. Unit Capacity Factor (Using DER Net) 63.8 71.1 66.5
- 23. Unit Forced Outage Rate 0.0 6.6 3.6 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 l
- 26. Units In Test Status (Prior to Commercial Operation):
Forcast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY N/A i
COMMERCIAL OPERATION i
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Refueling Information Fort Calhoua - Unit No. 1 Report for the month ending _Anril 1991 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 thereaf ter 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 New LOCA Analysis 6.
The number of fuel assemblies: a) in the core 133 Assemblies b) in the spent fuel pool 477 Assemblies c) spent fuel pool storage capacity 729 Assemblies d) planned spent fuel pool Planned to be increased storage capacity with higher density spent 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.
Prepared by %'W Date s- <. - o
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l DOCKET NO. 50-285 l
UNIf NAME Fort Calhodn Station DATE JMay 9.
1991 UllIT S!!UIDOWil5 AllD POWER REDUCT10NS C0!!PLETED llY _ M.L. Ednards 1ELEP110HE f4021 63s-24s1 REPORT fiOffill April 1991 ii s.
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91-01 910211 S
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N/A ZZ ZZZZZZ Continued operations at 70% power level to allow extension of the fuel cycle to January,1992.
91-02 910423 F
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4 N/A CH VALVEX Pows.r level was reduced to 35% when an instrument air fitting on Feedwater Regulating Valve FCV-1101 failed due to cyclic stresses / vibrations.
FCV-1101 was isolated and a major overhaul was performed on both the valve and the affected air lines.
On April 27th, af ter repairs were completed, the power level was increased to 75%.
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F-roveed Itansert Method Exhibit G
."nstructions S-Schedifad A-Err /pment in!!ure (Expla n) 1-Manual for Preparation of Data i
D-Matntenance or last 2-Manun' Scenm Entry Sheets for tjecosee C-nefualno 3-Automatic Scenm Event Report (LER) FNe (flUREG-010t}
D-negeintory Destriction 4-Other (Expfatn)
E-Operator Tenining a License Examination 6
F-Administ ative Exfibit 1 - Same Source G-operrf - '.t Error ll-othat rT_ wpf atn)
OHAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No. 1 April 1991 Monthly Operating Report (MOR) 1.
OPERATIONS
SUMMARY
On April 23, 1991, while the plant was operating at approximately 70%
power, an instrument air fitting on feedwater regulating valve FCV-1101 failed, due to cyclic stresses. The failed fitting resulted in erratic operation of feedwater to steam generator RC-2A.
Power was reduced to 35%
in an effort to isolate FCV-1101, and initiate repairs. On April 25th, with FCV-Il01 isolated, a major overhaul was performed on both the valve and affected air lines.
Maintenance was completed on April 27th and power ascension commenced to 75% with FCV-1101 operating properly.
The following NRC inspections took place in April IR-91-05 Residents' Routine Inspection (concluded April 9, 1991)
IR-91-12 Security IR-91-13 Safety Enhancement Program (SEP)
IR-91-07 Water Chemistry IR-91-01 EDSFI IR-91-14 Residents' Routine Inspection (from April 10,1991)
The following LERs were submitted:
LER-91-05 Violation of Instrumentat on and Control Technical Specifications 2.15 LER-91-06 Failure to Establish Compensatory Firewatches LER-91-07 480V Circuit Breaker Coordination Outside Design Basis A.
SAFETY VALVES OR PORV CHALLENGES OR FAILURES WHICH OCCURRED None B.
RESULTS OF LEAK RALE TESTS The results of the reactor coolant leak rate tests for April,1991 indicate that the reactor coolant system (RCS) and chemical and volume control system are both rel'tively leak tight.
Total RCS leakage averages a very low 0.08 gpm divided evenly between "known" and " unknown" leakage.
During the month, there were a few instances of negative leak rates that are attributed to the normal random variations encountered with this test co.nbined with the very low average leak rate.
Leak rate test accuracy was affected on April 23rd, when power was reduced from 70% to 35% and again on April 27th, when power was increased from 35%
to 75%.
Accuri;y of the leak rate tests is reduced whenever the plant undergoes any departure from equilibrium conditions.
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' Monthly Operating Report (MOR)
LIC-91-159R Page 2 The maximum leak rate for the month was recorded on April 26th when the total leak rate was 0.176 gpm and the unknown leak rate was 0.160 gpm.
Charging Pump CH-1A was found to have a hot packing leak-off line and was isolated.
This charging pump is now undergoing inspection and repacking.
C.
CHANGES, TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY COMMISSION AUTHORIZATION PURSUANT TO 10CFR50.59 Amendment Not Description None D.
SIGNIFICANT SAFETY RELATED MAINTENANCE FOR THE MONTH OF APRIL 1991 Diesel work for the month included:
DG-1 Adjusted the idle speed cam.
Installed an air flow device in the exhaust chimney which was removed after testing.
Trouble shooting indicated two of the air dryer filters were installed backwarJs.
The filters were reinstalled in the correct direction.
Troubleshooting of the fuel oil pressure switches revealed that the pressure snubbers associated with each fuel oil transfer pump pressure switch should be replaced due to contamination and plugging.
Four snubbers were replaced on the fuel oil system.
Replaced a torn gasket and pressure alarm switch PS-3374 for transfer pump F0-4A-1.
DG-2 Replaced jacket water inlet temperature switch TA-6131-1 that was causing faulty low engine water temperature alarms.
(
Retorqued the DG radiator fan blade bolts per the vendor manual instructions (30 to 60 days after blade pitch adjustment).
Raw Water Pump activities for the month included:
AC-10C
- Removed raw water pump AC-10C and replaced with new pump.
Replaced root isolation valve RW-ll6 for pressure switch PC-2856 on the discharge of AC-10C.
Repaired and replaced the pressure indicator and switch sensing at RW-116.
l Installed a 6" piece of tubing and tube union downstream of i
RW-ll6 for test purposes.
AC-108
- Replaced root isolation valve RW-120 for pressure switch PC-2855 on the discharge of raw water pump AC-108.
Component cooling water / raw water heat exchanger AC-1B was taken out of l
service to replace the lifting lugs on the end bell flanges and for 'ube cleaning.
The B phase overcurrent device for SI-3B containment spray pump motor feeder breaker 1B4-1 was found to be leaking oil and was replaced.
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