ML20070J693
| ML20070J693 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 02/28/1991 |
| From: | Edwards M, Gates W OMAHA PUBLIC POWER DISTRICT |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| LIC-91-106R, NUDOCS 9103180082 | |
| Download: ML20070J693 (8) | |
Text
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Omaha Public Power District 444 South 16th Street Mall Onwha. Nebraska 68102-2247 402/63& 2000 March 14, 1991 LIC-91 106R U. S. Nuclear Regulatory Comission Attn: Document Control Desk Mall Station PI-137 Washington, DC 20555
Reference:
Docket No. 50 285 Gentlemen:
EUBJECT:
February Monthly Operating Report (MR)
Please find enclosed the February 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, l
/W-W. G. Gates Division Manager Nuc' ear Operations WGG/scl l
Enclosures 1
i c: LeBoeuf, Lamb, Leiby & MacRae R. D. tw tin, NRC Regional Administrator, Region IV R. P.
'likin, NRC Senior Resident Inspector
/
D. K.
otell, Combustion Engineering
/
R. J. aimon, Westinghouse Office of Management & Pregram Analysis (2)
INP0 Records Center American Nuclear Insurers 9103180082 910228 PDR ADOCK 05000285 R
PDR 6 5124 Empoymen th 1 l opratunity (I
~ _ _
r AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-285 UNIT Fort Calhoun Station DATE March 12, 1991 COMPLETED BY M. L. EDWARDS TELEPHONE (402)636-2451 l
MONTH Februar_y 1991 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 488 17 357 2
488 18 356 3
488 19 356 4
488 20 355 5
488 21 355 6
488 22 353 7
488 23 328 8
488 24 329 9
488 25 329 10 487 26 329 11 459 27 329 12 359 28 328 l
13 355 14 355 15 356 16 356 INSTRUCTIONS 1
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.
.~,. _ _ _..,.
i OPERATING OATA REPORT 00CXET NO.
50-285 UNIT Fort Calhoun Station, DATE March 12, 1991 COMPLETED BY M. L. EDWAROS TELEPHONE _
(402)636-2451 i
OPERATING STATUS
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1.
Unit Name:
Fort Calhoun Station Notes
?.
Reporting Period:
February 1991 3.
Licensed Thermal Power (MWt):
1500 4.
Namep 1 ate Ra_ ting (Gr.o.si_MWe.).t_.. _.. 502:'
5.
Design Electrical Rating (Net MWe):
478 6.
Maximum Dependable Capacity ((Gross MWe):
502 7.
Maximum Dependable Capacity Net MWe):
478
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8.
If changes occur in Capacity Ratings _(Item Numoers 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 672.0 1,416.0 152,786.0
- 12. Number of Hours Reactor was Critical 672.0 1,236.0 118,024.7
- 13. Reactor Reserve Shutdown Hours 0.0 0.0 1,309.5 14.
Hours Generator On-Line 672.0 1,225.2 116,655.1 15.
Unit Reserve Shutdown Hours 0.0 0.0 0.0
- 16. CrossThermalEnergyGc..Luced(MWH) 841,517.9 1,629,760.7 T52,913,250.0
- 17. Gross Electrical Energy Generated (MWH) 284,356.0 544,322.0 50,294,448.2 18.
Net Electrical Energy Generated (MWH) 269,380.5 517,017.4 48,001,793.7
- 19. Unit Service Factor 100.0 86.5 76.4 20.
Unit Availability Factor 100.0 86.5 76.4
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21.
Unit Capacity Factor (Using MDC Net) 83.9 76.4 68.1 22.
Unit Capacity Factor (Using DER Net) 83.9 76.4 66.6 23.
Unit Forced Outage Rate 0.0 13.5 3.6 24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Eacn):
None 25.
If Shut Down at End of Report Period, Estimated Date of Startup: N/A
- 26. Units In Test Status (Prior to Commercial Operation):
Forcast Acnieved l
l INITIAL CRITICALITY INITIAL ELECTRICITY N/A COMMERCIAL OPERATION
Refueling Information Fort Calhoun - Unit No. 1 Report for the month ending February 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 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 a y 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.
ILgvember 1991 5.
Important licensing c m siderations 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 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.
Prepared by M s Date 3-8-t I 1
i DOCKET NO. 50-285 UNIT NAME Fort Calhoun Station i
UNIT SIUIDOWNS AND POWER REDUCTIONS DA1E - March 7, 1991 COMPLETED BY M _ I_ _ Edwards I
TELEPil0NE (402) 636-24s1 REPORT HONIll February 1991 I
I i
5 E
3oj jg 3h*
g g jg e
g-ucensee cause a corrective No.
Date Event e
- e Action to I
o
$E Report #
o f f
Prevent Recurrence R
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E i
91-01 910211 S
O H'
4 N/A ZZ ZZZZZZ Power level reduced from 100% to 75% for fuel burnup conservation i
to allow extension of the fuel-l cycle to Jdnuary.1992.
i l
9 I
1 2
i 3
4 F-Forced Reasort Method Extelt G - Instructione S-Scheduled A-Equipment FaRure (Explain) 1-Manual for Preparation of Data g
B-Maintenance or Test 2-Manual Scram Entry Sheets for Ucensee q
C-Refuelno 3-Automatic Scram Event Report (LER) F11e (FRJREG-0169 i
D-ReOulatory Restriction 4-Other (Explain)
E-Operator Tsalnino a License Exarnination s
F-Administatfwe 5
ExNbit 1 - Some Source G-Operational Error f
Il-Orher (Explain)
OMAHA PUBLIC POWER DISTRICT fort Calhoun Station Unit No.1 February 1991 Monthly Operating Report I.
OPERATIONS SUtt%RY fort Calhoun Station operated at a nominal 100% power level until February 11, 1991, when power was reduced to 75% for fuel burn up conservation.
This was done to extend the fuel cycle to January 1992. On February 22, 1991 power was reduced to 70Y. for fuel cycle extension and to dampen feedwater regulating valve oscillations.
On February 12, 1991, Design Engineering Nuclear (DEN) and Plant Management detennined a condition existed outside the design basis in the station's Offsite Power Low Signal (0PLS) degraded voltage protection system.
The concern was that under a certain accident scenario, adequate voltage may not be present to assure long-term operation of some safety related 480 volt equipment. New OPLS setpoints were imediately installed and adninistrative measures were initiated to limit the operation of certain plant equipment. These steps will ensure that-the plant remains within the design basis of the degraded voltage protection system. The administrative measures recently initiated are being revised to allow more flexibility in -
operating plant electrical loads.
On February 4,1991 a discrepancy was identified concerning containment penetration M-3, Ch#al and Volume Control System (CVCS) injection header to the Reactor Coolant System (RCS). It was discovered that the justification for excluding the penetration from 10CFR50 Appendix J Type C leak rate testing was incorrect. The justification is documented in a Safety Evaluation Report (SER) dated January 1,1986 and states that the CVCS header will remain pressurized above containment pressure following a =
design basis accident. Reevaluation of the containment pressure transient following an accident showed-that containment pressure could exceed CVCS system pressure when the charging pumps are secured after emergency boration. A 1-hour notification was made to the NRC, and Safety Analysis for Operability (SA0) 91-01 was processed to support continued plant -
operation with operator actions implemented to ensure containment integrity. Long tenn actions to address the discrepancy.are currently being evaluated.
During the week of February 4, new solenoid valves were installed on:
emergency diesel generator (DG)-1 for the inlet air dampers. This cleared
. a temporary modification and resolved the historical problem of sluggish operation of the damptrs during cold weather. _DG-2 inlet air damper..
solenoid valves were also replaced during the week of February 25.
Testing was perfonned on DG-1 which verified the design adequacy of the starting air system. This included setpoint verification and the -
capability of. each starting air _ system to provide at least five engine-starts from the minimum expected receiver tank pressure.
- u.
. a
Monthly Operations Report Page Two 4
A modification to the DG-2 radiator ductwork was installed which allowed for steam cleaning the radiator as well as inspection aid fin combing.
This work was performed to increase the cooling capabihty of the engine.
Further testing was perfonned on the radiator fan t; lades to determine the optimum fan blade pitch for maximun air flow.
A modification was conpleted on DG-2 which replaced the obsolete speed sensing device. The DG-1 speed sensing devir will be replaced at a later date.
The follcwing NRC inspections took place in February:
IR-91-04 Radiation Protection IR-91-03 MonthlyInspection(fromJanuary 15, 1991 to February 26,1991)
The following LERs were submitted:
Qitt.e LER-91-01 Containment Tendon Surveillance not 02/08/91 in Accordance with Technical Specifications LER-91-S01 Security Door inadvertently left in 02/04/91 Access Mode LER-90-22 Rev. 2 Nonfunctional Fire Barrier 02/06/91 Penetrations A.
SAFETY VALVES OR PORV CHALLENGES OR FAILURES WHICH OCCURRED None B.
RESULTS OF LEAK RATE TESTS Results of the Reactor Coolant Leak Rate tests for February,1991 show that the RCS and CVCS had a very low average leak rate during the nunth. Total RCS leakage averaged 0.08 gpm divided equally between "known" and " unknown" leakage.
A few instances of negative leak rates occurred due to normal random variation of the test data.
Reactor power reductions may also have contributed to the negative leak rate occurrences. RCS leak rate test accuracy is reduced whenever the plant undergoes any departure from equilibrium conditions. Maximum leak rate for the month was recorded on February 4, when the total leak rate was 0.128 gpm, known leakrate was 0.032 gpm, and the unknown leakrate was 0.096 gpm.
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- Monthly Operations Report fage Three C.
CHANGES.-TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY C0tti!SSION AUTliORIZATION PURSUANT TO 10CFR50.59 Amendnent No.
Descriotion NONE D.
SIGNIFICANT SAFETY RELATED !%1NTENANCE FOR THE MONTH OF FEBRUARY 1991 Significant maintenance activities during the month of February included the following:
Component Cooling Water / Raw Water Heat Exchanger (AC-1C) was tabn out of service to replace the lifting lugs on the end bell flanges.
During Surveillance Testing the lockout relay (86A/ RAS) failed to trip in the Engineering Safeguanjs Panel (Al-30A). The coil burn',- due to the -
lockout relay binding up and was replaced.
Reset several 0PLS relays to trip at a higher voltage. This_was necessary due to recalculation of the Engineered Safeguards bus voltage during a transient.
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