ML20066D844
| ML20066D844 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 12/31/1990 |
| From: | Gates W, Stice D OMAHA PUBLIC POWER DISTRICT |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| LIC-91-028R, LIC-91-28R, NUDOCS 9101170003 | |
| Download: ML20066D844 (8) | |
Text
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r Omaha Public Power District 444 South 16th Street Mall Omaha. Nebraska G8102-2247 402/636 2000 January 14, 1991 LIC 91-028R U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station PI 137 Washington, DC 20555
Reference:
Docket No. 50 285 Gentlemen:
SUBJECT:
December Monthly Operating Report (MOR)
Please find enclosed the December 1990 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, AV.Z?.5%
W. G. Gates Division Manager Nuclear Operations WGG/ sol Enclosures c: LeBoeuf, Lamb, Leiby & MacRao R. D. Martin, NRC Regional Administrator, Region IV R. P. Mullikin, NRC Senior Resident inspector D. K. Sentell, Combustion Engineering R. J. Simon, Westinghouse Office of Management & Program Analysis (2)
INP0 Records Center American Nuclear Insurers 9101170003 901231 PDR ADOCK 05000285 b
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AVERAGE DAILY UNIT POWER LEVEL I
DOCKET NO.
50 285 UNIT f6rt Calhoun Station DATE January 9, f791 COMPLETE 0 BY 0. L. Stice TELEPHONE (402)63F2474 MONTH December 1990 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWf> LEVEL (MWe-Net)
(MWe-Net) 1 488 17 0
2 488 18 0
3
_488 -
19 0
4 488 20 0
5 488 21 0
6 488 22 0
7 488 23 0
8 488 24 0
9 488 25 0
10 488 26 0
11 488 27 0
12 488-28 0
13 488 29 0
14 467 30 0
15 5
31 0
16 0
L-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 megcwatt.
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OPERATING DATA REPORT DOCKET NO.
50-285 UNIT Fort Calhoun Station DATE January 9, 1991 COMPLETED BY D. L. Stice TELEPHONE (402)636 2474 OPERATINGSTATES 1.
Unit Name:
Fort Calhoun Station Notes 2.
Reporting Period:
December 1990 3.
Licensed Thermal Power (MWt):
1500 4.
Nameplate. Rating (Gross MWe):
502 5.
Design Electrical Rating (Net MWe):
478 Maximum Dependable Capacity ((Gross MWe):
502
- f.,
Maximum Dependable Capacity NetMWe):
478 7.
8.
If changes occur in Capacity Ratings (Ttem 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 8,760.0 151,370.0 12.
Number of Hours Reactor was Critical 348.6~
5,622.4-116,788.7
- 13. Reactor Reserve Shutdown Hours 0.0 0.0 1,309.5 14.
Hours Generator On-Line 339.7 5,424.5
- 115,429.9'
- 15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
- 16. GrossThermalEnergyGenerated(MWH) 502,831.6 7,668,378.1 151,283,489.3
- 17. Gross Electrical Energy Generated (MWH) 171,600.0 2,540,018.0 49,750 126.2 18.
Net Electrical Energy Generated (MWH) 163,610.5 2,417,223.5 47,484I776TI~
- 19. Unit Service Fa: tor 45.7 61.9 76.3
- 20. Unit Availabili-y i;ctor 45.7 61.9 76.3
- 21. UnitCapacityFactor(UsingMDCNet) 46.0 57.7 68.0
~
22.
Unit Capacity Facto' (Using DER Net) 46.0 57.7 66.5 23.
Unit Forced Outage Rate 54.3 13.5 3.5 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: Januarv 8.
1991
- 26. UnitsinTestStatus(PriortoCommercialOperation):
Forcast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY N/A COMMERCIAL OPERATION 1
Refueling Information Fort Calhoun - Unit No.1 Repart for the month ending _Ofttember 1990 1.
Schejuled date for next refueling shutdown.
September 1991 2.
Scheduled date for restart following refueling.
November 1991 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.
H/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.
June 1911 5.
Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unroviewed 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 M1 Assemblies b) in the spent fuel pool 477 Assembli n c) spent fuel pool storage capacity 729 Assemblin 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 : pent fuel pool assuming the present licensed capacity.
1994*
Capability of full core offload of 133 assemblies lost, prepared by C.jdm Date l - 6 'i i I
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DOCKET NO. 50-285 UNIT NADE Fort Calhoun Station DATE _lanuarv 9.
19at UNIT SHUTDOWNS AND POWER REDUCTIONS CO R ETED BY n.
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REPtRT MONTH December 1990
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90-08 901215 F
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1 LER 90-028 XX PSX, AA On December 15, 1990, a through-wall i
i leak on an installed spare Control Element Drive Mechanism (CEDM) i pressure houting was identified and a cooldown to cold shutdewn was initiated.
The affected CEDM housing and a second installed spare housing were removed and replaced with blank flanges, i
- See LER 90-028 for further cause and t
corrective actiorr.
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1 2
3 4
F-Forced Ressort Method Ex!4it G - Irictnsettene 3-Schedded A-Equipment Failure IExplairt 14denmal for Properation of Date B-Makitenance or Teet 2-Manumi Scram Entry Sheets for Uconome 1
C MJ, 3-AutomeGe Scram Event Report SR4 F3e PluPEG-0184
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D-Regulatory Restriction 4-Other Expiebt E-operator Tretreno a Ucense Examine 6cn 5
F-Advdrdotative Exteft 1 - Some Source G-Operettanet Error l
H-Othat tExplek)
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OMAHA PUBLIC POSER DIS 1RICT Fort Calhoun Station Unit NO. 1 December 1990 Monthly Operating Report 1.
OPERA 110NS
SUMMARY
fort Calhoun Station operated at a nominal 100'r, power until December 14, 1990, when a power reduction to hot standby was initiated to investigate a possible Reactor Coolant System (RCS) leak in the reactor vessel (RV) head area.
On December IS, a through wall leak on an installed spare control element drive mechanism (CEDM) pressure housing was identified and a cooldown to cold shutdown was initiated.
The affected CEDM housing and a second installed spare housing were removed and replaced with blank flanges.
Both housings had several identified deep cracks.
Detailed metallurgical analyses showed it was caused by transgranular stress corrosion cracking (TGSCC).
This cracking phenomenon has been attributed to high oxygen levels in the housings which have not been vented since initial startup.
Two other installed spare CEDM housings, which had heated junction thermocou)les installed in 1982 for reactor vessel level monitoring, were clocked by ultrasonic testing and showed no signs of
- cracking, The active CEDM housings are not considered susceptible to TGSCC since they are self-venting.
Preparations are presently underway for plant startup.
New fuel oil transfer pumps were installed on Emergency Diesel Generator No. 1.
Startup of the water plant is complete after modifications.
The following NRC inspections took place in December:
IR 90 36 Maintenance Team inspection IR 90-39 Monthly inspection (October 23 thru December 4, 1990) 1R 90 45 Monthly inspection (Continued from December 5, 1990)
The following LERs were submitted:
LER-90 22, Rev. 1 Degraded Fire Barriers LER 90 25, Rev. 1 Component Cooling Water System Outside De3ign Basis LER-90-26 Manual Reactor Trip 000 to loss of Instrunent Air Pressure A.
SAFETY VALVES OR PORV CHALLENGES OR FAILVRES WHICH OCCURR D None B.
RESVLTS Of LEAK RATE TESTS The results of the Reactor Coolant Leak Rate Tests for December,1990 indicated a continuation of the elevated unknown leakage that began in October, 1990. An ongoing investigation of the high RCS leak rate concluded that the source of the leakage was arobably a component on the RV head.
This assumption was reinforced ay fire detector alarms on the head vent fans. The plant was taken to hot standby to inspect the RV head on December 14, 1990.
The inspection involved removal of
i the in Core Instrumentation (101) penetration covers from the RV head seismic skirt. Once the covers were removed, evidence of the leak was apparent.
Steam was blowing from the CEDM #9 pressure housing and a large quantity of boric acid crystals was found in the area. The
)lant was taken tn cold shutdown and tha spare CEDMs were removed and
'iind flanged.
The leak was caused by a through wall transgranular a
stress crack.
Two other similar CEDM pressure housings were ultrasonically tested and no indications were found.
The highest RCS total leak rate for the month was 0.672 gpm on December 12.
The lowest for the month was 0.286 gpm on December 13.
The "known" RCS leakage to the Reactor Coolant Drain Tank and the Quench Tank remained low, therefore, the source of the excessive leakage was considered " unknown".
C.
CHANGES, TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY COMMISSION AUTHORIZATION PVRSUANT T0 10CFRSO.59 Amendment _[h Deser19112D No. 135 This amendment makes changes to the Technical Specifications to delete redundant surveillanct requirements and correct an error contained in the Technical Specification.
Also a specification was renumbered as a result of deleting specifications.
No. 136 This amendment makes changes to the fort Calhoun Technical Specifications to restrict the containment spray system use as a backup for shutdown cooling.
D.
SIGNIFICANT SAFETY RELATED MAINTENANCE FOR THE MONTH OF DECEMBER Significant safety related maintenance activities completed in the month of December are outlined below:
Charging Pump CH lc tripped free upon trying to start pump.
The cause of the failure was a faulty trip device.
Post Maintenance Testing was done in accordance with the Calibration Procedure and Operability Testing was performed by running the motor two times.
While performing the Surveillance Test on HCV-403C it was noted that the valve started to move to its failed position before the instrument air was vented off.
The nature of the failure was deteriorated gaskets on the operator allowing air leakage.
Post Maintenance Testing required a leak test and cycling of the valve.
Operability Testing required completion of applicable sections of the SurveHlance Te-t, On Diesel Generator Number One (DG-1), the governor speed setting motor was running slow, causing DG 1 to fail its ten second starting requirement.
The motor was replaced.
Post Maintenance testing required verification of the speed setting in both the slow and fast speed modes.
Operability Testing was verified by performance of the Surveillance Test.
Trouble shooting of the qualified Safety Parameter Display System Panel revealed a failed thermocouple card for heated junction thermocouple probe YE-ll68.
The cause of the failure was a bad mul tiplexor.
Post Maintenance Testing was performed in accordance with the applicable sections of the calibration procedure.
During the forced outage commencing December 16, 1990, (see Operations Surrenary) many maintenance items were completed / corrected, including the following:
Replaced Heater Drain Tank to Condenser Dump valve, (LCV-1198).
Rebuilt a sample valve (HCV 2504A) off the primary system.
Rebuilt the steam seal feed valve to eliminate leakage past seat.
Repaired MS 164 (HCV 1040 isolation valve).
The drain off of RC 2A feedwater line was capped (fW 1002) due to
)
valve leaking through.
Replaced the solenoid on the component cooling water valve (HCV-491A) to heat exchanger AC-lC.
Replaced oil line in Reactor Coolant Pump Motor (RC-3A).
Repaired limit switch mounting to give proper control room indication on the letdown isolation valve (TCV-202).
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