ML20245A158
| ML20245A158 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 05/31/1989 |
| From: | Cook G, Morris K OMAHA PUBLIC POWER DISTRICT |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| LIC-89-607, NUDOCS 8906210123 | |
| Download: ML20245A158 (19) | |
Text
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n.sa e s& 4 Omaha Public Power District 1623 Hamey Omahn. Nebraska 60102 2247 402/536-4006 June 15, 1989 LIC-89-607 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station PI-137 Washington, DC 20555
Reference:
Docket No. 50-285 Gen tlemsa:
SUBJECT:
May Menthly 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 May 1989 Monthly Operating Report for the Fort Calhoun Station Unit No. 1.
Sincerely,
~l}kw
. J. tiorris Division Manager Nuclear Operations KJM/jak c: P. H. Harrell, NRC Seni 'r Resident Inspector Office of Management & Program Analysis (2)
R. M. Caru:;o - Combustion Engineering R. J. Simon - Westinghouse Nuclear Safety Analysis Center IlvP0 Records Center American Nuclear Insurers 8906230123 DR 090531
- ADOCK 05000205 rwu
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AVERAGE DAILY UNIT POWER LEVEL t
DOCKET NO. 5_0-285 UN:T Fort Calhoun Station DATE lune 13,1980 COMPLETED SY G. M. Cook TELEPP.0NE 402-636-2490 .
MONTH MAY 1989 i
DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)
I i
1 0 17 358 2 0 18 430 _
3 0 19 439 4 0 _
20 457 ;
5 72 21 4E3 i 6 124 __ 22 464 !
7 0 23 463 ,
l 8 0 _
24 462 _,
9 0 ,__ 25 463 10 0 _ , , _ _ 26 __ 464 11 0 27 465 j 12 0 28 466 __ j 13 _
0 29 464 14 71 30 463 15 110 31 463 J I 16 149 l
INSTRUCTIONS l
l On this format, 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 0ATA REPORT DOCKET N0. 50-285 UNIT Fort Calhoun St6 tion DATE Dune 13.1089 COMPLETED BY G. M. Cook TELEPHONE 402-636-2490 OPERATING STATMS,
- 1. Unit Name: Fort Caihoun Station Notes
- 2. Reporting Period: May 1989
- 3. Licensed Thermal Power (MWt): 1500
- 4. Nameplate Rating (Gross MWe): 502
- 5. Design Electrical Rating (Net MWe): 478 !
l 6t MaximumDependibleCapacity(GrossMWe): 502 l 7. MaximumDependableCapacity(NetMWe): 478 l 8. IfchangesoccurinCapacityRatings(ItemsNumber3Through7)SinceLastReport, Give Reasons:
N/A
- 9. P6Mer Level to Which Restricted, If Any (Net MWe): N/A
- 10. Reesons for Restrictions, If Any: N/A 4
This lionth Yr-to*Date Cumulative
- 11. Hours in Reporting Period 744.0 3.623.0, 137.473.0
- 12. Number of Hours Reactor Was Critical 583.3 2.760.8 106 130.6
- 13. Recctor Reserve Shutdown Hours 0.0 "
0,0 1.309.5 l 14. Hours Generator On-Lire 469.1 2.563.3 104.978.6
- 15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
- 16. Grco Thermal Energy Generated (MWH) _ 581.337.7 _3.438 550.0 .]36.327.543.9 - ,
- 17. GrossElectricalEnergyGenerated(MWH) ,.__185.8 % 0_ 1.117.184.0 44 J61.312 2 , !
- 18. Net Electrical Energy Generated (MWri) 175.450.5 1.061.423.1 42.832.927.9 _ !
- 19. Unit Service Factor 63.1 70.8 76.4 j
, 20. Unit Availah'lity Factor 63.1. 70.8 76.4 1 21 UnitCaracityFactor(UsingMDCNet) 49.3~ 61.3 _ '67.4
- 22. Unit Capacity Factor (Using DER Net) 49.3 61.3 65.8
- 23. Unit Forced Outage Rate . 27.0 6.3 3_. 0
- 24. Shutdowns Schedu hd Over INxt 6 Months (Type, Date, and Duration of Each):
None
- 25. If Shut Down at End of Report Period, Estimated Date of Startup: N/A ,
- 26. Units In Test Status (Priar to ConnercM Operation): Forcast Achieved INITIAL CRITICALITY '
.~
INITIAL ELECTRICITY N/A COMMERCIAL OPERATION i
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Refueling Information Fort Calhoua - Unit ho. 1 Report for the month ending May 1989
- 1. Schaduled date for next refueling shutdown. February 1990
- 2. Scheduled date for restart following refueling. Hav 1990
- 3. Will refueling or resumption of operation thereafter require a technical specification change or other license ameindment? Yes ,__
- a. If ar.swer is yes, what, in general, will these be?
I - Incorporate specific requirements l resulting from reload safety ana' lysis l
- b. If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Comittee to deter-mine whether any unreviewed safety questions are associated with the core reload. _
- c. If no such review has taker, place, when is it scheduled?
- 4. Scheduled date(s) for submitting proposed licensing l 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 cnanges in fuel design, new operatin'J procedures. __None Planned 6 The nmnber of fuel assemblies: a'; in the core ,
133 assemblies h) in the spent fuel pool 437 "
c) spent fuel pool t storage capacity __,, 729. "
l d)plannedspentfuelpool May be increased storage capacity via fuel ain !
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. 19.94*
- Full core offload of 133 assemblies lost.
Prepared by 4 -:4M C Date June 14, 1989
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i OMAHA PUBLIC POWER DISTRICT i Fort Calhoun Station Unit No. I l 1 May 1989 .
Monthly Operations Report
- 1. OPERATIONS
SUMMARY
Fort Calhoun Station I
Fort Calhoun Station was returning to power operation May 1, 2989, after turbine overspeed testing and auxiliary feedwater pump full flow tests, when it was discovered that main feedwater isolation valves wo.uld not close.
Further investigation showed that the torque switches were set too low for the valves to close against the design differential pressure of 1500 psi. A one hour report to the NRC was rude as a result of the valves being outside -
their design basis criteria. The torqce swstches were reset using M0 VATS..
The plant was placed on-line May 5 and power was increased to approximately 40% power. A plug in the pressure boundary of a check valve in the main i feedwater line was leaking and required 3 plant cooldown to repair. The i plant was taken off line May 6 and placed in cold shutdown. During the cold shutdown numerous maintenance items were perf6rmed wh ch could normally not i be done including a blacklight of the condenser to identify tube leaks. The !
plant was placed back on-line May 14 and . reached 100% May 20 where it has ,
remained for the rest of May. After placing the plant on-line one of the pipe plugs in the body of a main feedwater check valve was found to still ,
leak. A cap as welded over the plug to isolata the leakage. I Emergency diesel generator DG-2 was out of service several days for repair of the voltage regulator which would' initially control voltage too high: DG-2 also had governor adjustments and oil change performed.
Charging pump CH-1A has been out of service to determine why it has reduced flowrate. Investigations continue. 1 1
QSPDS (Qualified Safety Parameter Display System) Channel B modifications were completed.
As part of the design basis reconstitution effort, it was determined thnt l l some of the alternate Shutdown Panel power supplies were not independent of l
the Control Room. A one hour notification was made to the NRC. '
The water plant clarifier was out of service for repair and recoating. the l l presedimentation is out of service for similar repair, i Construction continues on the Chemistry /Radiaticn Protecticn Buildings.
During May, 1989, one License Senior operator resigned. One Shift Supervisor was transferred to the scheduling department. 1
l Monthly Operations Report I May 1989 I Page 2 During the month of May,1989, normal inspection activities were coriducted by ]
the NRC resident and senior resident inspectors, Mr. Ray Mullikin also l contributed to this inspection by revleMing fire pfotection issues. Mr. !
Nemen Terc conducted an inspection of emergency preparedness, including ;
review and closeout of pteviously identified inspection findings. Mr. A. B. 1 Earnest conducted 6 three-day inspection of the security area, following up l on a previous inspection. Mr. Gene Bates was a visitor at Fort CalMun on May 16 and 17, touring areas of interest to emergency planning.
i No s'a fety valves or PORV challenges or failures occurred. l 1
A. PERf0RMANCE CHARACTERISTICS l l
None j l
B. CHANGES IN OPERATING METHODS None j C. RESULTS OF SURVEILLANCE TESTS AND INSPECTION 5 l Wone '
l D. CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL i Procedure Description l
SP-FRCPT-1 Post Refueling Core Physics Te ting and Power Ascension.
This procedure did not constitute an unreviewed safety qu6stion as defined by 10CFR 50.59 because the Cycle I? low power physics testing was completed with acceptable results. All predictions were within the acceptance l criteria for the measured values. Power tscension was !
accomplished in a safe manner in accordance with fuel j preconditioning guidelines.
SP-FW-11 Auxiliary Feedwater Pump Operation Test This test performed a full flow cepacity test for both FW-6 and FW-10 at low power levels (< 2%). This procedure did not constitute an unreviewe.d safety question as defined by 10CFR 50.59 as the test was performad within the controls q of 01-FW-4 " Auxiliary Fnedwater Pump operation and Testing '
Auxiliary Feed Operatica". Therefore ne new or unanalyzed operating mods were created that would present an unreviewed safety question. j
_- _ _ _ a
Monthly Operations 'Raport May'1989 ;
Page 3 l l
)
D. CHANGES, TESTS AND EXPERIMENTS' CARRIED OUT WITHOUT COMMISSIO'N APPROVAL..
(Continued)
]
System Acceptance f ommitteo Packages for May 1989:
fig _k3gg Description / Analysis
-FC-83-169 Improved Fire Pump Performance.
This modification replaced jockey pop and FP-1 with new .!
l pumps, i- l This modification does not have an adverse effect on the.
safety analysis.
FC-83-080A Upgrade Water Plant Sampling This modification installed two Martek processors and a Yew recorder / alarm unit in the water plant.
This modification does not have an adverse effect on the safety analysis, FC-78-002 Main Steam Line Containmen Penetration Sleeve E;.pansion Joint Replacement This modification removed concrete from under main steam-penetration expansion bellows.
]
This modificct.on docs not have an adverse effect on the I safety analysis. ;
E. RESULTS OF LEAK RATE TESTS Reactor coolant leak rate increased slightly during the month. It was ;
determined that the increase in leak rate was caused by excessive '
packing leakage from CH-lC. The pump packing was replaced and the leak rate returned to normal.
F. CHANGES IN PL?.NT OPERATING STAFF ,
See appropriate paragr6ph on report.
One new operator hired during the month of May.
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Monthly Operations Report May'1989-Page 4 '
G. TRAIMNG During the month of May, construction of the simulator continued. As of the end of the month, 26 models have been successfully integrated and the simulator could be maneuvered, although'.in a limited fashion, from i 100% to 50% power. Progress is sufficient to assume that official !
combined acceptance test program can begin on ' July 1,1989. I The SR0 class continues with OJT training. The R0 class continues in preparation for the NRC Fundamentals exam in June. A comparison between the fundamentals exam bank and the Fort Calhoun Station objectives show that no additional objectives are required.
The annual CPPD licensed operator requalification exams continue. To date, all licensed operators have passed their examination. An EONA class, with three (3) participants, was completed and en EONT class, with nine'(9) participants, was initiated.
System Engineer training continues in week 15 of the classroom training. All Emergency Operating Procedures have been written and validated. Twenty-two of the thirty-one A0P's have been drafted.
The QA Training Program Master Plan has been sent to QA for review. l Development of the Storeroom Training Program was initiated. j i
H. CHANGES, TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY COMMISSION AUTHORIZATION PURSUANT T0 10CFR50.59 Amendment No. Description Amendment No. 120 This amendment modified thu Technical Specifications to change the minimum operating rt,quirements for the Raw Water Pumps to allow operations with one inoperable raw water pump when river water temperature is below 60*F.
Amendment No. 121 This amendment modified the Technical Specifications (TS) to (1) change'the containment-spray system surveillance testing i requirements to provide a quantitati'v e value to define the minimum acceptance criteria, (2) change the Basis of the containment spray system surveillance requirements by providing the minimum spray flow requirements determined from analysis, (3) reduce the' maximum power level ;
permitted on Figure 2-'7, timiting Condition for Operation for Departure from Nucleate Boiling Monitoring, (4) correct the neutron fluence' ,
value stated as occurring at 14 Effective Full l
I
Monthly Operations Report Hay *1989 Page 5 Power Years (EFPY) at the inner surface of the reactor vessel wall at19the cr{tical weld loggtion{ rom 1.4x10 n/cm to 1.21 x 10 n/cm , (5) revise Figure 2-3, Predicted Radiation Induced NDTT Shift, based on !
calculations using US NRC Regulatory Guide 1.88, Revision 2, and (6) changing the references in TS 3.6 from "FSAR" to "USAR" and adding an additional reference to USAR Section 14.16.
II. MAINTENANCE (Significant Safety Related)
]
See attached printout.
1 i
j G. R. Peterson Manager-Fort Calhoun Station I
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