ML20082R909
| ML20082R909 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 08/31/1991 |
| From: | Edwards M, Gates W OMAHA PUBLIC POWER DISTRICT |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| LIC-91-243R, NUDOCS 9109160299 | |
| Download: ML20082R909 (8) | |
Text
-
Omaha Public Power District September 13, 1991 444 South 16th Street Mall LIC-91-243R Omaha, Nebraska 68102-2247 402/636-2000 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 (MOR)
Enclosed is the August 1991 MOR for Fort Calhoun Station (FCS) Unit No. I as required by FCS Technical Specification Section 5.9.1.
If you should have any questions, please contact me.
Sincerely, A&. N br W. G. Gates Division Manager Nuclear Operations WGG/sel Enclosures c:
LeBoeuf, Lamb, Leiby & MacRae R. D. Martin,'NRC Regional Administrator, Region IV R. P. Hullikin, 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 C109160299 910831 PDR ADOCK 0S000285
,/,' g d p
PDR s
- Ne$F 45 5124 i
\\
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-285 UNIT Fort Calhoun Station DATE
-September 9, 1991 COMPLETED BY M.L. Edwards TELEPHONE (402)636-2T51 i
MONTH August 1991
-i DAT-
. AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 465 17 446 2
461 18 446 3
441 19 456 4
441 20 468 5
443-21 470 6
457 22 470
~
7 467 23 469 8
468 24 467 9
469 25 467 10 469 26 467 11 469 27 466 11 431 28 467 13 30 29 467 14 98 30 466 15 99 31 466 16 325-i l
INSTRUCTIONS r
0n 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.
l
i 0PERATING DATA REPORT DOCKET NO.
50-285 UNIT Fort Calhoun Station DATE-September 9, 1991 COMPLETED BY M.L. Edwards TELEPHONE (402)636-2451 OPERATING STATUS
-1.
Unit Name:
Fort Calhoun Station Notes
- 2.. Reporting Period:
August 1991 3..
Licensed Thermal Power (MWt):
T500 4.
Nameplate Rating (Gross-MWe):
502 5.
Design Electrical Rating (Net MWe): 478
- 6. -Maximum Depeadable Capacity ((Gross MWe):
__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;
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 5,831.0 157,201.0 L
- 12. Number-of Hours Reactor.was Critical 744.0 5,651.0 122,439.7~
13.- Reactor Reserve Shutdown Hours-0.0 0.0 1,309.5
- 14. Hours Generator 0n-Line 730.5 5,626.7 121,05b.6
- 15. Unit Reserve Shutdown Hours.
0.0 0.0~
0.0
+
16; -Gross Thermal Energy Generated (MWH) 1,007,756.3 6,993,830.8 158 277,320.1
- 17. GrossElectricalEnergyGenerated(MWH) 328,556.0 2,296,344.0
~~57,,046,470.i~
18..NetElectricalEnergy. Generated-(MWH) 311,831.3 2,172,373.0 49,657,149'.~I-19.1 Unit Service Factor 93.2=
96.5 77.0
'20.
Unit' Availability Factor 98.2 96.5 77.0
- 21. Unit _ Capacity Factor (Using MDC Net) 87.7 77.9 68.4
- 22. Unit Capacity Factor (Using DER Net) 87.7 77.9 66.9
- 23. Unit-Forced Outage Rate 1.8 3.5 3.5 l
24.-
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):-
Refueling outage scheduled to start on January 31, 1992 and last approximately three months.
25.
If Shut Down at End of Report Period, Estimated Date of Startup: N/A l
J26. Units'!n Test Status (Prior-to Commercial Operation):- Forcast
-Achieved L
I'ITIAL CRITICALITY INITIAL ELECTRICITY N/A
[
' COMMERCIAL OPERATION
Refueling Information Fort Calhoun - Unit No.1 Report for the month ending A_uaust 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 resul,ing 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.
U/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.
Reracking to be performed o
between the 1993 and 1995 Refueling Outages.
Prepared by C
rdN Date i+9/
i 1
1 DOCKET NO. 50-285 UNIT NAME Fort Calhoun Station DATE September 13. 1991 UNIT SHUTDOWNS AND POWER REDUCTIONS COMPLETED BY M. L. Edwards TELEPHONE (402) 636-2451 REPORT MONTH AUGUST 1991 Cause & Corrective No.
Date Type Duration Reason Method of Licensee System Component Action to (1)
(Hours)
(2)
Shutting Event Code Code (5)
Prevent P -
Down Report #
(4)
Reactor (3) l 91-04 910813 F
13.5 A
4 N/A EA XXXXXX A potential transformer failed in the 345 KV switch yard and was replaced. The reactor wa, held at less ths.- 10% power and the main generator was taken off-line to facilitate replacement, t
l 3
4 I
2 Exhibit G - Instructions for Preparation of Dats Entry Sheets-Afethod:
F-Forced Reason:
for Licensee Event Report (LER) File (NUREG-0161) 14fanual S-Scheduled A-Equipment Failure (Explain)
B-Maintenance or Test 24f anual Scram 3-Automatic Scram C-Refueling D-Regulatory Restriction 4-Other (Explain)
E-Operstor Training & License Examination 5
F-Ad ninistrative Exhibit 1 - Same Source G-Operational Error H-Other (Explain)
(9/77)
OMAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No. I l
AUGUST 1991 Monthly Operating Report I.
OPERATIONS
SUMMARY
Fort Calhoun Station reduced power from 100% to 95% on August 2,1991, for a Technical Specification required surveillance test on the reactor moderator temperature coefficient.
Power operation at approximately 100%
resumed on August 6, 1991. A power reduction was initiated on August 12, 1991 in preparation for the replacement of a failing potential transformer in the 345KV switch yard. On August 13, power was held at less than 10%
and the main generator was taken of; line to facilitate replacement of the potential transformer. The main generator was placed back on line later that day and power was increased to 30% and held for steam generator water chemistry considerations.
The station resumed operating at approximately 100% power on August 19, 1991.
A design basis deviation was identified where, during the recirculation phase of safeguard actuation, water from the containment sump could potentially leak back through isolation valves to the safety injection refueling water tank. The resultant leakage of iodine through the vents and to the environment could be above permissible icvels based on the
{'
present design basis assumptions.
A Safety Analysis for Operability justified operation until the solation valves are replaced during the 199?
refueling outage.
One of the laterals in the A" anion resin bed in the water treatment plant broke, allowing resin to carryover to that trains cation and mixed bed resin tanks.
Due to this failure and the condition of the other purification train, a vendor trailer was brought in as a backup source of water while repairs and replacement were completed.
Receipt of new fuel for Cycle 14 refueling is in progress.
The following NRC inspections took place in August:
IR 91-20 Routine Resident inspection IR 91-22 MOV (Generic Le"er ES10) Inspection The following LERs were submitted:
LER-91-015 Radiat'.on Monitor RM-060 Inoperable Due to Seismic Concerns LER-Pl-016 Diesel Generator Failed Roll Pins A.
SAFETY VALVES OR PORV CHALLENGES OR FAILURES WHICH OCCURRED NONE
Monthly Operating Report
- o Page Two B.
RESULTS OF LEAK RATE TESTS Monthly reactor coolant (RC) leak rate testing indicates that the reactor coolant system (RCS) and chemical and volume control system are both relatively leak tight.
Total RCS leakage averaged approximately 0.18 gpm during August.
The maximum leak rate was recorded on August 19th when the total leak rate was 0.367 gpm and the unknown leak rate to the RC drain tank was 0.128 gpm.
Charging pump CH-1A was determined to require repacking.
The leak rate returned to normal after CH-1A was repacked.
At the end of August, the leak rate increased slightly.
At this time, the cause of the increased leak rate is unknown.
C.
CHANGES, TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY COMMISSION AUTHORIZATION PURSUANT TO 10CFR50.59 Amenim_gnt No.
Description NONE D.
SIGNIFICANT SAFETY RELATED MAINTENANCE FOR THE MONTH OF AUGUST 1991 Raw water pump AC-10A was replaced with a rebuilt pump.
An inspection of the replaced pump's internal parts did not find any unexpected wear.
Post maintenance test results were satisfactory and r.ew baseline data was recorded.
Surveillance testing indicated there was a problem with the component cooling water (CCW) pump AC-3A inboard bearing.
The problem was due to normal wear and the pump was overhauled.
Surveillance testing verified operability of CCW pump AC-3A.
The gear box on raw water strainer AC-12A was rebuilt due to bearing f ailure caused by aging fatigue and normal wear.
The wide range logarithmic drawer nuclear instrument channel "B" high voltage light came on repeatedly.
Troubleshooting determined that tne high voltage bistable card had to be replaced.
After the card was replaced, applicable portions of the calibration procedure were performed.
Charging pump CH-1A developed a plunger packing leak. The gear box had water in it and was leaking oil.
Repairs included replacement of the packing, plungers, springs, packing adjustment rings, oil and oil filters. The baffle seal packing was replaced between the power end and the packing cooling well.
Surveillance testing verified operability of charging pump CH-1A.
Later in the month excessive leakage again developed from charging pump CH-1A and new packing was installed.
i l
Monthly Operating Report
.Page Three Diesel Generator (DG-2) coolant pump seals were leaking coolant out of the pump weep hole. The water pump was disassembled, inspected, and the shaft seal was replaced. Operability testing was done which required DG-2 to be loaded for a minimum of one hour.
Tlie boron concentration in safety injection (SI) tank SI-6D was found to be below the administrative limit of 2,000 ppm (Technical Specification limit is 1,900 ppm). The other three (3) Si tanks were found to be near the administrative limit.
Boric acid was added to all four (4) tanks and testing verified that each tank's boron concentration was above the administrative limit.
Maintenance activities during the outage (to repic.e the failed potential transformer) on August 13, 1991 included the following:
Replaced the positioner on the feedwater control to steam generator A operator (FCV-1101) with a rebuilt positioner.
Problems developed with the rebuilt positioner and the original positioner was reinstalled.
- Adjusted packing on the reactor coolant loop 2 sampling flow control valve (HCV-2501).
Replaced the valve seat on condenser "A" backwash valve (MOV-A-B2).
.--,.._____.____._m._
.______m._
p
__