ML20081L319
| ML20081L319 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 05/31/1991 |
| From: | Edwards M, Gates W OMAHA PUBLIC POWER DISTRICT |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| LIC-91-171R, NUDOCS 9107050001 | |
| Download: ML20081L319 (7) | |
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Omaha Public Power District 444 South 16th Street Mall Omaha, Nebraska 68102-2247 402/636-2000 June 14, 1991 LIC-91-171R U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station Pl-137 Washington, DC 20555
Reference:
Docket No. 50-285 Gentlemen:
SUBJECT:
May Monthly Operating Report (MOR)
Please find enclosed the May 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, 4 21. &
W. G. Gates Division Manager Nuclear Opera' ions WGG/sel Enclosures c:
LeBoeuf, Lamb, Leiby & MacRae 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 9107050001 910531 PDR ADOCK 05000285 i
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Omaha Public Power District 444 South 16th Street Mall Omaha, Nebraska 68102-2247 402/636-2000 June 14, 1991 LIC-91-171R V. S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station Pl-137 Washington, DC 20555
Reference:
Docket No. 50-285 Gentlemen:
SUBJECT:
May Monthly Operating Report (MOR)
Please find enclosed the May 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, 4 M./
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. 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 9 1 0 7 O *.10 0 0 1 910531 PDR ADOCK 05000285
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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-285 UNIT Fort Calhoun Station DATE June 4, 1991 COMPLETED BY M.L. Edwards TELEPHONE (402)636-2451 MONTH May 1991 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 351 17 342 2
351 18 342 3
350 19 346 4
350 20 348 5
350 21 347 6
349 22 344 7
351 23 341 8
352 24 341 9
352 25 340 10 351 26 341 11 349 27 340 12 348 28 338 13 346 29 336 14 344 30 337 15 344 31 335 16 344 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.
r
- 0PERATING DATA REPORT DOCKET N0.
50-285 UNIT Fort Calhoun Station DATE June 4, 1991 COMPLETED DY M.L. Cdwards TELEPHONE (402)636-2451 OPERATING STATUS 1.
Unit Name:
Fort Calhoun Statiori Notes 2.
Reporting Period:
May 1991 3.
Licensed Thermal Power (MWt):
1500 4.
Nameplate Rating (Gross MWe):
502 5.
DesignElectricalRating(NetMWe): 478 6.
MaximumDependableCapacity(GrossMWe):
502 7.
Maximum Dependable Capacity (Net MWe):
478 8.
IfchangesoccurinCapacityRatings(ItemNumbers3through7)SinceLastReport, 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 2,904.0 154,274.0
- 12.. Number of Hours Reactor was Critical 744.0 2,724.0 119,512.7-
- 13. Reactor Reserve Shutdown Hours 0.0 0.0 1,309.5
- 14. Hours Generator On-Line 744.0 2,713.2 118,143.1
- 15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
- 16. Gross Thermal Energy Generated (MWH) 838,25773 3,246,568.9 154,530,058.2
- 17. Gross Electrical Energy Generated (MWH) 273,060.0 1,075,350.0 50,825,476.2
- 18. Net Electrical. Energy Generated (MWH) 256,829.8 1,016,106.0
~'48,5D0,862.3 i
- 19. Unit Service-Factor-100.0 93.4 76.6 l
l
- 20. Unit-Availability Factor 100.0 93.4 76.6 l
- 21. UnitCapacityFactor(UsingMDCNet) 72.2 73.2 C3.1 1
- 22. Unit Capacity Factor (Using DER Net) 72.2 73.2 66.6
- 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 26.
Units-In Test Status (Prior to Commercial Operation): Forcast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY N/A COMMERCIAL OPERATION l
a
Refueling Information Fort Calhoun - Unit No.1 Report for the month ending May 1991
-1.
Scheduled date for next refuelir, shutdown.
January 31. 1992 2.
Scheduled date for restart following refueling.
May 1. 1992 i
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 i
any unreviewed safety questions are associated with the core reload.
N/A i
c.
If no such review has taken place, when is-it scheduled?
N/A 4.
Scheduled date(s) for submitting proposed j
licensing action and support information.
November 1991 5.
Important licensing considerations associated
. with refueling, e.g., new or dif ferent 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 D3 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.
o Prepared by F M h Date 6 6 't I
DOCKET NO. 50-285 UNIT hAME Fort Calhoun Station DATE June 7. 1991 UNIT SHUTDOWNS AND POWER REDUCTIONS COMPLETED BY M. L. Edwards TELEPHONE (402) 63o-2451 REPORT MONTH MAY 1991 l
No.
Date Type Duration Reason Method of Licensee System Componen Cause & Corrective j
(1)
(llours)
(2)
Shutting Event Cale Code (5)
Action to Prevent Recurrence l
Down Repost #
(4)
Reactor (3) 91-01 910'211 S
0 11 4
ZZ ZZZZZZ Operation at reduced power level (75 %) to extend fuel cycle to January 1992.
l l
l l
l 1
l l
l 1
2 3
4 F-Forred Reason:
Method:
Exhibit G - Instructions for Preparation of Data Entry Sheets S-Scheduled A-Equipment Failure (Explain) 1-Manual for Licensee Event Report (LER) File (NUREG-0161)
B-Maintenance or Test 2-Manual Scram C-Refueling 3-Automatic Scram D-Regulatory Restriction 4-Other (Explain)
E-Operator Training & License Examination 5
F-Administrative Exhibit 1 - Same Source G-Operational Error II-Other (Expfain)
- (9/77)
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OMAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No. 1 MAY 1991 Monthly Operating Report 1.
OPERATIONS
SUMMARY
Fort Calhoun Station operated at 75% power throughout the month of May 1991.
The plant is being held at 75% power to conserve fuel and allow operation until the scheduled refueling date of January 31, 1992.
The annual emergency preparedness (EP) exercise was conducted May 21 and 22, 1991.
Initial reactions from the NRC inspection team indicate that all but one open item from the last exercise will be closed and three new minor weaknesses may be identified.
On May 27, 1991, the NRC was inforned of a postulated high energy line break (HELB) of-an auxiliary heating steam line in an electrical penetration room which could affect redundant safety equipment. The potential for the HELB has been eliminated for the short term by isolating the auxiliary steam from this area.
The design wili be modified for permanent correction.
During the month of M:y.1991, a modification was completed to install air conditioning units to the static Exciter cabinets for emergency diesel generators DG-1 and DG-2.
The orig'nal design did not provide adequate cooling for many of the temperature-sensitive devices within the exciter / voltage regulator cabinets. The Ethylene-Glycol based antifreeze solution in DG-2's radiator was also replaced with water and rust inhibitor to improve diesel / jacket water cooling performance.
The coolant in DC-1 will be replaced in June.
Feedwater Pump, FW-48, was removed from service to repair a casing joint leak.
During repairs, areas of less than allowable minimum wall thickness were identified.
The pump vendor, Byron-Jackson, performed weld buildup repairs and re-machined the suspected areas.
The pump was in the process of reinstallation at the end of May.
The following NRC inspections took place in May:
IR-91-08 Annual EP Exercise IR-91-ll Emergency Preparedness IR-91-14 Resident's Routine Inspection The following LERs were submitted:
LER-91-08 Inappropriate Surveillance Requirements for RPS Level 1 Bistables LER-91-09 VIAS Actuation Due to Inappropriate Action A.
SAFETY VALVES OR PORV CHALLENGES OR FAILURES WHICH OCCURRED None
r,y e
i MONTHLY OPERATING REPORT l
MAY 1991:
B..
RESULTS OF LEAK RATE TESTS-The results of-the Reactor Coolant Leak Rate tests for Ha), 1991 indicate that the Reactor Coolant System (RCS) and Chemical and Volume Control System-(CVCS) are both relatively leak tight. Total RCS leakage averages a very. low 0.08 gpm, essentially divided evenly between "known" and " unknown" leakage.
The maximum leak rate for the month was recorded on May 22, when the total leak rate was 0.244 gpm and the unknown leak rate was 0.212 gpm. Charging pump CH-1B was found to be leaking at the packing-
~(while.in standby mode).
The pump was repacked and the plungers were replaced.
C.
CHANGES, TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY-
= -
--COMMISSION: AUTHORIZATION PURSUANT TO 10CFR50.59 Amendment-No.
Description None D.
SIGNIFICANT SAFETY RELATED MAINTENANCE FOR THE MONTH OF MAY 1991 Charging pump CH-1A and CH-1B were overhauled with new plungers, packing, suction & discharge valves.and valve seats.
Charging' pump.CH lC had one new valve, seat, and top cap installed.
DG-2 had the anti-freeze mixture drained from the cooling system and replaced with a water / rust inhibitor solution to improve summer operating performance.
-_ Breaker IA4-11 (for "B"_-Raw Water pump) experienced a cracked weld on-the strike plate as-.noted on an: inspection Preventative Maintenance
- Order (PM0) and the weld was repaired.
General Electric identified this problem in Service Advice Letter 325.1, which recommended inspection / repair of any cracked welds found, but indicated that-breaker-operatton would-not be affected.
Breaker 1B38-4 (for "A" Component Cooling Water pump) was found'to.
have oil leaking from all three of the phase trip devices. The trip devices were replaced.
HCV-507B (Containment Isolation Valve for thc Waste Gas Vent. Header) failed to stroke fully open during the~ pa formance.of a surveillance test. The problem was traced to the air solenoid,;which was replaced.
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