LIC-95-0087, Monthly Operating Rept for Mar 1995 for FCS
| ML20082J526 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 03/31/1995 |
| From: | Lippy D, Tira Patterson OMAHA PUBLIC POWER DISTRICT |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| LIC-95-0087, LIC-95-87, NUDOCS 9504180272 | |
| Download: ML20082J526 (8) | |
Text
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Omaha Public Power District 444 South 16th Street Mall Omaha. Nebraska 68102-224' 402/636-2000 April 13,1995 LIC-95-0087 l
U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station P1-137 Washington, DC 20555
Reference:
Docket No. 50-285
SUBJECT:
March 1995 Monthly Operating Report (MOR)
Enclosed please find the March,1995 MOR for Fort Calhoun Station (FCS)
Unit No. 1 as required by FCS Technical Specification 5.9.1.
If you should have any questions, please contact me.
Sincerely, h
W T. L. Patterson l
Division Manager i
Nuclear Operations i
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TLP/dll j
Enclosures c:
LeBoeuf, Lamb, Greene & MacRae j
L. J. Callan, NRC Regional Administrator, Region IV 1
S. D. Bloom, NRC Project Manager i
R. P. Mullikin, NRC Senior Resident Inspector j
R. T. Pearce, Combustion Engineering R. J. Simon, Westinghouse INP0 Records Center i
45-5124 I,0 C T C Q
~ Employment with Equal opportunity p/(
9504180272 950331
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PDR ADOCK 05000285
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1 LIC-95-008'7 Enclosure Page 1-
.0MAHA PUBLIC POWER DISTRICT Fort Calhoun. Station Unit No. 1 March 1995 Monthly Operating Report 1.
OPERATIONS
SUMMARY
The 1995 Refueling Outage continued throughout the month of March.
As of the end of March, the reactor had been defueled and refueled, the majority of engineered safeguards testing had been completed, and.the reactor headL had been reinstalled.
On. March 1,
it,was discovered that oil -hadLleaked 'from' Lube Oil-Conditioner LO-2 into the turbine building basement sump.
The sump pumps-were immediately secured and clean-up was initiated.
The:140-gallon oil spill was reported' to the Nebraska Department of Environmental Quality (DEQ) and the NRC.
Fuel sipping identified seven fuel assemblies. with suspected fuel pin failures. During reconstitution, the confirmed failed' pins were' replaced with stainless steel and a. visual inspection of the ' failed pins was performed with a high resolution camera.. Fourteen ofc the sixteen identified fuel pins had positive visual indication.of' failure due to grid-to-rod fretting.
Work continues on modification to the Control' Room air conditioners to address the design basis Component Cooling Water (CCW) temperature issue (Reference Licensee Event Report (LER)94-010, RevisionL ).
1 The following NRC inspections were completed during this reporting period:
IER No. 95-05 Inservice Inspection Program IER No. 95-06 Radiological Controls The following LER was submitted during.this reporting period:
LER 94-010, Rev 1-Potential. Accident ' Scenario ' Involving Loss of Control Room Air-Conditioners
-2.
-SAFETY VALVES OR PORV CHALLENGES OR FAILURES WHICH OCCURRED During the month of March, no Power.0perated Relief. Valve (PORV) or Primary System Safety Valve challenges or failures occurred.
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.i LIC-QS-0087 l;
Enclosure l
Page 2
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RESULTS OF LEAK RATE TESTS No ' Reactor Coolant. Leak Rate-information.. is being reported. this month.
j because of-the Refueling Outage.
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CHANGES. TESTS AND EXPERIMENTS RE0UIRING NUCLEAR REGULATORY COP 94ISSION:
AUTHORIZATION PURSUANT TO 10CFR50J1 l
3 Amendment No.
Description -
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None l
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SIGNIFICANT SAFETY RELATED MAINTENANCE FOR THE MONTH OF-MARCH-1995, I
Maintenance activities for March 1995 include'd the following-Rebuilt steam generator RC-2B inlet check valve FW-161..
l Removed, tested and reinstalled pressurizer relief valves RC-141 and -
L RC-142.
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Replaced seal flush line~ filters on reactor coolant pumps RC-3A,
-3B, -3C and -3D.
Completed maintenance activities on emergency.; diesel ' generators, i
DG-1 and DG-2 consisting of the DG 6-year maintenance which included-replacing head gaskets and jacket water seals, and cleaning and inspecting engine internals.
Repaired fasteners which hold the orifice plates in the hot leg of:
. steam generator RC-2A.
Flushed reactor coolant pump RC-3C thermal barrier heat exchanger.
Rebuilt HCV-2500 series primary safety valves.
Completed raw water /CCW valve work which included rebuilding valves-HCV-2877A, HCV-2881B, HCV-2883A, and HCV-438C.
Repaired containment sump recirculation isolation valve HCV-383-3.-
Repaired main steam valves HCV-1042A/8/C.
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-LIC-95-0087 Enclosure Page 3 6.
OPERATING DATA REPORT Attachment I i
7, AVERAGE DAILY UNIT POWER LEVEL I
Attachment II 8.
UNIT SHUTDOWNS AND POWER REDUCTIONS Attachment III 9.
REFUELING INFORMATION. FORT CALHOUN STATION UNIT N0. 1 l
Attachment IV f
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l ATTACHMENT I
!i OPERATING DATA' REPORT l
l DOCKET NO.
50-285 l
UNIT f6RT CALHOUN STATION DATE
. APRIL 0_7 1995 l
i COMPLETED BY D. L.
LIPPY OPERATING STATUS TELEPHONE (402) 513-6843
- l. Unit Name:
FORT CALHOUN STATION
- 2. Reporting Period:
MARCH 1995 NOTES i
- 3. Licensed Thermal Power
- ( MWt ) : 1500
- 4. Nameplate Rating (Gross MWe):
502
.478
- 5. Design Elec. Rating (Net MWe): ~ 502
- 6. Max. Dep. Capacity (Gross MWe):
l
- 7. Max. Dep. Capacity (Net MWe):
478
.{
- 8. If changes occur in Capacity Ratings (3 through 7) since last report, give reasons:
J N/A
- 9. Power Level to which restricted, if any (Net MWe): N/A l
- 10. Reasons for restrictions, if any:
N/A i
THIS MONTH YR-TO-DATE CUMULATIVE
- 11. Hours in Reporting Period...........
744.0 2160.0 188594.0
- 12. Number of Hours Reactor was Critical
.0 171677 14 76~3 4. 6~
- 13. Reactor Reserve Shutdown Hours......
.0
.0 1709.5 14.' Hours Generator On-line.............
.0 1212TT 145986.6 115.-Unit Reserve Shutdown Hours.........
.0
.0
.0
- 16. Gross Thermal Energy Generated (MWH)
.0 1770952.4 193919652.9
- 17. Gross Elec. Energy Generated (MWH)..
.0 601533TD~
~6T006478.2
- 18. Net Elec. Energy Generated (MWH)....
.0 574107.4 61065899.7~
- 19. Unit Service Factor.................
.0 56.1 77.4-
- 20. Unit Availability Factor............
.0 f6.1 777T~-
- 21. Unit Capacity Factor (using MDC Net)
.0 55.6 70.1
- 22. Unit Capacity Factor (using DER Net)
.0 55.6~
68.4
- 23. Unit Forced Outage Rate.............
.0
.0 4.0
- 24. Shutdowns scheduled over next 6 months (type, date,-and duration of each):
.THE FIFTEENTH REFUELING OUTAGE COMMENCED ON FEBRUARY 20, 1995 WITH A SCHEDULED DURATION OF 49 DAYS.
25.LIf shut down at end of report period, estimated date of'startup: 04/10/95 i
- 26. Units in test status (prior to comm. oper.):
Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY N/A COMMERCIAL OPERATION
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ATTACHMENT'II-AVERAGE DAILY UNIT POWER LEVEL-y DOCKET NO.
50-285 UNIT-FORT CALHOUN STATION DATE
- APRIL-07,1995 COMPLETED BY D. L. LIPPY TELEPHONE (402) 533-6843 1
MONTH MARCH 1995 DAY AVERAGE DAILY POWER LEVEL DAY.
' AVERAGE. DAILY POWER LEVEL (MWe-Net)
'(MWe-Net)
~1 0
17 0
2 0
18 0
3 0-19 0
'4 0
20 0'
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5 0-21 0
j 6-
-0
'22 0
7
-0 23' 0
8 0
24 0
9 0
25 C
10 0
26 0
1 11 0
.27 0
12 0
.28 0
,)
^
13 0
29 0
t I
i 14 0
30 0
15' O
31 0
16 0
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-INSTRUCTIOk'S l
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..
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ATTACHMENT III DOCKET N0. 50-285 UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME Fort Calhoun St.
DAiE April 7.1995 COMPLETED BY D. L. Lipov TELEPH0hE (402) 533-6843 i
l REPORT MONTH March 1995 I[N$It
!$9aie3.! NM" ItasaEidal.IRAaAN)
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? Reacteh, 95-02 950220 S
744.0 C
1 N/A ZZ ZZZZZZ On February 20,1995, Fort Calhoun Station -
commenced its 15th refueling outage.
1 2
3 4
F: Forced Reason:
Method:
Exhibit F - Instructions S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram Entry Sheets for Licensee C-Refueling 3-Automatic Scram Event ' Report (LER) File (NUREG-0161)
D-Regulatory Restriction
'4-Other (Explain)
E-Operator Training & License Examination F-Administrative 5
H-Other (Explain)
-Exhibit H - Same Source (9/77)'
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Attachment IV Refueling Information
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Fort Calhoun Station - Unit No. 1 Report for the month ending March 31. 1995
- 1. Scheduled date for next refueling shutdown.
Shutdown February 20. 1995
- 2. Scheduled date for restart following refueling.
Aoril 10.1995
- 3. Will refueling or resumption of operations thereafter require a technical specification change or other license amendment?
No a.
If answe: is yes, what, in general, will these be?
N/A 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.
Yes c.
If no such review has taken place, when is it N/A scheduled?
- 4. Scheduled date(s) for submitting proposed licensing action and support information.
No submittal reauired
- 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.
- / **
- 6. The number of fuel assemblies:
a) in the core 133 Assemblies I
b) in the spent fuel pool 618 Assemblies c) spent fuel pool storage capacity 1083 Assemblies
- 7. The projected date of the last refueling that can be discharged to the spent fuel pool assuming the i
present licensed capacity.
2007 Outaae OPPD utilized methodology employing the CASM0-3/ SIMULATE-3_ codes for reactor I
physics related analyses for Cycle 16.
This methodology was approved by the NRC in December 1994.
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- Seven fuel assemblies found with suspected / confirmed fuel pin failures.
Fuel assembly reconstitution effort, which included high magnification-visual examination of the individual rods, concluded that defects were a result of grid-to-rod fretting. All confirmed and suspected failed pins were replaced with stainless steel pins.
Prepared by b'- M Date 4 - n-9f