ML20085H879
| ML20085H879 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 05/31/1995 |
| From: | Lippy D OMAHA PUBLIC POWER DISTRICT |
| To: | |
| Shared Package | |
| ML20085H392 | List: |
| References | |
| NUDOCS 9506210329 | |
| Download: ML20085H879 (8) | |
Text
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1 LIC-95-0125
~
Enclosure A Page 1 OMAHA PUBLIC POWER DISTRICT Fort Calhoun Station (FCS) linit No.1 1
l MAY 1995 1
Monthly Operating Report 1.
OPERATIONS
SUMMARY
During the month of May, FCS operated at a nominal 100% power until May 11, 1995, when a manual reactor trip was initiated due to an indicated component cooling water (CCW) leak in the upper oil reservoir of the Reactor Coolant Pump (RCP) RC-30 motor.
All four of the RCP motors' upper lube oil coolers were eddy current tested, and a total of 10 tubes were plugged.
The plant was returned to power operation on May 15th.
On May 24th, the reactor was manually tripped from approximately 97%
power due to new indications of a CCW leak into the upper oil reservoir of the RC-3D motor.
The plant was taken to cold shutdown and the tube bundles in all four RCP motor upper oil reservoir lube oil coolers were replaced. The plant was returned to power operation on May 29th. Power was increased to a nominal 100% on May 31st.
During perfonnance of daily Reactor Coolant System (RCS) sampling on May 5th, the RCS sample inboard containment isolation valve, HCV-2504A, did not indicate closed as required. Technical Specification (TS) Limiting Condition for Operation (LCO) 2.6(1)a was entered, and the RCS sample outboard containment isolation valve, HCV-25048, was deactivated and locked in the closed position to restore containment integrity. The limit switch on HCV-2504A was repaired and tested, and the valve was declared operable on May 6th.
On May 9th, HCV-2504A again failed to indicate closed as required.
HCV-2504B was deactivated and locked in the closed position and TS LC0 2.6(1)a was entered.
The actuator diaphragm was replaced and tested satisfactorily, a Local Leak Rate Test (LLRT) was satisfactorily performed on HCV-2504A, and the valve was subsequently declared operable l
on May 10th. The actuator diaphragm was also replaced on HCV-2504B.
The May 20th, RCS radioactivity exhibited an increasing trend. The Fuel Reliability Indicator (FRI) had increased from the May lith value of 1
0.00024 pCi/g to 0.0678 pCi/g. As required by Standing Order 0-43, " Fuel Reliability Action Plan," reactor coolant charging and letdown flows were
]
increased to facilitate cleanup of the system.
Standing Order 0-43 l
requires this action with a FRI between 0.05 and 0.2 pCi/g.
The FRI value had decreased to 0.024 pCi/g prior to the reactor shutdown on May 24th.
Fuel rod failures due to spacer grid fretting is the probable cause of the high activity.
These failures were not unexpected since defective fuel rods due to fretting had been identified and replaced during the 1995 refueling outage.
l 9506210329 950615 PDR ADOCK 05000285 i
R PDR I
LIC-95-0125 Enclosure A i
Page 2 1
2.
SAFETY VALVES OR PORV CHALLENGES OR FAILURFS WHICH OCCURRED On May 25, 1995, the Power Operated Relief Valves (PORVs) were successfully tested during a plant cooldown.
1 i
3.
RESULTS OF RCS LEAK RATE TESTS The RCS leak rate was steady in May except during the two plant shutdowns. The leak rate data during these conditions was erratic and of limited use for trending purposes.
The nominal leak rate for May is ~
0.100 to 0.200 gpm, with no degrading trends noted. Besides the erratic 1eak rates noted during plant transients, the leak rate has remained
.l relatively unchanged this cycle.
I 4.
CHANGES. TESTS AND EXPERIMENTS RE0VIRING NUCLEAR REGULATORY COMMISSION AUTHORIZATION PURSUANT TO 10CFR50.59 Amendment No.
Description None 5.
SIGNIFICANT SAFETY RELATED MAINTENANCE FOR THE MONTH OF MAY 1995 Installed new sparging nozzles.in the air. sparging system for Raw.
Water Pumps AC-10A/B/C/D.
Replaced circuit board AI-31E-AW1-A8 when the rod drop circuit would not calibrate.
Replaced the tube bundles in the lube oil coolers for all four RCPs, RC-3A/B/C/D.
]
Adjusted the limit switch on Control Element Drive Mechanism RC-10-18.
~
- Cleaned CCW heat exchanger AC-ID.
6.
OPERATING DATA REPORT Attachment I
LIC-95-0125
' Enclosure A-Page 3 7.
AVERAGE DAILY UNIT POWER LEVEL
' Attachment II 8.
UNIT SHUTDOWNS AND POWER REDUCTIONS l
Attachment III l
9.
REFUELING INFORMATION. FORT CALHOUN STATION UNIT N0.1 l
l Attachment IV i
l
+
I i
l L
i l
ATTACHMENT I OPERATING DATA REPORT I
DOCKET NO.
50-285 UNIT FORT CALHOUN STATION DATE JUNE 07, 1995 l
COMPLETED BY D.
L.
LIPPY l
OPERATING STATUS TELEPHONE (402) 533-6843 t
- 1. Unit Name:
FORT CALHOUN STATION
- 2. Reporting Period:
MAY 1995~~
NOTES
- 3. Licensed Thermal Power (MWt): 1500
- 4. Nameplate Rating (Gross MWe):
502 j
j
- 5. Design Elec. Rating (Net MWe):
478 i
- 6. Max. Dep. Capacity (Gross MWe):
502_
t
- 7. Max. Dep. Capacity (Net MWe):
478 1
l 8.
If changes occur in Capacity Ratings'(3 through 7) since last report, j
l give reasons:
N/A i
- 9. Power Level to which restricted, if any (Net MWe): N/A i
- 10. Reasons for restrictions, if any:
N/A THIS MONTH YR-TO-DATE CUMULATIVE
- 11. Hours in Reporting Period...........
744.0 3623.0 190057.0
- 12. Number of Hours Reactor was Critical 538.8 2192.1 148610.0
- 13. Reactor Reserve Shutdown Hours......
.0~
.0 1309.5
- 14. Hours Generator On-line.............
519.6 2 f21. 6 146895.9
- 15. Unit Reserve Shutdown Hours.........
__. 0
.0
.0
- 16. Gross Thermal Energy Generated (MWH) 718797.7 2974134.8 195122835.3
- 17. Gross Elec. Energy Generated (MWH)..
240202.0 1002934.0 64407816.2
- 18. Net Elec. Energy Generated (MWH)....
228248.0 955272.4 61447064.7
- 19. Unit Service Factor.................
69.8 58.6 77.3
- 20. Unit Availability Factor............
_69.8 58.6 7773~
- 21. Unit Capacity Factor (using MDC Net) 64.2 55.2 70.0
- 22. Unit Capacity Factor (using DER Net) 64.2 55.2 68.3
- 23. Unit Forced Outage Rate.............
30.2 9.6 4.1
- 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:
- 26. Units in test status (prict to comm. oper.):
Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY N/A COMMERCIAL OPERATION
~~
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ATTACHMENT II' AVERAGE DAILY UNIT POWER LEVEL l
DOCKET NO.
iS0-285 UNIT FORT CALHOUN STATION DATE JUNE 07.1995-l COMPLETED BY D.
L.
LIPPY TELEPHONE-(402) 533-6843 MONTH MAY 1995 J
DAY ~
AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 1
486 17 483 l-2 486 18 483 1
3 486 19 483 4
486 20 483 5
486 21 482 i
j 6
486 22
'481 7
485 23 480 j
8 485 24,
O
]
9 485 25 0
j 10-485 26 0
l 11~
217 27 0
1 12 0
28 0
l' 13 0
29 38 14 0
30 98 15 75 31 386 16 464 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.
ATTACHMENT III DOCKET NO. 50-285 f
UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME Fort Calhoun St. ~
DATE June 8. 1995-a COMPLETED BY D. L. Liooy l
' TELEPHONE (402) 533-6843 v
REPORT MONTH May 1995 j[NQ iYh. M"I turation Reesed
' Method Ltcoasse System Caspement
<(Neurs) of Event Cedef '
CodePc J "
,,; - ' Casse & Corrective o x
No.
x..
' Actles to s
. Shutting Report f'/ F
^ Prevent Recurvesce s
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95-02 950511 F
95.8 A
2 95-003 CB HTEXCH On May 11, 1995 a manual reactor trip was initiated
[
due to a component cooling water (CCW) leak in the.
j upper oil reservoir of reactor coolant pump (RCP)
L RC-30 motor. All four of the RCP motors' upper i
lube oil coolers were eddy current tested and a total of 10 tubes were plugged. The plant was returned to power operation on May 15, 1995.
I 95-03 950524 F
128.6 A
2 95-003 CB HTEXCH On May 24, 1995 the reactor was manually tripped due to new indications of a CCW leak into the upper oil reservoir for the RCP RC-30 motor. The plant was taken to cold shutdown and the tube bundles in all four RCP motor upper oil reservoir lube oil coolers were replaced. The plant was returned to power operation on May 29, 1995.
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 i
F-Administrative 5'
H-Other (Explain)
Exhibit H - Same Source i
(9/77)
)
i 4
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Attachment TV Refueling Information Fort Calhoun Station - Unit No. 1 l
Report for the month ending May 31. 1995
- 1. Scheduled date for next refueling shutdown.
September 21. 1996
- 2. Scheduled date for restart following refueling.
November 2. 1996
- 3. Will refueling or resumption of operations thereafter require a technical specification change or other license amendment?
No a.
If answer is yes, what, in general, will trese 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.
No c.
If no such review has taken place, when is it Prior co November 1996 scheduled?
- 4. Scheduled date(s) for submitting proposed licensing action and support information.
No submittal planned
- 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.
N/A
- 6. The number of fuel assemblies:
a) in the core 133 Assemblies 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 present licensed capacity.
2007 Outaae N M,, L S e l<ev Date 4/6M f Prepared by
r LIC-95-0125 Enclosure B Fort Calhoun Station (FCS) Unit No. 1 Monthly Operating Report Revisions to "U'ft Shutdowns and Power Reductions" Forms n
for February, March and April 1995
References:
1.
LIC-95-0068 dated March 15, 1995 2.
LIC-95-0087 dated April 13, 1995 3.
LIC-95-0105 dated May 15, 1995 e
a d
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