LIC-96-0196, Monthly Operating Rept for Nov 1996 for Fort Calhoun Station Unit 1

Monthly Operating Rept for Nov 1996 for Fort Calhoun Station Unit 1

ML20132D006
Person / Time
Site:	Fort Calhoun
Issue date:	11/30/1996
From:	Edwards M, Gambhir S OMAHA PUBLIC POWER DISTRICT
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LIC-96-0196, LIC-96-196, NUDOCS 9612190098
Download: ML20132D006 (9)

Text

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kPPD Omaha PublicPowerDistrict 444 South 16th Street Mall l

Omaha NE68102-2247 l

December 13. 1996 LIC-96-0196 l I

U. S. Nuclear Regulatory Commission f

Attn: Document Control Desk Mail Station P1-137 )

Washington, D.C. 20555 i

Reference:

Docket No. 50-285

SUBJECT:

November 1996 Monthly Operating Report (MOR)

Enclosed please find the November 1996 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.

A S. K. Gambhir Division Manager Production Engineering SKG/mle I i 19 0 0' ^18 I Enclosures c: Winston & Strawn L. J. Callan. NRC Regional Administrator. Region IV q1 L. R. Wharton, NRC Project Manager W. C. Walker. NRC Senior Resident Inspector R. J. Simon. Westinghouse INPO Records Center 9612190098 961130 PDR ADOCK 05000285 R PDR cyment with Equal Opportunity

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1 LIC-96-0196 Enclosure

Page 1 OMAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No. 1 November 1996 Monthly Operating Report i

1. OPERATIONS

SUMMARY

The Fort Calhoun Station (FCS) was in a refueling outage for most of November J 1996. On November 25 at 0644 the reactor was made critical to start low power '

physics testing. The turbine generator was placed online at 0200 on November

27. The generator was maintained at a nominal 30% power level until November 28 at 0032 when turbine overspeed testing was conducted. The generator was returned to service at 0315 on November 28 and maintained at a nominal 30%

power level for secondary chemistry holds. On November 30 at 0808 a slow power ramp-up to full power commenced.

Major activities scheduled and completed during the refueling outage included:

complete core off-load / reload; fuel sipping and reconstitution: polar crane  !

feedrail replacement: Reactor Coolant Pump RC-3B motor replacement: Steam 1 4

Generator tube inspection and plugging: manual DC transfer switch replacement: :

replacement of the final three (3) of four (4) channels of the reactor l 1 protective system nuclear instrumentation wide range power drawers:

replacement of twenty-eight (28) incore detectors: control element drive mechanism seal rebuilds; motor operator valve testing (MOVATS): containment local leak rate penetration tests: low pressure turbine inspection; i circulating water system valve (FCV-1904B) repair; and AC supply bus maintenance and testing.

On November 11 at 1540 hours0.0178 days <br />0.428 hours <br />0.00255 weeks <br />5.8597e-4 months <br /> OPPD determined that the containment air coolers would not function as required for certain Updated Safety Analysis Report, Chapter 14 design basis accidents. This determination resulted from evaluations associated with NRC Generic Letter 96-06. During a loss-of-coolant-accident (LOCA) or main steam line break event coincident with a loss of offsite power, the containment air coolers could generate an internal steam bubble and upon restart of the component cooling water (CCW) pumps, the steam bubble could collapse and generate water hammer inside the piping. A safety analysis for operability evaluation has been completed to justify operability of the CCW system. Final resolution is expected by the end of the next refueling outage.

LIC-96-0196 Enclosure Page 2

2. SAFETY VALVES OR PORV CHALLENGES OR FAILURES WHICH OCCURRED During the month of November, no power operated relief valves (PORV) or primary system safety valve challenges or failures occurred.

3. RESULTS OF LEAK RATE TESTS No leak rate tests were performed from November 1 through November 19 due to the plant being shut down for the 1996 refueling outage.

Calculated leak rates on November 20 and 21 were higher than normal due to the changing plant conditions experienced during plant startup. Leak rates have since stabilized around 0.2 gpm with slight variations above and below.

4. CHANGES. TESTS AND EXPERIMENTS RE0UIRING NUCLEAR REGULATORY COMMISSION AUTHORIZATION PURSUANT TO 10CFR50.59 Amendment No. Descriotion l

None

5. SIGNIFICANT SAFETY RELATED MAINTENANCE FOR THE MONiH OF November 1996 l

Replaced CS/BT-183C (Control Switch for 480 V Bus Tie Breaker BT-IB3C)

Replaced CS/T1B-3A (T18-3A 4.16 KV Feeder Breaker Control Switch)

Replaced CS/183A (Control Switch for 480 V Transformer Secondary l Breaker 1B3A) i Replaced CS/1B4B (Control Switch for 480 V Transformer Secondary Breaker 184B)

Replaced 27-T1/1B3A and 27-T2/183A (Undervoltage Relays)

Replaced 43/1A2-1A4 (Bus 1A2 to Bus 1A4 Manual Transfer Switch)

Cleaned, coated and pulled a tube for failure analysis on AC-1B (CCW Heat Fxchanger) 2 Adjusted setpoint on AC-341 (CCW T. urge Tank AC-2 Nitrogen Relief Valve) for Safety Analysis for Operability (SAO) 96-02 Adjusted setpoint on AC-364 (CCW Surge Tank AC-2 Recirculation Relief Valve to Waste Disposal System) for SA0 96-02 Repacked CH-308 (Deborating Ion Exchanger CH-9B Demineralized Water Bed Lift Valve)

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l LIC-96-0196 '

Enclosure Page 3 l

Repacked CH-317 (Deborating Ion Exchanger CH-9B Outlet Isolation for Regenerative Drain Isolation Valve) i Repacked CH-359 (Charging Pump CH-1A Suction Drain Valve to Waste Disposal System)

Replaced sightglass on F0-2-2 (DG-2 Fuel Oil Day Tank) l l

Rebuilt HCV-1041B (Steam Generator RC-2A Main Steam Check Valve)

Replaced instrument air tubing and fittings on HCV-1042A-20B (Test Solenoid Main Steam Isolation)

Replaced solenoid on HCV-1388B (Steam Generator RC-2A Blowdown l Isolation Valve) i l -

Rebuilt actuator on HCV-1388B-0 (Steam Generator RC-2A Blowdown l Isolation Valve Operator) l -

Rebuilt HCV-2883A (CCW Heat Exchanger AC-1D. Raw Water Inlet Valve) '

Rebuilt actuator on HCV-484 (Shutdown Cooling Heat Exchanger AC-4A. CCW Outlet Valve)

Replaced coupling on HCV-485 (Shutdown Cooling Heat Exchanger AC-4B. CCW Outlet Valve) l Replaced drive motor on RC-10-08 (CEDM) l l -

Replaced drive package on RC-10-22 (CEDM)

Benchtested and reset setpoints on Pressurizer Relief Valves RC-141 and RC-142 Repacked RC-166 (Pressurizer Spray Line Vent Valve) I Plugged 36 tubes in RC-2A (Steam Generator A)  :

Plugged 21 tubes in RC-2B (Steam Generator B)  ;

Repacked RC-240 (Reactor Coolant Pump RC-3A Discharge Pressure to DPI-110W/124W Isolation Valve) l Performed CHAR" testing on pressurizer heater and mineral insulation cables Replaced twenty-eight (28) incore detectors ,

Replaced RC-70-22 (Incore Instrumentation)

Replaced diaphram in SI-7D (Safety Injection Leakage Cooler i Accumulator)

6. OPERATING DATA REPORT Attachment I

7. AVERAGE DAILY UNIT POWER LEVEL Attachment II 3

i b

LIC-96-0196 Enclosure Page 4

8. UNIT SHUTDOWNS AND POWER REDUCTIONS Attachment III

9. REFUELING INFORMATION. FORT CALHOUN STATION UNIT NO. 1 Attachment IV

ATTACEMENT I OPERATING DATA REPORT DOCKET NO. 50-285 UNIT FORT CALHOUN STATION DATE DECEMBER 10,1996 COMPLETED BY M. L. EDWARDS OPERATING STATUS TELEPHONE 402-533-6929

1. Unit Name: FORT CALHOUN STATION

2. Reporting Period: NOVEMBER 1996 NOTES

3. Licensed Thermal Power (MWt): 1500

4. Nameplate Rating (Gross MWe): 502

5. Design Elec. Rating (Net MWe): 478

6. Max. Dep. Capacity (Gross MWe): 502

7. Max. Dep. Capacity (Net MWe): 478

8. If changes occur in Capacity Ratings (3 through 7) since last report, give reasons:

N/A l'

9. Power Level to which restricted, if any (Net MWe): N/A

10. Reasons for restrictions, if any:

N/A

4. l THIS MONTH YR-TO-DATE CUMULATIVE

11. Hours in Reporting Period........... 720.0 8040.0 203234.0

12. Number of Hours Reactor was Critical 137.2 6239.6 159947.6

13. Reactor Reserve Shutdown Hours...... .0 .0 1309.5

14. Hours Generator On-line............. 92.2 6148.2 158128.7

15. Unit Reserve Shutdown Hours......... .0 .0 .0

16. Gross Thermal Energy Generated (MWH) 45107.6 8752978.9 211439287.2

17. Gross Elec. Energy Generated (MWH).. 11368.0 2923281.9 69857007.1

18. Net Elec. Energy Generated (MWH).... 9746.3 2784384.8 66641753.6

19. Unit Service Factor................. 12.8 76.5 77.8

20. Unit Availability Factor............ 12.8 76.5 77.8

21. Unit Capacity Factor (using MDC Net) 2.8 72.5~~~ 70.8

22. Unit Capacity Factor (using DER Net) 2.8 72.5 69.2

23. Unit Forced Outage Rate............. .0 5.9 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 (prior to comm. oper.): Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY N/A COMMERCIAL OPERATION

ATTACHMENT II -

AVERAGE DAILY UNIT POWER LEVEL  !

DOCKET NO. 50-285 I UNIT FORT CALHOUN STATION. j DATE DECEMBER 10,1996 COMPLETED BY M. L. EDWARDS '

TELEPHONE 402-533-6929  !

'I' MONTH NOVEMBER 1996 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL  ;

(MWe-Net) (MWe-Net) 1 0 17 0 l 2 0 18 0  ;

3 0 19 0 l 4 0 20 0  !

5 0 21 0 i

6 0 22 0 l

7 0 23 0  !

8 0 24 0 i

9 0 25 0 l i

10 0 26 0 11 0 27 63 l

12 0 28 79  !

13 0 29 109 l i'

14 0 30 155 15 0 i i

16 0 INSTRUCTIONS On this form, list the average daily unit power level in MWe-Net for each j day in the reporting month. Compute to the nearest whole megawatt.  ;

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ATTACHMENT III DOCKET NO. 50-285 .

• i UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME Fort Calhoun St.

DATE December 9. 1996 I

COMPLETED BY M. L. Edwards TELEPHONE (402) 533-6929 l REPORT MONTH November 1996 J Nol! [DAsb iTha:1 Duration..

,w Reagan MethodM Lcensee System, Component

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96-06 961004 S 627.8 C 1 N/A ZZ ZZZZZZ On October 4. 1996. Fort Calhoun i Station commenced its 16th  ;

refueling outage. The outage ended '

on November 27. 1996 when the i generator was synchronized to the j grid.

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l 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 i H-Other (Explain) Exhibit H - Same Source (9/77) j i

Attachment IV Refueling Information Fort Calhoun Station Unit No. 1 Report for the month ending: November 30. 1996

1. Scheduled date for next refueling shutdown. March 21. 1998

2. Scheduled date for restart following refueling. May 2. 1998

3. Will refueling or resumption of operations No thereafter require a technical specification change or other license amendment?

a. If answer is yes, what, in general will N/A these be?

b. If answer is no. has the reload fuel No 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?

c. If no such review has taken place, when is Prior to May 2. 1998 it scheduled?

4. Scheduled date(s) for submitting proposed No submittal required licensing action and support information.

a,.

5. Important licensing considerations associated None with refueling, e.g., new or differect #uel 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 b) in the spent fuel pool - 662 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 2007 Outage present licensed capacity.

Prepared by: C &* Date: i2 - eo -%

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