ML20079J155

Monthly Operating Rept for Sept 1991 for Fort Calhoun Station

ML20079J155
Person / Time
Site:	Fort Calhoun
Issue date:	09/30/1991
From:	Edwards M, Gates W OMAHA PUBLIC POWER DISTRICT
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LIC-91-258R, NUDOCS 9110150276
Download: ML20079J155 (8)

Text

l Omaha Public Power District 444 South 16th Street Mall October 14, 1991 Omaha, Nebraska 68102-2247 LIC-91-258R 402/636-2000 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station Pl-137 Washington, DC 20555

Reference:

Docket No. 50-285 Gentlemen:

SUBJECT:

September Monthly Operating Report (MOR)

Enclosed is the September 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 M

b W.

Gates Di ision Ma ager 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 9110150276 910090 1

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j-AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-285 UNIT fort Calhoun Station DATE October 3, 1991 COMPLETED BY M.L. Edwardt TELEPHONE (402)636-2451 MONTH-September 1991 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL

.(MWe-Net)

(MWe-Net) 1 466 17 0

2 468 18 0

3 469 19 0

4 470 20 0

5 471 21 0

6 472 22 0

7 472 23 0

8 470 24 0

9-470 25 0

10 470 26 0

11 470 27 0

12 366 28,

0

'13.

0 29 0

14 0

30 0

15 0

16 0

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.

~

' OPERATING DATA REPORT DOCKET N0.

50-285 UNIT Fort Calhoun Station DATE October 3, 1991 s

COMPLETED BY M.L. Edwards TELEPHONE (402)636-2451-OPERATING' STATUS 1.. Unit Name: Fort Calhoun Station Notes 2.~ ' Reporting Per.iod:

September 1991

3. Licensed Thermal Power-(MWt):

1500 4.-

Nameplate Rating (Gross MWe):

602-

~

'5.

Design Electr_ical Rating'(Net MWe): 478 6.

Maximum Dependable Capacity (Gross 11We):

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 tJ Which Restricted, If Any (Net MWe): 'N/A

10. Reasons (for Restrictiors, If'Any:_N/A This Month Yr-to-Date Cumulative

11. Hours in Reporting Period 720.0 6,551.0 157,921.0

12. Number of Hours Reactor was Critical 286.5 5,937.5 122,726.2

13. Reactor Reserve Shutdown Hours 0.0 0.0 1,309.5

14. Hours Generator On-Line 285.0 5,911.7 121,341.6~

15. Unit Reserve ~ Shutdown' Hours 0.0 0.0 0.0 16; GrossThermal?EnergyGenerated(MWH) 423,141.3 7,416,972.1 158,700,461.4 117. eGross Electrical-Energy Generated (MWH) - 139,400.0 2,435,744.0 52,185,870.2

18. Net Electrical Energy-Generated (MWH) 132,851.0

-2 305,224.0 49,790,000.3 1

19. Unit Service Factor 39.6 90.2 76.8 H20. : Unit Availability Factor 39.6 90.2 76.8

21. Unit Capacity Factor'(Using MDC Net) 38.6 73.6 68.3

22. Unit Capacity Factor (Using DER Net) 38.6 73.6 66.8

23. Unit Forced Outage Rate 60.4 "9. 8 3.8 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

26. -Units in Test _ Status (Prior to Commercial Operation):

Forcast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY N/A COMMERCIAL OPERATION

1 Refueling Information Fort Calhoun - Unit No.1 Report for the month ending September 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 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 any unreviewed safety questions are associated with the core reload.

N/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.

Eqyember 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 F) 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.

Pcepared by h ld S* _

Date Io-7-9/

DOCKET NO. 50-285 UNIT NAME Fort Calhoun Station DATE October 8. 1991 UNIT SHUTDOWNS AND POWER REDUCTIONS COMPLETED BY M. L. Edwards TELEPHONE (402) 636-2451 REPORT MONTH SEPTEMBER 1991 No.

Date Type Duration Reason Metixxl of Licensee System Component Cause & Corrective (1)

(th>urs)

(2)

Shutting Event Cale Code (5)

Action to Down Report #

(4)

Prevent Recurrence Reactor (3) 91-05 910912 F

435.0 A

1 91-18 EC BATTRY FCS entered hat shutdown as a result of cracks discovered in battery

1. 1 of the 125 vde system cauwt by stresses from corrosion buildup at the positive post seal area. The 125 vde system is designed to supply an uninterruptable source of power for plant instrumentation and control for a minimum of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> without any outside powtr source. On September 13, the plant was on shutdown cooling in preparation for the installation of batteries which alkm for corrosion product build up without inducing stresses on the battery cell cover or jar.

I 2

3 4

F-Forced 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 F-Administrative 5

G-Operational Error Exhibit ; - Same Source H-Other (Explain)

(9/,77)

OMAHA PUBLIC PAER DISTRICT Fort Calhoun Station Unit No.1 SEPTEMBER 1991 Monthly Operating Report 1.

OPERATIONS

SUMMARY

Fort Calhoun Station operated at 100% power until a forced shutdown began on September 12,1991 when the station batteries were declared inoperable. On September 11,_1991, a jar in one of the 125 vde station batteries cracked and began leaking electrolyte. On September 12, l991, a determination was made that propagating cracks found on the battery jars disqualified them seismically and a plant shutdown was initiated per Technical Specifications. The plant was placed in cold shutdown on September 13, 1991. Both station batteries have since been replaced and start-up is in progress.

Significant maintenance _ activities during the month of September included: removal of feedwater pump FW-4C motor and pump for overhaul, bearing replacement on component cooling water pump AC-3C, repair of two of the four wide range nuc! car instrument channels, and replugging of condenser tubes.

Modifications included:

removal of the control element assembly change machine from the reactor refueling cavity and removal of a section of waste piping containing a hot spot greater than 1,000 R.

New fuel receipt was completed for 44 of the 52 assemblies to be used for Cycle 14.

The last 8 assemblies are scheduled for delivery in December.

The INPG plant evaluation and simulator evaluation occurred during September,1991.

The following NRC inspections took place in September:

IR 91-21 Resident's Routine Inspection The following LERs were submitted:

LER 91-017 Potential for Radiological Release Due to SIRWT Vents LER 91-S02 Microwave Zone Inoperable A.

SAFETY VALVES OR FORV CHALLENGES OR FAILURES WHICH OCCURRED None

"y, U. S. Nuclear Regulatory Commission LIC-91-258R Page 2

- B.

RESULTS OF LEAK RATE TESTS The results of the Reactor Coolant (RC) leak rate tests for September,1991, indicate that the Reactor Coolant System (RCS) and Chemical and Volume Control System (CVCS) are both relatively leak tight. Total RCS leakage averaged 0.18 gpm during September.

The maximum leak rate was recorded on September 7,1991 when the total leak rate was 0.235 gpm and the unknown leak rate was 0.119 gpm Known leakage-to the RC drain tank was 0.116 gpm. The plant was taken to cold shutdown following a declaration of station battery inoperability on September 12,1991. As a result, no additional leak rate tests were performed in September.

C.

CHANGES, TESTS AND EXPERIh1ENTS REQUIRING NUCLEAR REGULATORY COhthilSSION AUTHORIZATION PURSUANT TO 10CFR50.59 AMENDMENT NO.

DESCRIPTION None D.

SIGNIFICANT SAFETY RELATED htAINTENANCE FOR THE htONTH OF SEPTEh1BER 1991 1.

Component Cooling Water Pump AC-3C showed increased vibration during performance of the quarterly Inservice Inspection (ISI) surveillance test.

Both inboard and outboard bearings were replaced.

Post maintenance and operability testing required performance of the applicable surveillance tests.

During surveillance testing conducted in August the initial attempt to start diesel generator number 2 (DG-2) using the secondary air start motors failed. The cause of the failure could not be determined nor could the failure be reproduced. On September 4,1991, the pressure solenoid valve (SA-191) was replaced. Operability testing using the secondary air start system to start DG-2 was performed satisfactorily.

q [.

U.' S. Nuclear Regulatory Commission LIC-91-258R Page 3 -

During plant shutdown the reactor protection system "B" channel (AI-31B) wide range Nuclear Instrumentation (NI) was found one-half (1/2) decade lower then the next closest channel during surveillance testing. When the channel went into extended range, counts went to three (3) counts per s

second which seemed unreasonably low as compared to_ the other -

channels. The discriminator board was replaced and the discriminator portion of the wide range channel was recalibrated.

The reactor protection system "D" channel NI wide range indication did not cperate properly during plant shutdown. Possible cause of failure was a bad connection on the preamp assembly mating with the detection cable assembly in the gamma metrics preamp box. Post maintenance testing required performance of the applicable secOn of the surveillance test.

2.

Maintenance activities during the forced outage included:

Adjusted the bistable trip units for tne reacter protective system surveillance test.

Replaced the 125 vde batteries #1 (EE-8A) and #2 (EE-8B).

Installed new "O" Rings and gaskets and adjusted the air regulator setting on component cooling water heat exchanger AC-1 A.

~

Repaired the middle coupling on the north side bypass damper and the south coupling on the west side bypass damper en inlet damper HCV-725B for containment cooling and filter unit VA-15B.

~

Doble tested the breaker (I A3-10) for raw water pump AC-10C.

Replaced relay 94-B2/ DSS in auxiliary instrumentation panel Al-66B.

l

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