LIC-97-0137, Monthly Operating Rept for Jul 1997 for Fort Calhoun Station

Monthly Operating Rept for Jul 1997 for Fort Calhoun Station

ML20210J666
Person / Time
Site:	Fort Calhoun
Issue date:	07/31/1997
From:	Gambhir S, Howman M OMAHA PUBLIC POWER DISTRICT
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LIC-97-0137, LIC-97-137, NUDOCS 9708180256
Download: ML20210J666 (3)

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Omaha Public PowerOstrict 444 South 16tt' Street Mall Omaha NE68102-2247 August 15, 1997 LIC-97-0137 U.- S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station-P1-137 Washington, D.C. 20555

^

Reference:

Docket No. 50-285

SUBJECT:

July 1997 Monthly Operating Report (MOR)

Enclosed please find the July Monthly Operating Report 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.

S. K. Gambhir Division Manager -

Engineering & Operations Support SKG/mah t'

Attachments 1.

c: Winston & Strawn il E. W. Merschoff NRC Regional Administrator. Region IV L. R. Wharton, NRC Project Manager

/

W. C. Walker NRC Senior Resident Inspector R. J. Simon, Westinghouse INP0 Records Center 9708180256 970731 0500 2 5 int wnh EqualOpportunity

u LIC 97 0137 ATTACHMENT I OPERATING DATA REPORT I DOCKET NO. _50-285_ .

UNIT NAME 10RLCALHOUN . STATION  :

DATE _AUGUSL14._199L.___

COMPLETED BY 1.A._HOWMAN TELEPHONE J402L533,_6939_ _._

REPORT PERIOD: July 1997

1. Design Electrical Rating (Mwe-Nat): 47B_._

2. Maximum Dependable Capacity (Mwe-Net): _ 478-._ _

ORERATING.. STATUS i

THIS HONTH YR TO DATE CUMULATIVE

3. Number of Hours Reactor was Critical: 741 0 _ 508LQ_ _209.065-.0__

4. Number of Hours Generator was On-line: 7A4.0_ _ 4546.4 _163414.2__.

5. Unit Reserve Shutdown Hours: JL O__._ 0.0_. _03 _

6. Net Electrical Energy Generated (MWH): _351025A _2148175L5_ 69134300.8 _

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ATTACHMENT II DOCKET NO. 50-285-UNIT-SHUTDOWNS UNIT NAME Fort Calhoun DATE August 14. 1997 REPORT MONTH JULY 1997 COMPLETED BY M. A. Howman-TELEPHONE (402) 533-6939 lhh6f3 h h ', -

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S0 M Reactor 9 t 9 Prevent:Recurrencei None L(1)' (2)

Reason:. Method:

A-Equipment Failure (Explain) 1-Manual B-Maintenance or Test 2-Manual Trip / Scram C-Refueling 3-Astomatic Trip / Scram D-Regulatory Restriction 4-Continuation E-Operator Training / License Examination 5-Other (Explain)

F-Administrative G-Operational Error (Explain)

H-Other (Explain)

OPERATIONS SUMMAPY:

Fort Calhoun Station (FCS) operated'at a nominal 100% power level until July 10, 1997. at 2001 hours0.0232 days <br />0.556 hours <br />0.00331 weeks <br />7.613805e-4 months <br />. At this time, reactor power.was reduced to 95% to facilitate scheduled. repairs to CW-2C. Screen Wash Pump which required a circulating water pump cell outage, Repairs to CW-2C were

-completed and reactor power ascensio: to 100% was begun on July 2.1. 1997, at 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br />.' Fort Calhoun Station reached 100% reactor power on July 12.1997 at 0441 hours0.0051 days <br />0.123 hours <br />7.291667e-4 weeks <br />1.678005e-4 months <br /> and remained there through the em 9f the month of July 1997.

During July 1997. no power operated relief valves (PORV) er primary system safety valve challenges or failures occurred.

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