LIC-97-0054, Monthly Operating Rept for Mar 1997 for Fort Calhoun Station Unit 1

Monthly Operating Rept for Mar 1997 for Fort Calhoun Station Unit 1

ML20137W245
Person / Time
Site:	Fort Calhoun
Issue date:	03/31/1997
From:	Edwards M, Gambhir S OMAHA PUBLIC POWER DISTRICT
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LIC-97-0054, LIC-97-54, NUDOCS 9704180064
Download: ML20137W245 (8)

Text

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Omaha PublicPowerDistrict 444 South 16th StreetMall Omaha NE68102-2247 April 15, 1997 LIC-97-0054 4

V. S. Nuclear Regulatory Commission j Attn: Document Control Desk l Mail Station P1-137 Washington,'O.C. 20555

Reference:

Docket No. 50-285 i

SUBJECT:

March 1997 Honthly Operating Report (MOR) I I

Enclosed please find the March 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,

,}

Q S. K. Gambhir Division Manager -

Engineering & Operations Support J

SKG/mle .\

Enclosures c: Winston & Strawn --

/

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

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.i LIC-97-0054 f ._ Enclosure.

Page 1

- 1 OMAHA PUBLIC POWER DISTRICT  ;

( -Fort Calhoun Station Unit No. 1

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March 1997 Monthly Operating Report q

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& f l1; .0EERATl0NSJUMMARY  ;!

.The Fort Calhoun Station _(FCS) operated at a nominal 100% power level between  !

' March 1',.1997: and March 22,- 1997. On March 22. 1997 at 2002 hours0.0232 days <br />0.556 hours <br />0.00331 weeks <br />7.61761e-4 months <br />. FCS began ,

.a ~ power reduction in order to complete scheduled quarterly main turbine.

' control valve? testing. The 95% power level was reached at 2236 hours0.0259 days <br />0.621 hours <br />0.0037 weeks <br />8.50798e-4 months <br /> on March '

-22, 1997; Testing was' completed satisfactorily and a power ascension began at

-0200 hours on March 23, 1997. The station reached 100% power at 0910 hours0.0105 days <br />0.253 hours <br />0.0015 weeks <br />3.46255e-4 months <br /> on .

March 23.-1997 and remained there through the end'of the month, i On March 12, 1997 FCS made a 1-hour report, concerning a condition which met 4

the criteria of 10 CFR 50.72(b)(2)(I). The condition was a follow-up to LER - 96-005, which involved the design of the FCS Auxiliary Building for tornado venting. The FCS Updated Safety Analysis Report.(USAR) does not indicate '

whether the Control and Cable Spreading Rooms were evaluated for the stresses imposed by the repressurization phase of a tornado. However, a recently completed safety analysis for operability (SA0-96-01, Rev. 2) determined that the Control Room and Cable Spreading Room envelopes remain operable and within

the design basis following a design basis tornado.

i During-the period of March 17,-1997 through March 26, 1997 a self-assessment l of the Operations Department was completed. Personnel from FCS and several other utilities were utilized to conduct the assessment, which was supported ,

_ by the Utilities Service Alliance (USA),

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-2.  : SAEETLVALVES_0R_PORLCHALLENGES_.0fLEAILURES_WilIClLOCCURRED

.t During the month of March 1997, no power operated relief valves (PORV) or '

primary system safety valve challenges or failures occurred.

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t LIC-97-0054 Enclosure Page 2

3. RESULTS_DE_ LEAK._ RATE _IESIS The reactor. coolant system (RCS)' leak rate was steady throughout the month

' continuing the trend of minimal RCS leakage following the 1996 refueling.

. outage. March daily-leak rates were constant at approximately 0.1 to 0.2 gpm.

'4. CHANGES._TESIS_AND_EXEERIMENISlEQUIRING_NUCLEARJEGULATORLCOMMISSION AUTHORIZATION _EURSUANI_T0.10CERSD.59 Amendment _No. Descdption 181 This amendment revises Section 5.2 of the Technical Specificationstorelccatecontrolsforworkinghours to the Updated Safet!/ Analysis Report.

5. SIGNIEICANLSAEETLRELATED_MAINIENANCEl0R_ THEL 0 NTH _0Elacch._1991

- Maintenance on Component Cooling Water Heat Exchanger AC-10 was performed which consisted.of plugging a tube, repairing several small leaks by rolling tubes, and tube cleaning.

- Boric Acid Storage Tank (BAST) CH-118. Bypass Valve CH-462 was l disassembled and parts were discovered missing. The valve was rebui; '

and the manway was removed from BASTS CH-11A & CH-118 to search for the missing parts. The outlet valve (CH-114) on BAST CH-118 was also searched for the missing parts. Four (4) pieces of the broken valve i gate were found in the bottom of BAST CH-118. j J

- . Seal welded coupling threads on FO-5A-2 (Transfer Pump F0-4A-2: Suction j Strainer).

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- Seal welded coupling threads on F0-58-2 (Transfer Pump FO-4B-2: Suction j Strainer). 1

- Replaced thermocouple on Containment Stack Radiation Monitor RM-052.

Replaced relays.74-2A/D2, 94-AS/02, 94-BS/D2 on Diesel Generator No. 2  !

per ECN-FC-95-374.

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' Replaced tubing and fittings on.HCV-400E (VA-1A Cooling Coil. Raw Water Inlet Valve) to step air leakage.

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'LIC 97 0054 Enclosure

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6. DEEPAIINGJ)ATA_REEORI Attachment I  :

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~ 7. AVERAGE _DAILL1)NLLPOWER.1EVEL r

't Attachment 11

8. 'UNII_SHUIDOWNSJJ40_E0WEfLREDUCIIONS

'l iAttachiaent III.

9. REEUELING_INE0RMAIION. EORLCALMOUN SIAIION_.UNII_NQ._1 ,

Attachment IV i

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ATTACRMENT I OPERATING DATA REPORT DOCKET NO. 50-285 UNIT WiMFCXOidO!i~5?ATYDN DATE XF.CL 097fs97~~~

COMPLETED BY M. L. EDWAR5s OPERATING STATUS. -TELEPHONE 402-533-6F29

1. Unit Name: FORT CALHOUN STATION

2. Reporting Peil'6~d: MARCH 1997 NOTES

3. Licensed Thermal Power (MWt): 1500

4. Nameplate Rating (Gross MWe): 502

5. Design Elec. Rating (Net MWe): 4 '7 5~

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

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

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

_N/A

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

10. Reasons for restrictions, if any:

N/A THIS MONTH YR-TO-DATE CUMULATIVE

11. Hours in Reporting Period........... 744.0 2160.0 206138.0

12. Number of Hours Reactor was Cri ical 744.0 2160.0 f62851~.6~~

13. Reactor Reserve Shutdown Hourr...... .0 .0 1309.5

14. Hours Generator On-line............. 744.0 2160.0 16f02T.6~~

15. Unit Reserve Shutdown Hours......... .0 .0 .0 fTi~ill2.6-~ 215706737.7

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16. Gross Thermal Energy Generated (MWH) 3202857.7

17. Gross Elec. Energy Generated (MKH).. 77Ff28.0 1091632.0 ~ 7130986s!1~- ~

18. Net Elec. Energy Generated (MWH).... ~~

36 79 2 3TC~ 16-(2 51i4 .T~ 68628~/65.9

'19. Unit Service Factor................. 100.0 100.0 78.1

20. Unit Availaoiiity Tactor............ 100.0 ~~~ 100.0 78.1

21. Unit Capacity Factor (using MDC Net) fo~2 .1 101.0 7 T. 2 -~

2?. Unit Capacity Factor 'using DER Net) fd 2Tf~~ 101.0 69.7

? Unit Torced Outage Rate............. .0 .0 4.0

24. Shutdowns scheduled over next 6 months (type, date, and duration of each):

WA

25. If snut down at end of report period, estimated date of startup:

i 26. Units in test status (prior to comm. oper.): Forecast Ach ened

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INITIAL CRIT CALITY INITIAL ILECTRICITY N/A _ . _ _ . , _

COMMERCIAL OPERATICN _ _ _

• ATTACHMENT II

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' AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-285 -

UNIT FORT CALHOUN STATION '

DATE APRIL 09 1997-COMPLETED BY M. L. EDWA_RDS  ;

TELEPHONE 402-533-6929 _

i MONTH MARCH 1997  !

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL I

(MWe-Net) (MWe-Net) 1 4C8 17 488 [

2 489 18 488 f

3 489 19 488 4 488 20 488 -

5 488 21 487 l 6 488 22 _.

484 7 489 23 481 8 489 24 488 9 489 25 488 ,

10 489 26 488 11 488 27 488 12 488 28 488 13 488 29 488 l 14 488 30 488 15 488 31 488 16 488 INSTRUCTIONS On this form, list the average daily unit power level in MWe-Net for eacn

, day-.in the reporting month. Compute to the nearest whole megawa::.

ATTACHMENT III' DOCKET N0. 50-285 UNIT SHUTDOWNS AND' POWER REDUCTIONS .UNITNAMEEort_Calhoun_StJ DATE Apt 11_3.1997 ' -

COMPLETED BY M.__L' Edwards TELEPHONE L402L533-6929 -

REPORT MONTH Idarch 1991 N x- 1'

$0 ate";

Wi% ,

i[Typeh -Durationi > Reason?

f(HoursP r

.HethoN)off[i.ibens~eet [hiystem.

qShutting: TEvent?  ::: Code 9 Componenti

' 4 Code5 A

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[ > TCaUse.iAction; s .

g Correcti tot ~~

[ <. 3.37 b!%

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Downl.l : 3 Report?, -d. _

~' q^_ .. Op' $PreventIRecur W

Reactor'= E No!. <  % 1 wa None e

i 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)

Attachment IV Refueling Information Fort Calhoua Station Unit No. 1 Report for the month ending: MarctL31J92

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 Prior to May 2. 1998  !

is it scheduled?

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

5. Important licensing considerations associated None 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 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 2007 Outage assuming the present licensed capacity.

Prepared by:___/ d a. W[ =- Date: 4M/E7