ML19242D256

Monthly Operating Rept for Jul 1979

ML19242D256
Person / Time
Site:	Fort Calhoun
Issue date:	08/09/1979
From:	Hickle B OMAHA PUBLIC POWER DISTRICT
To:
Shared Package
ML19242D253	List: ML19242D252 ML19242D256
References
NUDOCS 7908140758
Download: ML19242D256 (8)

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OPERATING DATA REPORT DOCKETNO. 50-285 DATE Augus t 9, 1979 COSIPLETED BY b. d. til ck le TELEPilONE l*Udl 536-4413 OPERATING STATUS

1. 81 nit Name: Fort Calhoun Station Unit No. 1 Notes

2. Reporting Period: July, 1979

3. Licensed Thermal Power (SIWt): 1420

4. Namephte Rating (Gross 5!We): 502

5. Design Electrical Ratini;(Net SIWE): 457

6. Staximum Dependable Capacity (Gross SlWe): 481

7. Staximum Dependable Capacity (Net SIWE): 457

8. If Changes Occur in Capacity Ratings (Irems Number 3 Through 7) Since Last Report. Give Reasons:

N/A

9. Power Level To which Restricted. If Any (Net SIWE): O ~

10. Reasons For Restrictions,If Any: N/A This $1onth Yr.-to-Date Cumulative

11. Ilours In Reporting Perioc' '

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12. humber Of flours Reactc,r % Critical 744 5,065.4 41,'030.4

13. Reactor Reserve Shutdown riours 0 0 1136.0

14. Ilours Generator On Line 744 5,050.6 40,116.7 _

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (51WH) 1,045,094.0 6,974,567.3 _ 48,622,990.6 .

17. Gross Electrical Energy Generated (5tWH) 343,142.0 2,345,221.9 15,149,483.6

18. Net Electrical Energy Generated (5thil) 326,235.1 2,230,894.2 15,252,299.9

19. Unit Sersice Factnr 100.0 99.3 78.3

20. Unit Assilability Factor 100.0 99.3 78.3

21. Unit Capacity Factor (Using .\lDC Net) . 96.0 65.7

22. Unit Capacity Factor (Using DER Net) 95.9 96.0 65.1

23. Unit Forced Outage Rate 0.0 0. 7 4.5

24. Shutdowns Scheduled Oser Next 6 51onths (Type. Date,and Duration of Eachi:

January 1,1980 - Refueling Outage - Two-month Duration

25. If Shut Down At End Of Report Period. Estimated Date of Startup: N/A

26. Units in Test Status t Prior to Commercial Operation): Forecast Achiesed INITIA L CRITICA LITY .

INITIA L ELECTRICITY CO\tNIERCI A L OPER ATION 7 ,

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(9/77 )

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AVERAGE DAILY UNIT POWER LEVEL

~ 50-285 DOCKET NO.

UNIT Ft. Calhoun #1 DATT.

July 9, 1979 COMPLETED BY B. J. Hickle TELEPilONE (402) 536-4413 MONTil July, 1979 DAY AVERAGE I PO ER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe-Net) 1 439.5 437.3 37 2 439.1 ,g 438.7 3

437.2 438.6 436.0 438.4 4 ,o 438.7 438.5 5 21 441.0 438.5 6

• 0 438.0 7 23 8

2., 437.5 9

443.9 436.4 25 10 441.6

'6 436.8 11 438.8 ,7 434.6 12 437.2 435.9

,3 436.8 ,

437.2 13 437.3 437.4 14 3g 15 436.8 438.3 3

I6 437.1 INS'IRUCTIONS On this format, list the average dady unit power levelin MWe Net for each day in the reportine inonth. C.unpute tii the nearest whole megawatt.

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e Refueling Infomation Fort Calhoun - Unit No. 1

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a Report for the nenth ending . July 31,1979 ,

1. Scheduled date for next refueling shutdown. January 1,1980 Scheduled date for restart following refueling. March 1,1980 2.

3. Will refueling or resumption of operation thereaf ter require a technical specification change or other license amendment?

a. If answr is yes, what, in general, will these be?

Stretching power to 1500 PWth is planned ir conjunction with .the change in fuel supplier to Exxon.

b. If answer is no, has the relcad fuel design and core configuration been reviewed by your Plant Safety Review Conr.uttee to deter-mine whether any unreviewed safety questions are associated with the core reload,

c. If no such review has taken place, when is it scheduled?

Stretch Pov er Aoplicatic-

4. Scheduled date(s) for sub:nitting proposed licensing . Site Related Information ,

action and support infccation. Jul v . 1979 - Submitted Non-Core Related Informa-

5. Ir. ortant licensir.g considerations associated with tion , October,1979 refueling, e.g. , new or different fuel design er Core Related Analysis and supplier, unreviewed design or perfor.ance analysis -

Tech. Spec. Changes, methods, sicnificant changes in fuel design, new November, 1979 cperating procedures.

First use of Exxon fuel in Fort Calhoun. '

Stretching power from 1420 MWth to 1500 MWth.

6. The nc er of fuel assentlies: a) in the core 133 assemblies b) in the s p t fuel pcol 157 c) spent fuel pool storage capacity 483 d) planned spent fuel pool "

storage capacity 483

7. W.e projected date af the last refueling that can he discharged to the spt fuel pool assu: ring the present 1985 licensed caoacity.

Prepared by k

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tate August 1, 1979

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OMAHA FUELIC PO'iER DISTRICT Fort Calhoun Station Unit No. 1 July 1979

!! nthly Operations Report I. OPERATIONS

SUMMARY

Fort Calhoun operated near a nc=inal 100T, power during the month of July. '"he fire protection projects continued en site.

Post Three Mile Island training continued as the shifts rotated through the training week.

A =utual fire drill was held with the Blair Fire Departnent. "'his drill de=cnstrated the ability of the Blair Fire Department pu=p truck to take suction from the Missouri River and pressurice the station fire header. This capability provides a defense in depth for providing fire suppression water at Fcrt Calhou . Statien.

The annual nu,: lear emergency drill was held during July. The oper-ations group at the plant responded to the alert and no significant deficiencies were noted.

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al in service, surveillance and operational testing were per-for=ed.

The training cf a hot license candidate grcup continued in pre-paration for the examination in late Auguct.

A. FERFCFy2iCI CHARACTERISTICS LEP. !!unber Deficiency NOME un,-

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- .m- r.n.Je. . m,14 6* 6v A.,0 NOHE C. RESULTS OF SURVIILIX;CE TESTS AliD I:ISPECTIO:;S The following is a surveillance test where an unusual result occurred:

Surveillance Test '!c . Descrirtion ST-?M-3 20: conpleted within specifie:1 period of time.

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Monthly Operations Report Page Two July 1979 D. CHA'IGES, TESTS AND EXPERIME';TS CARRIED OUT WITHOUT C0:01ISSION APPROVAL Prneedure Descrintion ST-RPS-5 Execre Detector Sy==etric Offset Calibraticn:

Parameters within limit:, no recalibration required.

FM-RM-1 Radioactive Source Surveillance of Licensed Sources not at the Fort Calhoun Station.

DCR 79-84 Install audible alarms en peri.a1 = nitor in Security Building.

SP-FAUD-1 Fuel Asse=bly Uplift Condition Detectien/all loops with available instrumentation show greater than 99% assu ance.

M.O. 10699 Install PR's in New Fuel Storage Area RM-25A/

c0=pleted as designed.

SP-CONT-2 Contain=ent Purge Supply and Exhaust Fenetration (M-88 and M-87) ?f pe C Leak Rate Test /c:=pleted per procedure.

SP-DI-2 Water Flant rem -"' "*ng Test /c0=pleted per procedure. Plant Er. gin-ers evaluating results.

SP-FAUD-1 Fuel Asse=bly Uplift Condition Detection /all loops with available instru.=entation show grecter than 995 assurance.

M.O. 933 VA-TlA & 3/cc=pleted as designed M.0. 10200 Additional FR's in Roc = Tl/ccepleted as designed.

EEAR 79-115 Centrol Switch-Ereaker 1A22/Cc=pleted as designed.

M.O. 3625 Additional PR's in Roc = 69/cc=pleted per design.

DCR 77-26 Auxiliary Euilding Fire Protection Systen - Diesel Generator S)rinkler "odification/c =pleted as designed.

SP-RPS-5 Excore Detector Synnetric Off Set Rec nibraticn/

c =pleted per procedure.

DCR 78-53 Fire d1=per =odification/cc=pleted as designed.

DCR TT k5 Fire Protection Water Line Tie-in "cr Zecu-ity 3uilding/ccepleted as designed.

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Monthly Operations Report Fage Three July 1979 D. Continued Procedure Descrintion DCR 76A-13 Modificaticn of Feedvater Heater Pipe Supports /

cc=pleted as designed.

EEAR 79-22 Security Diesel Battery 3ack/ completed per design.

EEAR T3 h5 Bullet Nose Pressurization / completed per design.

E. RESULTS OF LF.AK RATE TESTS The six month 60 psig leak rate tegt was perfor=ed on the Fer-scnnel Air Lock. 3esults were within the .6 L, li=it.

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2 m. .aA .. -.. .ss s The training at Fort Calhoun Station consisted cf requalification training and hot license training for the operators, Radiation Protection Training, First Aid Training and general system training for the crafts.

3. CHA: IGE 3, TE3TS A!!D EXPERIEITS REQUIRING NUCLEAR REGULATORY CC'SIISCIO:i AL"HORI7ATIO: FURCUA:T TO 10 CFR 50.59 Changes to Operating License DPR k0 Amendment No. h6 dated July 2,1979 The amendment revised the Technical Specificatiens to incorporate surveillance requirecents fcz in-service inspection of stea generator tubes and replaced existing in-service inpsection and testing Technical Specifications with an in-service inspection and terting program that meets the requirements of 10CFR50.55A.

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'hnager-For: Calhoun Station e

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Monthly Operations RepoM.

July 1979 Pas ? Four II. MAI::TEUd'CI (Significant Safety Related)

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• Oate l Description Corrective Action i

i 1202 T-7-79 SIS ko Anchor Bolts Cc=pleted per procedure 1155 T-9-79 Stud Tensioning per Bulletin 79-02 Completed per procedure 133h T 79 RPS-Channel "A" V0PT =eter operating i= properly Cer.pleted per procedure 1421 T-25-79 MSS-10/CCncrete expansion anchor located in south baseplate Cc=pleted per M.O.

1L26 T-2 5-79 SIS-27 Pipe support cotter pin

=isaing on upper support Cenpleted per M.0.

1h25 T-2 5-79 SIS-2TA pipe support nut missing frc= bolt en support SIS-27A Cc=pleted per M.0.

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