ML19208A725

Monthly Operating Rept for Aug 1979

ML19208A725
Person / Time
Site:	Fort Calhoun
Issue date:	09/10/1979
From:	Hickle B OMAHA PUBLIC POWER DISTRICT
To:
Shared Package
ML19208A724	List: ML19208A723 ML19208A725
References
NUDOCS 7909170358
Download: ML19208A725 (8)

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-285 UNIT Fort Calhoun #1 DATE Sentember 10, 1979 CO%1PLETED BY B . .T . Ilickle TELEPil0NE h02-536 hh13 h!ONTil Au ,~u n t . 1070 DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (SMe Net) (MWe Net)

I h'7.7 17 h38.6 2 h'6.8 18 L17.6 3 h35.o 39 h35.0 4 h 3.2 20 h3h.9 5 h3?.6 21 270. L 6 h31.6 22 0.0 7 _

h31.8 23 27 0 g h 31.1 24 310.3 9 h 32. 3 25 hoh.6 10 h3h.5 26 hob. 8 3i k35.9 27 h06.6 32 h %. 9 28 h07.1 33 h 39. 0 29 h10.5 34 300.8 30 h29 1 15 30I*0 31 I*O 16 37.6 INSTRUCTIONS On this format, list the average daily unit power leselin MWe Net for each day in the reporting month. Compute to the nearest whole megav.att.

135ssi!G (9/771 7909170 M

OPERATING DATA REPORT DOCKET NO. 50-285 DATE Senten.ber 10, 1979 COMPLETED BY B. J. Hickle TELEPilONE h 02-5 WTh13 OPER ATING STATUS

1. Unit hame: W"+ NM'" " tnt 4~ 164+ 'I o . 7 Notes

2. Reporting PericJ: Au m t, 1979

3. Licensed Thennal Power 1.\lW ): 1h20

4. Nameplate Rating (Gross 31We): 502

5. Design Electrical Rating (Net Athe): -h57

6. Maximum Dependable Capacity (Gross %1We): h81

7. Stasimum Dependable Capacity (Net 3the): 457

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

n/A

9. Power Lesel To Which hestricted. If Any (Net MWe): U/^

10. Reasons For Restrictions. lf Any: 3/A This 3!onth Yr..to-Da t e Cumulatise

!!. Ilours In Reporting Period Thh.0 5,831.0 52,008.0

12. Number Of Ilours Reactor Was Critical 721.1 5,786.5 h1,751.5

13. Reactor Rewne Shutdown flours 0.0 0.0 1,136.0

14. Ilours Generator On-Line 695.9 5,7h6.5 h 0 ,812.'6

15. Unit Resene Shutdown llours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (N1Wil) 9h8,080.5 7,922,6h7.8 ho,571,071.1 .

17. Gross Electrical Energy Generated (Mhli) 306,98h.0 2,652,205.9 16 h56,h67.6

18. Net Electrical Energy Generated IMWil) 200,879.2 2,521,767.h 15,5h3,173.1

19. Unit Senice Factor 97.5 98.6 78.5

20. Unit Asailability Factor 93.5 98.6 78.5

21. Unit Capacity Factor (Using MDC Net) 85.5 9h.6 66.0

22. Unit Capacity Factor (Using DER Net) 85.5 95.6 65.h

23. Unit Forced Outage Rate 6.5 1.h h.5

24. Shutdowns Scheduled Oser Nest 6 Months tty pe. Date.and Duration of Each):

Jan uary 1, 1980 - Refuelinc Outare - Wo Month Duratien

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

26. Units in Test Status (Prior to Commercial Operation): Forecast Achiesed INITIA L CRITICALITY INITI AL ELECT RICI FY COMMERCI AL OPER ATION

@h (9/77)

UNIT SilUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-285 UNIT NAME Fort Calhoun ut DATE E^n+a"% " lo- 1979 COMPLETED BY 14 - J- !i i '[k l "

REPORT MONTil Aummt, 1979 ,

TELEPIIONE ung_5 %._a51a I

~. ~

- E No.

, 3? l3f; 4 53 Licensee E-r, [*. Cause & Correctise Date i 5g [ 2~5 Event 37 a Action to H j= 5 3

e @ =f Report e tn' U u

h'l Prevent Recurrence 6

79-03 79621 F 48.1 H 3 :l/A - -

E2ectrical noise spike caused turbine trip / reactor trip. Timer to be installed into circuit to prevent spurious trip.

A I 2 3 4 g2 F: Forced Reason: Method: Exhibit G - Instructions Q

S: Schedu!ed A. Equipment Failure (Explain)

B-Maintenance of Test 1 -Manual 2-Man ual Scram.

for Preparation of Data Entry Sheets for Licensee M C-Refueling 3 Automatic Scram. Esent Repori (LER) File (NUREG-N D. Regulator) Restriction 4-Ot her ( E xplain ) 0161)

I? Operator Training & License Examination F- Ad numst ratise 5 G-Operational Error (Explain) Exhibit I - Same Source (9/77)  !!-Ot her ( E xplain )

Refueling Information Ebrt Calhoun - Unit Ib. 1 a

Peport for the nonth ending August 31, 1979 .

1. Scheduled date for next refueling shutdown. January 1, 1980

2. Scheduled date for restart folloaing refueling. March 1, 1980

3. Will refuelin3 or resumption of operation thereafter require a technical specification change or other license a.~end:n2nt? Yes

a. If ansmr is yes, wnat, in general, will these be?

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

b. If answer is no, has tne reload fuel design ard core configuration been reviewed by your Plant Safety Review Comittee to deter-mine whether any unreviewed safety questic ns are associated with the core reload.

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

Stretch Power Application

4. Scheduled date(s) for submitting proposed licensing . Site Related Information, action and support inforration. July, 19/9 - Submitted Non-Core Related Informa-

5. Inportant licensing considerations associated with tion, October, 1979 refueling, e.g. , new or different fuel desian or . Core Related Analysis supplier, unreviewed design or perfonr.ance analysis and Tech. Spec. Changes, rethods, significant changes in fuel design, new November, 1979 operating procedures.

First use of Exxon fuel in Fort Calhoun.

Stretching power from 1420 MWth to 1500 MWth.

6. The nu-ter of fuel assenblies: a) in the core 133 assemblies b) in the spent fuel pool 157 c) spent fuel pool storage capacity 483 d) planned spent fuel pool "

storage capacity 483

7. The projected date of the last refueling that can be discharged to the spent fuel pool assu:ning the present licensed capacity. 1985 Prepared by ] Inte September 5, 1979 f Y unaw

CMAEA FUELIC PCWER DISTRICT Fort Calhou= Statien Unit No. 1 August 1979 Monthly Operations Report I. OPERATICNS SD! MARY Fort Calhoun =aintained essentially 100% pcVer during the =cnth of Augus t , 1979, with the exception of one unit cutage en August 21 .

This outage resulted frc= a =ccentary DC pcVer interrupt to the electro-hydraulic centrol unit of the turbine. During the unit cutage several =aintenance items were ec=pleted and certain required surveillance tests cc=pleted as scheduled.

The full cc=pli=ent cf operations staff has been achieved and a Oc=-

plete change to six section shift verk is expected by late Septe=ber.

A Nuclear Regulatory Cc =ission license examiner administered reacter Operator license exa s to four (h) candicates during August.

The Operatiens Depart =ent is =aintaining an active participation in the Three Mile Island owners group. Several =eetings were held during the =cnth of August to develop cperator guidelines for the energency procedure folleving a lecs of ecolant accident. In addition, the District has developed a Three Mile Island task force to start an evaluation of NUREG-0578's impact en Fort Calhoun Station.

Surveillance tests and ner:al Operational tests were cc=pleted with no outstanding deficiencies noted.

a. .e.r:-ce

.r v...va u m.av C e Ca.

ar . ra..r.e . r e.u ,

LER Uu=ber Deficiency 79-017 During ner-a pcver cperatien, "D" channel vide range nuclear instru=entatien failed with cc=plete loss of pcVer. The system was placed in a 2 cut of 3 trip logic by bypassing "D" channel while the pcVer supply was being troubleshot. He previous event of this nature has occurred at FCS1. Reference Tech. Spec. 2.15, Table 2-2, Ite= 10. No Technical Specification require =ents were violated.79-013 While performing ST-ESF-ll, F.1, it was noted that C/PIC-902, "A" steam generater pressure indicater/ controller for "C" Channel vould not reset. The "C" channel steam generator "A" pressure was bypassed with the three re=aining channels operable. Reference Tech. Spec. 2.15 No Technical Specificatien violatien cccurred.

% 6203

Mcnthly Operations Report Page Two August 1979 B. CHA'IGES I'I OPERATI:IG IETRCDS

1one C. RESULTS OF SLdVEILLAUCE TESTS AIID IIISPECTIC?iS The folicving are surveillance tests where an unusual result occurred:

Surveillance Test IIc. Description ST-CEA-1, F.6 During performance of ST-CF).-l it was found that Group 2 Rod Motions was not prohibited after PDIL L Red Blcck alarms were in alarm.

ai-u l-~n

- , . , . ~ . -

u,m 205 ,4sh . p4im ngement ST-EM-3 OI-821 - Failed to perfer: test en time ST-EM-3 OIJ21 - Test ec=pleted one day late D. CP2iGES, TESTS AIID EGERI'CITS CARRIED CUT '4ITECU'" CCMMISSIO!i n:r n0,in. ,

Procedure Descrittien DCR 78-67 SI-136 Pipe Suppcrt/Cc=pleted as designed.

SP-FAUD-1 All icops were functional instruments indicate greater than 99". assurance that greater than 150 pounds devnvard force exists en fuel bundles.

EEAR-FC-79-96 Exhaust fan in ace: 12 er Envirennental lab.

Cc (__ced as designed.

DCR 75A-70 Spent Fuel Rack Modification (Part 2) cc pleted as designed.

EEAR FC-79-127 Telephone System Modification EEAR 79-105 Service Air to Intake Structure Isolation /

completed as designed.

MR FC-78-51 Fuel Tank for CP-13 ccdification/cenpleted as de signe d. QMQ!jd SP-MEAS-2 Measurements for oil collecticn systen en RC pump =cters. Critical reasurements taken.

Annua' 7-a g. Drill, Conducted as planned 7-31-79 SP-CPTP-12 Measurement of isothe = al temperature ccefficient using Center CEA.

Monthly Operations Report Page Three August 1979 E. REULTS OF LEAK RATE TESTS Surveillance Test ST-CO IT-2, F.2, was performed en PAL Dcor and leakage was 12 ce per =inute.

F. CHAIiGES III PLAlir GPERATUG STAFF The following =anagement changes have been made at 0.P.P.D. and are effective September 1, 1979:

W. C. Jones, Division Manager-Production Operations R. L. Andrews, Section Manager-Operations R. L. Javorski, Section Manager-Technical Services J. K. Gasper, Manager-Reactor and Co=puter Technical Services S. C. Stevens, Manager-Fort Calhoun Station J. L. Connolley, Supervisor-Instrument and Centrol and Electric Field Maintenance, Fort Calhoun Staticn D. W. Jones, Superviscr44aintenance, Central Maintenance G. R. Petersen, Superviscr-Maintenance, Fort Calhoun Station L. G. Sealock, Superviscr4iuclear Physics and Cenputer Applications, Technical Services A. W. Richard, Plant Engineer, Fort Ca' houn Station G. TRAIIIDG Training for August included het license and requalification sessicas. Four Hot License candidates were examined en August 21 ,

22 and 23 by the I.PC and preliminary indicatiens were favorable towards the candidates. Areas covered by training also included crane operations, detector theory, EDO, and radiation protecticn in addition to systems training for plant saintenance.

E. CHA:iGES, TESTS A iD EXPERIME:CS REC.UIRIIIG :iUCLEAR REGULATCRY COM4ISSIC:I AUTHORIZATICII PURSUA:IT TO 10CFR50.59

Tone n.- r-

.J Q 't,n op/d L.

Approved by Manager-Fort Calhcun Station

$ E F.cnt hl:. Operatic s Reper.

Augast 1979 PEE e Four

. E2..s.A'C ( S15" ~ * - Saf ety Relat ed )

• Late i Descriptier i Cer ectiIe Acticn 997 6-16-79 Elec. Fire Fu=p Pull Flev Test Satisfied Tech. Spec. require-ments for full flow.

1015 7-17-79 Diesel Fire Pump Full Flow Test Satisfied Tech. Spec. require-ments for full flow.

1k53 T-27-79 Valves ECV kolB and HCV h01D vill Found dirt in orifice. Accuated not shut. the clean cut pcrts en the re-lays. Valves checked satisfac-torily.

4 O

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