ML19210C971

Monthly Operating Rept for Oct 1979

ML19210C971
Person / Time
Site:	Fort Calhoun
Issue date:	11/08/1979
From:	Hickle B OMAHA PUBLIC POWER DISTRICT
To:
Shared Package
ML19210C970	List: ML19210C969 ML19210C971
References
NUDOCS 7911200381
Download: ML19210C971 (8)

Text

a i

AVERAGE DAILY UNITPOhLit LE\\ 21.

DOCKET NO.

50-285 UNIT Fort Calhoun #1 DATE November 8. 1979 COMPLETED BY B. J. Hickle TELEPilONE h02-526_hh12 MON 111 n a + ^b"

'070 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) g h22.0 37 hhl.0 2

L29.b gg hh0.5 3

h28.1 39 hh0.1 4

h*0.8 20 hh0.h 5

bhn_2 21 hh'.0 6

h h, 22 hhl.6 7

hh0-23 hh2.6 g

hh0.5 24 h42.5 9

hh0.0 25 hhl 9 10 hh0.6 26 hhl.1 11 hkl.2 27 hh0.9 12 hh1.0

g hh0.7 13 hh1 s 29 hh0.1 34 LL2.3 30 h30.h 15 hhi.o 31 320.0 16 hh1.2 INSTRUCTIONS On this format. list the average daily unit power levelin MWe. Net for each day in the reporting month. Compute.o the nearest whole megawatt.

(9/77) 7(

f,) b i

E h5 7911200

OPERATING DATA REPORT DOCKET NO.

50-285 DATE 'Imder 8,1979 COh!PLETED BY B. J. Hickle TELEPHONE 302-596 hh13 OPERATING STATUS N

'*5

1. Unit Name:

Fort Calheun Statien Unit No. 1

2. Reportin,2 Period:

October. 1979

3. Licensed Thermal Power (SIWtp:

1h20

4. Nameplate Rating (Gross SIWE):

502 5I

5. Design Electrical Rating (Net 51We):

6. Slaximum Dependable Capacity (Gross 51We):

L R,

7. Slasimum Dependable Capacity (Net 51We):

hs7 S. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:

N/A

9. Power Lesel To Which Restricted. If Any (Net 51We):

N/A

10. Reasons For Restrictions.If Any:

'I/A This 51onth Yr..to.Date Cumulative

!!. Hours in Reporting Period 7h5.0 7,296.0 53,h73.0

12. Number Of Hours Reactor Was Critical 742.5 7,249.0 43,214.0

13. Reactor Reserve Shutdown Hours 3.1 3.1 1,139.1

14. Hours Generator On Line Thl.9 7,208.h 42,274.5

15. Unit Resene Shutdown Hours 0.0 0.0

'O.0

16. Gross Thermal Erargy Generated (SIWH) 1,038 hkl.0 9,974,967.3 51,623,390.6

17. Grow Electrical Energy Generated (51WH) 341,9h2.0 3,322,001 9 17,126,263.0

18. Net Electrical Energy Generated (51WH) 325,204 5 3,15c,5o4.0 lo,179,9c9 7

19. Unit Senice Factor 99.6 98.8 79.1

20. Unit Availability Factor 90.6 98.8 79.1

21. Unit Capacity Factor (Using 51DC Net) 05.5 ch.7 66.8

22. Unit Capacity Factor (Using DER Net) 95.5 9h.7 66.2

23. Ur..: Forced Outage Rate 0.0 1.2 h.4

24. Shutdowns Scheduled Over Next 6 51onths ! Type. Date.and Duration of Each t:

Refuelinst Outage, January 18, 8 Week ILration

25. If Shut Down At End Of Report Period. Estimated D.ite of Startup:

Nov "her 7 1070

26. Units In Test Status IP ior to Commercial Operation):

Forecast Achiesed INITIA L CRITICALITY INITIA L ELECTRICITY CO\\l%1ERCIAL OPER ATION 7(^

0BS i

1"i77 >

s 50-285 DOCKET NO.

UNITSifUTDOWNS AND POWER REDUCTIONS UNIT NAhtE Fort Calhoun #1 DATE flovember 8.1979 REPORT A!ONTil October, 1979 COMPLETED BY B-J-

rHekin TELEPIIONF la 09_c; v _.h M 3 e.

E c

.$ g 3

}.E 3 Licensee

,E*

{e.

Cause & Corrective No.

Date R

5 ij s

.c 5 5 Event gy g3 Action to Report #

mo O

Prevent Recurrence H

f:

3 gy3 c o

g o

e O

79-05 791031 S

3.1 B

1 Reactor shutdown to perform non-destructive testing of steam generator nozzle to piping velds pursuant to !!RC IE Bulletin 79-14.

[

t 2

3 4

F: Forced Reason:

hiethod:

Exhibit G Instructions i

^

S: Scheduled A Equipment Failure (Explain) l-blanual for Preparation of Data B-htaintenance ci Test 2-klanual Scram.

Entry Sheets for Licensee C Refueling 3-Automatic Scram.

Event Repori t LE RI File iNtlREG-O D-Regulatory Restriction 4-Other ( Explain) 0161)

CC E-Operator T aining & License Examination Q

F-Adnunistratise 5

G-Operationa! Error (Explain)

Exlubit I - Same Source (9/77)

II-Other ( Explain)

Refueling Information Fort Calhoun - Unit No. l-Report for the nonth ending October 31, 1979 January 18, 1980 1.

Scheduled date for next refueling shutdown.

11 arch 1,1980 2.

Scheduled date for restart following refueling.

3.

Will refueling or resumption of operation thereafter require a technical specification change or other yes license a n dment?

If answer is yes, what, in general, will a.

these be?

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

b.

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

c.

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

Stretch Povar Application 4.

Scheduled date(s) for submitting proposed licensing

- Site Ralated Information, acticn and support infornution.

July, 1979 - Submitted

- Core Re'ated Analysis 5.

Imoortant licensing considerations associated with and Tech. Spec. Changes, refueling, e.g., nea or different fuel design or November, 1979 supplier, unreviewed design or perfomance analysis nethods, significant changes in fuel design, nes operating procedures.

First use of Exxon fuel in Fort Calhoun..

Stretching power from 1420 ftWth to 1500 ftWth 133 assemblies 6.

The number of fuel assemblies: a) in the core 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 puol assuming the present licensed capacity.

1985 Prepared bv_

Date November 1, 1979

{l l

rm

OMAHA FUBLIC POWER DISTRICT Fort Calhoun Station Unit No.1 October 1972 Monthly Operations Report I.

OPERATIONS

SUMMARY

During the month of October,1979, the Fort Calhoun Station operated at a nominal 100% power frem October 1 thru October 30.

On October 31 the plant started its decension in power in order to be in hot shutdown by midnight of October 31st. This scheduled shutdown is necessary for an inspection and ultrasonic test of the main feedvater line nozzle's veld connections. The inspection of seismic supports (Bulletin 79-02) continued.

A.

PERFORMANCE CHARACTERISTICS LER Number Deficiency 79-019 During normal rotation of component cooling water heat exchangers, inlet valve HCV h89A to C.C.W. heat exchanger AC-1A, vould not operate frcs the re=ote switch in the conuol room. The valve was operated locally by use of the =anual hand wheel, thus allowing normal operation of ce=ponent cooling heat exchanger AC4A as defined in Technical Specifications 2.3 and 2.46.

B.

CHANGES IN OPERATING METHODS None C.

RESULTS OF SURVILLANCE TESTS AND INSPECTICNS Surveillance tests as required by the Technical Specifications Section 3.0 and Appendix B, were performed in accordance with the annual surveillance test schedule. The following is a sum =ary of the surveillance tests which results in Operations Incidents and are not reported elsewhere in the report:

Operations Incident Deficiency OI-854 ST-ISI-C7CS-3 Boric Acid Pump showed high discharge pressure.

OIJ52 ST-ISI-CC-3 Unable to locste results.

OI448 ST-ESF41 C/PIC-902 failed to reset.

OI 838 ST-FD-1 Zone 6 detector 15, 24 and 27 and Zone 7 detector 1 out of tollerance.

OI-847 ST-FD4 Detector #2 - Zone #13.

OI-856 ST-FD4 Was not completed as scheduled.

~

OI 859 ST-ESF-6 Diesel Generator D2 failed to start on secondary air.

75' 091 4

Monthly Operations Report October 1979 Page "vo C.

RESULTS OF SURVEILLANCE TESTS AND INSPECTIONS (Continued 1 Surveillance Test No.

Descrintion ST-ESF-11 (F.ll Steam Generator Pressure Channel Check -

Signa C/PIC-902 failed to reset after trip test. Repaired per Maintenance Order #2035 D.

CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITEOUT COMMISSION APPROVAL Procedure Descrietion DCR FC-79-9 Addition of loop load resister to loop C/112-H - completed as designed.

Test using center CEA/Results SP-CPTP-12 Variable T"}$ test.

docunented SP-RPS-5 Excore Detector Sy= metric Offset Recalibration/

results are noted on special procedure.

E.

RESULTS OF LEAK RATE TESTS NONE F.

CHANGES IN PLANT OPERATING STAFF NONE G.

TRAINING Training at Fts Calhoun Station consisted of radiation protection refresher, vaste disposal procedures for operators, general =ain.-

tenance and H.P. as per OIE-7919, and procedural compliance for plant staff. Central Maintensace personnel received radiation protection refresher, procedural compliance training, mask fit and physical refresher in lieu of the November outage at the plant.

H.

CHANGES, TESTS AND EXPEMTIS REQ, RING NUCLEAR REULATORY COMMISSION AUTHORIZATION PURSUANT TO 10CFR50 59,

'\\ l f

NONE (g

F g'er-Fort CaIhoun Station

-m

Monthly Operations Report Page II. MAINTENANCE (Significant Safety Related)

M. O. #

Date Descrintion Corrective Action 1956 10-3-79 SI-2C Discharge Valve (HCV-2918)

Disassembled operator and air failed to close during ST-SI/CS-1.

cylinder, cleaned parts, and reassembled. New parts on order.

Valve is maintained in its accident (open) position.

203h 9-20-79 Rav Water Hanger RWH - 60 has a Hanger was tightened up loose clevis. Reference IE Bulletin satisfactorily.

79-14.

20h1 9-26-79 Seismic Restraint SIS-8h is missing Missing cotter pin replaced, a cotter pin. Reference IE Bulletin Snubber inspected and found to 79-14.

be in good shape.

20k2 9-26-79 Seismic Restraint SIS-2h is missing Missing cotter pins replaced.

. cotter pins. Reference IE Bulletin Snubber inspected and found to 79-14.

be in good shape.

20h3 9-26-79 Seismic Restraint SIS-26 needs to Retraint realigned to the correct be realigned slightly so that it angle.

is horizontal. Reference IE Bulletin 79-14.

20hh 9-26-79 Seismic Restraints SIS h5 and Restraints realigned to the SIS-46 need to be realig;ed slightly correct angle.

so that they are horizontal.

Reference IE Bulletin 79-lh.

2092 10-2-79 Seismic Retraint SIS-29 needs to Restraint and hanger realigned be realigned so that pipe hanger to correct positions.

SIH-110 can assume its proper position. Reference IE Bulletin 79-1h.

2107 11-1-79 Feed water pipe hanger FWE llh has Hanger was centered and the a loose U-bolt and the support U-bolt was tightened.

needs to be centered in its guides.

Reference IE Bulletin 79-lh.

2108 9-28-79 Remove U-bolt from Safety Injection U-bolt removed. U-bolt was Pipe hanger SIH-55 U-bolt was installed when a preliminary installed per IE Bulletin 79-lk.

analysis indicated that it was needed. Follovup ccmputer analysis showed that the U-bolt would restrict ther=al expansion and thus was not needed.

0)D

'?'

Mcuthly Operations Report Page II. MADTENANCE (Significant Safety Related)

M. O. #

Date Descrittion Corrective Action 2130 10-3-79 h 11 leak at elbow of demineralized Weld repaired as per procedure water flushing line on the suction MP-CH-1-2.

side of "C" chazJing punp.

g 278 3-26-79 FE-532 Waste Gas Release orffee--

Completed change flow orfice.

2225 10-15-79 Fire Penetration Repair Temporary Repair Only.

2226 10-15-79 Fire Penetration Repair Temporary Repair Only.

2227 10-15-79 Fire Penetration Repair Temporary Repair Only.

2229 10-15-79 Fire Penetration Repair Temporary Repair Only.

222k 10-15-79 Fire Penetration Repair Temporary Repair Only.

2166 10-32-79 SI-93 & gh replace "all thread" Completed and channel iron with 2h" certified U-bolts frcm stores.

2328 10-24-79 Diesel failed to start on Secondary Found loose wire IOC for SAP-2 Air. No air pressure downstream of on T3.

Found relay RS-1 and regulator.

RS-2 loose in base.

2271 10-22-79 WD-708 - Stuck close Repaired O

4 ~l { 1

( G l' U/

.