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Monthly Operating Rept for Jul 1980
	ML19331C435
Person / Time
Site:	Fort Calhoun
Issue date:	08/08/1980
From:	Hickle B; OMAHA PUBLIC POWER DISTRICT
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ML19331C434	List: ML19331C433; ML19331C435;
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{) AVER AGE DAILY UNIT POWER LEVEL DOCKET NO. 50-285 UNIT Fort Calhoun #1 DATE August 8.1980 COMPLETED BY B. J. Hickle TELEPHONE 402-536-4h13 MONTH July. 1980 '

DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe-Net) (MWe Net) 437.0 17 431.1 2 h37.9 18 432.9 3 h37.7 19 h32 5 4 h38.7 20 h32.h 5 h37 7 21 h32.8 6 h35.1 22 h3h.2 7 .4 432.1 23 317.5 8 h30.h -

28 290.2 9 b29 6 25 h32.6 3o 430.5 26 h33.3 429.6 27 h3h.0 12 428.9 434.0 28 13 h30.2 29 h33.5 3.g h31.0 30 .

432.6 15 h30.h 3 h33. h 16 430.k INSTRUCTIONS On this forrnat. list the average daily unit power levelin MWe Net for each day in the reporting inonth. Compute to the rearest whole megawait.

(9/77) 8 0 081803N

OPERATING DATA REPORT DOCKET NO. 50-285 DATE August 6, 1980 COMPLETED TELEPHONE J2->jb-4413 BY }B. J . nick OPERATING STATUS

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Fort Calhoun #1 Notes - '

1. Unit Name:

2. Reporting Period: July, 1980

3. Licensed Thermal Power (MWt): 1420

4. Nameplate Rating (Gross MWe): 502

5. Design Electrical Rating (Net MWe): MSI

6. Maximum Dependable Capacity (Gross MWe): 481

7. Maximum Dependable Capacity (Net MWe): N5I

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

N/A

9. Power Level To Which Restricted.If Anv Net MWe): N/A

10. Reasons For Restrictions. If Any: DA This Month Yr. to.Date Cumulative -

11. Ilours Ls Reporting Period -

7 .0 5,111.0 Q ,0 W.0 #

12. Number Of Ilours Reactor Was Critical 737 3 1,705 1 h6,106.7

13. Reactor Reserve Shutdown flours 0.0 0.0 1,309.5

14. Ilours Generator On.Line 73h.3 1.643.3 45,091r.'h

15. Unit Reserve Shutdown flours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWil) 1,030,436.1 2,u7,593 7 55,352,623.0 .

17. Gross Electrical Energy Generated (MWH) 332,760.0 _, 668,506.0 18,346,735 6

18. Net Electrical Energy Generated (MWil) 315,940.8 651,627.8 17,339,147.6 98.7 32.2

19. Unit Senice Factor 75 1

20. IJnit Availability Factor 98.7 32.2 73 1

21. Unit Capacity Factor (Using MDC Net) 92.9 27.9 .u3.6

22. Unit Capacity Factor (Using DER Net) 92 9 27 9 63.2

23. Unit Forced Outage Rate 1.3 0.6 4.4

24. Shutdowns Scheduled Oser Next 6 Months (Type, Date.and Duration of Each t:

None

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

26. Units in Test Status irrior to Commercial Operation): Forecast Achiesed INITIA L CRITICALITY -

INITIAL ELECTRICITY COMMERCIA L OPER ATION (9/77) 7

- . . , . y 9 r

s DOCKET NO. 50-285 -

UNITSilVTDOWNS AND POWER REDUCTIONS UNIT NAME Fort Calhoun #1 h DATF Ausust 8. 1955 COMPLETED BY B. J. Hickle REPORT MONTH July, 1980 TELEPHONE 402-536-4413 l ":.

, .5? 3 .Y Licensee ,E-r, he, Cause & Corrective No. Date g 3g ( .g g 5 Event g Action to H

$5 5 Zo @= Report # mV o.}

! Prevent Recurrence

e. g o O

80-02 800721 F 9.6 A 3 N/A ED CKTBRK Inverter 'D' output breaker j tripped, lost instrument bus, i Reactor tripped on low steam generator level.

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1 2 3 4 F: Forced Reason: Method: Exhibit G -Instructions l S: Scheduled A Equipment Failure (Explain) I-Manual for Preparation of Data i B-Maintenance of Test 2 Manual Scram. Entry Sheets for Licensee

] C Refueling 3-Automatic Scram. Event Report (LER) File (NUREG-D Regularory Restriction 4-Oiher (Explain) 0161)

E-Operator Training & License Examinatioa F-Administrative 5 G-Operational Error (Explain) Exhibit I- Same Source (9/77) lI-Other (Explain) i

_ . . . _ . __ = - - - . - -.

Refueling Infor. nation Z

Fort Calhoun - Unit No. 1 .

Report for the conth ending July 31,1980 ,

Scheduled date for next refueling shutdown. .- Sept. 15, 1981 1.

Scheduled date for restart follcaing refteling. Nov. 15, 1981 2.

j 3. Will refueling or rest:mption of operation theresfter require a technical specification change or other No license amndment?

a. If ans'.cr is ye what, in general, will -

l these be?

i-4 .

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

c. If no such review has taken place, when is Sept. 1, 1981 it scheduled?

4. Scheduled date(s) for submitting proposed licensing action and support information.

5. Inportant licmsing considerations associated 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.

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The number of ftml assentlics: a) in the core 133 assemblics l 6. "

! b) in the spent fuel pool 197 c) spent fuel pool "'

storage capacity 483 d) planned spent fuel pool * "

storage capacity 483 7 She projected date of the last refueling that can be discharged to tbc spent fuci pool asst:ning the present licensed capacity. 1985

. Prepared by Date August 1, 1980 ru d, 4

w *e- me. am 6 +*e r-'1 ~r pr . , , , _

. e CMAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No. 1 July 1980 Monthly Operations Report I. OPERATIONS SUICfARY Fort Calhoun experienced a reactor trip on July 23 at 17h6 hours due to loss of instrument bus inverter "D". The outage lasted 6.6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and by 1200 hours0.0139 days 0.333 hours 0.00198 weeks 4.566e-4 months on July 2h the Fort Calhoun Station had returned to 100% power. .

Other than this outage there vere no other power reductions in the month of July and the unit continued to operate at 100%.

All required surveillance tests and operational tests were completen.

The operations staff participt.ted in the annual emergency drill at Fort Calhoun Station during July.

A. PERFORMANCE CHARACTFRISTICS LER Number Deficiency LER 80-016 The veld on the suction side of the pump CH-13 in the demineralized water flush line cracked.

Redundent charging pumps CH-1A and CH-1C vere operable therefore Technical Specifications 2.2. requirements vere satisfied. Related LER's are LER-78-005,78-006, 78-046.

3. CHANGES IN OPERATI'IG METHODS NONE C. RESULTS OF SURVEIL. LANCE TESTS AND INSPECTIONS 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 summary of the surveillance tests which results in Operations Incidents and are not reported elsewhere in the report:

Operations Incident Deficiency oI-989 ST-RPS-3 It vac discovered that trip setroint for trip unit 3 (flev) had drifted out of specifications in a non-conservative-direction.

Monthly Operations Repor+

July 1980 Page Two C. RESULTS OF SURVEILIANCE TESTS AND INSPECTIONS (Continued)

Operations Incident Deficiency OI-99h ST-74-1 Surveillance Test not. reviewed by Plant Engineer within 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months .

OI-1000 ST-ENV-3 '4aste Lagoon Release Permit 80 0M .

80-0h5, 80-Oh6, 80-Ch7 samples lost prior to running grease and oil analysis.

D. CHANGES, TESTS A*TD EXPEREENTS CARRIED OUT WITRCUT COMESSICN APPROVAL Procedure Descii;tien DCR 79-50 Arailiary Stes= for Caustic Trailer Tank Floving/ccepleted per designed.

EEAR 80 h6 ~ Emergency Feedvater Storage Tank Backup Fill /

completed as designed.

EEAR 80 h5 RC? Cooling Pipe Corrosion /ccepleted as designed.

E. RESULTS OF LEAK RATE TESTS On July 22, 1980, the personnel air icek was tested for integrity.

The measured leakage was 80 scem. No other leak tests vere perfor=ed.

F. CRANGES IN PLANT OPERATING STAFF NONE G. TRAETING During the =cnth of July training was conducted for the folleving:

Safety Meetings E=ergency Duty Officer respcnsibilities Alternate Energency Centrol Center Cperatica-Monitor Team functions Cycle 6 Technical Specification changes Fire Brigade functions Security Badges

'4aste Handling and Shipments Procedural Cccpliance

Monthly Operations Report July 1980 Page Three.

H. CHANGES, TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY C0:44ISSION AUTHORIZATION PURSUANT TO 10CFR50 59

1. Changes to Facility Operating License DPR-40.

Amendment No. 49, dated July 25, 1980. This amendment added requirements for verifying auxiliary feedwater system operability following maintenance and deleted requirement for cycling redundant safety injection valves for maintenance.

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/

l Approved Mhd @ r-Fort Calhoun Station 1

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Monthly Operations Repcrt July 1980 Page Four II. MA DTINANCE (Significant Sa'ety Related)

M. 3. 4 Cate i Description Corrective Acticn 6312 6-25-80 Stack gas =onitor reading high. Changed detector and calibrated.

6310 6-25-80 Pr: heaters breaker tripped. Replaced breaker.

6266 6-21-80 CH-lC demineralized water solenoid Vacuum tube replaced.

vill not shut.

h313 2-28-80 HCV-20h leaking through. Turned seat right side up.

6355 7-2-80 RM-OST fluctuation. Adjusted vacuus valve.

633h 6-28-80 TAR 2 and 3 temperature out of Check OK.

spec.

6282 6-23-80 Seal hole in vall between centro ned Repaired hole.

and uncontrolled area.

1 3682 1-17-80 HCV-2918 stuck open. Partially rebuilt valve.

6307 6-25-80 CH-1B excessive gland seal leak-off Check OK.

617h 6-11-80 D1 Secondary starting air compresso: Changed oil and oil pressure.

not loading.

6003 6-5-80 Svagelock Tee F.ttings leaking Replace Tee Fitting.

downstream of RC-138 and RC-139 6215 6-16-80 AI-125 Breaker tripped and will Softened loose wires.

not reset.

6193 6-13-80 TA1 Secondary Lov Voltage Sensor Replaced defection voltage is in alarm. sensor.

5855 5-6-80 Determine leakage of primary case Per PRC approved procedure.

gasket for all Reactor Coolant pumps.

6106 6-7-80 CH-1B has internal leak. Prepacked pump.

615h 6-11-80 RPS "D" Channel 112H temperature Rercuted cables in RPS cabinet reading erratic, cc=puter feeding noise into D112H.

.60h3 6-11-80 Containment Sump level is pegged Replaced chip in curr?nt converter high. and calibrated per CP-305 s+

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.u_______._. . _ _ _ _ _ _ . _ . _ _ - - - _ _ . _ _ - _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ . _ _ . - _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ . _ _ _ _ _ . - _ . .

Menthly Cperaticas Report July 1980

?sge Five II. '4AL : iA*TCI (Significant Safety Related)

4. O .

Date i Descri; 1:n i Ocr eceive Accien 59h8 6-3-80 D/LI-90h "B" Stes= Generator Level Calibrated C/90h, replaced =ani-lagged far behind other "3" Stes fcld en C/90h filled reference Generator level indicators. legs en A/90h, 3/90k, D/90h.

59h7 6-3-80 A/LI-90h "A" Stes= Generater Level Filled reference legs on A/901,

vas lagging far behind other 3/901, D/901, replaced C/901 indicators while draining Stea: =anifcid . Calibrated C/901 Generator, new transmitter.

5338 5-22-80 ECV-2881A =cves c=1y frc= c10 sed Re=cved operater and repositioned to half open. valve.

h696 3-T-80 HCV-716A valve failed leak test. Repaired per precedure MF-C7-A/

5329 6-12-80 Reneve RC-3A =ctor and repair '4crk cc=pleted per approved punp gasket, procedure.

2590 5*23-80 Inspect and clean AC-13. Cc=pleted per procedure MP-AC-1.

2589 5-23-80 Inspect and clean AC-1A. Cc=pleted per precedure MP-AC-1.

6052 6 h-80 First pipe suppc-t devnstrea= cf Replaced.

AC-286 has nut =issing frc= V-belt.

5912 6-1-80 Reasse=ble RC-3C. Cc=pleted per PRC approved precedure.

58hk 6-2-80 Insula. RC-33 pu=p hcusing. Cc=pleted.

5919 5-29-80 Replace insulatica en RC-3D. Cc=pleted.

6384 T h-80 :Iuelear pcver indicatien Channel Replaced Card A5 cperational A'e A gain drift. A3 gain drift and recalibrated.

T-22-80 FIC-2hh and 2h2 Letde n Press"~ r ound pri- -/ link en F.C.

6513 Interlock in alar =. disconnected.

! 5234 T-16-80 Rec 111brate and check RM-055 Recalibrate RM-055 sensitivity factor.

6LOS T-8-80 RFS "3" Channel ~~l-3 recalibrated. Cc=pleted.

6387 T-11-80 AI h0D Inverter Output 3reaker Placed plyvced --- d "verter tripped. cabinets.

596h 6-2-80 ?CV-Th6A Centain=ent Purge . Replaced internals and capped -

I failed leak rate. _ in seats. -

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ML19331C435

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