ML19351G348

Monthly Operating Rept for Jan 1981

ML19351G348
Person / Time
Site:	Fort Calhoun
Issue date:	02/09/1981
From:	Tira Patterson OMAHA PUBLIC POWER DISTRICT
To:
Shared Package
ML19351G344	List: ML19351G343 ML19351G348
References
NUDOCS 8102230560
Download: ML19351G348 (8)

Text

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-285 UNIT Fort Calhoun #1 DATE February 9, 1981 COMPLETED BY T. L. Patterson TELEPHONE (402)S36-4413 Nf0NTil January, 1981 DAY AVER AGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (htWe-Net) (51We Net) 1 354.8 i7 354.4 2 354.8 18 353.7 3 355.9 39 354.9 4 356.6 20 355.0 5 356.8 21 354.1 6 356.3 22 353.9 7 _-a 356.7 23 353.7 g 356.3 _ 24 353.9 9 355.1 25 353.2 to 252.1 26 353.4 11 247.4 27 '354.7 12 302.6 28 353.9 13 354.6 29 354.7 l

34 355.0 3o 125.2 15 355.5 3, 80.2-l 16 354.9 l

INSTRUCTIONS On this format. list the average daily unit power levelin htWe Net for each day in the reporting month. Compute to the nearest whole megawatt.

(9/77) i 8102230fGo

OPERATING DATA REPORT DOCKET NO. 50-285 DATE February 9, 1981 COMPLETED BY T. L._Patterson TELEPilONE (4U2)b &-4413 OPERATING STATUS Fort Calhoun Station Unit No. 1 Notes

1. Unit Name:

2. Reporting Period:

January, 1981

3. Licensed Thennal Power (MWt):

1500

4. Nameplate Rating (Gross MWe):

513

5. Design Electrical Rating (Net MWe): 490

6. Masimum Dependable Capacity (Gross MWe):

513

7. Maximum Dependable Capacity (Net MWe):

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: N/A a

This Month Yr.-to Date Cumulative .

I1. Ilours In Reporting Period 744.0 744.0 64,465.0

12. Number Of !!ourS Reactor Was Critical 725.1 725.1 50.503.4

13. Reactor Reserve Shutdown flours 0.0 0.0 1,309'5 .

14. liours Generator On-Line 716.2 716.2 49,476.1

15. Unit Resene Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWil) 781,266.2 781,266.2 60,499,506.5 .

17. Gross Electrical Energy Generated (MWil) 261,590.0 261,590.0 20,049,861.6

18. Net Electrical Energy Generated (MWil) 245,621.6 245,621.6 . y ,943,804.5

19. Unit Senice Factor 96.3 96.3 76.7

20. Unit Availability Factor 96.3 96.3 76.7

21. Unit Capacity Factor (Using MDC Net) 67.4 67.4 64.5

22. Unit Capacity Factor (Using DER Net) 67.4 67.4 64.1-

23. Unit Forced Outage Rate 3.7 _

3.7 4.1

24. Shutdowns Scheduled Over Next 6 Months (Type. Date.and Duration of Each): -

None

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

26. Units in Test Status IPrior to Commercial Operation): Forecast Achiesed

'n INITIA L CRITICALITY INITIAL ELECT RICITY COMMERCIAL OPERATION (9/77)

i l

l 50-285 l

UNIT SilUTDOWNS AND POWER REDUCTIONS DOCKET NO.

UNIT N AME Fort Calhoun #1 DATE -Februarv 9. 1481 COMPLETED BY T. L. Patterson REPORT MONTI January, 1981 TELEPilONE (402)S36-4413 l l

. "h -

, 3E 3 Yk Licensee E

% be. Cause & Corrective No. Date g 3= d ,g g 5 Event Fg 83 Action to H

$ :. 5 5is=g Report # (E V  !' Prevent Recurrence e u Q

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l 81-01 810130 F 27.8 A 3 N/A IA INSTRU Coincident voltage spikes on channels B and D caused high reactor power trip of reactor and turbine. Several items of corrective maintenance completed prior to restart.

i l

l-1 2 3 4 F: Forced Reason: Method: Exhibit G-Instructions S: Scheduled A Equipment Failure (Explain) 1 -Manual for Preparation of Data

H-Maintenance of Test 2-Manual Scram. Entry Sheets for Licensee l C Refueling 3 Automatic Scram. Event Report (LER) File (NUREG-l D Regulatory Restriction 4-Other (Explain) 0161)

, E-Operator Training & License Examination i

.F Administrative 5 G-Operational Error (Explain) Exhibit 1 - Same Source (9/77) 11-O:her ( Explain)

Refueling Informtion Fort Calhoun - Unit No. l .

Report for the nonth ending January 1981 .

Scheduled date for next refueling shutdcran. . September 15, 1981 1.

November 15, 1981

2. Scheduled date for restart following refueling.

3. Will refueling or restaption of operation thereafter require a technical specification change or other No license anundaunt?

a. If answer is yes, what, in general, will these b3?

b. If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Costittee 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 September 1, 1981 it scheduled?

4. Scheduled date(s) for submitting proposed licensing action and support infon"ation.

5. Inportant licensing considerations associated with refueling, e.g., new or differt_nt fuel design or supplier, unreviewed design or performance analysis nothmis, significant changes in fuel design, new l

operating procedures.

4 l

6. The nttrber of fuel assenblies: a) in the core 133 assemblies

' b) in the spent fuel pool 197 i

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 asstating the present licensed capacity. 1985 Prepared by.

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b_M (/

Date February 3, 1981

e i

• f OMAHA PUBLIC POWER DISTRICE

Fort Calhoun Station Unit No. 1 January 1981 Monthly Operations Report I. OPERATIONS

SUMMARY

Fort Calhoun operated at approximately 75% reactor power during the <

month of January.

Power was reduced during the weekend of January 11 to approximately 55% power to accon:modate condenser tube leak testing.

Power was returned to 75% at the co.npletion of the testing.

One reactor trip occurred on January 30 at 0908. The unit was resynchronized to the grid at 1254 on January 31, 1981.

The Supervisor-Operations participated in an emergency procedures workshop in Windsor, Conn. on January 10 thru 12.

Surveillance tests and operational tests were completed as required.

One new Operations personnel reported for duty in January.

A. PERFORMANCE CHARACERISTICS LER Number Peficiency LER 80-030 During the performance of ST-ESF-6, F.2, Appendix F, Diesel Generator #1 (DG-1) failed to start on its secondary air system. DG-1 was removed from service in accordance with Tech. Spec. 2.7(2)i and the secondary air start motors were repaired. Prior to the incident, DG-1 had successfully started on

• its primary air start system. In addition,-

DG-2 was started to verify its operability.

LER 80-031 During normal operation, a leak developed in l the veld which connects the demineralized i vater flush line to the discharge manifold of Charging Pump CH-1B. Charging pu=ps CH-1A and CH-lc were operable; therefore, the require-ments of Technical Specification 2.2 were met.

A similar' event is described in LER 78-021.

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Month Operations Report i January 1981 Page Two A. PERFORMANCE CHARACTERISTICS (Continued)

LER Number Deficiency LER 80-032 on 12-10-80, while operating at approximately ,

75% power, the primary heat tracing circuits associated with the piping located between the Boric Acid Pump (CH-hA) discharge and one of the isolation valves (HCV-268) to the charging pump suction header were found to be inoperable.

During the time of the failure, the secondary heat tracing circuits associated with the afore-mentioned piping were operable. In addition, there were at least two remaining operable flov 1 paths from the concentrated boric acid tanks to l

the reactor coolant system as well as a flow path from the SIRWT to the charging pumps as required by Technical Specification 2.2.

B. CHANGES IN OPERATING METHODS None C. RESULTS OF SURVEILLANCE TESTS AND INSPECTIONS None D. CHANGES, TESTS AND' EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL Procedure Description / Safety Analysis Summary SP-ALIGN-1 Time-Motion Study for Auxiliary Feedvater Valves W-171, W-172, W-Thk, W-745 Performance of this special procedure does not constitute an Unreviewed Safety Question as defined in 10CFR50_.59, since it incorporates ST- N-1, F.1, to' insure proper valve alignment according to Technical Specification 3 9 and FSAR Section 9.h.

SP-FAUD-1 Fuel Assembly Uplift Condition Detection - all test results acceptable indicating adequate downward force on the fuel assemblies.

SP-FAUD-1 Fuel Assembly Uplift Condition Detection - down-vard force indications on fuel assemblies is acceptable.

Monthly Operations Report January 1981 Page Three D. CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL (Continued)

Procedure Descriution/ Safety Analysis Summary SP-FAUD-1 (Continued)

Performance of this special procedure does not constitute an Unreviewed Safety Question as defined in 10CFR50.59, since it only involves taking test data and making calculations.

EEAR-80-lh WD-39A/ completed as designed.

Completion of this procedure did not constitute an Unreviewed Safety Question as defined in 10CFR50.59, since it upgraded existing system components for improved performance and safety.

E. RESULTS OF LEAK RATE TESTS PAL door was tested on 1-28-81. The leakage measured was O scem.

F. CHANGES IN PLANT OPERATING STAFF New Auxiliary Operator (Nuclear) is John Paulsen.

G. TRAINING Training for January, 1981, included approximately 35 hours4.050926e-4 days <br />0.00972 hours <br />5.787037e-5 weeks <br />1.33175e-5 months <br /> per week of prepared lectures for Operations, systems training and Tech. Spec. training for all maintenance personnel. Four Hot License candidates received their Reactor Operator licenses.

Fire brigade training was conducted for the fire brigade members.

H. CHANGES, TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY C0!CIISSION AUTHORIZATION PURSUANT TO 10CFR50 59 Amendment No. 54 regarding Technical Specifications for NUREG 0578, Category A, Modifications and Procedural changes.

I. CHALLENGES TO PORV AND SAFETY VALVES None

-Approved By W eptfGr Manager-Fo[CalhounStation

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1 Menthly 0;erstions Repor, January 1981

PMe Four II. MAI

i*E'IANCE (Significant Safety Related) j M. O.

• Date Description Corree:17e Action 79h0 11-21-80 SI-1A check alignment Realigned.

7771 11-21-80 Relief valve CH-182 leaks by Repaired per Procedure MP-RV-1 and tested per ST-ISI-CVCS-1.

8342. 12-27-80 B-PIA-102Y failed low giving trip Replaced fuse.

on RPS "B" Channel.

1959 9-25-79 Calibrate condensate instruments Required instruments for stretch power test. recalibrated.

7772 1-8-81 Relief Valve CH-183 leaks by Valve repaired per MP-RV-1 and tested per ST-ISI-CVCS-1.

7776 11-17-80 Transfer spent resin from spent Resin transfer completed per resin storage tank to transfer SP-WDS-14.

cask.

8052 12-18-80 High vibration on inboard bearing Alignment checked and ad, justed.

of LPSI Pump SI-1B. Pump retested satisfactorily i per ST-SI/CS-1.

8509 1-15-81 Perform preventive maintenance Maintenance performed per PRC on SI-1A motor and breaker. approved procedures PM-EE-1.2 and MP-EE-8.

8546 1-13-81 Hydrogen Purge Fan VA-80A vill not Sticky contactor found as the start even though pump and motor problem. Lubricated with vill rotate by hand. silicone and tested fan satis-factorily.

6231 7-28-80 HCV-2908 von't shut with the key Repaired pump and directional switch. valve.

8519 1-10-81 RM-061 Stack Gas Rad. Monitor - . Replaced vacuum pump.

I no flow.

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8333 12-26-80 "B" Boric Acid Pump Breaker Trips Replaced breaker.

When pump tries to start.

6806 1-23-81 PIC-905C High Alarm vill not clear. Replaced meter.

7189 1-22-81 PIC-905D High Alarm vill not clear. Replaced meter.

i 8h20 1-21-81 D/ PIA-102Y High Alarm vill not Replaced meter.

I reset.

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