ML20052G441

Monthly Operating Rept for Apr 1982

ML20052G441
Person / Time
Site:	Fort Calhoun
Issue date:	05/07/1982
From:	Short R OMAHA PUBLIC POWER DISTRICT
To:
Shared Package
ML20052G436	List: ML20052G435 ML20052G441
References
NUDOCS 8205180361
Download: ML20052G441 (8)

Text

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AVER AGE DAILY UNIT POWER LEVEL 50-285 DOCKET NO.

Fort Calhoun Station UNIT May 7, 1982 DATE R. W. Short COMPLETED BY (402)S36-4543 TELEPHONE April, 1982 MONW DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 485.5 484.3 37 2

316.3 484.0 18 225.5 484.2 3

39 4

470.2 484.6 20 482.2 484.9 5

21 6

484.2 485.0 22 485.4 404*O 7

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485.6 484.1 24 i

9 485.9 463.4 25 485.7 483.1 10 26 11 485.0 482.9 27 484.9 483.6 12 28 484.6 483.1 13 29 i4 484.1 483.0 3o 15 483.7 3,

16 483.8 INSTRUCTIONS On this format. list the average daily unit power levelin MWe Net for each day in the reporting inonth. Connpute to the nearest whole megawatt.

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OPERATING DATA REPORT 7

DOCKET NO.

50-285 DATE May 7. 1982 COSIPLETED BY R. W. Sjlort TELEPHONE (402)S36-4543 OPERATING STATUS

1. Unit Name:

Fort Calhoun Station Unit No.1 Notes

2. Reporting Period:

April, 1982

3. Licensed Thermal Power (N!Wt):

1500

4. Nameplate Rating (Gross alwe):

501 478

5. Design Electrical Rating (Net MWe):

501

6. Maximum Dependable Capacity (Gross MWe):

470

7. Maximum Dependable Capacity (Net MWe):

8. If Changes Occur in Capacity Ra:ings (Items Num:ur 3 Through 7) Since Last Report. Give Reasons:

None

9. Power Level To Which Restricted,If Any(Net MWe):

N/A

10. Reasons For Restrictions.lf Any:

'N/A 1

This Month Yr..to Date Cumulative

' 11. Hours in Reporting Period 719.0 2,879.0 75,360.0

12. Number Of Hours Reactor Was Critical 706.4 2,812.9 59,051.9

13. Reactor Reserve Shutdown Hours 0.0 0.0 1,309;5

14. Hours Generator On-Line 702.8 2,803.8 57,893.8

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWH) 1.041,907.5 4,103,593.0 70,805,423.1 17 Gross Electrical Energy Generated (MWH) 354,00_8.L.

1,395,159.9 23,469,105.5

18. Net Electrical Energy Generated (MWH) 337,620.6 1,330,583.8 22,178,452.3

19. Unit Service Factor 97.7 97.4 76.8

20. Unit Availability Factor 97.7 97.4 76.8

21. Unit Capacity Factor (Using MDC Neti 98.2 96.7 64.1 l

22. Unit Capacity Factor (Using DER Net) 98.2 96.7 63.8

23. Unit Forced Outage Rate 2.3 2.6 3.9

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:

26. Units in Test Status ! Prior to Commercial Operationi: None Forecast Achieved j

INITIA L CRIIICALITY INITIA L ELECTRICITY COMM ERCIAL OPER ATION (9/77) l.; -

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s 50-285 DOCKET NO.

UNIT SilUTDOWNS AND POWER REDUCTIONS Fort Calhoun Station l;

UNIT NAME DATE Mav 7-1QR2 COMPLETED BY R.'W Short REPORT MONTil April, 1982 i

TELEPl!ONE (402)S36-4543 l

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Cause & Corrective No.

Date g

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Report c

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Prevent Recurrence H

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!I 82-03 820402 F

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3 N/A EA ZZZZZZ Generator tripped due to a transient l i' on 345 KV power line.

Probable cause was high winds from stormy

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weather. The District is continuing to investigate the event to deter-l[l mine if any corrective actions can prevent the incident from rccurring.

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4 F: Forced Reason:

Method:

Exhibit G -Instructions

.J S: Scheduled A Equipment Failure (Explain) 1 Manual for Preparation of Data

'l B-Maintenance of Test 2 Manual Scram.

Entry Sheets for Licensee

j C-Refueling 3 Automatic Scram-Event Report (LER) Fde (NUREG-t D-Regulatory Restriction 4-Other ( Explain) 0161)

'4 E-Operator Training & License Examination F Administrative 5

G-Operational Error (Explain)

Exhibit I - Same Source

f (9/77)

Il Other (Explain) i I r'a

Refueling Information Fort Calhoun - Unit No. 1 Peport for the month ending April 1982 1.

Scheduled date for next refueling shutdcran.

January 7, 1983 2.

Scheduled date for restart following refueling.

April 1, 1983 3.

Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?

Yes a.

If answer is yes, what, in general, will these be?

A Technical Specification Change b.

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

c.

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

4.

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

October 1, 1982 5.

Irmortant licensing considerations associated with refueling, e.g., nea or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, nea operating procedures.

6.

The number of fuel assemblies: a) in the core 133 assemblies b) in the spent fuel pool 237 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 assuning the present licensed capacity.

1985 Prepared by Date May 3, 1982 v

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b ps OMAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No. 1 April, 1982 i

Monthly Operations Report I.

OPERATIONS SUIS!ARY Fort Calhoun Station operated at a nominal 100% power for the month of April. One forced outage occurred on April 2, 1982 at approximately 1600. The unit was returned to service at approxi-mately 0800 on April 3, 1982.

The cause of the forced outage invol-ved protective relaying on the main transformer.

Two new employees reported to the operations department during April and are currently participating in the training program at Fort Calhoun Station.

The Institute of Nuclear Power Operations conducted their second evaluation and assistance audit at Fort Calhoun Station.

The audit was two weeks in length and involved all major areas of interest at Fort Calhoun Station.

Normal surveillance tests and operational tests were completed.

No safety valve or PORV challenges occurred.

A.

PERFORMANCE CHARACTERISTICS LER #taber Deficiency LER-006 On March 23, 1982 at approximately 0930, HCV-506A failed to close via the control room switch.

This was observed during the performance of surveillance test ST-ISI-WD-1, F.1.

Upon discovery, air was immediately isolated from the valve allowing it to fail closed.

Energency Procedure EP-25, " Loss of Containment Integrity" was initiated and carried out.

During the incident, the redundant isolation valve, HCV-506B, remained operable and did close via control switch demand.

LER-007 During the performance of the monthly test (ST-EGF-6) of diesel generator #2, while the plant was at approximately 93% power, a leak was discovered in the copper tubing vent line from the thermal mixing valve to the coolant expansion tank. Diesel genera-tor #2 was shutdown for repairs in accordance with Tech. Spec. 2.7(2)i. During this time,- diesel gener-ator #1 and its associated safeguards equipment were operable.

In addition, both-offsite power supplies (161 KV and 3h5 KV) were available.

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4 Monthly Operations Report I

April, 1982 Page Two f

B.

CHANGES IN OPERATING METHODS NONE 4

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C.

RESULTS OF SURVEILLhNCE 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 Operation

. Incidents and are not reported elsewhere in the report:

Operation Incidents Deficiency OI-1526 ST-ISI-NG-1 HCV-260hA valve stroke time was not reviewed as required by the procedure.

0I-1530 ST-ISI-CC-3 Review of the surveillance test was not i

completed within the specified time limit.

i OI-1529 ST-FW-3 A procedure step was skipped which resulted in both auxiliary feedvater pumps inadvertently starting. ~The con-i tainment isolation valves remained closed, preventing the flow of auxiliary feedwater.

L OI-1528 ST-ESF-1, During performance of ST-ESF-1, F.2, F.2 C/ PIA-102Y upper alarm contact would not reset.

OI-1475 ST-ESF-1, During performance of ST-ESF-1, F.h the F.h 86A/CIAS lockout relay failed to trip.

D.

CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMblSSION APPROVAL Procedure Description SP-FAUD-1 h-6-82 Fuel Assembly Uplift Condition Detection.

This procedure did not constitute an unreviewed safety question as defined by 10CFR50.59 since jl it only involved evaluating data from a surveil-lance test.

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Monthly Operations Report April, 1982 Page Three D.

CHANGES, TErTS AND EXPERIFE'ITS CARRIED OUT WITHOUT COMMISSION a

APPROVAL Procedure Description SP-FAUD-1 h-23-82 Fuel Ass'embly Uplift Condition Detection.

This procedure did not constitute an unreviewed safety question as defined by 10CFR50 59 since it only involved evaluating data from a surveil-lance test.

E.

RESULTS OF LEAK RATE TESTS NONE F.

CHANGES IN PLANT OPERATING STAFF NONE G.

TRAINING Licensed operator requalification training continued as scheduled.

P.T.S. has been included.

Initial auxiliary operator training was conducted for three new operators.

Fire brigade training and drills were conducted. Maintenance and Technical training was con-conducted as scheduled.

H.

CHANGES, TESTS AND EXPERIMENTS REQUIRIhG NUCLEAR REGULATORY COMMISSION AUTHORIZATION PURSUANT TO 10CFR50.59 NONE

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-Monthly Operations Report l

April, 1982 Page Four II.

MAI:ITENANCE (Significant Safety Related)

M. O. #

Date Description Corrective Action 13868 2 h-82 Area Monitor RM-05hA, Alarn setpoint Cleaned contacts.

coming in too early.

Ih363 3-24-82 DG-2 Governor needs repair.

Replaced governor.

Ih346 3-23-62 Sigma for SGLS initiation out of Reset trip setpoint performed tolerance on setpoint.

Surveillance Test.

lbh77 h-6-82 Sigma Meter C/ PIA-102Y, Upper alarm Replaced upper & lower alarm vill not clear.

units, 14355 3-29-82 DG-2 leak at flange by thermal mixing Installed new line.

valve.

lh3h0 3-22-82 RM-050 belt burnt up.

Replaced pump & belt.

1h368 4-5-82 Fire Pump FF-13 replace diesel cool-Complete.

ing water copper tubing.

14530 h-7-82 Replace DC3-1 Breaker.

Complete.

1hh10 h-2-82 HCV-2501 leak on RCS Loop 2.

Tightened packing.

14523 h-7-82 Component cooling Water Heat Replaced solenoid valves.

Exchange Valves HCV-402C & 402D vill not open.

14h50 h-2-82 CELM Rod #17 moves slowly during Completed ST-CEA-1, F.9 for withdrawal.

verification of Drop Time.

14633 h-19-82 Component Cooling Water Heat Repaired ASCO solenoid valve.

Exchanger Valve HCV h02D will not open.

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