ML20079E291

Monthly Operating Rept for Dec 1983

ML20079E291
Person / Time
Site:	Fort Calhoun
Issue date:	12/31/1983
From:	William Jones, Munderloh D OMAHA PUBLIC POWER DISTRICT
To:	Deyoung R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
LIC-84-016, LIC-84-16, NUDOCS 8401170226
Download: ML20079E291 (11)

Text

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-285 UNIT Fort Calhoun Statior-DATE January 13, 1984 COMPLETED BY D. J. f1underloh TELEPHONE 402-536-4001 MONTH December, 1983 8)AY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe Net)

(51We-Net) 458.2 17 457.0 2

456.8 is 456.8 3

456.3 i9 456.9 4

456.7 20 456 9 456.5 5

21 457.0 6-456.3 22 457.1 455.9 7

23 457.1 455.7 457.3 g

24 9

455.8 25 456.6 to 455.9 26 457.2 455.7 gi 27 457.1 456.1 12 28 457.3 455.8 13 29 456.8 g4 455.4 30 456.7 15 454.9 3

456.5 16 456.6 INSTRUCTIONS On this format. list the average daily unit power leselin 51We Net for each day in the reportmg month. Coinpute to the nearest whole megawatt.

(9/77 )

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36k a

OPERATING DATA REPORT DOCKET NO. _50-285 DATE January 13, 1984 COMPLETED BY D. J..'1underloh TELEPilONE -402-536-4001 OPERATING STATUS

1. Unit Name:

Fort Calhoun Station Note $

2. Reporting Period:

December, 1983

3. Licensed Thermal Power (MW ):

1500 501

4. Nameplate Rating (Gross MWe):

478

5. Design Electrical Rating (Net MWe):

401

6. Maximum Dependable Capacity (Gross MWe):

438

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 Any (Net MWel:

N/A

10. Reasons For Restrictions.lf Any:

None This Month Yr.-to Date Cumulative

11. Hours in Reporting Period 744.0 8,761.0 90.002.0

12. Number Of Hours Reactor Was Critical 74a.0 6.503.9 69.893A

13. Reactor Reserte Shutdown llours 0.0 0.0 1,309.5

14. Hours Generator On-Line 744.0 6,405.0 69.402.5

15. Unit Reserse Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWH) 1,108,677.3 9,143,165.3 86,759,713.7

17. Gross Electrical Energy Gerscrated (MWH) 356,570.0 2,894,090.0

_28,317,569.7 339,67 2.5 2,749,833.5 27,079,867.9

18. Net Electrical Energy Generated (MWH)

19. Unit Service Factor 100.0 73.1 77.1

20. Un;t Asailability Factor 100.0 73.1 77.1

21. Unit Capacity Factor (Using MDC Net) 104.2 71.7 65.6 95.5 65.7 63.3 l

22. Unit Capacity Factor (Using DER Net) l'. U 0.8 3.6

23. Unit Forced Outage Rate

24. Shutdowns Scheduled Oser Nest 6 Months (Type. Date.and Duration of Each):

l 1984 refueling outage scheduled to start around flarch 3.1984

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

N/A

26. Units in Test Status IPrior Io Commeicial Operation):

Forecast Achiesed INITIAL CRITICALITY INITIA L ELECTRICITY COMMERCIAL OPER ATION l

('l/77 )

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-285 UNIT N AME Fort Calhoun Station DATE January 13. 1984 REPORT MONTH December, 1983 COMPLETED BY D. J Munderloh TELEPHONE an?_civ_ anni e.

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C rB 3 to 4 6"

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E 2ES LI" 5" 5 .

c.

Cause & Corrective

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83 Action to No.

Date g

3g g

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Event u?

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j;5g Reporie rE 0 Prevent Recurrence c5 No unit shutdowns during the month of December,1983.

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3 4

F: Forced Reason:

Method:

Exhibit G -Inst ructions S: Seneduled A-Equipment Failure (Explain) 1 Manual for Preparation of Data B-Maintenance of Test 2-Manual Scram.

Entry Sheets for Licensee C Refueling

% Automatic Scram.

Event Report (LER) File (NUREG-D-Regulatory Restriction 4-Other ( Explain)

Ololl E-Operator Training & License Examination F-Administrative 5

G-Operational Error (Explain)

Eshibit 1 - Same Source el/77)

Il-Other (E splain)

e Refueling Infonnation Fort Calhoun - Unit No. 1 Report for the nonth ending December 1983 1.

Scheduled date for next refueling shutdown.

March 1984 2.

Scheduled date for restart following refueling.

May 1984 3.

Will refueling or resumpti >n of operation thereafter require a technical specification change or other licence amendment?

Yes a.

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

A Technical Specification Change b.

If answer is no, has the reload l'uel design and core configuration been reviewed by your Plant Safety Review Conmittee to deter-mine whether any unreviewed safety questions are associated with the core reload, c.

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

4.

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

Tech. Specs. - February 1984 5.

Important licensing _ considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or perfo m ce analysis methods, significant changes in fuel design, new operating procedures.

6.

The' number of fuel assenblies: a) in the core m

assemblies b) in the spent fuel pool 265 c) spent fuel pool storage capacity 483 d) planned spent fuel pool storage capacity 728

7. ' The projected date of the last refueling that can be discharged to the spent fuel pool assu: ring the present licensed capacity.

1985 Prepared by M

Date January 1, 1984 Q.

Il

OMAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No.1 December, 1983 Monthly Operations Report I.

OPERATIONS SUt&tARY Fort Calhoun Station operated at a nominal 100%. power throughout the month of December, 1983.

Fort Calhoun Station participated in the annual emergency exercise. The exercise involved full participation of the states and the NRC.

The areas of fire protection, radwaste transportation and design changes were audited by the Regional office of the NRC. The annual SALP review was conducted and a public meeting was held during December.

The spent fuel pool rerack continues.

Outage preparations continue for the 1984 refueling outage.

No safety valve or PORY challenges occurred.

A.

PERFORffANCE CHARACTERISTICS

--.R Uumber Deficiency LE 83-008 Rev.1 While at approximately 100% power and during the perfcrmance of monthly surveillance test 3T-ESF-6, Section F.2, " Diesel Generator Check", diesel generator DG-2 started and was run up to operating speed. However, the generator field failed to flash and the control room had no indication that the diesel was running (that is, the diesel intake air dampers did not open, the diesel stop light did not go out, and the control room diesel tachometer had no RPM indication).

Subsequently, diesel generator DG-2 was shutdown and the redundant diesel generator DG-1 was satisfactorily started to verify operability. The 161 KV and 345 rsV supplies l

were also available throughout the incident.

Revision 1 involvad a change to Attachment 2, Corrective Action only.83-010 During the perfonnance of surveillance test, ST-ESF-5, i

Section F.1 (the monthly AC sequencer timer test),

timer SI-1A (corresponding to the low pressure safety injection pump) on sequencer SI-2 failed to time out within the prescribed limit.

During the time of the failure, the DC sequencer circuitry which activates SI-1A as well as the AC and DC sequencer circuitry actuating the redundant low pressure safety injection punp (SI-18) was operable.

. Monthly Operations Report December, 1983 Page Two A.

PERFORf1AtlCE CHARACTERISTICS (Continued)

LER fiumber Deficiency S3-011 ilhile operating at approximately 100% power and during perfonnance of annual surveillance test ST-Efe-6, F.5, " Diesel Generator Inspection",

diesei generator DG-1 failed to field flash.

Diesel generator DG-2 had been proven operable at the start of the surveillance-test, ST-ESF-6, F.5.

The 161 KY and 345 KV supplies were available throughout the incident.

B.

CHAtlGES Ii1 OPERATItJG METHODS flone C.

RESULTS OF SURVEILLANCE TESTS NID IllSPECTIONS Operaticn Incident Deficiency 01-1786 ST-ESF-14, F.2 ST-ESF-14, Section F.2 was not perforned within the specified time frame.

01-1787 ST-FP-9, F.1 During the perforaance of ST-FP-9, Section F.1, it was noticed that a bolt was missing froa 4160 volt breaker SI-1A.

01-1791 ST-ESF-3, F.2 During the performance of ST-ESF-3, Section F.2, it was found that pressure switches were out of tolerance.

CHN1GES, TESTS AND EXPERIf1ENTS CARRIED OUT WITHOUT COMlilSSION APPROVAL D.

Procedure Description SP-FAUD-1 Fuel Assembly Uplift Condition Detection.

This procedure did not constitute an unreviewed safety question as defined by 10CFR50.59 since it only involved the evaluation of data from a survnillance I

test to verify that a fuel assembly uplift condition did not exist.

l 4

. Monthly Op3r.ations Report

.]

December 1983 Page Three D.

CHANGES, TEST AND EXPERIMEllTS CARRIED OUT WITHOUT C0flMISSION APPROVAL (Continued)

Procedure Description SP-VA-80 Hydrogen Purge System Test.

This procedure is a quarterly test to verify the operability of the Hydrogen Purge System fans, valves and filters.

It does not constitute an unreviewed safety question as defined by 10CFR50.59 since it does not adversely affect containment integrity; remote valve operation capability is maintained for one fan at all times; no Technical Specification basis is affected; and the system has no automatic emergency functions which are bypassed.

System Acceptance Committee Packages for December, 1983:

Package Description / Analysis EEAR FC-83-53 Concentrate Line Improvements.

This modification provided the installation of unions in the concentrate line from the drumming station to the concentrate tanks providing poir.ts of access to open tha line for cleaning.

This modification has no adverse effect on the safety analysis.

EEAR FC-81-135 QA Records Vault (QA Office).

This modification provided the installation of an insulated false wall and suspended ceiling.

This modification does not effect safety related equipment, therefore, it has no adversa effect on the safety analysis.

DCR 73-22 HI-LO Level Alarm on SIRWT.

This modification increased the level nf safety due to the fact that the level of the SIRWT is now more easily monitored. This modification has no adverse effect on the safety analysis.

DCR 76-61 Waste Evaporator Concentrate Cooler.

This modification provided the installation of a This bypass around the concentrate cooler.

modification has no adverse effect on the safety analysis.

7_

-.w-.

a Monthly Op gtfons Report

• Page Four December,1983 Package Description / Analysis DCR 77-89 Change Out Valve Design on Steam Seal System.

This modification replaced a steam valve with a valve that would not erode. This modification did not affect safety related equipment, therefore, it has no adverse effect on the safety analysis.

EEAR FC-79-11 PORY Low Pressure Operation Failure Mode.

This modification eliminates the possibility of a LOCA caused by the opening of the PORV's due to a loss of power to the pressure recorders.

This modification has no adverse effect on the safety analysis.

DCR 77-76 Electrical Penetration Leak Test Connection.

This modification only moved the Icak test gauges outside the penetration covers.

This modification has no adverse effecton the safety analysis.

DCR 74A-18 Automatic ilydrazine Analyzer.

This modification added an automatic analyzer for hydrazine off of the discharge of flo. 6 heater and improves the chemistry monitoring for the steam generators. This modification did not affect safety related equipment, therefore, it has no adverse effect on the safety analysis.

DCR 75A-58 Tertiary Treatment Plant (Sewage Lagoons).

This modification installed the tertiary treatment plant which is not safety related.

This nedification has no adverse effect on the safety analysis.

EEAR FC-80-125 Control of Gas Leaks from WD-32.

This modification is only an extension of WD-32 and does not involve a safety related system or component. This modification has no adverse effect on the safety analysis.

EN

ilonthly Operations Report

• December, 1983 Page Five Package Description / Analysis EEAR FC-81-126 Warehouse Gas Cylinder Dock.

This modification to the warehouse gas cylinder dock does not involve a safety related system or component. This modification has no adverse effect on the safety analysis.

DCR 78-35 tJoise Spikes on RPS.

This modification increased the reliability of the reactor protective system. This modification has no adverse effect on the safety analysis.

EEAR FC-83-12 Conversion of Turbine to Full Arc Admission.

This modification to the turbine was made for ease of operation only. This modification did not affect safety related equipment, therefore, it has no adverse effect on the safety analysis.

DCR 74A-4D Process Radiaticn lionitor Rft-055A.

This modification installed a second overboard discharge monitor, Ril-055A, a redundant monitor.

This modification has no adverse effect on the safety analysis.

DCR 74A-4G Process Radiation lionitor PJi-059.

This modification replaced a process radiation monitor that had failed due to overheating with a better one and relocated it away from the evapo rator. This modification has no adverse effect on the safety analysis.

e EEAR FC-79-36 Drain Line for Suction Piping to Feedwater Pumps.

This modification is to put drain lines on the suction headers to the feedwater pumps FW-4A, 4B and 4C. This is not a safety related section of piping. This modification has no adverse effect on the safety analysis.

E.

RESULTS OF LEAX RATE TESTS There are no new leak rate results to report.

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tionthly Operations Report December, 1983 Page Six F.

CHANGES IN PLA!!T OPERATING STAFF Effective December 15, 1983, Mr., lames J. Fisicaro transferred to the Licensing Department. Mr. Michael E. Kallman, formerly a Shift Technical Advisor, replaced Mr. Fisicaro as Supervisor-Administrative Services and Security.

G.

TRAINING Training for December was conducted as scheduled in the areas of operator requalification (licensed and non-licensed operators), fire brigade, maintenance, crane operator, emergency plan and general employee training.

Seven NRC licensed candidates participated in the Commission examination.

II.

CHitNGES, TESTS AND EXPERIMENTS REQUIRING f.UCLEAR REGULATORY COMt11SSION AUTHORIZATIO!1 PURSUANT TO 10CFR50.59 None II. MAINTEtlAtlCE (Significant Safety Related)

None y j.

E/EN!

W. Gary Gates Manager Fort Calhoun Station

~

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Omaha Public Power District 1623 Harney Omaha, Nebraska 68102 402/536 4000 January 13, 1984 LIC-84-016 l

Mr. Richard C.

DeYoung, Director Office of Inspection & Enforcement U.

S.

Nuclear Regulatory Commission Washington, D.C.

20555

Reference:

Docket No. 50-285

Dear Mr. DeYoung:

Monthly Operating Report December, 1983 Please find enclosed ten (10) copies of the December Monthly Operating Report for the Fort Calhoun Station Unit No.

1.

Sinc,e ely, 1

{Ir i)

W.

C. Jones Divis1.5n Manager Produbbion Oper&tions WCJ/DJM:jmm Enclosures cc:

NRC Regiorial Office Office of Management & Program Analysis (2)

Mr.

R.

R.

Mills - Combustion Engineering Mr.

T.

F.

Polk - Westinghouse Nuclear Safety Analysic Center INPO Records Center NRC File 9 574 f

45 5124 Employment with Equal Opportunity MalC/remaie

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