ML20083C336

Monthly Operating Rept for Nov 1983

ML20083C336
Person / Time
Site:	Fort Calhoun
Issue date:	11/30/1983
From:	William Jones, Matthews T OMAHA PUBLIC POWER DISTRICT
To:	Deyoung R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
LIC-83-316, NUDOCS 8312230066
Download: ML20083C336 (10)

Text

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AVERAGE DAILY UNIT POWER LEVEL DOCKE1 NO. 50-285 UNIT Fort Calhoun Statio DATE December 15, 1983 COMPLETED ilY T. P. flatthews lELEPHONE 402-536-4733 MON 1y llovember, 1983 DAY AVER AGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe-Net) iMWe Neu 434.6 i7 457.2 3 430.8 18 457.5 3 440.9 39 457.5 4 455.3 20 457.6 5 456.8 21 458.1 6 457.3 22 458.4 7 457.1 23 458.5 g 456.8 24 459.0

, 457.4 25 459.1 in 457.7 26 459.3 454.4 27 459.0 12 251.4 g 458.8 33 249.5 29 458.4 34 326.5 3o 458.4 15 449 9 31

i. 455.6 INS 1RUC11CNS On this format. list the average oaily unit power levelin MWe-Net for each day in the irporting month. Compute to the nearest whole megawatt.

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8312230066 831130 PDR ADOCK 05000285 R PDR L_ .%. -

OPERATING DA TA REPORT DOCKET NO. 50-285 DATE December 15, 1983 COMPLETED HY T. P. Fatthews TELEPilONE 402-536-4733 Oe'ERATING STATUS

1. Unit Name: Fort Calhoun Station Notes

2. Reporting Period: fiovember, 1983

3. Licensed Thermal Power (MWt): 1500

4. Nameplate Rating (Gross MWe): 501

5. Design Electrical Rating (Net MWe): 470

6. Maximum Dependable Capacity (Gross MWe): 4

7. Masimum Dependable Capacity (Net MWe):

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

II/A

9. Power Level To which Restricted lf Any (Net MWe): N/A

10. Reasons For Restrictions,if Any: None This Month Yreto Date Cumulatise

11. Hours In Reporting Period 720.0 .

8,017.0 89.258.0

12. Number Of Houn Reacto Was C.itical 720.0 5,759.9 69,149.9

13. Reactor Resene Shutdown flour, 0.0 0.0 1t309.5

14. Hours Generator On.Line 720.0 5,661.0 68.658'.5

15. Unit Rewne Shutdown Houn 0.0 0.0 0.0

16. Gross lhermal Energy Generated (MWH, 1,029.985.8 8.034.488.0 85.651.036.4 17 Gross Electrical Energy Generated (MWH) 330,466.0 2,537,520.0 314,60CI- 27.960.9992 7_

18. Net Electrical Energy Generated (MWH) 2,410,161.0 26,740,195.4

19. Unit Senice Facto, 100.0 70.6 76.9

20. Unit Agailabil tv Factor 100.0 70.6 76.9

21. Unit Capacity Factor (Using MDC Neil 99.8 68.6 65.3

22. Unit Capacity Factor (Using DER Net) 91.4 62.9 63.0

23. Unit Forced Outage Rate 0.0 0.8 3.6 2 4. Shutdowns Scheduled Oser Nest 6 Months (Type, Date.and Duration of Each L 1984 refuelin9 outage scheduled to start around March 3.1984.

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

26. Units in Test Status lPrior to Commercial Operationi: None l'orecast Achiesed INITIA L CRITICA LITY INITIAL ELECTRICITY COMMERCI A L OPER A IlON rail?o

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DOCKET NO. 50-285 UNIT SHUTDOWNS AND POWER REDUCTIONS Fort Calhoun Station UNIT NAME DATE December 15. 1983 COMPLETED BY T- P_ Matthnwe REPORT MONTH November 1983 TELEPHONE 402-536-4733

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- jg 3 jY5 Licensee ,Eg je, Cause & Corrective

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3g 4 2ss Event 17 gy Action to gE 5 jg Report mV g' Prevent Recurrence d

No unit shutdowns during the 4

month of November, 1983.

i I 2 3 4 F. Forced Reason: Method: Exhibit G-Instructions S Scheduled A-Eqmpment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance of Test 2-Manual Scram. Entry Sheets for Licensee C-Refueling 3 Automatic Scram. Esent Report tLER) File (Nt1 REG-D-Regulatoi> Reueistion 4-Other (Esplain ) Gioli E Operator Training A License L samination F Adnunistratne 5 G-Operational Error (Esplain) Eshibit 1 - Same Source p8/77) Il-Othes ( E splain )

Refueling Infonnation Ebrt Calhoun - Unit No.1 Report for the nonth ending November 1983 .

l 1. Scheduled date for next refucling shutdown. March 1984

2. Scheduled date for restart following refueling. May 1984

3. Will refueling or restmption 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 answer 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 taken place, when is it scheduled?

4. Scheduled date(s) for submitting proposed licensing action and support infonnation. Tech. Specs. - February 1984

5. Inportant licensing 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.

6. The number of fuel assemblies: a) in the core 133 assemblies b) in the spent fuel pool 265 c) spent fuel pool storage capacity 483 d) planned spent fuel pool storage capacity 728

7. 'Ihe projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity. 1985 Prepared by __

el2,~fM Date December 1- 10W1 9 (/

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OttAHA PUBLIC POWER DTSTRICT Fort Calhoun Station Unit No.1 November, 1983 lionthly Operations Report I. OPERATIONS

SUMMARY

After completion of itTC testing at 95% power, Fort Calhoun Station returned to 100% power November 4,1983. Power was reduced to 60% on November 12 to repair condenser tube leaks. Operation at 100% power was resumed on November

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15, 1983.

During November, Fort Celhoun Station exceeded last year's record of over 200 days of continuous operation.

The NRC is onsite to give Senior Reactor Operator examinations to four engineers and two operators. Also, a Reactor Operator examination will be given to one operator.

The Spent Fuel Pool rerack continues.

No safety valve or PORY challenges occurred.

A. PERFORMANCE CHARACTERISTICS None B. CHANGES IN OPERATING ftETHODS None C. RESULTS OF SURVEILLANCE TESTS AND INSPECTIONS Operation Incident Deficiency 01-1759 ST-ESF-6, F.2 During the performance of ST-ESF-6, Diesel Generator No. 2 failed to show any indication of RPM's in the control room or locally, DG-2 field flashing contactor failed to seal in, the air dampers for DG-2 failed open and the l

diesel stop light did not go out.

01-1765 ST-ESF-6, F.2 During the performance of ST-ESF-6, Section F.2, Diesel Generator No. I tripped due to energizing of a reverse current protective relay during nonnal shutdown of the diesel.

l 01-1780 ST-PL-1, F.2 During the performance of ST-PL-1, Section F.2, it was found that the first and second l backup charging pump setpoints had drifted out of tolerance.

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Monthly Op; rations R: port November, 1983 Page Two D. CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL 1

i Procedure Description l

I SP-FAUD-1 Fuel Assembly Uplif t 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 surveillance test to verify that a fuel assembly uplift condition did not exist.

SP-AB-1 Hydrostatic Test of Water Side of the Auxiliary Boiler This procedure did not constitute an unreviewed safety question as defined by 10CFR50.59 since it involved work on non-safety related equipment.

SP-EHC-4 EHC Coolers Leak Test This procedure did not constitute an unreviewed safety question as defined by 10CFR50.59 since it involved work on non-safety related equipment.

System Acceptance Committee Packages for October,1983:

Package Description / Analysis DCR 76-85 FH-1 Bridge Trolley Permissive.

This nodification allows slight moveuent of the bridge and trolley over the core so that fuel bundles do not hang up on each other when inserting bundles. This modification has no adverse effect on the safety analysis.

DCR 76-27 Reactor Coolant Level Indication During Cold Shutdown.

This modification added a wide range reactor coolant level indicator which did away with the long tygon tube method. This modification has no adverse effect on the safety analysis.

l DCR 74A-107 Additional Demineralized Water Outlets. l l

This modification added additional demineralized l water outlets in the auxiliary building. This nodification has no adverse effect on the safety analysis.

Monthly Operaticns R; port November, 1983 Page Three Package Description / Analysis EEAR FC-79-59 Outlet for Jib Crane at Loading Dock.

This modification added a 480V outlet to the truck dock only. This did not involve any safety related equi pment. This modification has no adverse effect on the safety analysis.

DCR 77-64 Fort Calhoun Station Undervoltage Protection.

This modification resulted in improvenent in the undervoltage protection. This modification has no adverse effect on the safety analysis.

EEAR FC-80-136 Minor Electrical Modifications.

This modification consisted of adding minor power receptacles and lighting. This did not involve any safety related equipment. This modification has no adverse effect on the safety analysis.

EEAR FC-80-119 Emergency Lighting.

This modification added emergency lighting in the stairwells leading down to the maintenance shop.

This did not involve any safety related equipment.

This modification has no adverse effect on the safety analysis.

EEAR FC-83-112 Turbine Building Crane Catwalk.

This modification resulted in the installotion of a catwalk for the turbine building crane. This did not involve any safety related equipment. This modification has no adverse effect on the safety analysis.

EEAR FC-81-149 FW-8 Corrosion Phase II This nodification w1s done to install new seal water heat exchangers and separator tanks onto the condenser evacuation pumps FW-8A,B and C. This did not involve any safety related equipment. This modification has no adverse effect on the safety analysis.

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H:nthly Op2 rations Report November,1983 Page Four Package Description / Analysis EEAR FC-81-140 TAR Recorders 1, 2, 3 and 4 Replacement.

This modification ensures heat tracing points are read and recorded daily to avoid Technical Specification violations. This modification has no adverse effect the safety analysis.

EEAR FC-83-118 Discharge Line Off Chemical Lagoon Recirculation Pump.

This modification did not involve a safety related system. This modification has no adverse effect on the safety analysis.

DCR 77-83 Expansion of P-250 Computer Capabilities.

This modification added a second computer only.

This modification has no adverse effect on the safety analysis.

EEAR FC-80-132 Rework of Chemistry Lab Fume Hoods.

This modification did not involve a safety related systen. This modification has no adverse effect on the safety analysis.

DCR 758-24 Instrument Inverter Frequency Detection.

t This modification improved the safe operation of the clutch coils by keeping the instrument inverters in synchronization and not tripping them out spuriously. This modification has no adverse effect on the safety analysis.

DCR 74A-36 RPS Cable Rerouting.

This modification only changed the location of RPS cableing and did not effect the operation of the cableing. This modification has no adverse effect on the safety analysis.

EEAR FC-83-110 Modification to Upgrade QA Records File Room.

This modification upgraded the fire protection qualities cf the QA Records File Room. This modification has no adverse effect on the safety analysis.

Monthly Operations Report November, 1983 Page Five I

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

F. CHANCIS IN PLANT OPERATING STAFF None G. TRAINING Training for November was conducted as scheduled in the areas of operator requalification, non-licensed operators, fire brigade, maintenance and general employee training. Additional training was conducted for seven NRC licensed candidates who were examined the week of November 28 by the Commission.

H. CHANGES, TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY COMMISS10u AUTHORIZATION PURSUANT TO 10CFR50.59 None II. MAINTENANCE (Significant Safety Related)

H.O. No. DATE DESCRIPTION CORRECTIVE ACTION 22086 10/31/83 Pressurizer backup heaters Per PRC approved procedure.

bank No. 3 groups No. 9 will not energize.

21878 10/14/83 Loop flow for RC-2A loop Replaced transmiter, calibrated failed high. per CP-RPS-3.

&. [Q W. Gary Gates Manager Fort Calhoun Station

Omaha Public Power District 1623 Harney Omaha. Nebraska 68102 402/536-4000 December 15, 1983 LIC-83-316 Mr. Richard C. DeYoung, Director office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D.C. 20555

Reference:

Docket No. 50-285

Dear Mr. DeYoung:

Please find enclosed ten (10) copies of the November Monthly Operating Report for the Fort Calhoun Station Unit No. 1.

Sincerely, i \ 'n tV E g/cm W. C. /, ones Division Manager Production Operations WCJ/TPM:jmm Enclosures cc: NRC Regional Office Office of Management & Program Analysis (2)

Mr. R. R. Mills - Combustion Engineering Mr. T. F. Polk - Westinghouse Nuclear Safety Analysis Center INPO Records Center NRC File l

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45 5t24 Employment with Equal Opportunity t t Male! Female

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