ML20138J747

Monthly Operating Rept for Nov 1985

ML20138J747
Person / Time
Site:	Fort Calhoun
Issue date:	11/30/1985
From:	Andrews R, Matthews T OMAHA PUBLIC POWER DISTRICT
To:	Taylor J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
LIC-85-563, NUDOCS 8512170633
Download: ML20138J747 (8)

Text

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AVERAGE DAILY UNIT POWER LEVEL 50-285 DOCKET NO.

UNIT Fort Calhoun Station DATE December 11, 1985 COMPLETED BY T.P. Matthews TELEPHONE 402-536-4733 MONE November,1985 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net)

(MWe-Net) 0.0 17 0.n 2

0.0 18 0.0 3

0.0 39 0.0 4

0.0 20 0.0 5

0.0 21 0.0 6

0.0 22 0.0 7

0.0 23 0.0 0.0 8

24 0.0 0.0 9

0.n 25 go 0.0 0.0 26 11 0.0 27 0.0 12 0.0 28 0.0 13 0.0 0.0 29 14 0.0 30 0.0 15 0.0 31 n.n 16 0.0 INSTRUCTIONS On this format. list the average daily unit power levelin MWe Net for each day in the reporting month. Compute o the nearest whole rnegawatt.

(9/77) 8512170633 851130 PDR ADOCK 05000285 R

PDR ZE *2$,l g

50-285 UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKETNO. Fort Calhoun Station UNIT NAME DATE December 11. 1985 COMPLETED BY T.P. Matthews REPORT MONTH November.1985 TELEPHONE 402-536-4733 e.

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.Y 3 Licensee E-r, je, Cause & Corrective

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.5 g 5 Event g?

No.

Date g

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Action to f5 5

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~ ji =e Report e mU Prevent Recurrence u;

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6 85-01 850928 s

1526.2 C

1 N/A XX XXXXX 1985 refueling outage commenced September 18, 2985 i

2 3

4 F: Forced Reason:

Method:

Exhibit G-Instructions S: Scheduled A Equiprnent Failure (Explain) 1 Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram.

Entry Sheets for Licensee C Refueling 3-Automatic Scram.

Esent Report (LER) File (NUREG.

D-Regulatory Restriction 4 Other (Explain) 0161)

E Operator Training & License Examination F-Administratise 5

G-Operational Error (Explain)

Exhibit ! Same Source 19/77)

Il-Other i Explain)

OPERATING DATA REPORT DOCKET NO. 50-285 DATE December 11, 1985 COMPLETED BY T. P. Matthews TELEPilONE 402-536-4733 OPERATING STATUS

1. Unit Name:

Fort Calhoun Station Notes

2. Reporting Period: November, 1985

3. Licensed Thermal Power (MWt):

1500 502

4. Nameplate Rating (Gross MWe):

5. Design Electrical Rating (Net MWe):

6. Maximum Dependable Capacity (Gross MWe):

c;n?

7. Maximum Dependable Capacity (Net MWe):

47A

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 MWe):

M/a

10. Reasons For Restrictions,if Any:

Nnne This Month Yr. to-Date Cumulative

11. Ilours In Reporting Period 79n n A n1A n inA,gn?_n

12. Number Of liours Reactor Was Critical 0.0 6.466.1 R1.7a6 t

13. Reactor Reserve Shutdown flours 0.0 0.0 1 ano.R-

14. Ifours Generator On.!.ine 0.0 6,455.5 81,122.9

~

15. Unit Reserve Shutdown liours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MW11)

O.0 9,564.277.6 103.751.n44.6

17. Gross Electrical Energy Generated (MWil) 0.0

_.J.,214.944.0 33.984.569.0

18. Net Electrical Energy Generated (MWii) 0.0 3,066,256.1 32,477.893.4

19. Unit Service Factor 0.0 80.5 76.0

20. Unit Availability Factor 0.0 80.5 76.0

21. Unit Capacity Factor (Using MDC Net) 0.0 80.0 66.0

22. Unit Capacity Factor (Using DER Net) 0.0 80.0 63.9

23. Unit Forced Outage Rate 0.0 0.0 3.5

24. Shutdowns Scheduled Over Next 6 Months (Type, Date.and Duration of Eacht:

The 1985 Refueling Shutdown commenced September 28, 1985 with startup tentatively scheduled for December 1985.

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

De cem.bm. 29, 1935

26. Units in Test Status (Prior to Commercial Operationi:

Forecast Achieved INITIA L CRITICA LITY INITIA L ELECTRICITY

~

COMMERCI AL OPER ATION N/A (9/77)

t Refueling Information Fcrt Calhoun - Unit No.1 Report for the month ending Noveber 1985 1.

Scheduled date for next refueling shutdown.

October 1985 2.

Scheduled date for restart following refueling.

D'cember 1985 3.

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

Yes a.

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

Te&nical Specification change submitted September 3,1985.

b.

If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Cocmittee 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 Submitted action and support infontation.

September 3,1985 5.

Inportant licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis nethods, significant changes in fuel design, new operating procedures.

Submitted and approved.

6.

The number of fuel assemblies: a) in the core 133 assemblies b) in the spent fuel pool 305 c) spent fuel pool storage capacity 729 d) planned spent fuel pool May be increased storage capacity via fuel pin consolidation 7.

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

1996 Prepared by M

Date December 2,1985 V

//

OMAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No.1 November, 1985 Monthly Operations Report

'I.

OPERATIONS

SUMMARY

The Fort Calhoun Station continued with its ninth refueling and maintenance outage through November,1985.

The jobs completed during November are as follows: The reactor core was refueled.

Part length poison rods were included for the first time in the reload to shield the vessel belt line eelds. Strain measurements of the control element assemblies (CEA's) sMwed deformation at the rod tips nearest the neutron flux.

Ten replace-ment CEA's were used for those most severely strained.

Eddy current tests resulted in 16 tubes in Steam Generator RC-2A and 17 tubes in Steam Generator RC-2B being plugged. The steam generators were also sludge lanced and had a secondary side inspection.

The 233 HFA relays have been replaced and tested. Thirty-one SBM switches have been replaced and tested. The 77 containment penetration subassemblies and 4 spares have been installed and tested. The modification to the main generator field to eliminate copper dusting is finished and the rotor has been installed.

The condenser was partially eddy current tested, inspected and three tubes were pulled for examination.

Some of the high pressure feedwater heaters were eddy current tested with favorable results. The new low pressure heater installation is essentially complete.

The new HCV-335 has been installed.

The status of major jobs in progress is as follows:

Seven of.the eight Engineered Safety Feature (ESF) tests are done.

The delta-T power modi-fication supplying separate temperature channels is 45% complete. The battery charger and inverter replacement is 35% complete.

The changeover of points from the P-250 to the ERF computer is wired but not tested.

The 4160/480V transformer replacement has started with equipment receipt and testing.

During November Shift Technical Advisor training started with six students.

NRC SR0 upgrade exams were given to four candidates.

Licensed operator requal examinations are in progress; NRC requal exams were administered to eight licensed operators.

No safety valve or PORV challenges or failures occurred.

A.

PERFORMANCE CHARACTERISTICS None t

B.

CHANGES IN OPERATING METHODS None C.

RESULTS OF SURVEILLANCE TESTS AND INSPECTIONS None

Monthly Operations Report November, 1985 Page Two D.

CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL Procedure Description SP-ECT-1 Eddy Current Testing of Heat Exchanger Tubes (FW-1B).

This procedure did not constitute an unreviewed safety question as defined by 10CFR50.59 since this is a test of heat exchangers in the secondary system only.

System Acceptance Committee Packages for November,1985:

Package Description / Analysis EEAR FC-82-ll4 Seismic Restraints for Containment Pressurization Piping.

This modification provided for the installation of seismic restraints on the containment pressuri-zation piping. This modification does not have an adverse effect on the safety analysis.

EEAR FC-83-70 Clamping Devices for Charcoal Filter Trays.

This modification provided for the installation of new clamps on charcoal filters in VA-66 and VA-26A&B.

This modification does not have an adverse effect on the safety analysis.

EEAR FC-83-153 Removal of ATCOR Cart and Rails.

This modification provided for the removal of the ATCOR drum capper, cart and rails.

This modification does not have an adverse effect on the safety analysis.

EEAR FC-84-174 Fuel Oil Transfer Discharge Filter Changeout.

This modification provided for new fuel oil filters for the Station's diesel generators.

The old filters were intermittently plugging and were no longer available from the manu-facturer.

This modification does not have an adverse effect on the safety analysis.

Monthly Operations Report November,1985

-Page Three D.

CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL (Continued)

System Acceptance Coninittee Packages for November,1985:

(Continued)

Package Description / Analysis EEAR FC-84-187 Demineralized Water Piping Rerouting.

This modification provided for the movement of some demineralized water pipes so that feedwater heaters could be removed / installed under modifi-cation EEAR FC-83-90.

This modification does not have an adverse effect on the safety analysis.

E.

RESULTS OF LEAK RATE TESTS Refueling leak testing is in progress.

Total leakage will be reported l

after testing is completed.

F.

CHANGES IN PLANT OPERATING STAFF None G.

TRAINING During November, Shift Technical Advisor training started with six students.- NRC SR0 upgrade examinations were given to four candidates.

Licensed operator requalification examinations are in progress; NRC requalification examinations were administered to eight licensed operators.

H.

CHANGES, TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY COMMISSION AUTHORIZATION PURSUANT'T0 10CFR50.59 None 2

II. MAINTENANCE (Significant Safety Related)

A report of all significant safety related maintenance performed during the 1985 refueling outage will be submitted at the conclusion of the outage.

$/ A lh W. Gary Gates Manager Fort Calhoun Station 7

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Omaha Public Power District 1623 Hamry amaru wtnashi 68102 2247 402 SJE 4000 December 13, 1985 LIC-85-563 Mr. James M.

Taylor, Director Office of Inspection and Enforcement U.S.

Nuclear Regulatory Commission Washington, D.C.

20555

Reference:

Docket No. 50-285

Dear Mr. Taylor:

November Monthly Operating Report Please find enclosed ten (10) copies of the November, 1985 Monthly Operating Report for the Fort Calhoun Station Unit No.

1.

Sincerely, Q [ '}v-ev r<~ [rv R.

L. Andrews Division Manager Nuclear Production RLA/TPM/me Enclosures cc: NRC Regional Office Office of Management & Program Analysis (2)

Mr.

R.

R. Mills - Ce-bustion Engineering Mr.

R. J. Simon - Westinghouse Nuclear Safety Analysis Center INPO Records Center American Nuclear Insurers NRC File

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