ML20215G497

Monthly Operating Rept for Sept 1986

ML20215G497
Person / Time
Site:	Fort Calhoun
Issue date:	09/30/1986
From:	Andrews R, Matthews T OMAHA PUBLIC POWER DISTRICT
To:	Taylor J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
LIC-86-533, NUDOCS 8610200397
Download: ML20215G497 (9)

Text

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a.

t AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-285 Fort Calhoun Station UNIT DATE October 8, 1986 COMPLETED BY T. P. Matthews TELEPHONE 402-536-4733 4

September, 1986 MONTH DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWFR LEVEL (MWe-Net)

(MWe-Net) 475.6 17 481.3

~

i 475._3 18 481.1 2

479.6 475.9 19 3

480.2 476.4 20 4

475.3 21 480.1 5

476.3 479.8 6

22 4 7.9 479.3 7

23 479.6 480.0 8

24 9

25 482.0 479 4 481.3 479.1 26 to 480.8 478.3 27 is 478.5 12 28 477 7 478.4 13 474 3 29 479.R 30 481.3 14 480.3 15 3,

481.3 16 INSTRUCTIONS On this format. list the average daily unit power levelin MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.

(9/77 )

8610200397 860930 Q

DR ADOCK 0500 5

/ /

OPERATING DATA REPORT DOCKET NO. 50-285 DATE Octnber 8, 1986 COMPLETED BY T p-Matthews TELEPHONE 402-536-4733 OPERATING STATUS

1. Unit Name:

Fort Calhoun Station Notes

2. Reporting Period:

September, 1986

3. Licensed Thermal Power (MWt):

1600

4. Nameplate Rating (Gross MWe):

502

5. Design Electrical Rating (Net MWe): 478 502

6. Maximum Dependable Capacity (Gross MWe):

7. Maximum Dependable Capacity (Net MWe):

478

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

N/A

9. Power Level To Whii!h Restricted lf Any (Net MWe):

N/A

10. Reasons For Restrictions,If Any:

NONE This Month Yr to-Date Cumulative 720.0 6,551.0 114,097.0

11. Hours in Reporting Period 720.0 6,276.3 88,022.5

12. Number Of Hours Reactor Was Critical

13. Reactor Reserve Shutdown Hours 0.0 0.0 1,309.5

14. Ilours Generator On-Line 720.0 6,055.2_

87,178.1

15. Unit Resene Shutdown Hours 0.0 0.0 0.0 1,070,908.8 8.035,274.8 111,/86,319.4

16. Gross Thermal Energy Generated (MWH)

17. Gross Electrical Energy Generated (MWH) 361,342.0 2.669.753.2 36,654,322.2 344,904.2 2.541.092.8 35,018,986.2

18. Net Electrical Energy Generated (MWH) 100.0 92.4 76.4

19. Unit Sen' ice Factor

20. Unit Availability Factor 100.0 92.4 76.4

21. Unit Capacity Factor (Using MDC Net) 100.0 81.1 bb.b

22. Unit Capacity Factor (Using DER Net) 100.0 81.1 64.5 0.0 1.7 3.4

23. Unit Forced Outage Rate

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

NONE

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

N/A

26. Units In Test Status IPrior o Commercial Operation):

Forecast Achiesed N/A INITIA L CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPER ATION (0/77)

DOCKET NO.

50-285 UNIT SHUTDOWNS AND POWER REDUCTIONS Fort Calhoun Station UNIT NAME DATE October 8. 1986 COMPLETED BY T.

P Matthows REPORT MONTH September, 1986 402-636-4/33 TELEPHONE w.

E c

.5 g 3

.E Ii Licensee g t,

[a, Cause & Corrective No.

Date i

3g 2s5 Event g?

g3 Action to f=

5 3 gjj g Report

• mV O

Prevent Recurrence H

o a

u Q

There were no unit shutdowns or power reductions during the month of Septem-ber, 1986.

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2 3

4 w

F: Forced Reason:

Method:

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

Entry Sheets for Licensee C-Refueling 3-Automatic Scram.

Event Report (LER) File (NUREG-D-Regulatory Restriction 4-Other (Explain) 0161)

E-Operator Training & License Examination F-Administrative 5

G-Operational Error (Explain)

Exhibit I Same Source (9/77)

Il-Other (Explain)

' Refueling Information Fort Calhoun - Unit No. 1 1

Report for the month ending September. 1986 1.

Scheduled date for next refueling shutdown.

March. 1987 2.

Scheduled date for restart following refueling.

May. 1987

~3.

Will refueling or resump' tion of operation thereafter require a technical specification change or other license amendment?

Yes a.

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

Fuel supplier change from ENC to CE and possible Technical Specification change.

b.

If answer is no, has the reload fuel design-and core configuration been reviewed by your Plant Safety Review Committee 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 information.

February, 1987 5.

Important. 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.

New fuel supplier (Combustion Engineering) but the new fuel will be essentially the same as that supplied by Coubustion.

Engineering for Cycle 5.

6.

The number of fuel assemblies: a) in the core 133 assemblies b) in the spent fuel pool 349 c) spent fuel pool storage capacity 729 d) planned spent fuel pool May be increased storage capacity via fuel nin consolidation 7.

The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present j

licensed capacity.

1996 1

)

Prepared by M Date September 29. 1986 J

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0MAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No. 1 September, 1986 Monthly Operations Report I.

OPERATIONS

SUMMARY

Fort.Calhoun Station operated at 100% power throughout September,1986.

Condensate pump FW-2C overhaul is nearing completion.

Circulati.ng pump CW-IC had to be taken out of service twice for repacking due to worn shaft 2

keyways and bearing sleeve.

The security power transfer switch failed requiring use of the security diesel for a long period of time and has since been repaired.

Construction 4

has started on the security. building expansion. Three radioactive waste 7

concentrate liners were solidified and one was shipped off-site.

With the aid of Western Regional, Inc., the Technical department has

.recently completed a review of diesel generator reliability. Results and recommendations stemming from the approximately three-month research will be published shortly.

The new position of Supervisor-Outage Projects was filled to aid in the scheduling and planning of maintenance and refueling outages.

Training for Senior Operator's License candidates was initiated.

Maintenance training was conducted in areas such as vibration measurement, rigging, piping and protective coatings.

Requalification and refresher training continued for Operations and Chemical and Radiation Protection technicians. The last of the 10 required Self Evaluation Reports were submitted to INP0.

No safety valves or PORV challenges or failures occurred.

A.

PERFORMANCE CHARACTERISTICS None 4

B.

CHANGES IN OPERATING METHODS None C.

RESULTS OF SURVEILLANCE TESTS AND INSPECTIONS None 4

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Monthly Operations.Repcrt September, 1986 Page Two D.

CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL 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 surveillance test to verify that a fuel assembly uplift condition did not exist.

SP-VLPM-4 Core Barrel Motion.

This procedure.did not constitute an unreviewed safety question as defined by 10CFR50.59 because the procedure only provided for recording and analysis of excore detector outputs to determine the thermal shield integrity.

System Acceptance Committee Packages for September, 1986:

Packaae Descriotion/ Analysis DCR 76-054 Spent Fuel Pool Cross-Tie.

This modification provided for the installation of piping to furnish a method to cross connect the spent fuel pool to the shutdown cooling system.

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

EEAR FC-80-076 Containment Nuclear / Fire Emergency Alarms / Lights.

This modification provided for the addition of nuclear / fire emergency lights in containment and the auxiliary building. This modification does not have an adverse effect on the safety analysis.

EEAR FC-81-099 Instrumentation for the Detection of Inadequate Core Cooling.

This modification provided for the installation of the reactor vessel level instrumentation (HJTC's) and the QSPDS panels in the control room which provide the data links to the Safety Parameter Display System. This modification does not have an adverse effect on the safety analysis.

~...

2 Monthly.0perations Report September, 1986 Page Three i

D.

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

EEAR FC-84-119 Instrument Inverters.

This modification provided for the removal of battery chargers and inverters and installation of new battery chargers, battery discharge test-breakers and inverters. This modification does not have an adverse effect on the safety analysis.

EEAR FC-84-138 Vacuum Deaerator Sampling System.

i This modification provided for the installation of conductivity sensors upstream and downstream of vacuum deaerator, and the installation of dissolved oxygen downstream ~of vacuum deaerator. This modification does not have an adverse effect on the j

safety analysis.

EEAR FC-85-009 Replacement of EEQ Related Penetration Subassemblies.

n This modification provided for the replacement of penetration subassemblies required for EEQ items with equipment qualified per the requirements of 10 CFR 50.49. This modification does-not have an

. adverse effect on the safety analysis.

EEAR FC-85-040 Upgrade of E/P Converters.

4 This modification provided for the installation of new environmentally qualified E/P converters for valves HCV-1107B, HCV-11088,.HCV-400C, HCV-401C, HCV-402C, HCV-403C, HCV-344, HCV-345, HCV-341 and FCV-326. This modification does not have an adverse effect on the safety analysis.

EEAR FC-85-220' Rewire of EEQ Limitorque Valves.

[

This modification provided for internal wiring of certain safety related Limitorque valves to be inspected and altered if necessary to ensure all 4

electrical equipment qualification requirements were met or satisfied. This modification does not have an adverse effect on the safety analysis.

4 m

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Monthly Operations Report

-September, 1986 Page-Four E.

RESULTS OF LEAK RATE TESTS None F.

CHANGES IN PLANT OPERATING STAFF None.

G.

TRAINING Training for Senior Operator's License candidates was initiated.

Maintenance training was conducted in areas such as vibration measurement, rigging, piping and protective coatings.

Requalification and refresher training continued for Operations and Chemical and Radiation Protection technicians. The last of the 10. required Self Evaluation Reports were submitted to INPO.

H.

CHANGES, TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY COMMISSION AUTHORIZATION PURSUANT-TO 10CFR50.59 Amendment No.

Descriotion 100 The amendment changes the reactor coolant system pressure-temperature limits for heatup and cooldown to provide for operation through 15 effective full power years.

'II. MAINTENANCE (Significant Safety' Related)

None i

N W. Gary Gates Manager Fort Calhoun Station

Omaha Pubilc Power District 1623 Harney Omaha. Nebraska 68102-2247 402/536 4000 October 13, 1986 LIC-86-533 Mr. James M. Taylor, Director Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, DC 20555

Reference:

Docket No. 50-285

Dear Mr. Taylor:

September Monthly Operating Pseport Please find enclosed ten (10) copies of the September,1986 Monthly Operating Report for the Fort Calhoun Station Unit No.1.

Sincerely, R. L. Andrews Division Manager Nuclear Production RLA/jb Enclosures cc: NRC Regional Office Office of flanagement & Program Analysis (2)

R. fl. Caruso - Combustion Engineering R. J. Simon - Westinghouse Nuclear Safety Analysis Center INP0 Records Center American Nuclear Insurers NRC File 1

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