ML20214A306

Monthly Operating Rept for Oct 1986

ML20214A306
Person / Time
Site:	Fort Calhoun
Issue date:	10/31/1986
From:	Andrews R, Matthews T OMAHA PUBLIC POWER DISTRICT
To:	Taylor J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
LIC-86-466, NUDOCS 8611190393
Download: ML20214A306 (8)

Text

-

s AVER 4GE DAILY UNIT POWER LEVEL 50-285 DOCKET NO.

UNIT Fnet Calhoun Station DATE November 13, 1986 T. P. Matthews COMPLETED BY 402-536-4733 TELEPHONE MONTH October. 1986 DAY AVER AGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

MWe-Net)

I ani_o 37 486.3 2

482.C 13 486.8 3

483.0 19 das_A 4

482.3 20 486.5 5

482.2 485.6 21 482.4 6

22 484.7 484.0 7

482.6 23 482.5 34 484.7 8

482.0 484.9 9

25 10 482.8 26 484.9 483.8 484.9 11 27 485.5 12 3

gg, y 486.2 13 29 484.5 487.1 14 30 484.8 6.6 485.2 15 3,

16 486.4 INSTRUCTIONS l

On this format. list the average daily unit power level in MWe. Net l'or each day in the reporting inonth. Coinpute io the nearest whole rnegawatt, i

07/776

,l

~

l 8611190393 861031

\\\\\\

PDR ADOCK 05000285 R

PDR 1

o OPERATING DATA REPORT DOCKET No.

50-285 DATE Nnvomher 13, 1986 COMPLETED BY T. P. Matthews TELEPHONE 402 516-4733 OPERATING STATUS

1. Unit Nsme: Fort Calhoun Station Notes

2. Reporting Period:

October, 1986 1500

3. Licensed Thermal Power (MWt):

4. Nameplate Rating (Gross MWe):

502

5. Design Electrical Rating (Net MWe):

478 502

6. Maximum Dependable Capacity (Gross MWe):

470

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. lf Any (Net MWe):

N/A

10. Reasons For Restrictions.If Any:

None This Month Yr..to.Date Cumulative 745.0 7.296.0 114.842.0

!I. Hours in Reporting Period 745.0 7,021.3 88,767.5

12. Number Of floam Reactor Was Critical 0.0 0.0 1,309.5

13. Reactor Reserve Shutdown Hours

14. Hours Generator On Line 745 n 6.800.2 87,923.1

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWH) 1 110.974.4 9.146.2L9.2 112.R97.291.R

17. Gross Electrical Energy Generated (MWH) 377,190.0 3,046,9L3.2 37.031.512.2 360,928.7 2,902,021.5 35,379,914.9

18. Net Electrical Energy Generated (MWH)

19. Unit Service Factor 100.0 93.2 76.6

20. Unit Availability Factor 100.0 93.2 76.6 101.4 83.2 66.7

21. Unit Capacity Factor (Using MDC Nett 101.4 R1.2 64.7 l

22. Unit Capacity Factor (Using DER Net)

23. Unit Forced Outage Rate 0.0 1.6 3.4

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

None

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

N/A l

26. Units in Test Status 1 Prior to Commercial Operationi:

Forecast Achiesed INITI A L CRITICALITY INITIAL ELECTRICITY N/A COMMERCIA L OPER ATION (9/771 l

DOCKETNO. 50-285 UNIT SHUTDOWNS AND POWER REDUCTIONS Fort Calhoun Station UNIT NAME DATE Navomhpr 13. 1986, COMPLETED BY T. P. Matthews October, 1986 REPORT MONTH TELEPHONE 402-536-4733

~.

E c

Licensee Eg

{"3 Cause & Corrective

.[?

3 yYE o-Action to No.

Date g

3g i!j jj5 Event gg Report e mO

!O Prevent Recurrence

$E Ji;5=g H

u e

O There were no unit shutdowns or power reductions during the month of October, 1986.

I 2

3 4

w F: forced Reason:

Method:

Exhibit G. Instructions S: Scheduled A-Equipment Failure (Explain)

I-Manual for Preparation of Data B-Maintenance of Test 2-Manual Scram.

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

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

E-Operator Training & License Examination 5

F-Administrative Exhibit I. Same Source G-Operational Error (Explain)

(9/77)

IIOther (Esplain)

a O

Refueling Information Fort Calhoun - Unit No. 1 Report for the month ending October, 1986 1.

Scheduled date for next refueling shutdown.

March, 1987 2.

Scheduled date for restart following refueling.

May, 1987 3.

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

Yes a.

If answer 1: 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 i

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 Combustion 1

Engineering for Cycle 5.

I 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 Din consolidatioa 7.

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

1996 l

Prepared by h II.2Ak Date October 27. 1986

.~,,,-~_..-r--

OMAHA FUBLIC POWER DISTRICT Fort Calhoun Station Unit No. 1 October, 1986 Monthly Operations Report I.

OPERATIONS

SUMMARY

Fort Calhoun Station operated at 100% power throughout October, 1986. The repacking of circulator CW-IC has been postponed due to not being able to drain the cell since the cell crosstie is inoperable. The annual inspection was performed on emergency diesel generator DG-1.

The 18-month frequency calibration was performed on all six toxic gas monitors.

The CVCS cation exchanger resin was sluiced and replaced. Work continues on the security building expansion modification. An NRC control room habitability audit was performed.

Preparations were made for the November INP0 evaluation. On October 29 a major portion of the plant staff participated in a full scale emergency preparedness drill. Off-site agencies were not included in this drill. One Auxiliary Operator-Nuclear resigned during the month.

Requalification training continued for non-licensed and licensed operators.

An Equipment Operator-Nuclear (Turbine Building) training class was initiated. Continued refresher training for maintenance and chemical and radiation protection technicians. Training was initiated for the Technical staff. General Employee Training continued.

No safety valves or PORV challenges or failures occurred.

A.

PERFORMANCE CHARACTERISTICS None B.

CHANGES IN OPERATING METHODS None C.

RESULTS OF SURVEILLANCE TESTS AND INSPECTIONS None D.

CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL Procedure Description SP-PC-2 Software Modification Procedure.

This procedure did not constitute an unreviewed safety question as defined by 10CFR50.59 because the procedure only provided for connecting the labeling of a point on the plant system.

./

Monthly Operations Report October, 1986 Page Two e

D.

CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL Procedure Descrintion 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-EEAR-2 Closing Out Old Modifications.

This procedure did not constitute an unreviewed safety question as defined by 10CFR50.59 since it only provided guidelines for ensuring adequate documentation was completed in order to ensure the level or margin of safety of the plant as evaluated in the USAR and as directed by the Technical Specifications was not decreased and thus allow for the close out of old modifications at the Fort Calhoun Station.

SP-MOV-1 timitorque Motor-0perated Valve Inspection.

This procedure did not constitute an unreviewed safety question as defined by 10CFR50.59 because the procedure was used to assure the great in 26 Limitorque valves was okay.

This helped maintain the qualification of the valves.

E.

RESULTS OF LEAK RATE TESTS None F.

CHANGES IN PLANT OPERATING STAFF One Auxiliary Operator-Nuclear resigned during October.

G.

TRAINING Requalification training continued for non-licensed and licensed operators.

An Equipment Operator-Nuclear (Turbine Building) training class was initiated.

Continued refresher training for maintenance and chemical and radiation protection technicians.

Training was initiated for the Technical staff.

General Employee Training continnad.

Monthly Operations Report October, 1986 Page Three H.

CHANGES, TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY COMMISSION AUTHORIZATION PURSUANT T0 10CFR50.59 None II. MAINTENANCE (Significant Safety Related)

None

/# f f6 W. Gary Ga'tes Manager-Fort Calhoun Station

Omaha Public Power District 1623 Harney Omaha. Nebraska 68102-2247 402/536 4000 l

l November 14, 1986 LIC-86-466 Mr. James M. Taylor, Director Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Reference:

Docket No. 50-285

Subject:

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

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

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

+

4h 7124

( iT?{T h i ' Tit'fil W fI'l ( Q!idl !![Tb tT[Unsf Q MMi

• l tilTid t t