ML20099E912

Monthly Operating Rept for Oct 1984

ML20099E912
Person / Time
Site:	Fort Calhoun
Issue date:	10/31/1984
From:	Andrews R, Matthews T OMAHA PUBLIC POWER DISTRICT
To:	Deyoung R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
LIC-84-387, NUDOCS 8411260138
Download: ML20099E912 (8)

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.'

50-285 UNIT.. Fort Calhoun Station DATE November 9, 1984 T. P. Matthews COMPLETED BY TELEPHONE (402) 536-4733

-MONTH October. 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LFVEL (MWe-Net)

(MWe-Net) 483.5 g

g7 484.4' 2

484.9 18 ans n 485.7 gg 484.8 3

485.4 485.1 4

20 485.1 21 485.1 5

485.2 6

22 484.9 484.8 485.0 23 7

8 485.0 24 485.0 9

483.7 25 483.5 484.1 483.3 26 10 483.1 485.3 g

27 484.9 483.6 28 12 484.0 484.8 13 29 14 483.8 30 484.8 483.8 15 31 484.9 484.5 16 INSTRUCTIONS On this format. list the aserage daily unit power levelin MWe Net for each day in the reporting :nonth. Compute to the nearest whole rnegawatt.

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l' i 8411260138 841031 PDR ADOCK 05000285

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OPERATING DATA REPORT DOCKET NO.

50-285 DATE Mnvomber 9, 1984 COhlPLETED BY T. P. Matthews TELEPilONE (402) 536-4733 OPERATING STATUS Notes

1. Unit Name:

Fort Calhoun Station

2. Reporting Period:

October. 1984 1500

3. Licensed Thermal Power (5 twt):

501

4. Nameplate Rating (Gross SlWe):

478

5. Design Electrical Rating (Net SIWE):

501

6. Staximum Dependable Capacity (Gross SIWE):

478

7. Sf aximum Dependable Capacity (Net alwe):

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

N/A

9. Power Lesel To which Restricted.lf Any (Net alwe):

N/A None

10. Reasons For Restrictions,if Any:

This alonth Yr..to.Date Cumulative

11. Ilours In Reporting Period 745.0 7.320.0 97.322.0

12. Number Of flours Reactor Was Critical 745.0 4.243.1 74.137.0

13. Reactor Resene Sherdown flours 0.0 0.0 1.309.0

14. Ilours Generator On-Line 745.0 4,136.5 73,539.0'

15. Unit Reserve Shutdown llours 0.0 0.0 0.'0

10. Gross Thermal Energy Generated (5tWil) 1.110.458.1 5.853.527.9 92.613.241.6

17. Gross Electrical Energy Generated (51Wil) 377,874.0 1,920,266.0 30.237.835.0

18. Net Electrical Energy Generated (51Wil) 360.987.8 1.825.814.4 28,905,683.1

19. Unit Senice Factor 100.0 56.5 75.6

20. Unit Availability Factor 100.0 56.5 75.6

21. Unit Capacity Factor (Using 51DC Net) 101.4 52.2 64.7

22. Unit Capacity Factor (Using DER Net) 101.4 52.2 62.4

23. Unit Forced Outage Rate 0.0 0.4 3.4

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

,.Q

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

N/A

26. Units in Test Status tPrior to Commercial Operationi: N/A Forecast Achiesed INITIAL CRITICALITY INITIA L ELECTRICITY

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CO\\l.\\lERCIAL OPER ATION (9/77)

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50-285

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DOCKET NO.

UNIT SHUTDOWNS AND POWER REDUCTIONS UNITNAME _ Fore Calhoun Statione '

DATE -November 9-1984 T. P. Matthews COMPLETED 8Y October, 1984 TELEPHONE (402) 536-4733 REPORT MONTH b

c Cause & Corrective.

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Licensee

$ r, l

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Action to

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No.

Date g

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yss Event p

Prevent Recurrence mV l

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}- 5 g Report a g

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_There were no unit shutdowns or power reductions during the month-of October, 1984, i

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~ 2 Method:

Exhibit G -Instructions.

F: Forced Reason:

1-Manual for Preparation of Data S: Scheduled

' A Equipment Failure (Explain)

}

2-Manual Scram.

' Entry Sheets for Licensee B-Maintenance of Test 3 Automatic Scram.

Event Report (LER) File (NUREG-C Refueling 4-Other (Explain)

.0161)-

D Regulatory Restriction E-Operator Training & License Examinatien S'

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

(9/77) llother (Explain)

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. Refueling Information Ibrt Calhoun - Unit No.1 s

Report for the month ending October, '1984 1.

Scheduled date for next refueling shutocre.

October 1985

'2.

Scheduled date for restart following refueling.

December 1985

- 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?

Technical Specification change to accommodate increased radial peaks due to further reduction in radial leakage, b.

If answer.is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Conmittee to deter-mine whether any unroviewed 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 subinitting proposed licensing action and support information.

September 1985 5.

Important licensing considerations associated with Methodology Changes refueling, e.g., new or different fuel design or June 1985 supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures.

6.

We number of fuel asserrblies: 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 fuci pin consolidation 7.

%c projected date of the last refueling that can be discharged to the spent fuel poo' assming the present licensed-capacity.

1996 Prepared by_ h e s /)

Date Novenber 1,1984 f

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OMAHA PUBLIC POWER: DISTRICT Fort Calhoun Station Unit No.1 October, 1984'

. Monthly Operations Report -

I.

OPERATIONS

SUMMARY

Fort Calhoun' Station operated at a nominal.100% power through the month of October,1984. The Fort Calhoun staff participated in the annual q

emergency exercise on

_:ober 24, 1984. A Shift Supervisor retired effective October 1,1984.

No safety valve or PORV challenges or failures occurred.

A.

PERFORMANCE' CHARACTERISTICS LER Number Deficiency _

84-019 VIAS Actuation (RM-061).84-008 R1 Steam Generator Tube Rupture, Supplement.

B.

CHANGES IN OPERATING METHODS None C.

RESULTS OF SURVEILLANCE TESTS A:," INSPECTIONS I

None D.

CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL Procedure Description SP-VA-80 Hydrogen Purge System Test.

This procedure did not constitute an unreviewed safety question as defined by 10CFR50.59 because this proce-dure only checks operability of fans and cleanliness of the filters.

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.

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. Monthly Operations-R: port October, 1984 Page Two a

D.

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

Procedure Description

'SP-VLPM-1 Vibration'and Loose Parts Monitoring Core Barrel Motion.

This procedure did not constitute an unreviewed safety question as defined ~by 10CFR50.59 because it merely allows for recording of vibration signatures corre-sponding to the nuclear instrumentation channels in an effort to gather and _ interpolate data which could possibly identify excessive core barrel motion. At no time during the performance of this test was any equipment important to safety affected.

SP-VLPM-3 Vibration and Loose Parts Monitoring Core Barrel Motion.

This procedure did not constitute an unreviewed safety question as defined by 10CFR50.59 because it merely allows for recording of vibration signatures corre-sponding to the nuclear instrumentation channels in an effort to gather and interpolate data which could possibly identify excessive core barrel motion. At no time during the performance of this test was any equipment important to safety affected.

E.

RESULTS OF LEAK RATE TESTS None F.

CHANGES IN PLANT OPERATING STAFF Mr. Robert F. Johnston retired as Shift Supervisor effective October 1, 1984.

G.

1 RAINING Non-licensed operators continued individual training as part of the initial operator training program during the month of October,1984.

Licensed operators attended simulator requalification training at Combustion Engineering's simulator in Windsor, Connecticut.

Emer-gency plan training was completed for plant staff and crafts in oreparation for the annual emergency exercise held in October.

Other training was conducted per annual schedule. Special training was conducted for NRC license candidates in preparation for an exam to be administered in November,1984.

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-- C MMonthly Opraticns R5 port

-October. 1984.

Page:Three D-

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^ CHANGES, TESTS-ANDLEXPERIMENTS REQUIRING NUCLEAR REGULATORY COMMISSION

. AUTHORIZATION ^ PURSUANT:TO 10CFR50.59

-Package.

Description / Analysis

'AmendmentLNo. 85 LThis amendment revises-the. technical specifications

. to include' mora formal administrative-requirements

on limiting overtime and. reporting of. pressurizer safety valveJand relief' valve challenges and failures.

'II.

MAINTENANCE (Significant Safety Related)

None Y

AM.

W. Gary Gates J

Manager i

Fort Calhoun Station i

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t Omaha Public Power District 1623 Hametj Omaha. Nebraska 68102 402/536 4000 November 12, 1984 LIC-84-387 Mr. Richard C. DeYoung, Director Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, DC 20555

Reference:

Docket No. 50-285

Dear Mr. DeYoung:

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

Sincerely,

// 2kA't !

R. L. Andrews Division Manager Nuclear Production RLA/TPM/dao:2614 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 h

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45 5124 Employment with Equal Opportunity Mdle/ female