ML20087G919

Monthly Operating Rept for Feb 1984

ML20087G919
Person / Time
Site:	Fort Calhoun
Issue date:	02/29/1984
From:	William Jones, Mathews T OMAHA PUBLIC POWER DISTRICT
To:	Deyoung R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
LIC-84-074, LIC-84-74, NUDOCS 8403200176
Download: ML20087G919 (10)

Text

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AVIR AGE DAILY UNIT POWER LEVEL DOCKET NO.

50-205 UNIT Fort Calhoun Statior DATE Jurch 13, 1984

,r COMPLETED BY

.T. P. ?btthews TELEPHONE (402) 536-4733 MONTH February, 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 454.7 453.6 37 2

454.7 is 443.5 3

454.5 19 437.7 4

455.2 20 430.5 5

454.9 425.1 2

454.6 419 4 6

22 7

454.7 413.6 23 454.9 407.7 8

24 9

454.4 402.7 25 10 454.3 26 397.4 11 454.6 392.3 27 12 454.4 387.1 28

.454.7 382.0 13 29 454.5 34 30 35 454.0 3,

16 453.9 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) 8403POO176 840229 PDR ADOCK 05000285 R

PDR..

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OPERATING DATA REPORT DOCKET NO. 50-285 DATE March 13, 1984 COMPLE'IED fly 7. P Miltthews (402D36-4733 Ti LErilONE OPFRATING STAT US N"

1. Unit Name:

Fort Calhom station

2. Reporting Period:

February, 1984 1500

.t. E.icenwd Thermal Power (MWI):

501

4. Nameplate Rating (Gross MWe):

470

5. Design Electrical Rating (Net MWe)-

461

6. Maximum Dependable Capacity (Gross MWe):

438

7. Masimum 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 Nono

10. Reasons For Restrictions.lf Any:

This Month Yr. to Date Cumulative

11. Hours in Reporting Period 696 0 1,440.0 91,442.0

12. Number Of Hours Reactor Was Critical 696.0 1,440.0 71,333.0

13. Reactor Resene Shutdown Hour, 0.0 0.0 1,309.0

14. Hours Generator On-Line 696.0 1,440.0 70,842.5

15. Unit Resene Shutdown Hours 0.0 0.0

'0.0

16. Gross Thermal Energy Generated (MWH) 997,882.7 2,103,770.5 88,863,484.2

17. Grou Electrical Energy Generated (MWH) 319,88h0__,,,

675,442.0 28,993,011.0

18. Net Electrical Energy Generated (MWH) 303,974.7 642,754.7 27,722,623.4 100.0 100.0 77.5

19. Unit Senice Factor

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100.0 100.0 77.5

20. Unit Asailability Factor 99.7 101.9 66.1

21. Unit Capacity Factor (Using MDC Net)

22. Unit Capacity Factor (Using DER Net) 91.4 93.4 63.7

23. Unit Forced Cutage Rate 0.0 0.0 3.5

24. Shutdowns Scheduled Over Nest 6 Months (Type. Date and Duration of FSh1:

3984 refueling outage scheduled to start Mardi 3,1984

N/A-2$. If Shul Down At End Of Report Period. Estimated I) ate of Startup:

26. Unitiin Test Stat'is IPrior io Commercial Operation 1:

Forecast Achiesed INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL DPERATiON (9/77I T

a.

DOCKET NO. 50-235 UNIT SHUTDOWPIS AND POtiER REDUCTIONS UNIT NAME Fort Calhoun Station DATE Jurch 13. 1994 COMPLETED BY T. P. Futthas REPORT MONTH February, 1984 TELEPHONE (402) 536-4733 -

.g g 3

Y Licensee

[g fg Cause & Currective Action to No.

- Date g

3g

• s 2s5 Event g?

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Prevent Recurrence f

5 j;2g Report =

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d No unit shutdowns during the month.of February,1984.

4

. I

'2 3

4 Method:

Exhibit G - Instructions

' F: Forced Reason:

1-Manual for Preparation of Data S: Scheduled A Equipment Failure (Explain)

B-Maintenance of Test 2-Manual Scram.

Entry Sheets for Licensee 3-Automatic Scram.

Event Repost tLER) File tNUREG-C-Refueling D Regulatory Restriction 4 Other (Explain) 0161)

E-Operator Training & License Examination 5

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

(9/77)

Il-Other (Explain)

r Refueling Information Ebrt Calhoun - Unit No.1 Peport for the nonth onding February 19M__.

1.

Scheduled dato for next refueling shutdown.

March 1984 2.

Scheduled dato for restart following refueling.

May 1984 3.

Will refueling or resumption of operation thereafter require a technical specification chango or other licenso amendment?

Yes a.

If an. wor is yes, what, in general, will theso be?

Technical Specification changes include the incorporation of the statistical ombination of uncertaintics program, higher radial peaking facters, a dif-forent 'It1/LP equation, a r: ore negativo moderator temperature coefficient of reactivity limit, noro restrictivo Um and DNDR ICO's on axial shape index, arxl the addition of asynnotric steam generator transient protection trip function.

b.

If answer is no, has the reload fuel design and coro configuration been reviewed by your Plant Safety noview Comnittee to deter-mine whether any unreviewed safety questions are associated with the core roload.

c.

If no cuch review has taken place, when is it scheduled?

4.

Scheduled date(s) for submitting proposed licensing action and support information.

Tech._Snees. have been submitted 5.

Inportant licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performanac analysis nothorls, significant changes in fuel design, now operating procedurcs.

6..The number of fuel assemblics: a) in the coro 133 asscsnblics b) in the spent fuel pool 26ci c) spent fuel pool storage capacity 729 4 "

-d) planned spent fuel pool storage capacity

• may be increased 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 M

Prepared by hlA Date_

March 1,'1984 v

v

OMAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No.1 February, 1984 Monthly Operations Report I.

OPERATIONS

SUMMARY

Fort Calhoun Station cor tinu'.d its record online run at 100% power until February 18, 1984, when it Mgan an end of cycle coast down at about 1% per day.

Preparations continue for the 1984 refueling and maintenance outage which is scheduled to begin March 3.

New fuel receipt for Cycle 9 has been completed.

The Nuclear Regulatory Commission was onsite during February to audit the training department.

No safety valve or PORY challenges occurred.

A.

PERFORMANCE CHARACTERISTICS LER Number Deficiency 84-001 Auxiliary Building Crane Interlocks Bypa'ssed.

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-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 etaluation of data from a surveillance test to verify that a fuel assembly uplift condition did not exist.

Monthly Operations Report Page Two Februa ry,1984 0.

CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL l

(continued)

Procedure Description SP-WDS-16 Spent Resin Disposal.

This procedure did not constitute an unreviewed safety question as defined by 10CFR50.59 because this procedure only provides for sampling of a waste gas decay tank.

The sample is returned to the waste disposal system, so there is no gas release.

SP-VA-80 Hydrogen Purge System Test.

This procedure did not constitute an unreviewed safety question as defined by 10CFR50.59 because this procedure only checks operability of fans and clean 11-ness of the filters.

System Acceptance Committee Packages for February,1984:

Package Description / Analysis DCR 748-18 Loose Parts Monitoring System.

This modt fication added sensors and a system to monitar vibration and thus detect loose parts in vital systems.

This feproves the detection of potentially damaging vibration.

This modification has no adverse effect on the safety analysis.

DCR 74A-77 Refueling Machine Grapple and Spreader Modification.

This modification installed an articulated grapple and appropriate spreader that was consistent with the modified fuel. This made it easier, and thus safer, to handle the fuel bundics.

This modification has no adverse effect on the safety analysis.

DCR 77-01 Isolation Yalves for Diesel Generator Air Compressors.

This modification installed a valve in the diesel generator air compressor lines so that one could isolate the air receivers, and not have to blow down the tank during maintenance. This modification has no l

adverse effect on the safety analysis.

e Monthly Operations Report Page Three Feb rua ry,1984 D.

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

System Acceptance Committee Packages for Februar,1984:

Package Description / Analysis DCR 77-59 Radioactive Waste System Modification.

This modification installed piping to direct waste from the evaporator to the floor drain in the room.

This modification has no adverse effect on the safety analysis.

EEAR FC-80-65 Electrical Power for Emergency Communication.

This modification is not safety related, therefore, there is no adverse effect on the safety analysis.

EEAR FC-80-23 Replacement of Alarm Typer on P-250.

This modification replaced a slower printer with one that is much faster, and thus does not cause infomation to be lost. This modification has no adverse effect on the safety analysis.

EEAR FC-83-31 HCV-348 Shaft Change.

This modification changed the shaft and gearbox and resulted in increased speed of operation.

This modification has no adverse effect on the safety analysis.

EEARFC-51-81 AI-41A/B Bus Failure.

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This modification installed bus failure annunciation only. Annunciation has no effect on the safety analysis.

EEAR FC-79-215 Additional Gai-tronics in Containment.

The gai-tronics system is not safety related, therefore, there is no adverse effect on the safety analysis.

Monthly Operations Report Page Four Feb rua ry, 1984 D.

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

System Acceptance Committee Packages for February,1984:

Package Description / Analysis EEAR FC-80-110 Diesel Generator Tachometer Circuit Noise.

This modification eliminates A-C noise associated with the diesel generator speed sensing circuitry.

Installation or removal of this capacitor will not effect the ability of the diesel generator from starting and operating under accident circumstances.

Installation of this capacitor will help circuit stability and help control the sensing circuitry setpoints from drifting.

This modification has no adverse effect on the safety analysis.

E.

RESULTS OF LEAK RATE TCSTS The Fort Calhoun Station is currently performing 8 and C penetration tests. A report will be sc9t out at the end of the refueling outage.

F.

CHANGES IN PLANT OPERATING STAFF Mr. Gene Creamer started March 6,1984, as an Auxiliary Operator -

Nuclear.

G.

TRAINING Operations personnel completed ERF computer training. General employee training classes were increased to accomodate the additional personnel that will be supporting the 1984 outage. Other training continued as scheduled.

H.

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

}

Monthly Operations Report,

Page Five Februa ry,1984 II. MAINTENANCE (Significant Safety Related)

None M

M W. Gary Gates Manager Fort Calhoun Station t

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

March 13, 1984 LIC-84-074 l

Mr. Richard C. DeYoung, Director Office of Inspection and Enforcement U.

S. Nuclear Regulatory Commission l

Washington, D.C.

20555

Reference:

Docket No. 50-285 l

Dear Mr. DeYoung:

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

Sincerely, L

'42 W. C Jones Divi J,on 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 l

INPO Records Center NRC File gg-24 c55R0 Employmen h qualOpporturuty ll