ML20134F680

Monthly Operating Rept for Jul 1985

ML20134F680
Person / Time
Site:	Fort Calhoun
Issue date:	07/31/1985
From:	Andrews R, Matthews T OMAHA PUBLIC POWER DISTRICT
To:	Taylor J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
LIC-85-370, NUDOCS 8508210215
Download: ML20134F680 (8)

Text

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AVERAGE DAILY UNIT POWER LEVEL 50-285 DOCKET NO.

Fort Calhoun Station UNIT August 9, 1985 DATE T. P. Matthews COMPLETED BY (402) 536-4733 TELEPHONE MONTH July, 1985 DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY PO',iER LEVEL (MWe Net)

(gwe. Net) 470.5 17 467.8 1

467.6

_469.4 18 2

469.2 466.9 3

466.9 469.1 20 4

469.0 467.0 5

21 467.4 468.9 22 6

468.1 467.8 7

,3 467.3 467.0 8

466.2 466.3 25 9

465.5 466'.0 to 26 465.1 466.2 465.5 466.6 12 28 464.9 467.5 13 464.3 467.4 34 39 464.8 470.0 15 3

467.0 16 INSTRUCTIONS On this fortnat. fist the average daily unit power leselin MWe Net for each day in the reporting nronth. Compute to the nearest whole megawatt.

19I77) 8508210215 850731 PDR ADOCK 05000285 PDR mv%

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OPERATING DATA REPORT DOCKET NO.

50-285 DATE Auoust 9. 1985 COMPLETED BY T. P. Ma tthews TELEPil0NE (402) 536-4733 OPERATING S'I ATUS

1. Unit Name:

Fort Calhotm Station N"5

2. Reporting Period:

July, 1985 1500

3. Licensed Thermal Power (SlWt):

502

4. Nameplate R.iting(Gross alWe):

478

5. Design Electrical Rating (Net SIWE):

502

6. Maximum Dependable Capacity (Gross MWe):

470

7. Maximum Dependable Capacity (Ner MWe):

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

N/A

9. Power Lesel To Which Restricted,if Any (Net MWe):

N/A None

10. Reasons For Restrictions.lf Any:

This Month Yr..to Date Cumulative 744.0 5,087.0 103,873.0

11. Ifours in Reporting Period 744.0 5,060.6 80,340.8 l'. Number Of flours Reactor Was Critical 0.0 0.0 1,309.5'

13. Reactor Resene Shutdown flour, 14.11ours Generator On-Line 744.0 5,052.7 79,720.1'

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

16. Gross Thermal Energy Generated (MWil) 1,110,686.9 7,478,935.4 101,665.702.4

17. Gross Electrical Energy Generated (MWil) 364,894.0 2,523,278.0 33,292,903.0

18. Net Electrical Energy Generated (MWil) 347,599.1 2,407,385.5 31.819.022.8

19. Unit Senice Factor 100.0 99.3 76.7 100.0 99.3 76.7

20. Unit Availability Factor

21. Unit Capacity Factor (Usin?. MDC Net) 97.7 99.0 66.6 97.7 99.0 64.4

22. Unit capacity Factor (Using DER Net) 0.0 0.0 3.6

23. Unit Forced Outage Rate

24. Shutdowns Scheduled Oser Nest 6 Months IType. Date and Duration of Eacht:

1985 Refuelino Shutdown is tentativelv scheduled for October. 1985 with startup in December, 1985.

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

N/A

26. Units in Test Status 1 Prior to Commercial Operation):

N/A Forecast Achiesed INill A L CRi flCALI TY INITI.,\\ L ELECTRICi fY COM\\lERCI A L OPI:R A TION P1/77)

SG-285 DOCKETNO. Fort Calhoun Station UNITSHUTDOWNS ANDlOWER REDUCTIONS UNIT NAME DATE August 9, 1985 REPORT MONTH July, 1985 COMPLETED By T. P. Ma tthewc; TELEPHONE (402) 536-4733

~i E

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3 4h Licensee Eg j%

Cause & Correctise No-Date i

3g 4

2g5 Event s7 a '?

Action to y5 3 5 :!

Report =

SV 5L Prevent Recurrence H

e u

6 There were no unit shutdowns during the month of July.

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I 2

3 4

F: Forced Reason:

Method:

Exhibit G. Instructions S: Scheduled A Equipment Failure (Explain) 14tanual for Preparation of Data B-Maintenance of Test 2 Manual Scram.

Entry Sheets for Licensee C-Refueling 3 Automatic Scram.

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

E-Operator Tr.iining & License Examination F-Administratiu 5

G Operational listor (Explaini Eshibit I-Same Source (9/77)

Il Other iE splaini

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Refueling Information Ebrt Calhoun - Unit No.1 Report for the nonth ending Julv. 1985 l

1.

Scheduled date for next refueling shutdown.

October, 1985 2.

Scheduled date for restart following refueling.

December, 1985 3.

Will refueling or resumption 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 Specifications 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 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 infonnation.

September, 1985 5.

Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or perfonnance analysis methods, significact changes in fuel design, new operating procedures.

liethodology Changes June, 1985 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 pooI~ May be increased storage capacity via fuel pin consolidation 7.

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

1996 Prepared by_ h - jd e A,M e Date Auaust 2. 1985 y

v

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

OPERATIONS

SUMMARY

Fort Calhoun Station operated at a nominal 100% power throughout July, 1985.

Four Reactor Operator and two Senior Reactor Ooerator candidates passed the NRC license examination.

No candidates failed. Training programs continue for Equipment Operator-Nuclear (Turbine Room),

emergency plan, C/RP Technicians and general employee training.

New fuei receipt and. inspections of the 44 assemblies for Cycle 10 were completed in July.

No abnormalities were noted during these inspections.

The annual emergency preparedness drill was held on July 10 and the exercise was held on July 24.

There were no major deficiencies noted by the NRC exercise observers. The modified OSC/TSC organization was implemented and functioned well.

Responses to the INP0 evaluation and assistance visit were prepared and submitted in July.

Reduction in long term low level radioactive waste continued during July.

Several shipments of High Integrity Containers (HICs) aided in eliminating several drums of waste which have been stockpiled at the Station No safety valve or PORV challenges or failures occu"rred.

A.

PERFORMANCE CHARACTERISTICS None B.

CHANGES IN OPERATING METHODS None C.

RESULTS OF SURVEILLANCE TESTS AND INSPECTIONS None

Monthly Operations Report July, 1985 Page Two D.

CHANGES, TESTS AND EXPERIMENTS CARRIED :,UT WITHOUT COMMISSION APPROVAL Procedure Description SP-FAUD-1 Fuel Assembly Uplift Condition Detection.

This procedure did not constitute an unreviewed safety qcestion as defined by 10CFR50.59 since it only involved the evaluation of data from a surveillance test to verify that a fuel asser.bly uplift condition did not ' exist.

SP-EEQ-1 LOCA Qualified Electrical Equipment Identification Check.

This procedure did not constitute an unreviewed safety question as defined by 10CFR50.59 because this procedure is simply an inventory list of qualified equipment and indications located on various panels and control boards in the plant.

No plant operations or evolutions are involved.

System Acceptance Connlittee Packages for July,1985:

Package Description / Analysis EEAR FC-84-73 Replacement of Containment Penetration Splices.

This modification provided more reliable safety related cables / splices under accident and post-accident conditions.

This modification has no adverse effect on the safety analysis.

EEAR FC-82-94 EHC Hydraulic Power Unit Modification.

This modification was installed in order to prevent overpressurization of the recirculating tank (a portion of the transfer and fuller earth filtering unit of the EHC).

This modi-fication would protect the recirculating tank from overpressurization should a relief valve fail to open. The transferand fuller earth filtering unit comes into existance when the EHC main reservoir is being filled. This modification has no adverse effect on the safety analysis.

~.

Monthly Operations Report July,1985 Page Three E.

RESULTS OF LEAK RATE TESTS During the month of July, the biannual leak rate surveillance test for the Containment Personnel Air Lock (PAL) was completed. The previous six month leak rate was 3,560 secm.

The July,1985, leak rate for the PAL doors was found at 3,600 secm.

This increases the previous "B" and "C" leak rate total of 9,427.53 sccm to 9,467.53 sccm. The current leak rate total is well below the allowed leakage of.6 La (62,951 secm) as specified in 10CFR50 Appendix J.

The next test that will affect the "B" and "C" leak rate total is the upcoming 1985 refueling outage leak rate test scheduled to start in September,1985.

F.

CHANGE IN PLANT OPERATING STAFF During July Calvin Taylor, David Sweeney and John Borger started work as Auxiliary Operators-Nuclear.

Dennis Schwieger started work in July as an Operations Helper.

Dennis Bonsall, an Equipment Operator-Nuclear Licensed, resigned in July.

G.

TRAINING Four Reactor Operator and two Senior Reactor Operator candidates passed the NRC license examination.

No candidates failed.

Training programs continue for Equipment Operator-Nuclear (Turbine Room),

emergency plan, C/RP Technicians and general employee training.

H.

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

MAINTENANCE (Significant Safety Related)

None 4&.

N W. Gary Gates Manager Fort Calhoun Station

T Omaha Pubilc Power District 1623 Harney Omaha. Nebraska 68102 402/536 4000 August 13, 1985 LIC-85-370 i

I Mr. James 11. Taylor, Director Office of Inspection and Enforcement U. S. Nuclear Regulatory Conmission l.

Washington, DC 20555

Reference:

Docket No. 50-285

Dear Mr. Taylor:

l l

July Monthly Operating Report Please find enclosed ten (10) copies of the July,1985 Monthly Operating Report for the Fort Calhoun Station Unit No.1.

Sincerely, R. L. Andrews Division Manager Nuclear Production RLA/TPM/dao Enclosures cc:

NRC Regional Office Office of Management & Program Analysis (2) l Mr. R. R. Mills - Combustion Engineering Mr. T. F. Polk - Westinghouse Nuclear Safety Analysis Center l

INP0 Records Center American Nuclear Insurers NRC File t6 2.tL i

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