ML20082A530

Monthly Operating Rept for Oct 1983

ML20082A530
Person / Time
Site:	Fort Calhoun
Issue date:	11/14/1983
From:	William Jones, Matthews T OMAHA PUBLIC POWER DISTRICT
To:	Deyoung R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
LIC-83-287, NUDOCS 8311180174
Download: ML20082A530 (10)

Text

1 C AVERAGE DAILY UNIT POWER LEVEL

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DOCKET NO.

50-285 UNIT Fort Calhoun Station DATE flovember 14, 1983 COMPLETED BY T. P. ilatthews

TELEPHONE (402) 536-4733 MONTH October, 1983 DAY AVER AGE DAILY POWER i.EVEL DAY WER AGE DAILY POWER LEVEL -

(MWe-Net) IMWe Net) 452.4 37 456.8 2 452.1 is 457.0 3 452.9 19 457.2 4 453.8 :o 456.9 5 453.9 2 456.4 6 454.5 22 456.5 7 454.5 23 455.9 8 456.3 y 456.5 9 456.3 25 456.2 go 456.6 26 456.0

456.9 27 455.4 33 457.4 453.1 23 13 457.1 29 437.6 34 457.1 3o 453.3 3 456.9 3 435.0 16 456.8 INSTRUCTIONS On this format. list the average daily unit power lesel in MWe Net for each day in the reporting snonth. Coinpuie to the nearest whole megawatt.

19/77) 8311180174 831114 PDR ADOCK 05000285 R PDR II I

., t OPERATING DATA REPORT DOCKET NO. 50-285 DATE Ilovemoer 14, 1983 COMPLETED BY T. P. flatthews TELEPilONE T4FITTJ6-4733 OPERATING STAT US Fort Calhoun Station N"k'

1. Unit Name:

2. Reporting Period:

October, 1983 1500

3. Licensed Thermal Power (MWt):

4. Nameplate Rating (Gross MWe): 501

5. Design Electrical Rating (Net MWe):

470

6. Maximum Dependable Capacity (Gross MWe): 401

7. Maximum Dependable Capacity (Net MWe):

438

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

f1/A

9. Power Lesel To %hich Restricted. If Any (Net MWe): H/A

10. Reasons For Restrictions.If Any: llone This Month Yr. to-Date Cumulatise

11. Hours in Reporting Period _

745.0 7,297.0 88,538.0

12. Number Of Hours Reactor Was Critical 745.0 5,039.0 68,429.9

13. Reactor Reserve Shutdown llours 0.0 0.0 1,309.5

14. Hours Generator On-Line 745.0 4,941.0 67,938.5

15. Unit Resene Shutdown Hours 0.0 0.0 ' O.0

16. Gross Thermal Energy Generated (MWH) 1,106,546.6 7,004,502.2 84,621,050.6

17. Gross Electrical Energy Generated (MWHI 355,004.0 2,207.054.0 27,630,533.7

18. Net Electrical Energy Generated (MWH) 338,049.9 2,095,551.9 26,425,586.3

19. Unit Senice Factor 100.0 67.7 76.7

20. Unit Availability Factor 100.0 67.7 76.7

21. Unit Capacity Factor (Using MDC Net! 103.6 65.6 64.8

22. Unit Capacity Factor (Using DER Net) 94.9 60.1 62.8

23. Unit Forced Outage Rate 0.0 1.0 3.7

24. Shutdowns Scheduled Oser Nest 6 Months tType. Date and Duration of Each t:

1984 refueling outage scheduled to start around March 3,1984

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

26. Units in Test Status (Prior to Commercial Operation): Forecast Achiesed INITIA L CRITICA LITY INITIAL ELECTRICITY

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Refueling Information Ebrt Calhoun - Unit No. 1 Report for the nonth ending October 1983 .

1. Scheduled date for next refueling shutdown. March 1984

2. Scheduled date for restart following refueling. May 1984

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?

A Technical Specification Change 4

b. If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Otmmittee 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. Tech Rnoc- . Fohrugry 1984

5. Inportant licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performanc analysis

! methods, significant changes in fuel de. t, new operating procedures.

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6. The number of fuel assenblies: a) in the core 133 assemblies b) in the spent fuel pool 265 c) spent fuel pool "

_ storage capacity 483 d) planred spent fuel pool "

storage capacity 728 l

7. The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity. 1985 i

Prepared by '

< CAtl/f Date November 1.1983

(/ /

OMAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No.1 October, 1983 Monthly Operations Report I. OPERATIONS

SUMMARY

Fort Calhoun Station operated at a nominal 100% power through the month until October 28, 1983, when power was reduced to 95% for required moderator temperature coefficient testing October 31.

INP0 was on site two weeks for their annual evaluation of site activities.

The spent fuel pool rerack is in progress.

No safety valve or PORY challenges occurred.

A. PERFORMANCE CHARACTERISTICS LER Number Deficiency 83-008 While at approximately 100% power and during the performance of monthly surveillance test ST-ESF-6, Section F.2, " Diesel Generator Check", diesel generator DG-2 started and was run up to operating speed. However, the generator field failed to flash and the control room had no indication that the diesel was running (that is, the diesel intake air dampers did not open, the diesel stop light did not go out, and the control room diesel tachometer had no RPM indication). Subsequently, diesel generator DG-2 was shutdown and the redundant diesel generator DG-1 was satisfactorily started to verify operability. The 161 KY and 345 KY supplies were also available throughout the incident.

i l B. CHANGES IN OPERATING METHODS None C. RESULTS OF SURVEILLANCE TESTS AND INSPECTIONS Operation Incident Deficiency l

01-1752 ST-FD-1, F.3 During the performance of ST-FD-1, Section F.3 zones 18, 19 and 26 did not actuate zone alarm light.

01-1753 ST-FD-1, F.1 During the performance of ST-FD-1, Section F.1 for May,1983, it was determined that two fire detectors could not be tested.

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Monthly Operations Report October,- 1983

_Page Two C. RESULTS OF SURVEILLANCE TESTS AND INSPECTIONS (continued)

Operation Incident Deficiency '

01-1754 ST-FD-1 F.1 During the performance of ST-FD-1, Section F.1 for June,1983, it was determined that two fire detectors could not be tested.

i D. CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL Procedure Description SP-SFS-2 Receipt of Spent Fuel in NLI 1/2 Cask.

This procedure did not constitute an unreviewed safety

, question as defined by 10CFR50.59 because receipt and handling were in accordance with approved procedures and safety analysis requirements.

i SP-WDS-14 Spent Resin Disposal.

This procedure did not constitute an unreviewed safety question as defined by 10CFR50.59 since it only provided for transfer and solidification of spent resin.

Appropriate radiation protection requirements have been addressed.

SP-WDS-16 Gas Decay Tank Alternate Sample Method.

This procedure did not constitute an unreviewed safety question since it only provides an alternate method for

sampling a waste gas decay tank. Technical Specifications dealing with radioactive gas releases have been addressed.

i System Acceptance Committee Packages for October,1983:

Package Description / Analysis EEAR FC-78-30 Replacement of Cell 18, Battery No.1. -

This modification replaced one of the cells in the Station batteries and nothing else was done. This nodification has no adverse effect on the safety analysis.

9

i Monthly Operations Report October, 1983 Page Thret:

Package Description / Analysis EEAR FC-78-34 Alterrex Locking Hardware.

This modification increased the reliability of the generator system by substituting tight fitting anti-rotation pins for loose fitting ones that could fall out. This modification has no adverse effect on the safety analysis.

EEAR FC-79-48 Site Security Lighting.

This modification improved the site security lighting system only. This modification has no adverse effect on the safety analysis.

EEAR/MR FC-79-117 domen's Rest Room / Shower Addition.

This modification only added a women's rest room / shower facility in the maintenance shop.

This modification has no adverse effect on the safety analysis.

EEAR/MR FC-79-121 Intake Structure Veranda Security Lights. .,

This modification changed the light fixtures on -

the intake structure veranda so that an electrician would not have to hang out over the river to change a bulb. This modification has no adverse effect on the safety analysis.

EEAR/MR FC-79-126 Jib Crane Base Extension.

This modification only raised the base of the turbine building truck bay jib crane. This modification has no adverse effect on the safety analysis.

DCR 77-65 Plant Communication Deficiencies.

This modification effected the plant communication system which is not safety related, therefore, has no adverse effect on the safety analysis.

Monthly Operations Report October, 1983 Page Four Package Description / Analysis EEAR FC-79-44 Weather Tower Work Platfonn.

This modification consisted of pouring a concrete pad around the weather tower and using a collapsible ladder to reach the weather instrumentation when it is lowered for maintenance. It is not safety related, therefore, has no adverse effect on the safety analysis.

EEAR FC-79-211 400 Cycle Computer Inverter Cooling Fans.

This modification consisted of replacing 400 cycle cooling fans with more readily available 60 cycle cooling fans. It does not effect the operation of the fans. This modification has no adverse effect on the safety analysis.

EEAR FC-79-213 Relocate Microwave Tower and Duct Bank.

This modification only moved the microwave communications tower approximately 150 feet farther south. It is not safety related, therefore, has no adverse effect on the safety analysis.

E. RESULTS OF LEAK RALE TESTS There are no new leak rate results to report.

F. CHANGES IN PLANT OPERATING STAFF None l

G. TRAINING l General employee training was conducted as scheduled. Training for Operations personnel included lectures on emergency procedures,

! Technical Specifications, emergency plan, ERF computer, fire brigade, l spent fuel storage modifications and incore instrumentation.

Maintenance personnel training included emergency monitor team, crane, technical augmentation, systems and general employee badge initial and requalification training. Chemistry and Radiation Protection group completed an on site radio chemistry course conducted by N.U.S.

Corporation.

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

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Monthly Derations Report October, ~ 1983 .

Page Five II.- MAINTENANCE (Significant Safety Related)

None Au f , b W. Gary Gates Manager Fort Calhoun Station l

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Omaha Public Power District 1623 Harnetj Omaha. Nebraska 68102 402/536 4000 Novembec 14, 1983 LIC-83-287 Mr. Richard C. DeYoung, Director Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D.C. 20555

Reference:

Docket No. 50-285

Dear Mr. DeVoung:

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

Sincerely,

- r, 8 -

W. C. Jones Division Ilandger Production Operations WCJ/TPM:jmm Enclosures cc: NRC Regional Office

Office of Management & Program Analysis (2) l Mr. R. R. Mills - Combustion Engineering Mr. T. F. Polk - Westinghouse Nuclear Safet.y Analysis Center INPO Records Center NRC File

'I'i l 45.5124 Employment with Equal Opportunity Male! Female

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