ML20078K041

Monthly Operating Rept for Sept 1983

ML20078K041
Person / Time
Site:	Fort Calhoun
Issue date:	09/30/1983
From:	William Jones, Matthews T OMAHA PUBLIC POWER DISTRICT
To:	Deyoung R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
LIC-83-266, NUDOCS 8310180162
Download: ML20078K041 (10)

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AVER AGE DAILY UNIT POWER LEVEL DOCKET NO. 50-285 UNir Fort Calhoun Station DATE October 13, 1983 COMPLETED BY _T. P. fiatthews TELEPilCNE (402) 536-4733 MONTH Seoternbar. 1983 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1MWe-NetI i 440.1 17 453.4 2 440.4 18 452.9 3 440.9 19 452.1 4 441 9 20 454 1 5 443.3 21 455.6 6 444 4 22 457 4 7 445.2 23 457.9 s 445.5 24 457.8 9 445.5 25 457.5 to 444.5 26 456.1 II 446.1 27 454.9 12 448.1 454.4 28 i3 450.1 29 453.4 14 450.9 3o 452.7 15 453.1 3 16 453.7 INSTRUCT 10NS On this format. list the average daily unit power leu:i in MWe Net Ihr each d; e in the reponimg anonth. Compute to the nearest whole megawatt.

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8310100162 830930 DRADOCK05000g

OPERATING DATA REPORT DOCKET NO. 50-285 DATE _0ctober 13, 1983 COMPLETED liY T. P. flatthews TELEPHONE (402) M6-4733 OPERATING STATUS

1. Unit Name: Fort Calhoun Station N"

2. Reporting Period: September, 1983

3. Licensed Thermal Power (MW ):

1500

4. Nameplate Rating (Grc.ss MWe): 501

5. Design Electrical Rating (Net MWe): 470

6. Maximum Dependable Capacity (Gross MWe): 461

7. Muimum Dependar.'e Capacity (Net MWe): 438

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

ft/A

9. Power Level To Which Restricted.If Anv INet MWe): fi/A

10. Reasons For Restrictions. If Any: hone This Month Yr.-to.Date Cumulatise II. Hours in Reporting Period 720.0 6.552.0 87.793.0

12. Number Of Hours Reactor Was Critical 720.0 4,294.9 67,684.9

13. Reactor Reserve Shutdown llours 0.0 0.0 1.309.5

14. Hours Generator On-Line 720.0 4.196.0 67.193.5

15. Unit Reserve Shutdown Hours 0.0 0.n nn

16. Gross Thermal Energy Generated (MWH) 1.073.897.6 5.397.955.6 83.514.504.0

17. Gross Electrical Energy Generated (MWH) 5 1,852,050.0 340 n_74_.0 27.275.529 7

18. Net Electrical Energy Generated (MWH) 324,093.5 1,757,502.0 26,087,536.4

19. Unit Service Factor 100.0 64.0 76.5

20. Unit Availability Factor 100.0 64.0 76.5

21. Unit Capacity Factor IUsing MDC Net) 102.8 61.2 64.5

22. Unit Capacity Factor IUsing DER Net) 94.2 56.1 62.5

23. Unit Forced Outage Rate 0.0 1.2 3.7

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

1984 refueling outage scheduled to start around fiarch 16. 1984 and will last approximately two months.

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

26. Units in Test Status IPrior o Commercial Operationi: Forecast Achiesed INIIIA L CRITICALITY INITI AL ELECTRICITY CO\lMERCIA L OPER AEON 011 7)

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DOCKET NO. 50-285 UNIT SHUTDOWNS AND POWER REDUC 110NS UNIT NAME Fort Calhoun Station DATE Octohor 1% 1083 COMPLETED BY T P. flattheta REPORT MONT11 Sentomber' 1983 1TLEPHONE (402) 536-4733 4

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- E E E_ g 3i; $Y5 Licensee ,E-r, ye, Cause & Corrective No. Date g 3g jg5 Event ~g Action to .

H f: 5 j;ji g Reporta mV g{ Prevent Recurrence d

There were no unit shutdowns for the month of September,1983.

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i 2 3 4 F: Forced Reason: Method: Exhibit G Instructions S: Scheduled A Equipment Failure (Explain) l-Manual for Preparation of Data

B-Maintenance of Test 2 Manual Scram. Entry Sheets for Licensee C Refueling 3 Automatic Scram. Event Report (LER) File (NtlRI G-D-Regulatory Restrietion 4-01her (Explain) 0161)

E Operator Training & License Examination F Administrative 5 G-Operational E:ror (Explain) Exhibit 1 - Same Source l'8/77) 11-O her (Explain)

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i Refueling Infomation Ebrt Calhoun - Unit No.1 Report for the month ending September -1983 .

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.L Scheduled date for next refueling shutdcun. March 1984

2. - Scheduled date for restart folicwing 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

' b. If answer is no, has the reload fuel design

~ and core configuration been reviewed by your_ Plant Safety Review Ccmnittee to deter-mine whether any unreviewed safety questions are assiociated 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 atformation. Tech. Specs. - February 1986

5. Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or perfomance analysis -

methods, significant changes in fuel design, new operating procedures.

6. The number of fuel asserblies: a) in the core 133 asscsnblies b) in the spent fuel pool 265 c) spent fuel pool storage capacity 483 d) planned spent fuel pool storage capacity 728

7. Tne projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity. 1985 Prepared bY t u/) A24A Date October 1.1983 1 g

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

SUMMARY

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_' Fort Calhoun Station operated at 100% power the entire month of September. Three The new~ spent fuel racks began arriving on site September 19, 1983.

operators and one engineer are participating in hot license training at Combustion Engineering's simulator in Windsor, Connecticut.

No safety valve or PORV challenges occurred.

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. A. PERFORMANCE CHARACTERISTICS LER Numbe_r Deficiency

_j 83-007 During routine power operations at approximately 100%

power, the RPS "B" channel Axtsl Power Distribution (APD) positive trip setpoint was noticed to be operating

.out of specification tolerance in the non-conservative direction. The "B" channel of the RPS for Axial Power

' " - Distribution was immediately placed in bypass. During the event the redundant Axial Power Distribution channels of the RPS (i.e., A, C, & D) were verified to be operating satisfactorily and as designed.

B.- CHANGES IN OPERATING METHODS None C. RESULTS OF SURVEILLANCE TESTS AND INSPECTIONS Surveillance tests as required by the Technical Specifications Section 3.0 and Appendix B were peformed in accordance with the annual sur-veillance test schedule. The following is a sumary of the surveil-lance test which resulted in an Operation Incident and is not reported elsewhere in the report:

Operation Incident Deficiency 4

1. 01-1758 ST-ISI-CVCS-3 The 96-hour engineering review l

signoff was not completed within

the required 96-hours.

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Monthly Operations RGport SeptembGr, 1983 Fage Two D. ~ CHANGES, TESTS AND EXPERIMENTS' CARRIED OUT WITHOUT COMMISSI0t; APPROVAL Procedure Description / Summary SP-FE-10 Inspection of Spent Fuel using CE Curb Mount Equipment.

This procedure did not constitute an unreviewed safety question as defined by 10CFR50.59 since it only involved inspection of spent fuel assemblies in the spent fuel pool. Only external measurements were taken and all movement of fuel assemblies was done in accordance with established procedures.

SP-UF6-1 Uranium Hexafloride Storage Cylinder External Visual Inspection.

This procedure did not constitute an unreviewed safety question as defined by 10CFR50.59 since it only involved the inspection of storage cylinders.

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.

System Acceptance Committee Packages for September,1983:

Package Description / Analysis DCR 77-91 Backflush Connections on Raw Water Pumps This modification added a connection to "C" raw water pump to allow for backflushing before startup of the pump which improves the reli-ability of the pump. This modification has no adverse effect on the safety analysis.

I' EEAR FC-78-36 Repair of AS-594 This modification changed out an auxiliary steam valve (non-safety related). This modification has no adverse effect on the safety analysis.

EEAR FC-78-48 Steam Generator Blowdown Isolation Valves HC'<- ! ' 37AB and HCV-1388AB This modification changed the internal trim and body gaskets of these valves which improved their reliability. This modification has no adverse effect on the safety analysis.

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Monthly Operations Report September,1983 Page Three Package Description / Analysis EEAR FC-78-70 Auto Close Breaker Mode Switch Wiring Change This modification changed a set of contacts on one of the diesel auto close breaker mode

. switches. The operation of the switch was not effected. This modification has no adverse effect on the safety analysis.

EEAR FC-79-64 Install Unions on AC Safety / Relief Valves This modification added unions to component cooling relief valves. The operation of the valves and the setpoints of the valves remained unchanged. This modification has no adverse effect on the safety analysis.

EEAR FC-82-139 TSC Batteries This modification changed out the TSC batteries with those of a higher quality. This modifica-tion has no adverse effect on the safety analysis.

EEAR FC-83-60 Moisture Separator Bypass on Auxiliary Building (SRDC0 83-33) Crane This modification provided a bypass for an air line moisture separator. This modification has no adverse effect on the safety analysis.

DCR 77-10 Dual Setpoint Operation of PORV's This modification provided dual setpoint operation for the PORV's. One setpoint for low temperature, and one for operating temperature. This modifica-tion has no adverse effect on the safety analysis.

EEAR FC-79-200 Stack Flow Monitor Improvement This modification improved the readability and operation of the stack flow monitor. This modi-fication has no adverse effect on the safety ,

analysis.

EEAR MR-FC-81-128, Waste Filters, Part 1 (Pilot Filters Installation)

Part 1 Only This modificdtion installed two new tie-in points to the Liquid Radioactive Waste System which allow the addition of a temporary Pilot Filter to the waste system. These tie-ins were designed to meet piping class 152. This modification has no adverse effect on the safety analysis.

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Monthly Operation.; R:p3rt Septemb;r,1983 Page Four Package . Description / Analysis Raw Water Pump Room Stairs 1 EEAR FC-80-123 l

This n'odification replaced the old raw water pump l room stairway with one that was less steep. This modification has no adverse effect on the safety analysis.

EEAR FC-80-102 Sixth Stage Extraction Erosion This modification replaced elbows on the sixth stage extraction piping with a more suitable material than carbon steel for resistino erosion.

This modification has no adverse effect on the safety analysis.

EEAR FC-79-201 Storeroom Lighting This modification added more lighting to CQE storage areas in the storeroom. This modifica-tion has no adverse effect on the safety analysis.

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

F. CHANGES IN PLANT OPERATING STAFF None G. TRAINING General employee training was conducted as scheduled. Operator requalification training included physics review, properties of fluids, hydrostatics, thermal dynamics, fire brigade, heat balance, I

heat transfer, hydrodynamics and emergency procedures. Non-i licensed operator training was included. Emergency plan training I was conducted for plant personnel. Maintenance personnel received training on plant systems. Three operators and one engineer participated in hot license training at Combustion Engineering's simulator in Windsor, Connecticut.

H. CHANGES, TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY COMMISSION r.JTHORIZATION PURSUANT T0 10CFR50.59 Amendment No. 75 Allows an increase in the storage capacity for the spent fuel pool from 483 whole fuel assemblies to 729 whole fuel assemblies.

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1 Monthly Operations Report S:ptemb:r,- 1983 Page-Five-II. MAINTENANCE (SignificantSafetyRelated)

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- . . A W. Gary _ Gates Manager Fort Calhoun Station 9

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Omaha Public Power District 1623 Harney Omaha. Nebraska 68102 402/536 4000 October 13, 1983 LIC-83-266 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. DeYoung:

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

Sincefely,

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\lfL4 W. C. Jones

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Division 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 INPO Records Center NRC File i

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i 45 5124 Employment with Equal Oppcc; unity Male / Female

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