ML20080C881

Revised Monthly Operating Rept for Jan 1982

ML20080C881
Person / Time
Site:	Fort Calhoun
Issue date:	02/04/1983
From:	William Jones, Matthews T OMAHA PUBLIC POWER DISTRICT
To:	Deyoung R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
Shared Package
ML20080C870	List: ML20080C868 ML20080C874 ML20080C877 ML20080C881
References
LIC-83-041, LIC-83-41, NUDOCS 8308290358
Download: ML20080C881 (9)

Text

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i AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-285 UNIT Fort Calhoun Station DATE February 4, 1983 COMPLETED BY T. P. Matthews TELEPilONE -(402)536-4733 MONm January, 1983 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (Mwe. Net) 0.0 ,7 0.0 2 0.0 gg 0.0 3 0.0 i, 0.0 4 0.0 0.0 20 5 0.0 21 0.0 6 0.0 22 0.0 7 0.0 23 0.0 8 0.0 24 0.0 9 0.0 25 0.0 to 0.0 26 0.0 11 0.0 0.0 27 12 0.0 28 0.0 13 0.0 29 0.0 14 0.0 3o 0.0 15 0.0 3i 0.0 16 0.0 INSTRUCTIONS On this format. list the aserage daily unit power le elin MWe-Net for each day in the reporting nonth. Compute to the nearest whole megawatt.

(9/77 )

8308290358 830824 PDR ADOCK 05000285 R PDR

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i OPERATING DATA REPORT DOCKET NO. 50-285 DATE February 4,1983 COhlPLETED BY T. P. Matthews TELEPHONE (407)536_4733 OPERATING STATUS

1. Unit Name: Fort Calhoun Station Notes

2. Reporting Period: danuary, 1983 1500

3. Licensed Thermal Power (.\lWt):

4. Nameplate Rating (Gross NIWe): 501 S. Design Elactrical Rating (Net SIWE): 470

6. Sf aximum Dependable Capacity (Gross SIWE): 501

7. Staximum Dependable Capacity (Net 31We): 0

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

N/A i

9. Power Level To Which Restricted. If Anv (Net alWe): N/A I 10. Reasons For Restrictions. If Any: One This Sionth Yr.-to Date Cumulative i1. Hours In Reporting Period 744.0 744.0 81,985.0

12. Number Of Hours Reactor Was Critical 0.0 0.0 64,110.5

13. Reactor Reserve Shutdown Hours 0.0 0.0 1,309.5

14. Hours Generator On-Line 0.0 0.0 62,947.5

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (.\tWH) 0.0 0.0 77.616.548.4 -

17. Gross Electrical Energy Generated (5tWH) 0.0 _, 0.0 ._25,735,333.5

18. Net Electrical Energy Generated (SIWH) 0.0 0.0 _24,330,034.4

19. Unit Service Factor 0.0 0.0 76.8

20. Unit Availability Factor 0.0 0.0 76.8

21. Unit Capacity Factor (Using .\lDC Neti 0.0 0.0 64.4

22. Unit Capacity Factor (Using DER Net) 0.0 0.0 64.1

23. Unit Forced Outage Rate 0.0 0.0 3.9

24. Shutdowns Scheduled Oser Nest 6 Nionths (T)pc. Date,and Duration of Each):

None

25. If Shur Down At End Of Report Period. Estimated'Date of Startup

March 20, 1983

26. Units in Test Status (Prior io Commercial Operationi: N/A Forecast Achiesed INITIA L CRITICALITY INITIA L ELECTRICITY CO\l%IERCIAL OPER ATION J

j (9/77)

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DOCKET NO. 50-283 .

UNITSilUTDOWNS AND POWER REDUCTIONS UNIT NAME l-ort Calhoun Station i

DATE Februarv 4.1983 COMPLETED Hy T. P. ffatthews REPORT MONTil January, 1983 TELEPIIONE (402)S36-4733 i

e.

. E c

, jE 3g $ $3 Licensee [g  % Cause & Corrective No. Date g :s g jgy Event n7 a? Atrion to H

$= 5 C ;jj=5 Repose n (E U $'

o Paesent Recurrence C

4 4

82-06 821206 S 1350 C 4 N/A XX XXXXXX 1982/1983 refueling outage commenced December 6, 1982.  ;

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1 1 2 3 4 F: Forced Reason: Method: Exhibit G -Instructions S: Scheduled A Equipment Failure (Explain) 1 Manual for Preparation of Data i B-Maintenance of Test 2 Manual Scram. Entry Shecis for Licensee i C Refueling 3 Automatic Scram. Event Report (LER) File (NUREG-D Regulatory Restriction 4 Other (Explain) 0161)

E-Operator Training & License Examination

, F-Administrative 5 G-Operational Er ror ( Explain) Exhibit 1 Same Source (9/77) Il-Other (E xplaini

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Itefueling Information l Ebrt Calhoun - Unit No.1 Peport for the renth ending January 1983 .

1. Scheduled date for next refueling shutdom. March 1984

2. Scheduled date for restart following refueling. Mav 1984

3. Will refueling or resumption of operation thereafter require a technical specification change or other license amendment? Yes

a. If answr is yes, what, in general, will these be?

A Technical Specification Change

b. If answer is no, has the reload fuel design anl core ccnfiguration been reviewed by your Plant Safety Review Cc"rtittee to deter-mine whether any unrevieed 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 Methodology - Dec. 1983 action and support information.- Tech. Specs. - Feb. 1984

5. Inrcrtant licensing considerations associated with refueling, e.g. , nea or different fuel design or supplier, unreviemd design or performance analysis methods, significant changes in fuel design, nea operating procedures.

6. The number of fuel asse::blies: a) in the core 133 assemblies b) in the spent fuel pool 265 c) spent fuel pool I

storage capacity 483 d) planned spent fuel pool storage capacity 728

7. 'Ihe projected date of the last refueling that can be discharged to the spent fuel pool asst:ning the present licensed capacity. 1985 Prepared by 6.-1,CU) Date February 1, 1983

OMAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No. 1 January, 1983 Monthly Operations Report I. OPERATI0h5

SUMMARY

Fort Calhoun Station continued refueling outage operations during the month of January.

Several important jobs were completed during January. They include the following:

1. Integrated Leak Rate Test (ILRT). The test was completed successfully and leakage has been calculated to be acceptable.

2. The cycle 7 core was completely offloaded into the spent fuel pool in preparation for the reactor vessel internals inspection.

3. The reactor vessel internals including the core support barrel were removed and stored in the lower cavity area of containment.

4. The ten-year reactor vessel internals inspection was initiated.

The start of inspection efforts was delayed slightly due to align-ment pin location problems. The alignment pins were relocated to the correct position and inspection efforts are currently in progress.

Several N.R.C. audits were conducted during January in the areas of security, outage health physics, fire protection, and requalification training. American Nuclear Insurers conducted a fi-re protection inspection and initiated an ongoing inspection covering the reactor vessel internals ten-year inservice i ns pection.

Mr. A. Richard successfully completed the simulator exam portion of his Senior Reactor Operators license. This completes Mr. Richard's senior license program.

No safety valve or PORV challenges occurred.

A. PERFORMANCE CHARACTERISTICS LER Number Deficiency 82-021 During performance of " refueling" surveillance test ST-ESF-3, F.2, " Containment Pressure Channel Check", pressure switch A/PC-742-1 was found to initiate above the Technical Specification limit of 5 psig. Pressure switch A/PC-742-1 is one of four switches in the "A" channel of the contain-ment pressure high signal (CPHS) initiation i matrix. During the time period A/PC-742-1 would l have failed to initiate at or below 5 psig, the other three pressure switches of the "A" channel l

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"nnthly nperations Report .

January, 1983 Page Two -

A. PERFORMANCE CHARACTERISTICS (Continued)

LER Number Deficiency were operational and a CPHS could have been initiated by two of these three switches actuating. Additionally, the redundant "B" channel pressure switches which initiate the "B" CPHS were fully operable and would have actuated to mitigate the consequences of an accident, if required.

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 performed in accordance with the annual surveillance test schedule. The following is a summary of the surveillance tests which resulted in Operation Incidents and are r.ot reported elsewhere in the report:

Operation Incidents Deficiency 01-1623 ST-CONT-2, Missing Documentation for 10/8/81, 10/30/81, F.1 - 11/9/81, 11/11/81, 11/20/81, 11/21/81, and 11/22/81 as required.

01-1621 ST-ISI-CVCS-3, Missed Q.C. verification of calibration of F.1 test equipment.

01-1622 ST-ISI-RW-3, Test not performed as required during F.1 November, 1981. Plant was in refueling outage.

Raw Water System could not be aligned to the configuration specified in the . test due to maintenance and modi fications being performed.

01-1632 ST-IR-1, .. Test results had less than 85% radio-iodine F.3 retention.

01-1636 ST-RM-1, During the performance of ST-RM-1, F.3, F.3 monitor RM-070, 071, 072, 073, 081, 084, 085, and 086 were found to be out of calibration tolerance specification.

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a. .. . .

l Mont,hly Operations Report January, 1983 Page Three 1

i j D. CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COM-MISSION APPROVAL

} Procedure Description i SP-FH-2 Puel Holst Removal from Mast.

Not an unreviewed safety question l because

The procedure only pro-vides for the orderly removal, re-

pair, and reassembly of the re-

, fueling machine hoist box. The -

i appropriate surveillance testing i

will be performed prior to use.

i l SP-ECT-1 Eddy Current Testing of Heat Ex-

changer Tubes. Completed per procedure.

! This procedure did not constitute an unreviewed safety question as defined by 10CFR50.59 since it only involved eddy current test-1 ing of feedwater heaters.

E, RESULTS OF LEAK RATE TESTS All. leak rate tests p'erformed during January and February will be reported to the PRC per a special report (which concerns itself with all CONT-2, 3, 7, and associated tests). This special report will be submitted to the PRC prior to startup.

l F. CHANGES IN PLANT OPERATING STAFF The following promotions were effective January 1, 1983:

Gary L. Roach Supervisor - Chemical & Radiation Protection 4

( Gerald Chatfield Shif t Supervisor Joseph'M. Mattice Plant Health Physicist Two new operators, Dan Hochstein and Dave Harrison, were added to the ogerations Department.

Revised 8/24/83 I

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Monthly Operations Report January, 1983 Page Four f G. TRAINING Training for January, 1983, General Employee Training was 4

conducted several times a week to accommodate the in-crease in support personnel for the 1983 outage. Oper-ations on-the-job training was conducted on the refueling machine and outage operations. NRC conducted an audit on

, operator initial and requalification and fire brigade training.

H. CHANGES, TEST AND EXPERIMENTS REQUIRING NUCLEAR REGU-LATORY COMMISSION AUTHORIZATION PURSUANT TO 10CFR50.59.

Amendment No. 66 adds a temporary authorization to per-form secondary tests at a lower temperature.

II. MAINTENANCE (Significant Safety Related) l Refueling outage maintenance will be submitted as one package in April, 1983.

W. G. Gates Manager Fort Calhoun Station I

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Revised 8/24/83

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l Omaha Public Power District .

1623 MARNEv e OMAMA. NE8RASMA 65102 e TELEPHONE 536-4000 AREA CODE 402 February 10, 1983 LIC-83-041 f

Mr. Richard C. DeYoung, Director Office of Inspection and Enforcement U. S. fluclear Regulatory Commissicn Washington, D.C. 20555

Reference:

Docket fio. 50-285

Dear Mr. DeYoung:

Please find attached ten (10) copies of the January Monthly Operating Report for the Fort Calhoun Station Unit fio.1.

Sincerely, W. C. nes Divisidn Manager Production Operations WCJ/TLP:jm Attachments cc: fiRC Regional Office -

Office of Management & Program Analysis (2)

Mr. R. R. Mills - Combustion Engineering Mr. T. F. Polk - Westinghouse Mr. L. A. Yandell - f4RC Senior Resident Inspector fluclear Safety Analysis Center fiRC File

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