ML20065A796

Monthly Operating Rept for Jan 1983

ML20065A796
Person / Time
Site:	Fort Calhoun
Issue date:	02/04/1983
From:	Gates W, Matthews T OMAHA PUBLIC POWER DISTRICT
To:
Shared Package
ML20065A786	List: ML20065A784 ML20065A796
References
NUDOCS 8302220168
Download: ML20065A796 (8)

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o AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-285 UNIT Fort Calhoun Station DATE February 4,1983 COMPLETED BY T. P. Matthews TELEPHONE (402)S36-4733 anua n , 1983 MONTH DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe-Net) (Mwe. Net)

0.0 0.0 37 2 0.0 ig 0.0 3 0.0 39 0.0 4 0.0 20 0.0 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 10 0.0 26 0.0

0.0 27 0.0 12 0.0 28 0.0 13 0.0 29 0.0 14 0.0 3o 0.0 15 0.0 3, 0.0 16 0.0 INSTRUCTIONS On this forrnat. list the average daily unit power levelin MWe. Net for each day in the reporting month. Compute to the nearest whole megawatt.

(9/77) 8302220168 830210 .

PDR ADOCK 05000285 R PDR

OPERATING DATA REPORT DOCKET NO. 50-285 DATE February 4,1983 COMPLETED BY T. P. Matthews TELEPHONE (402 M36 _4733 OPERATING STATUS

1. Unit Name: Fort Calhoun Station Notes

2. Reporting Period: January, 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): 501

7. Ma.simum Dependable Capacity (Net MWe):

470

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. If An (Net MWe): N/A

10. Reasons For Restrictions.If Any: One This Month Yr..to.Date Cumulative

11. 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 (MWH) 0.0 0.0 77.616.548.4 .

17. Gross Electrical Energy Generated (MWH) 0.0 _ , . , ,

0.0 _25,735,333.5

18. Net Electrical Energy Generated (MWH) 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 MDC Net) 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 Ne.st 6 Months (Type. Date.and Duration of Eacht:

None

25. If Shut Down At End Of Report Period. Estimated Date of Startup: March 20, 1983

26. Units in Test Status IPrior to Commercial Operation): N/A Forecast Ac:iiesed INITIA L CRITICALITY INITI A L ELECTRICITY COMMERCIAL OPER ATION (9/77) - -

DOCKET NO. 50-285 UNIT SHUTDOWNS AND POWER REDUCTIONS Fort Calhoun Station UNIT NAME DATE Februarv 4.1983 COMPLETED BY T. P. Matthnws REPORT MONTil January, 1983 TELEPHONE (402)536-4733

_ ~E E

.5g 3 $Yi Licensee g r, '"

f ', Cause & Corrective No. Date i 3g 4 jj$ Event  ?? o. Action to H

f: $ j ;ji g Report u iE U j 'E Prevent Recurrence 6

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

I 2 3 4 F: Forced Reason: Method: Exhibit G-Instructions S: Scheduled A Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or Test 2 Manual Scram. Entry Sheets for Licensee C-Refueling 3-Automatic Scram. Event Repost (LER) File (NUREG.

D-Regulatory Restriction 4-Other (Explain) 0161)

E-Operator Training & License Examination F.Admimstrative 5 G-Operational Error (Explain) Exhibit 1 - Same Source (9/77) Il-Other (Explain)

J

Refueling Information Fort Calhoun - Unit No. 1.

Poport for the month ending January 1983 .

1. Scheduled date for next refueling shutdown. 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 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 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 sutmitting proposed licensing Methodology - Dec. 1983 action and support information. Tech. Specs. - Feb. 1984

5. Inportant licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures.

6. The number of fuel assemblies: a) in the core 133- assemblies b) in the spent fuel pool 265 c) spent fuel pool 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 assuming the present licensed capacity. 1985 February 1, 1983 Prepared by

, M, .

Date

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

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 canpletely 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 fire 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 Senier Reactor Operators license. This complctes 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 matrix. During the time period A/PC-742-1 would have failed to initiate at or below 5 psig, the other three pressure switches of the "A" channel

0 . , 3 Monthly 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 a:n 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 not 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.

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

l Raw Water System could not be a.ligned to the configuration specified in the . test due to maintenance and modifications being performed.

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

i 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.

O I

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- s Monthly Operations Report January, 1983 Page Three-D. CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL Procedure Description SP-FH-2 Fuel Hoist Removal from Mast.

Not an unreviewed safety question because:

The procedure only provides for the orderly removal, repair, and reassembly of the refueling machine hoist. box. The appropriate surveil-lance testing will be performed prior to use.

E. RESULTS OF LEAK RATE TESTS All leak rate tests performed 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.

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

Gary L. Roach Supervisor - Chemical and Radiation Protection Gerald Chatfield Shift Supervisor Joseph M. Mattice Plant Health Physicist Two. new operators, Dan Hochstein and Dave Harrison, were added to the Operations Department.

G. TRAINING Training for 'ar ;ry,1983, General Employee Training was conducted several time' a Ret to accommodate the increase in support personnel for the is '.f On* ,ne. Operations on-the-job training was conducted on the reft.l. in; ,., sine and outage operations. NRC conducted an audit on operator initial and requalification and fire brigade training.

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

Amendment No. 66 adds a temporary hathorization to perform secondary tests at a lower temperature.

Monthly Operations Report' January, 1983 Page Four II. MAINTENANCE (Significant Safety Related)

Refueling.0utage Maintenance will be submitted as one package in April,1983.

4&. 2 & .

W. G. Gates Manager ',

Fort Calhoun Station T

i

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