ML20041A467

Monthly Operating Rept for Jan 1982

ML20041A467
Person / Time
Site:	Fort Calhoun
Issue date:	02/08/1982
From:	Short R OMAHA PUBLIC POWER DISTRICT
To:
Shared Package
ML20041A465	List: ML20041A464 ML20041A467
References
NUDOCS 8202220191
Download: ML20041A467 (8)

Text

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AVER AGE DAILY UNIT POWER LEVEL DOCKET NO.

50-285 usir Fort _Calhoun #1 DATE February 8, 1982 R. W. Short COMPLETED BY (402)S36-4543 TELEPHONE January, 1982 gg DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) iswe. Net) 476.1 481.7 37 2

474.7 481.7 18 3

474.8 481.1 39 474.5 481.9 4

20 5

474.1 480.8 21 464.8 481.4 6

22 7

462.2 401 9 23 463.7 483.9 8

2.s 476.1 484.3 9

25 to 476.4 482.1 26 477.1 480.5 27 12 476.4 477.3 28 477.8 472.3 i3 34 479.1 467.9 3o 484.6 462.4 15 3,

16 481.2 INSTRUCTIONS On this format. list the average daily unit power level in MWe-Net for each day in the reporting rnanth. Compute to the nearest whole meg.swatt.

(9/77) 8202220191 820212 PDR ADOCK 05000285 R

PDR

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OPERATING DATA REPORT DOCKET NO. _50-285 DATE February 8, 1982 COMPLETED BY R. W. Short

- TELEPHONE (402)536-4543 OPERATING STATUS Fort Calhoun Station t..'it No.1 Notes

1. Unit Name:

2. Reporting Period:

da nua ry, 1982

3. Licensed Thermal Power (MWt):

501

4. Nameplate Rating (Gross MWe):

r S. Desian Electrical Rating (Net MWe): 470 501

6. Maximum Dependable Capacity (Gross MWe):

478

7. Maximum Dependible Capacity (Net MWe):

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

i None Net MWe):

N/A

9. Power Level To Which Restricted.lf Any /A

10. Reasons For Restrictions,if Any:

This Month Yr.-to-Date Cumulative i1. Hours In Reporting Period 744.0 744.0 73,225.0

12. Number Of Hours Reactor Was Critical 744.0 744.0 56,983.0 l

13. Reactor Reserve Shutdown Hours 0.0 0.0 1,309.5

14. Hours Generator On-Line 744.0 744.0 55,834.0

15. Unit Reserve Shutdown Hours 0.0 0.0

~0.0

16.. Gross Thermal Energy Generated (MWH) 1.G93.509.8 1.093.509.8 67,795,339.9 l

17. Gross Electrical Energy Generated (MWH) 371.288.0 371,288.0 22,445,233.6

18. Net Electrical Energy Generated (MWH) 354,595.2 354,595.2 21,202,463.7

19. Unit Service Factor 100.0 100.0 76.2

20. Unit Availability Factor 100.0 100.0 76.2 i

21. Unit Cagucity Factor IUdng MDC Net) 99.7 99.7 63.2

22. Unit Capacity Factor (Using DER Net) 99.7 99.7 62.8

23. Unit Forced Outage Rate 0.0 0.0 3.9

24. Shutdowns Sc:veduled Over Next 6 Months (Type. Date.and Duration of Eacht:

None

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

N/A

26. Units in Test Status Irrior to Commercial Operation): None Forecast Achiesed INITIA L CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION l

(9/77)

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i DOCKET NO. _50-285 UNIT SHUTDOWNS AND POWER REDUCTIONS Fort Lalhoun #1 UNIT N AME DATE February. 1982 January, 1982 COMPLETED BY R. W. Short REPORT MONTil TELEPilONE (402)536-4543

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Licensee E r, E".

Cause & Corrective t

No.

Date g

3g f;

jg5 Event u?

S3 Action to

$E 5

j di y Report a N0 Prevent Recurrence

'd No unit shutdowns or power reductions during the month of January,1982.

t i

2 3

4 F: Forced Reason:

Method:

Exhibit C 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 Report (LER) File (NUREG-D Regulatory Restriction 4-Other (Explain) 0161)

E-Operator Training & License Examination F-Administrative 5

G-Operational Error (Explain)

Exhibit I-Same Source (9/77) llother (Explain)

E

Refueling Information Ebrt Calhoun - Unit No.1 Report for the nonth enda.ng January 1982 1.

Scheduled date for next refueling shutdown.

December 1. 1982 2.

Scheduled date for restart following refueling.

March 1. 1983 3.

Will refueling or resumption of operation thereafter require a technical specification change or other license anendment?

Yes a.

If answer is yes, what, in general, will these be?

A Technical Soecification chanae, b.

If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Comnittee 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.

September 1. 1982 5.

Irportant 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 237 c) spent fuel pool storage capacity 483 d) planned spent fuel pool storage capacity 483 7.

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

1985 Prepared by

) [l M Date Februarv 4. 1982 y

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9

+

+

OMAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No. 1 January, 1982 Monthly Operations Report I.

OPERATIONS

SUMMARY

~ Fort Calhoun Station _ operated at a nominal 100% power for the month of January.

A new stretch power rating of h86.3 MWe net output was achieved on January 15, 1982.

The station successfully operated at a record low river level during the initial part of January.

Efforts from all disciplines at Fort Calhoun Station contributed to the operation of the unit under low river level conditions.

A New Reactor Operators' License was received at Fort Calhoun Station during January, providing another licensed operator for the operations staff.

The Supervisor-Operations attended a workshop in Windsor, Conn.'on the new Functional Guideline to be included in the Energency Procedures at Fort Calhoun Station.

No safety valve or PORV challenges occurred.

A.

PERFORMANCE CHARACTERISTICS NONE 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 results in Operations Incidents and are not reported elsewhere in the report:

Operations Incident Deficiency OI-lkh5 ST-PL-1( F. 3 )

Pressurizer Level HIC-101 out of tolerance.

OI-lh66 ST-RM-2(F.3)

Radiation Monitoring RM-05hA, 055B, 057, out of tolerance.

OI-lh70 ST-RM-2 Failed Fuel Monitor Calibration.

bnthly Operations Report January, 1982 Page Two D.

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

This procedure did not constitute an unreviewed safety question as defined by 100FR50 59 since it only invol-ves evaluating data from a surveillance test.

SP-GT-2 Gai-tronics & Nuclear Emergency Alarm Audibility Test for Containment.

This procedure did not constitute an unreviewed safety question as defined by 10CFR50 59 since it only invol-ved going to.various locations in containment with the reactor'in a hot shutdown condition and listening for the nuclear emergency alarm.

SP-CTPC-1 Core Thermal Power Calculation. NSSS Calorimetric.

Completed per procedure.

Special Procedure SP-CTPC-1 does not involve an unre-viewed safety question'since plant _ operation is totally unaffected by the procedure. The procedure consists entirely.of evaluating instrument readings.

E.

RESULTS OF LEAK RATE TESTS Leak Rate Test Report for NUREG-0578.

Tech. Spec. 5.lk.2 / Licensing Action Log Item 10281.

The surveillance testing required by Technical Specification 5.1h.2 for leakage from the systems listed in Table 1.of the District's response to NUREG-0578, Item 2.1.6.a has been completed for Cycle 6.

The total measured leak rate from the systems at normal operating i

pressure was 40 milliliters per hour.

Maintenance Orders have been initiated for all leaks found.

Every effort is being made to reduce the leakage rate to as lov as is reasonably achievable.

The system leak rate measurement results should.be included in the next Monthly Operations Report.

ST-CONT-2(F.2) " Personnel Air Lock Leak Test" was performed 1-28-82.

Leakage measured was 3200 sccm. This combined with the final leak rate measured during the recent outage (23035.52 seem) is well below the.6La-62,951 seem maximum allovable leakage limit.

2

_ Monthly Operations Report January, 1982' Page Three F.

' CHANGES IN PLANT OPERATING STAFF NONE G.

TRAINING Training for January included continued general employee train-ing and retraining. Health Physics qualification training, operator non-license and licensed training and Systems Training for Maintenance.

H.

CHANGES, TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY C0!GiISSION AUTHORIZATION PURSUANT TO 10CFil50 59 Limitations to the condenser cooling water discharge temperature and temperature changes, were eliminated by amendment to Appendix B of the Fort Calhoun Station Technical Specifications.

\\.

i Approved By:

S.\\.C. Stevens Manager-Fort Calhoun Station l

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Monthly Operations Report' January, 1982 Page Four II. ' MAINTENANCE (Significant Safety Relate *.)

M. O. #

Date Description Corrective Action 12202-10-12-81 Area Monitors RM-070 does not respond Replaced high range board.

to radiation on the high range.

1013h 9-29-81. Repack RC-131. Instrument Root Valve.

Valve Repacked.

11305 10-30-81 Steam Generator RC-2B perform secon-Performed per MP-RC-2 h.

dary side inspection.

11304 10-30-81 Steam Generator RC-2A perform secon-Performed per MP-RC-2 h.

dary side inspection.

12h 5h.

10-27-81 Repair Security Diesel Generator.

Replaced valve & tightened fittings.

12207 10-15-81 Rav Water Valve HCV-2878A replace Installed new liner & packing.

liner & check shear key.

12652 11-25-81 FI-334 Safety Injection Flow Indi-Complete.

cator, replace studs & nuts.

i 12653 11-25-81 FI-328 Safety Injection Flow Indi-Complete.

cator, replace studs & nuts.

12651 11-25-81 FI-330 Safety Injection Flow Indi-Complete.

cator, replace studs & nuts.

13056 12-3-81 HCV-10hlA/10h2C repair. Main Steam Cleaned shaft & greased.

Isolation Valves.

7012 12-2-81 RPS "D" channel out of tolerance.

Recalibrated.

12245 10-17-81 Repair leak in Containment Cooler Retreaded plugs.

in VA-8A Cooling Coil.

9905 11-2-81 Repair CEDM 25 leakage.

Completed per MP-RC-10 h-B.

112hl 12-2-81 FCV-1101 "A" Steam Generator Feed-Recalibrated.

water Control Automatic Control.

13h86-12-29-81 Charging Pump CH-1C Packing leaks.

Repacked pump.

13555 1-7-82 Charging Pump CH-lC Flow & Amp lov.

Installed new valves.

I i

13051 12-13-81 Level Control Switch for Contain-Replaced Micro switches on ment Sump Pump Start signal locked magnetral.

{

in causing pump to cycle excessively.

13h56 1-6-82 AFW System started on Reactor Trip.

No Action Required. Setpoints were all within tolerance.

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