ML20077C442

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Monthly Operating Rept for Apr 1991 for Joseph M Farley Nuclear Plant Unit 2
ML20077C442
Person / Time
Site: Farley Southern Nuclear icon.png
Issue date: 04/30/1991
From: Dennis Morey, Woodard J
ALABAMA POWER CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9105210413
Download: ML20077C442 (6)


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May 13, 1991 Docket No. 50-364 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C.

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Joscoh M. f arley Nuclear Plant Unit 2 Monthlv Operatina Data Reqprt Attached is the April 1991 Monthly Operating Report for Joseph M. farley Nuclear Plant Unit 2, as required by Section 6.9.1.10 of the Technical Specifications.

If you have any questions, please advise.

Respectfully submitted,

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@N.JDN. Woodard AEJ:edb3014 Attachments cc: Mr. S. D. Ebneter Mr. S. T. Hoffir'n Mr. G. f. Maxwl, oionto413 oto uo PDR ADOI.K 0%HJO%4 g

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i JOSEPH H. FARLEY NUCL EAR PL ANT UNii 2 NARRATIVE

SUMMARY

Of OPERA 110NS April 1991 There were three reactor trips during the month of April, At 1055 on 4-1-91, while operating at approximately 100 percent power, a reactor trip occurred when rod H-10 dropped into.the core.

The reactor trip occurred due to a high negative flux rate as detected by the power range nuclear detectors.

The operator was performing FNP-2-STP-5.0 (full Length Control Rod Operability Test). When control rod group C was tested, rod H-10 dropped into the core.

This event was caused by defective circuit card (s) in the rod control system.

The suspect cards were replaced and the unit returned to power operation at 1208 on 4-9-91.

At 2040 on 4-9-91, while operating at approximately 34 percent power, the reactor was manually tripped following the loss of the operating (2A) steam generator feedwater pump (SGFP). The loss of the SGFP was caused by a f ailed electro-hydraulic (EH) fluid supply line coupling and subsequent loss of EH fluid.

Examination of the failed tubing revealed that the failure resulted from cyclic fatigue.

The EH tubing was repaired and all-accessible welds ca the EH systems on Units 1 and 2 SGFps were inspected.

Vibration readings were taken on the EH tubing in the vicinity of the failure. The failed coupling was repaired and an investigation is continuing to determine if additional corrective action is necessary.

The unit returned to power operation at 1648 on 4-10-91.

At 1616 on 4-20-91, while operating at approximately 100 percent power, the Unit two reactor tripped due to turbine generator trip caused by a loss of condenser vacuum.

The condenser lost vacuum because an instrument air valve which supplies air to the steam admission valve on "A"

steam jet air ejector was inadvertently closed.

1he valve was closed as workers were rolling up an air hose after completing a work assignment in the area.

The unit returned to power operation at 0426 on 4-21-91.

There were no other unit shutdowns or major power reductions during the month of April.

The following major safety-related maintenance war performed during the month of April:

1.

Defective circuit card (s) were replaced in the rod control system.

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OPPRATING DATA REPORT DOCKET NO. 50-364 DATE May 7, l'75l COMPLETED 11Y D. N. Morey TEl.EPil0NF'T2D5THW5356

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OPERATING STATtlS

_ Notes

1. Unit Names _

Joseph M. Farley - Unit 2

1) Cumulative data since
2. Reporting Period:

April 1971 7-30-81, date of i

3. Licensed Thermal Power (HVt):

2,657-commerc3al operation.

4. Nameplate Rating (Gross MVe):

860 j

~

5. Design Electrical Rating (Net RWe):

829

6. Maximum Dependable Capacity (Gross HVe):

I64.2

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7. Maximum Dependable Capacity (Net HVe):

873.0 l

8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons: N/A
9. Power Level To WGh Restricted, If Any (het HVe):

N/A

10. Reasons for Resttictions, If Any:__

N/A This Month Yr-to,3 ate Cumulative

11. lirArs In Reporting Period 719 28il 85,488
12.,.nber Of !!ours Reactor Vas Critical 575T7~~

261TIU 73,003.1

13. Reactor Reserve Shutdown flours 0.0 0.0 138.0
14. Ilours Generator On-Line 494.5 257470 72,07572

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15. Unit Reserve Shutdown flours 0.0 ~

0.0 0.0

16. Gross Thermal Energy Generated (HVil)

T 237.745 6 412 TE 616 579

17. Gross Electrical Energy Generated (MVil)

. 91Q)78

~I,D93D,630 TF UDD,72

18. Net Electrical Energy Generated (HVil) 377,504

~~1,980,94E~~ ~37 5,070

19. Unit Service Factor 68.8

~1777 84.3

20. Unit Availability Factor 68.8 8777 ~

84.3

21. Unit Capacity Factor (Using HDC Net) 62.9 83.5 81.7
22. Unit Capacity Factor (Using DER Net) 62.5 837D 80.7
23. Unit Forced Outage Rate 31.3 8.2 4.4~
24. Shutdowns Scheduled Over Next 6 Honths (Type, Date, and Duration of Each):

N/A

25. If Shut Down At End Of Report Period, Estimated Date oT~5tartupt_N/A
26. Units In Test Status (Prior to Commercial Operation):

Forecast Achieved INITIAL CRITICAL.ITY 05/06/81 05/08/81 INITI AL ELECTRICITY 05/24/81 D5725781 COMMERCIAL OPERATION DE7Dl7BI

,,07/30/81 Form 2/30

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DOCKET No.

50-364 UNIT 2

DATE Hay 7, 1991 COMPLETED BY D. N. Morey TELEril0NE (205)899-5156 HONTH April DAY AVERAGE DAILY POVER LEVEL DAY AVERAGE DA1LY POVER LEVEL (MVe-Net)

(HVe-Net) 1 365 17 824 2

0 18 826 3

0 19 826 4

0 20 549 5

0 21 449 6

0 22 827 7

0 23 822 8

0 24 831 9

37.5 25 830 10 23 26 826 11 320 27 820 12 902 28 816 13 820 29 816 14 824 30 823 15 823 16 023 INSTRUCTIONS On this format, list the average daily unit power level in MVe-Net for ea-h day in the reporting month.

Compute to the nearest whole megawatt.

Form 13/21 t

T2T SW"DoletS ARJ POWER REERTIONS DEKET No.

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F: Forced Reason:

Method:

Exhibit G-Instructions S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparatioe of Data B-P!aintenance or Test 2-Manual Scram.

Entry Sheets for Licensee C-Refueling 3-Automatic Scram.

Event Report (IIR) Fi3e (NUREG-I EHtegulatcry Restriction 44)ther (Explain) 0161)

E44)*rator Training & License Examination F-Administrative Exhibit I -Same Source G-operational Error (Explain)

H-Other (Explain)

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UNIT SIRFIDDtEES AND POWER REDtKTIONS DOCIET L').

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DATE May 7, 1991

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COMF12TED ET D. N. ?URET REPok? PONTH AFRIL TEIZPIDEE (205)S99-5156 1

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I F: Forced Peason:

Method:

Exhibit G-Iestructions S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-claintenance or Test 2-Manual Scram.

Dstry Sheets for Licensee C-Refueling 3-Automatic Scram.

Event Report (IER) File (NUREG-D-Regulatory Restriction 4Mxhor { Explain) 01613 E-operator Training & License Examination F-Ade nistrative rehibit I -Same Source G operational Error (E viain)

(9/77)

H-Other (Explain)

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