ML20043G134

Monthly Operating Rept for May 1990 for Jm Farley Nuclear Plant,Unit 2

ML20043G134
Person / Time
Site:	Farley
Issue date:	05/31/1990
From:	Hairston W, Dennis Morey ALABAMA POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9006190103
Download: ML20043G134 (5)

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':--:? I Atb;rna Power CompW 40 inntness Ccnter Parkway i

Post Office Dox 1295 Birmingham, Alabama 35201.

• f Telephone 205 868 5581

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. W. G, Hairston, til J Senior Vice President Nuclear Operations Alabama Power.

g Itesouthern electrc system I

June 12, 1990 I

Docket No. 50-364 U. S.' W elcar Regulatory Commission ATIN: DCc.m@t Control Desk Washington, D.

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Joseph M. Farley Nuclear Plant Unit 2 i

Monthly operating Data Report 1

l Attached is the May 1990 Monthly Operating Report for' Joseph M. Farley.

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Nuclear Plant Unit 2, required by section 6.9.1.10 of the Technical 9

Specifications.

If you have any questions, please advise.

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Respectfully submitted, i

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l JGS: map /1.6 Attachment 4

cc: Mr. S. D. Ebneter Mr. S. T. Hoffman Mr. G. F. Maxwell j

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JOSEPH M. FARLEY 'NUCIE\\R plMr UNIT 2-NARRATIVE SUbMARY OF OPERATIONS May, 1990-

. The outage to replace containment coolers continued thivugh May 12. The outage-

- was extended approximately three days due to oil leaks on 2A and 2B residual

' heat removal ptanp, motors., The reactor was unde critical at 0047 on May 12.

At 0615 on May 12, during the unit startup, the reactor. tripped due to low-low water level in the. 2A steam generator. - The low-low water level occurred'when:

t.he steam supply valves for the on-service steam generator feedwater planp (SGFp) closed. Testing being perforsned in 'accordance with ~ FNp-2-STp-151'.4j (Main Turbine Protective-Device Test,) resulted in' low electro-hydraulic fluid j

presaure which caused the SGFP valves to close.

-t The unit was synchronized to the grid at 2216 on May 12 and returned to full; power on May 14.

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There were no other unit shutdowns or significant power reductions during the '

month of Sy..

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i The following major safety-related maintenance was perforwxi in the morith of'

'May:

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1. - Replaced two cont.ainment coolers. The fan motors were refurbished-on the-two rennining coolers.

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2. _ Repaired oil leaks on the 2A and 2B RIIR pump motors.

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3. : Replaced blown fuses in auxiliary relay-cabinet to restore main steam:

1 atmospheric relief valve 2B _ to_ full stroke.

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4.

Replaced.the rotating assembly on the 2n charging ptunp. Also, replaced:

existing seal assembly with~a mechanical seal-assembly.

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Miscellaneous corrective and preventive maintenance was perfonned on i

the diesel generators,.

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OeERATING o m REem T DOCKET NO.

50-364 DATE June 6, 1990 s

03tPLETED BY D. N. Morey

'IELEPfENE (205)899-5156 OPERATING STATUS Notes

1. Unit Name:

Joseph M. Farley - Unit 2

1) Cumulative data since

2. Reporting Period:

May 1990 7-30-81, date of

3. ' Licensed 'Ihermal Power (Mt):

2,652 comercial operation.

4. Nameplate Rating (Gross Me):

860

5. Design Electrical Rating (Net NWe):

829 6.: Maximum Dependable Capacity (Gross NWe):

868.6

7. Maximum Dependable Capacity (Net MWe):

828.2

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 Any (Net MWe):

N/A

10. Reasons For Restrictions, If Any:

N/A

'Ihis Month Yr-to-Date Cumlative

'11. Hours In Reporting Period 744 3,623 77,472

12. Number Of Hours Reactor Was Critical 474.0 3,279.4 59,957.3

13. Reactor Reserve Shutdown Hours 0.0 0.0 138.0

14. Hours Generator On-Line 457.7 3,262.8 66,334.8

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWH) 1,168,621 8,436,301 168,692,568

17. Gross Electrical Energy Generated (MWH) 380,622 2,782,340 55,448,882

18. Net Electrical Energy Generated (MWH) 355,632 2,641,644 52,585,034

19. Unit Service Factor 61.5 90.1 85.6

20. Unit Availability Factor 61.5 90.1 85.6

'21. Unit Capacity Factor (Using MDC Net) 57.7 88.0 82.9

.22.. Unit Capacity Factor (Using DER Net) 57.7 88.0 81.9

23. Unit Forced Outage Rate 16.6 2.7 4.5

24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

Refueling / Maintenance Outage, September 14, 1990, approximately 7 weeks.

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.25. If Shut Down At End Of Repoit Period, Estimated Date of Startup: N/A

.26. Units In Test Status (Prior to Commercial Operation):

Forecast Achieved INITIAL CRITICALITY 05/06/81 05/08/81 INITIAL ELECTRICITY 35/24/81 U5723/81 -

COMMERCIAL OPERATICN V8/01/81 07/30/81-L Form 2/30 l

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DOCKET NO.

50-364 UNIT-2' DATE ' June 6, 1990 COMPLETED BY D. N. Morey TELEPHONE (205)899-5156 M0tml -

May i

DAY AVERAGE DAILY POWER LEVEL DAY AVrEAGE DAILY POWER LEVEL (M4e-Net)

(MWe-Net) 1 0

17 821 2

0 18 834 l

-3 0

19 831 4

0 20 824 5

0 21 823 6

0 22 829-7 0

23 834 8

0 24 829 9

0 25 825 10 0

26 824 t

11 0

27 823 12 0

28 811 13 276 29 829 14 764 30 835 15 824 31 831 16 825 INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.

I Form 13/21 i

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7 UNIT SHUTDOWNS AND POWER CEDUCTIONS DOCKET NO.

'50-364 m

UNIT NAME J. M. FARLET - UNIT 2, DATE June 6-1990-C

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COMPLETED BT-D. N.'MOPTT~

8 REPORT MONTH mat

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TELEPHONE:

(2051899-5156 l

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l METHOD OF l LICENSEE l l

l CAUSE & CORRECTIVE l

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l l DURATION l l SHUTTING l EVENT l SYSTEM l COMPONENT l

ACTION TO l

lNO.

l DATE l TTPE l (HOURS)

.l. REASON l DOWN REACTCR l REPORT $ l CODE l CODE l

PREVENT RECUR 2E*fCE

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l l 002 l 900501 l

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195.3 l

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. l N/A l BK l

MO lThe outage to replace containment coolers continued l l

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lfrom 4/27/90.

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75.0 l

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N/A l BP l

MO lThe outage was extended approximately three days l

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l ldue to oil leaks on 2A and 2B residual beat

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jremoval pump motors. The reactor wac made l

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16.0 l

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3 l90-001-00 l SJ l

P lAt 0615 on 5-12-90, during a unit startup, the l

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l reactor tripped due to low-low water level in the l l

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l2A steam generator. The low-low water level l

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l lon-service steam generator feedwater pump {SGFP) l l

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l lwith FNP-2-STP-151.4 (Main Turbine Protective l

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l l Device Test) resulted in low electro-hydraulic (EN)l l

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l fluid pressure which caused the SGPP valves l

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l lThis event was caused by procedural inadequacy.

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l lFNP-2-STP-151.4 did not provide adequate guidance l l

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lconcerning the initial conditions required to l

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l lnot appropriate to perform this procedure while l

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l feedwater is b.ing provided by a SGFP.

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l lFNP-2-STP-151.4 has been revised to provide l

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l lthe procedure when a SGTP is in service.

j h: 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 Report (LER) File (NUREG-D-Regulatory Restriction 4-Other (Explain) 0161)

E-Operator Training & License Examination F-Administrative Exhibit I -Same Source G-Operational Error (Explain)

H-Other fxplain)

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