ML20116J912

Monthly Operating Repts for Oct 1992 for Joseph M Farley, Units 1 & 2

ML20116J912
Person / Time
Site:	Farley
Issue date:	10/31/1992
From:	Hill R, Woodard J SOUTHERN NUCLEAR OPERATING CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9211160442
Download: ML20116J912 (9)

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. , k. Southern Nxie'ar Opwa9ng Cornpany Post Oke Bex 1295

[9rmingham A!abama 35?0t Teleprxca 2J5 868 fcS6 J, D. Woodard t

OUbm MCM Q N M3COG Q ye P'y the scasern c!ectoc system November 13, 1992 Docket Nos. 50-348 50-364 U. S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, D. C. 20555 Joseph M. Farley Nuclear Plant Unit 1 and 2 Mo; hiv Operatina Data Reports Ge.. 2n:

Attached are the Octboer 1992 M6nt'nly Operating Reporte, for Jc.5eph-'M.

Farley flut. lear Plant Units 1 and 2, as required by Section 6.9.1.10 of the Technical Specifications.

If you have any questions, please advise.

Respectfully submitted,

. D fo AEJ:edb3014 Attachments cc: Mr. S. D. Ebneter Mr. S'. T. Hoffinat Mr. G. F. Maxw :ii 160000 c2111LO442 921031

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JOSEPil M. FARLEY NUC1. EAR Pl>WT UNIT 1 NARRATIVE

SUMMARY

OF OPERATIONS October,1997 The cycle 11-12 refueling outage continued through the month of October.

The following major safety related maintenance was performed during the month of October

1. Performed testing and maintenance on various safety-related hydraulic and mechanical snubbers.

\ 2. Performed eddy current inspection on 100 percent of the available tubes in all three stcam generaturs (SGS). .

1

3. Completed 112 of 118 piping penetration local leak rote tests (LLRTs).

4. Completed 49 of 49 electrical penetretion LLRTs.

5. Replaced tube hundle in 600 vo'i load center ID toom cooler. .

6. Performed various design changes on the service water system including the replacement of some existing carbon steel piping with stainless steel.

7. Pertormed numerous maintenance tasks on the 1B diesel generator including the installation of filters in the air start system.

8. Performed various design changes on the reactor make-up vater system, including a changeout of % tank diaphragm.

9. Performed miscellanecar .otrective and preventive maintenance on the diesel generators and the B1G sequencer.

10. Various safety related check valves and motor operated valves were inspected.

DOCKET E0. 50-348 UNIT 1 DATE November 4, 1992 COMPLETED BY R. D 11111 TELEP110NE (205)899-5156 MONTil October DAY AVERAGE DAILY F0VER LEVEL DAY AVERAGE DAII.Y POVER LEVEL (MJe-Net) (MVe-Net) 1 0 17 0 2 0 18 0 3 0 19 0 4 0 20 0 5 0 21 0 6 0 22 0 7 0 23 ,

0 8 0 24 0 0 0 25 0

' *%:dwewax.:..,y u,.,,, ,

10 0 , g,2 6 0 11 0 27 0 12 0 28 0 13 0 29 0 14 0 30 0 15 _

0 31 0 16 0 INSTRUCTIONS On this format, list the average daily unit power level in MVe-Net for cach day in the reporting month. Compute to the nearest whole megavatt.

Form 13/21

OPERATING DATA REPORT DOCKET No. 50-348 DATE November 4, 1992 COMPLETED BY R. D. Hill TELEPHONE (205)899-5156 OPERATING STATUS ~~

Notes

1. Unit Naues Joseph M. Farley - Unit 1 1) Cumulative data since

2. Reporting Period: October 1992 12-1-77, date of

3. Licensed Thermal Power (MVt): 2,652 commercial operation.

4. Nameplate Rating (Gross MVe): 860

5. Design Electrical Rating (Net h?e): oz9

6. Maximum Dependable Capacity (Gross MVe): 855.7

7. Maximum Dependable Capacity (Net MVe): 812.0 ~

8. If Changes occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons: N/A

9. F6ver Level To Vhich Restricted, If Any (Net MVe): N/A

10. Reasons For Restrictions, If any: N/A This Ponth Tr-to-Date Cumulatise

11. Ilours In Reporting Period 745.0 7,320.0 130,776.0

12. Number Of Hours Reactor Vas Critical 0.0 6,454.4 102,365.3

13. Reactor Reserve Shutdown Hours 0.0 0.0 3,650.0

14. !!ours Generator On-Line ~~~

0.0 6,454.1~ ~

100,718.4

15. Unit Reserve Shutdevn Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MVH) 0 76 '~ 17,035 988.5 258,440,512.6~

17. Gross Electricel Energy Generated (MVH)

~~ ~

0.0 ~3T,7586.0'~83,269,348.0

18. Net Electrical Energy Generated (MVH) (470'6) 5,196,944.0 ~78,611,742.0

19. Unit Servtce Factor 0.0 8877~ 77.0

20. Unit Availability. Factor 0.0 ~ 88.2 77.0

21. Unit Capacity Factor (Using MDC Net) _

N/A ~[ 8774~ 74.3 l .22. Unit Capacity Factor (Using DER Net) N/A __,_85.6 72.5

23. Unit Forced Outage Rate 0.0 0.0 6.7

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

N/A

25. If Shut Down At End Of Report Period, Estimated Date of Stoctup: 11/26/92

l. 26. Units In Test Status'(Prior to Commercial Operation): Forecas* Achieved INITIAL CRITICALITY 08/06/77 08/_09/77 INITIAL ELECTRICITY 08/20/77 08/18/77 COMMERCIAL OPERATION 12/01/77 12i01/77 Porm 2/34 i

' tN27 StrJTDuten AND IOE3t MCNS IncKET No,-- 50-348 ,.

IMIT IEWwK- J. M. FMtLET - t3CT 1 '

rmez !sovester 4( 1793 CtP!PLETED BT R. D. Erl, REPORT M OCTCh8ER TE12PHcrtE (2651899-5156 .

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l 002 l921001' I s l 745' C l 1 l 1r/A l N/A l T/A lThe cycle 11-12 refmling continued from 92092, . l l I l- 1 1 1 1 I i i i i I .I i  ; I I I I I -1

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.I I I li I i 1. I i 1 <l F: Forced Peason: Method: '* Exhibit G-Instructions S Schedsled 'A-Equipment Failure (Explain) 1-Macual for Preparation of Dsta B-Maintenav e or Tes: 2-Mamal Scraa. Entry Sheets for Licensee C-aafueling 3-Automatic scrza. Event Report (UER) File (NUREG-0-ftegalatory Restriction .. 44Rher (Explain) 0161)

E4M:erator Training 6 License Examination S

F-Admin 4.strdive' Exhibit 1 -c m source

' G-operational' Ettor (Explain)

(9/77) H-other.(Itplain)- 3

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JOSEPli H. FARLEY NUCLEAR PLANT UNIT 2 NARRATIVL

SUMMARY

OF OPERATIONS October, 1992 At 0023 on 10-20-92, while operating at 65 percent power, the Unit 2 reactor was manually tripped due to" reduced feedvater flow leading to low levels in all SGs. The reduced feedvater flow was caused by a loss of~ condenser hotvell

, level Lt a rate beyond its make-up capability. The loss of condenser hotwell level vas caused by the inadvertent isolation of one sectJon of condenser cooling water in conjunction with the intent.ional isolation of one section of condenser cooling vater. The loss of cooling caused hotwell temperature to -

increase resulting in saturation and loss of level. The lov hotvell 3evel caused the condensate pumps to cavitate resulting in a loss of steam generator feedvater puup (SGFP) suction pressure which, in turn, led to rsiuced feedvater flow te all SGc.

i The unit vaa tied to the grid at 1813 on 10-21-92 and reached 56 percent power l at 1026 on 10-22-92. At 1440 on 10-22-92, ramp down to 15 percent was g initiated due to suspected main condenser tube leaks. The ramp down to 15 percent was completed at 2129 on 10-22-92. Three leaking tubes were g ideatified in the AB section of the A main condenser. The three leaking tubes and twelve surrounding tubes were plugged. The unit returned to 100 percent pover at 0916 on 10-24-92.

There were no other unit shutdowns or major power r~ eductions during the month of October.

The following major safety-related malatenance was performed during the month:

1. Miscellaneous corrective and preventive maintenance was performed _

on the diesel generators.

2. Replaced tube bundle in 600 volt motor ;onttal center 2A room cooler.

J. Performed various design changes on the reactor make-up water system,

4. Plugged 15 tubes in the AB section of the A main condenser.

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l OPERATING DATA REPORT '

DOCKET NO. 50-364 DATE ~fEvember 4, 1992 COMPLBTED BY R. D. Hill TELEPHONE (205)899-57 56 -

OPERATING STATUS Notes

1. Unit Name: Joseph H. Farley - Unit 2

~~ 1) Cumulative data since

2. Reporting Period: Octobe'r 1992 7-30-81, date of-

3. Licensed Thermal Power (HVt): 2,652 commercial operation.

4. Nameplate Rating (Gross HVe): ~~

860

5. Design Electrical Rating (Net MVe): 829

6. Maximum Dependable Capacity (Gross MVe): 864.3

7. Maximum Dependable Capacity (Net HVe): 824.0

8. If Changes occur in capacity Ratings (Items Number ? Through~7T ~ Circe L.st Report, Give Reasons: N/A

9. Power Level-To Vhich Restricted, If Any (Net MVe): N/A

10. Reasons For Restrictiot.s, If Any: N/A This Month Yr-to-Date Curulative

11. Hours In Reporting Period 745.0 7,320.0 98,689.0

12. Number Of Hours Reactor Vas Critical 724.4 5,693.6 84,557.9:

13. Reactor Reserve Shutdown Hours 0.0 0.0 138.0

14. Hours Generator On-Line 703.2 5,524.2

~

83,452.7

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (HVH) 1,742,799.0 ~TI~729,514.7 212,688,836.3

17. Grosr Electrical Energy Generated (HVH) 565,8857D~~ 4,451,120.0- 69,747,204.0

18. Net Electrical Energy Generated (HVH) 535,715.0 4,200,068.C 66,134,130.'U

19. Unit Service Factor 94.4 '5.5 -8476

20. Unit Availability Factor 94.4 75.5 EITE

'21. Unit Capacity Factor (Using HDC Net) 87.3 69.6 81.7

22. Unit Capacity Factor (Using DER Net) 86.7 69.2 80.8-23.-Unit Forced Outage Rate 5.6 3.5 4.1

24. Shutdowns Schedulcd Over Next 6 Honths (Type, Dato, and Duration of Each):.

N/A

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

26. Units In Test Status (Prior to Commercial Operation): Forecas't Achieved INITIAL CRITICALITY 05/06/81 05/08/81 INITIAL ELECTRICITY 05/24/81 -05/25/81 C0HMERCIAL OPERATION' 08/01/81 '7/30/81 i

Form 4/30

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, i DOCKET'NO. 50-364-UNIT 2

-DATE_Npvember 6, 1992 COMPLETED BY R.-D. Hill TELEPHONE (205)B99-5156-i

- H0hTil October DAY AVERAGE DAILY POVER LEVEL DAY AVERAGE DAILY POVER LEVEL (MVe-Net) (MVe-Net) 1 822 17 818 2 820 18 777 3 15 19 807-4 815 20 0 5 818 21 A 6- 821 22- 268 7 818 23 74 8 815 24 753 9 815 25 852 -

.30 CP0' _

-26 820 ~

- 11 -818 27 815 12 824 28- 85

- 13 821 _

29 -816 14 819- 30- ,

815 15' 819 31- 817 ,

- 1!6 818 L

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the-reporting month.- Compute to the nearest whole megawatt, a

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