Text

Monthly Operating Rept for May 1992 for Jm Farley Unit 2
	ML20101E405
Person / Time
Site:	Farley
Issue date:	05/31/1992
From:	Hill R; SOUTHERN NUCLEAR OPERATING CO.
To:	;
Shared Package
ML20101E395	List: ML20101E394; ML20101E405; ML20101E409;
References
	NUDOCS 9206230188
	Download: ML20101E405 (8)
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._.

i JOSEPH M. FARIEY NUCLEAR PLANT UNIT 2 MARRATIVE

SUMMARY

OF OPERATIONS May,.1992 The cycle 8-9 refueling outage continued through the month of May.

Power operation began at 0652 on 5-12-92.

The generator was taken off line at 1050 on 5-14-92 to perform a turbine overspeed trip test. The unit returned to povet operation at 0211 on 5-15-92.

The reactor remained crit-leal during the test.

There vere sour reactor trips during the montn of May.

At 1331 on 5-12-92, with the up*'

in mode 1 operating at 12 percent power, the L

reactor tripped due to lov vater level in the 2C steam generator coincident with l.

a feedvater flow less than steam flov signal. The unit returned to power operation at 0822 on 5-14-92.

On 5-15-92 at 2004, while operating at 35 percent power the reactor tripped on a lc power range high flux signal due to control power fuses blowing and the subsequent loss of control pover to power range nuclear instruments NI-41 and NI-43.

The nnit returned to power operation at 1743 on 5-16-92.

.At 0545 on 5-25-92. While operating at 100% power the reactor was manually tripped due to the loss of 2A steam generator fecd pump (SGFP). The unit

. returned co pover operation at 0549 on 5-26-92.

At 1818 on 5-26-92, while operating at 45 percent power, a negative flux rate reactor trip occurred due to the de-energization of the rod centrol power cabinet IED stationary gripper coils. The unit was returned to power operation at 0132 on 5-28-92.

For the remainder of the month the unit was at approximately 58% power dus to tt:e monitoring of the 2A SGFP.

The tollowing major safety-selated maintenance vas performed during the month of Pays p

1. Rodded out and cleaned the service water side of 2A, 2B, 2C and 7D containment cooler.

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1. Completed hydrotest of 2A and 2B contaiament spray system, i,

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3. Performed various corrective and preventive maintenance on the post accident hydrogen analyzers.

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4. Replaced actuator cylindecs on various MSIVs.

5. Performed STP-608.1 " Main Steam Line Safety Valve Test" on the main f

steam line safety valves.

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15. _ Performed various corrective. maintenance on the auxiliary feedvater -

pumps.

7. Performed corrective maintenance and testing on the containment y

purge dampers.

8. Inspected-various service vater pump discharge check valves.

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9. Performed Local Leak Rate Testing (LLRT) on s the cor.tainment personnel and auxiliary hatches.

10. Miscellaneous corrective and preventive maintenance vas performed on the diesel generators.

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,m 4 9 OPERATING DATA REPORT DOCKET No. 50-364 DATE June 8, 1992 COMPLETED BY R. D. Hill TELEPHONE (205)899-5156 OPERATING ETATUS Notes

.1. Unit Name:

Joseph M. Farley - Unit 2

1) Cumulative data since

2. Reporting' Period

~~May 1997 7-30-81, date of 3.'Licenced Thermal Power (HWtJ:

2,652 commercial operation.

4. Nameplate Rating-(Gross MVe):

850

5. Design Electrical Rating (Net MVe):

829

6. _ Maximum Dependable Capacity :(Gross MWe):

864.3

'7.

Maximum Dependable Capacity (Net MVe):

824.0

8. It Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons: N/A 9 Power Level To Whi!E Restricted,-If Any (Net MVe):

N/A

~~

-10. Reasons For Restrictions, If Any:

N/A L

t This Month Yr-to-Date Cumulative

11. Hours In' Reporting Per'od 744.0 3,647.0 95,016.0 32..Numoer Of-Hours Rteactor Vas Critical 476.1 2,041.2 80,905.5

13. Reactor Reserve Shutdown Hours 0.0 0.0 138.0

14. Hours Generator On-Line 346.9 1,893.0 79,821.5

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MVH) 513,303.9 4,579.532.2 203.538,853.8

17. Grass Electrical Energy Generated (MVH) 153,454.0 1,493,22176 66,789,306.0

18. Net Electrical Energy Generated (MUH) 128,290.0 1,393,444.0 63,327,506.0

19. Unit Service Factor 46.6 51.9 84.0 20.LUnit Availability Factor 46.6 51.9 84.0 L21._ Unit Capacity Factor (Using MDC Net) 20.9 46.4 81.3 22.; Unit-Capacity Factor (Using DER Net) 20.8 46.1 80.4

23. Unit Forced Outage Rate 25.'

7.6 4.2

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

N/A

~

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

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

Forecast Achiev53' p

INITIAL CRITICALITY 05/06/81 05/08/81 INITIAL ELECTRICITY 05/24/81 05/25/81 COMMERCIAL OPERATION 08/01/81 07/30/81 l-Form 2/30 l

-? '

. DOCKET NO.

50-364 UNIT 2_

DATE June 8, 1992 COMPLETED BY R. D. Hill TELEPHONE (205)899-5156 MONTH' May1

-DAY AVERAGE DAILY POVER LEVEL DAY

' AVERAGE DAILY POVER LEVEL (MVe-Uet)

(MVe-Net)

-- 1 0

17 167 2

0-18 183 3

0 19 270 4:

0 20 359 5

0=

21 571

6-0 22 651

'7 0 _ _

23 761 8

0 24 805 9

0 25 168 10.;

O 26 54 11 0 --

27 0

12 0

28 296 13 O

29 449 14-9 30 440 15 83 31 448 16 0

INSTRUCTIONS On this format, list the average daily unit power level in MVe-Net for each-day in

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

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11 NIT SIRRTIMNS MD POWE2 REECITIONS DOCEET m.

l50-304 IIIIT NVIE J. M. FARIZT - tMIT 3 '

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June 8, 19D2 C[PG'IETED ST R. D. HILL REPORT M3fTH MAI TEIKFtmE (205)S99-5156 I

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N/A lN/A l N/A l h Cycle S-9 Refueling continued from 7-6-92.

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l Power operation began at 0652 >n 5-12-92.

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l004 l920512 l T l

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3 l 92-005-40 l AB ' l N/A l At 1331 on 5-12-92, with the unit in sm>de 1 l

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jeperating at 12 peront power, the reactor trigged l l

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jdue te low water level in the 2C steam generator l

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l l coincident with a feedwater flow less than steam l

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l lflowsignal. h low level in c.he steam generator l l

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loccurredbec*weofaplanttransientinducedfroml l

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la main generator trip that occurred at 1243 on l

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i 15-12-92.

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l lThis event u caused by personnel er or in that l

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l lthe control room crew did not dampen J eam l

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l generator lent oscillations. A critique was l

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l l con &cted with the Shift Supervisor and Plant l

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l l Operator m drty at the time of the trip.

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lOpertrors.

ta reir.structed e options availat-:=

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lwhen steam generator level cwitrol cannot be l

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l lmaintainedinautomatic. The unit returned to l

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l l power operation at 0822 on 5-14-92.

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N/A N/A l N/A l

N/A lThegenerato? was taken off line for a turbine l

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l loverspeed trip test. The reactor remained critica1l l

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larinsthetest.

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F: Forced Reason:

Method; Exhibit G-Instructions S Scheduled A-Equireent Failure (Explain) 1-Manual for Preparation of Data B-Maintenance er Test 2-E?snual Scras Entry Sheets for Licensee

?

C-Refueling 3-Automatic Scram.

Event Report (12R) File OPJREG-D.-Regulatory Restriction 4-Other (Explain) 0161)

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

( 9/'4 7 )

H-Other (Explain).

Page 1

a tmT Samown anD nowER REIcenms m:EET m.

So-r4 WIT NAME J. M. FARIKT - tMIT 2 mrE aune 8 Im2 C2TLETED BT R. D. FTIL REPORT MMIN MAY TE1ZPHOttE (2051899 5156 1

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N/A Ls'n 5-15-92 at 2004, while operating at 35 percent l l006 l920515 l

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l jflumsignalduetocontrolpowerfusesblowingandl l

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lthe subsequent loss of control power to power range l A

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lnuclearinstrumentsNI-41andNI-43.

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l l surveillance test procedure was in progress at the l

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ltimeofthetripwithdigitalvoltmetersconnectedl l

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lto all four pcwor range NI drawers. The use of l

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la 60 herts signal to be superimposed at thenormall l

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lDCsignalfromthepowerrangedetectorsinthe l

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l lNuclearInstrumentationSystem. Because the plant l l

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lpowerlevel(35%)vssatapowerpermissive l

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l lsetpoint, the superiaposed signal caused the l

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j lbistablesiliconcontrolrectifiersto l

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l jrapidlyturnonandoff. This cycling action l

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lcausedincreasedcurrentthroughthecontrolpowerl l

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l l fuses of the power range NIs. The high current l

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lcausedthecontrolpowerfusestobeatupand

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l lsubseg.tently blow on NI-41 and NI-43.

The test l

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lbe connected to only one powe range drawer at a l

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l l time. Furtherere, the proce.12re was revised to l

Exhibit G-Instructio6 Method:

F: Forced Reason:

S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data 2-ttanual Scram.

Entry Sheet s for I.icensee 84%sintenance or Test 3-Autoastic S"rha.

Event Report (LER) File (NUREG-C-Refueling D-Regalatory Restriction 4-Other (Explain) 0161)

E~ operator Training & License Examination Exhibit I -Same Source F-Administrative G-operational Error (Explain)

(9/77)

H W.or (Explain)

Page 2

tsIT SHtmpetS AND POWE1. LEDGCTIONS-DCtIET m.

'50-364 tK2IT NAME J. M. FARIET - IN2T 2 IATE ' June 8, 1992 CEPTIJ.TED BY

' R. D. HIII REPCRT NTTE MAY TELEPHONE

'(205)S99-5156 I

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ACTI N TO

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l 006 (con't) l

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l require the use of shielded leads for connecting.l l

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l test instrumentation to prevent irdaced voltages l

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l lfromaffectingNISperformance. All control l

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l lpo m r fuses for the four power range NIs were l

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l l replaced. We unit returned to power operation at l 6

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i 11743 on 5-16-92.

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N/A lAt0545on5-25-92,whileoperatingat100 percent l l

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l l power,thereactorwasmanuallytripped<ksetothel l

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l loss of the 2A steam generator feed pump (SGFP).

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lThe2ASGFPtrippedduetolowautostopoil l

l l

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l l pressure. S e low auto stop oil pressure was l

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l lcausedbydegradationofthelubeoilpumpsand l

l l

l j

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l l excessive water in the lube oil system for the 2A l l

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lSGFP. The 2A SGFP lube oil was drained dad the oil l l

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l l sung was c] wned. The lube oil pumps were l

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!overhauledandreinstalled. Weunitwasreturnedl l

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lto power operation et 0549 on 5-26-92.

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l 008 l 920526 l

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31.2 l

G j

3 l92-003-00l AA l

N/A lAt1818on5-26-92,whileoperatingat45 pere.ent l l

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l power, a negative fluz rate reactor trip occurred l l

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ldue to the de-energization of the rod control power l i

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l lcabinetIBDstationarygrippercoils. his event l l

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Iwu.:aused by per=-1 error in that the 1

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-l l individual mistakenly opened the disconn ct which l l

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lsuppliedpowertothe1BDstationarygrippercoils.l F: Forced Reason:

Method:

Exhibit G.-Instructious l

S: Scheduled A-Equipment Failure (Esplain) 1-Manual for Prvaratice of Data B-Maintenance or Teit 2-Manual Scram.

Entry Sheets for Licensee C-Refuelf r.!!

3-Automatic Scram.

Event Report (i.ER) File (NUREG-D-Regulatic' Restriction 4-Other (Explain) 0161)

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

(9/77)

HHXher (Explain)

Page 3 i

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m--,;

TNT 4 SHirfDOWits AND PMER REDUCTIONS DocxET too.

50-364 UNC NAfE J. M. FARLEY - TRIT 3 DATE

'.hnw 8, 199 2 N BY R. D. RIII REPORT MDerfH mar TEID904E (205)899-5156 s

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cause a cDamEcrnE I

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IcuaArrow I I swrrim iEmr-I SrSm I cama:rr i AcTuw To i

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l008(c<.,n't) l l

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l lTheindividualsirvolvedinthiseventhavebeen l

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l coached. Theunitwasreturnedtopoweroperationl l

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lat 0132 on 5-2S-92.

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lror the renautder of the month the unit was at l

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lapproximately58%powerduetothemonitoringof l

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F: F;<ced Reason:

Method:

Ezhibit G-Instructions S: Scheduled A-Equipmer't Failure (Explain) 1-%nual for Preparation of Data S-Maintenance or Test 2-Manual Scram.

Entry sheets for 1.icense.

C-Refueling 3-Automatic Scram, Event Report (123t) File (NUREG-D-Regulatory Restriction 4-Other (Explain) 0161)

E-Operator Training & I.icense Examination F-Administrative Exhibit I -Same source G-Orsrational Error (Explain)

(9/77) ff4h her (Explain)

Page 4

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ML20101E405

Text

SUMMARY

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