ML20086K011

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Monthly Operating Repts for June 1995 for Jm Farley Plant Units 1 & 2
ML20086K011
Person / Time
Site: Farley  Southern Nuclear icon.png
Issue date: 06/30/1995
From: Allison S, Dennis Morey
SOUTHERN NUCLEAR OPERATING CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9507190327
Download: ML20086K011 (11)
v • d • e


Text

Southun Nuclear Opvating Company

. Post Offee Box 1295

. 8:rmingham. Alabama 35201 Telephone (205) 868-513 t mk o.ve uorey Southern Nudcar Operating Company "

Vr.e Pres dent Fa*ey Project the southem +9/eCf 0C System July 11, 1995 Docket Nos. 50-348 50-364 U. S. Nuclear Regubtory Commission ATTN: Document Control Desk Washington, D.C. 20555 Joseph M. Farley Nuclear Plant Monthly Operating Data Reoort Gentlemen:

Attached are the June 1995 Monthly Operating Reports for Joseph M. Farley Nuclear Plant Units I and 2, as required by Section 6 9.1.10 of the Technical Specifications.

If you have any questions, please advise.

Respectfully submitted, g #l Jhy,< -

t' Dave Morey RWC:jgp(mor)

Attachments cc: Mr. S. D. Ebneter Mr. B. L. Siegel Mr. T. M. Ross a,

"A o

I f t f 's #

f I 9507190327 950630 l PDR ADOCK 05000348 'k.

R PDR j j i

4 Joseph M. Farley Nuclear Plant Unit i Narrative Summary of Operations June 1995 At 2139 on June i 1,1995, with the Unit I reactor in mode 1, operating at 100 percent pewer, the reactor tripped due to a turbine trip in response to a spurious main steam line isolation valve (MSIV) closure. The unit was synchronized to the grid at 2315 on June 17,1995.

The following safety related maintenance was performed during the month:

1. Following the June 11,1995, reactor trip, the unit was cooled down to mode 5 for an inspection of MSIV 3370C. No damage to MSIV 3370C was evident.

l l

1 p,.,-- - - - - -

i '. l 1

OPERATING DATA REPORT DOCKET NO. 50-348 DATE July 7,1995

, COMPLETED BY S. M. Allison

, TELEPilONE (334) 899-5156 cxt. 3442 j l

OPERATING STATUS

1. Unit Name: ,Ioseph M. Farley - Unit i Notes
2. Reporting Period: June 1995 1) Cumulative data since 12-01-77,
3. Licensed Thermal Power (MWt): 2,652 date of commercial operation.
4. Nameplate Rating (Gross MWe): 860
5. Design Electrical Rating (Net MWe): 829
6. Maximum Dependable Capacity (Gross MWe): 855.7
7. Maximum Dependable Capacity (Net MWe): 812 .
8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since l Last Report, Give Reasons: N/A l
9. Power LeveFlo Which Restricted, if Any (Net MWe): N/A l
10. Reasons For Restrictions,If Any: N/A l l

l This Month Yr. to Date Cumulative i1. Ilours in Reporting Period 720.0 4,343.0 154,103.0

12. Number ofIlours Reactor Was Critical 590.4 4,123.1 123,379.9
13. Reactor Reserve Shutdown Hours , 0.0 0.0 3,650.0
14. Ilours Generator On-line 574.4 4,087.3 121,541.2
15. Unit Reserve Shutdown Ilours 0.0 0.0 0.0
16. Gross Thermal Energy Generated (MWH) 1,432,289.5 10,718,918.2 312,854,635.2 l'i Gross Electrical Energy Generated (MWH) _461,977.0 3,513,320.0 100,927,025.0 l
18. Net Electrical Energy Generated (MWH) 432,843.0_ 3,329,628.0 95,329,617.0

)

19. Unit Service Factor 70.8 94.1 78.9 1
20. Unit AvailaMCty Factor 79.8 94.1 78.9 )
21. Unit Capacity Factor (Using MDC Net) _

74.0 94.4 75.9 '

22. Unit Capacity Factor (Using DER Net) 72.5_ 92.5 74.6
23. Unit Forced Outage Rate 20.2 5.9 6.0
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

lhfheling/ Maintenance Outage, September 16, I995. Approxiriately 33 days.

25. If Shut Down a End Of Repon Period, Estimated Date of Startup: N/A
26. Units in Test Stitus (Prior To Commercial Ort,ation): Forecast 4.chieved initia! Criticality 08/06/77 08/09/77 Ini.ial Electricity 08/20/77 08/l8/77  ;

Ct.mmercial Operation 12/01/77 12/01/77 l

. uGCKET NO. 50-348 UNIT 1 DATE July 7,1995 COMPLETED BY S. M. Allison TELEPilONEJ334) 899-5156 ext. 3442 MONTII June DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LE'7EL (MWe-Net) (MWe-Net)

I _ _ __ _

818 __

17 0 2 _ _ . _ _ _ . _ _ _ _ 815 _ 18 289 3 816 19 335 4 817 20 561 5 818 21 818 6 817 22 819 7 _ __ __ .__8 l _4_ _ _ _ _ . _

23 817 8 813 24 814 9 813 25 815 10 __ _ 814 __

26 81_4 _

11 __

__..________7_33___ _ __ _ _ 27 _

816 12 0 28 816 13 0 29 817 14 0 30 816 15 .

0 31 NA 16 0 INSTRUCTIONS On this fonnat, list the average daily unit power level in MWe-Net for each day in the reporting period. Compute to the nearest whole megawatt.

~~

UNIT SIIUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-348 - -

UNIT NAME J. M. Farley - Unit I .

DATE July 7,1995 COMPLETED BY S. M. Allison REPORT MONTil June TELEPIIONE (334) 899-5156, ext. 3442 7 _ _ _ . _ _ , . _ _ _ _ _ _ _ _ , _ _ _ . _ _ .

I l NfETilOD OF LICEMEE CAUSE ANDCORRECTIVE i DURATION S!!UT11NG EVENT SYSTEM COMPONENT ACTION TO t NO DATE TYPE (lj IIOURS REANON (2(IX)WN R_EACTOR ()). RLPORT # CODE 14) COI)Eg] P_REVENT RECURRENCE g l 003'950611 F 145.6 II l 3 '95-005-0T sir ! isy 'At :139. on 9506i i. w ith unit i in mode i. operating at ico 3

l percent power, the reactor tripped due to a turbine trip in i

response to a spurious main steam line isolation valve (MSIV) closure. The MSIV closure was attributed to I

j water intrusion into a junction box. Cause and corrective j , actions are discussed in detail in the referenced LER.

The unit was synchronized to the grid at 2315 on 950617.

i

! i i 2 1: 2: 3: O 5:

F: Forced Reason Method Exhibit G- Instructions for Exhibit I - Same Source S. Scheduled A - Equipment failure (Explain) 1 - Manual Preparations of Date Fntry D - Maintenance or Test 2 - Manual Scram sheets for Licensee Event C - Refueling 3 - Automatic Scram Report (LER) File (NURFG-016l)

D - Regulatory Restriction 4 - Other (Explain)

E - Operator Training & License Examination F - Administrative G - Operational Error (Explain) iI - Other (Explain) e

. l Joseph M. Farley Nuclear Plant Unit 2 Narrative Summary of Operations June 1995 There was no major safety related maintenance performed during the month.

At 0058 on June 1,1995, with the Unit 2 reactor in mode 1, operating at approximately 30 percent power, the reactor was manually tripped following the loss of the operating (2A) steam generator feed pump (SGFP). The loss of the SGFP was caused by a failed electro-hydraulic (Ell) fluid supply line and subsequent loss of EH fluid.

'Ik fath re was in the heat affected zone of the tubing-to-fitting socket weld on the EH supply to the high pressure governor valve to the 2A SGFP. The unit was synchronized to grid at 1912 on June 2,1995.

Imdallv, she June 1,1995, event was attributed to cyclic fatigue (pending the results of meciturgical analysis) caused by a loose support clamp, and higher than normal l vibrations, which are associated with feed pump operations at low power. The EH l tubing and support ciamp were repaired, and the failed tubing was sent off site for detailed failure analysis. Subsequently, at 0948 on June 3,1995, with the reactor in r.iode 1, operating at approximately 33 percent power, the reactor was manually tripped following the loss of the operating (2A) SGFP caused by a failed EH fluid supply line on the 2A SGFP and subsequent loss of EH fluid. The unit was synchronized to the grid at 1515 on June 5,1995.

Examination of the failed tubing revealed that the failures experienced on June 1, 1995 and June 3,199F were sudden impact failures caused by servovalve failures, which resulted in mechaical and hydraulic oscillations in the EH system. j l

At 2000 on June 10,1995, with the Unit 2 reactor in mode 1, operating at approximately 64 percent power, reactor power was decreased to 15 percent power for steam generator clean-up. At 0300 on June 11,1995, with the Unit in mode 1, operating at approximately 15 percent power, the 2B SGFP high pressure stop valve closed, which caused the SGFP speed to decrease. Subsequently, the main turbine was removed from the grid and reactor power was decreased to 1.4 percent power. The unit was synchronized to the grid at 1508 on June 12,1995.

1 At 2102 on June 21,1995, with the unit in mode 1, operating at 100 percent power, the unit ,

was ramped to approximately 60 percent power due to 2B SGFP low pressure l governor valve oscillations. The 2B SGFP EH servovalves were replaced.

At 1640 on June 25,1995, with the Unit 2 reactor in mode 1, operating at approximately 63 percent power, the reactor tripped due to a turbine trip caused by 2C steam generator water level scaching the Ili-Hi setpoint of 79 percent. The unit was synchronized to the grid at 0525 on June 29,1995.

OPERATING DATA REPORT DOCKET NO. 50-364 DATE July 7,1995

. W COMPLETED BY S. M. Allison TELEPilONE _(334) 899-5156 )

ext.3442 OPERATING 3TATUS

1. Unit Name: . Joseph M. Farley - Unit 2 I Notes
2. Reporting Period: June 1995 1) Cumulative data since 07-30-81,
3. Licensed Thermal Power (MWt)- '652

, date of commercial operation. ,

l

4. Nameplate Rating (Gross MWe): 860
5. Design Electrical Rating (Net MWe): 829
6. Maximum Dependable Capacity (Gross MWe): 863.6
7. Maximum Dependable Capacity (Net MWe): .

822

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 This Month Yr. to Date Cumulative
11. Ilours in Reporting Period 720.0 4,343.0 122,016.0
12. Number OfIlours Reactor Was Critical 641.0 2,890.0 104,547.7
13. Reactor Reserve Shutdown llours 0.0 0.0 138.0
14. Ilours Generator On-line 503.5 2,662.2 102,884.8
15. Unit Reserve Shutdown Ilours 0.0 0.0 0.0
16. Gross Thermal Energy Generated (MWil) 880,007.9 5,474,786.9 261,814,492.6
17. Gross Electrical Energy Generated (MWil) 266,973.0 1,754,944.0 85,809,486.0
18. Net Electrical Energy Generated (MWil) 239.327.0 1,618,738.0 81,341,036.0
19. Unit Service Factor 69.9 61.2 84.3
20. Unit Availability Factor 69.9 61.3 84.3
21. Unit Capacity Factor (Using MDC Net) 40.4 45.3 81.3
22. Unit Capacity Factor (Using DER Net) 40.1 45.0 80.4
23. Unit Forced Outage Rate 30.1 7.5 4.1
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Dure w.r. of Each):

N/A

25. If Shut Down at End Of Report 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 05/24/81 05/25/81 Commercial Operation 08/01/81 07/30/81 I

I

. DOCKET NO. 50-364 UNIT 2 DATE July 7,1995  !

COMPLETED BY S. M. Allison l TELEPIIONE (334) 899-5156 ext. 3442 MONTIl June DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 0 17 815 I 2 __ _

2 18 827 3 53 19 828 4 _

0 20 828 5 36 21 789 6 ,..__ _ _ _ 209 22 470 l 7 __ __ _ _ 372 23 462 8 459 24 460 9 444 25 307 10 _ _ _ _

473 26 0 11

______._0_______ 27 _

0 12 0 28 0 13 67 29 12 14 397 30 323 15 _ _ _ _ _ _ _727 _ ___ _ _ _ 31 NA 16 306 INSTRI'CTIONS On this format, list the average daily unit power level in MWe-Net !br each day in the reporting period. Compute to the nearest whole megawatt.

3 UNIT SliUTDOWNS AND POWER REDUCflONS ,

1 DOCKET NO. 50-364 - - -

UNIT NAME J. M. Farley - Unit 2 DATE July 7,1995 COMPLETED BY S. M. Allison REPORT MONTil . lune TELEPIIONE (334) 899-5156, ext. 3442 1 i  ;  ; , MEHIOD OF l LICENSEE CAUSE AND CORRFCTIVE

l.  !. Dt: RATION i, SlitITitNG f EVENT SYSTEM COMPONENT ACUON TO l!

e l! NO DATE TYPF(iyi not:Rs ! REAM)N (2) tX)WN REACTOR O[ RTPORT # . CODE 14) CODI (5) i PREVENT RFCt!RRENCE j F i 42.2 A  ; 2 ~ ]95-005-0 l SJ XXXXXX j At 0058 on 950601, with the unit in mode 1, ogwa:ing at l[005 r950601 l  !

h j f l I l !approximately 30 percent power, the rmctor was manually

' tripped following the loss of the opcating (2A) steam

{ l  !

j j j j  ! generator feed pump (SGFP). The loss of the SGFP was i i  !

! caused by a failed electro-hydraulic (Ell) fluid supply line and I

l i subsequent loss of Ell fluid. Cause and corrective actions f

are discussed in detail in the referenced LER. lhe unit was

! synchronized to the grid at 1912 on 950602.

i f .

006 950603 F 53.5 A 2 95-005-0 SJ l XXXXXX l At 0948 on 950603, with the unit in mode 1, operating at

i approximately 33 percent power, the reactor was manually j tripped following the loss of the operating (2A) SGFP caused by a failed Ell fluid supply line on the 2A SGFP and subsequent loss of Ell fluid. The cause and corrective j actions are discussed in detail in the referenced LER.

l , l The unit was synchronized to the crid at 1515 on 950605. ,

1: 2- 3. 4- 5:

F: Forced Reason Method Exhibit G- Instructions for Exhibit I - Same Source S: Scheduled A - Equipment Failure (Explain) 1 - Manual Preparations of Date Entry 11 - Maintenance or Test 2 - Manual Scram Sheets for Licensee Esent C - Refueling 3 - Automatic Scram Report (LER) File (NUREG-0161)

D - Regulatory Restriction 4 - Other (Explain)

E - Operator Training & License Examination F - Administratise G - Operational Error (Explain) 11 - Other (Explain)

UNIT SIIUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-364 UNIT NAME J. M. Farley - Unit 2 DATE Julv7.1995 COMPLETED BY ~

S. M. Allison REPORT MONT11 June TELEPHONE (334) 899-5156, er. 3442 l

y DURATION j SilUTTING EVENT SYSTEM COMPONENT ACTION TO h

{

b NO DATE IWPE (1)I FLOURS lRFANON (2) DOWN REAC10R (3)REPORT # CODEJ4)_ L_ CODE (5) PREVENT RfCURRI'NCF f i007 950610l S i 0.0 .

11 j 4 N/A AB SG I At 2000 on 950610, with the unit in mode 1, operating at j

i l l rapproximately 64 percent power, the reactor was

! l i I f decreased to 15 percent power for steam generator clean l l ,

p l up.

i W008 950611 F 36.1 A 4 N/A SJ SilV At 0300 on 950611, with the unit in mode 1, operating at  ;

j i approximately 15 percent power, the 2B steam generator l

feed pump (SGFP) high pressure stop valve closed, which  !

! caused the SGFP speed to decrease. Subsequently, the l' t main turbine was removed from the grid and reactor pow er l was decreased to 1.4 percent power. The high pressure stop valve closure was attributed to a failed solenoid valve, which was replaced. The unit was synchronized to the grid at 1508 on 950612.

G$ . L 3:

4: 5:

O 1: 2:

I - Forced Reason Method Exhibit G- Instructions for Exhibit ! - Same Source S: Scheduled A - Equipment Failure (Explain) 1 - Manual Preparations of Date Entry B - Mamtenance or Test 2 - Manual Scram Sheets for Licensee Esent C - Refueling 3 - Automatic Scram Report (LER) File (NUREG.0161)

D - Regulatory Restriction 4 - Other (Explain)

E - Operator Training & License Examination F - Administrative G - Operational Error (Fxplain)

Il - Other (Explain)

UNIT SIIUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-3M - '

UNIT NAh1E J. N1. Far:ey - Unit 2 ,

DATE July 7,1995 CON 1PLETED BY S. N1. Allison REPORT N10NTil June TELEPilONE (334) S99-5156, ext. 3442 s- _ . _ _ _ _ , _ _

} l l l 3 N1ETilOD OF l LICENSIE f CAUSE ANDCORRECTIVE ,j, l

4 Dt: RATION '- SilUTTING EVENT SYSTEN! CON!PONENT ACTION TO i 3

l NO ! DATL f1VPF (l)l IlOURS !RI ASON (2)'DOWN RI ACTOR (3)j RFPORT # _ col}E(4) " CODE.15)  ! PREVENT RFCURRENCE i; l 009 [950621 ' F O.0 ,

A l 4 l N/A SJ SCV  ! At 2102 on 950621, with the unit in mode 1. operating at 100

}  ! l l l  ! percent power, the unit was ramped to approximately 60 l percent power due to 2B SGFP low pressure gosernor

]h

[

f i j i l lI

! valve oscillations. The 2B SGFP Eli senovalves were

] { j

! l l , replaced.

')

h l l l l h 010 950625 F  ! 84.7 i G 3 95-007-0 AB SG At 1640 on 950625, with the Unit in mode 1, operating at l  : l l approximately 63 percent power, the reactor tripped due to ,

l f a turbine trip caused by the 2C steam generator water level l l

ld' l reaching the Ili-Ili setpoint of 79 percent. This occurred l

! , .during the evolution of transferring feedwater flow from the

{ 1 i l(2A) operating SGFP to the 2B SGFP. The cause and

i i l
corrective actions are discussed in detail in the referenced h l l LER. The unit was synchronized to the grid at 0525 on !q i l 950629. l lj_ _ _ _ m ' ,

1: 2: 3: 4: 5:

F Iorced Reason hiethod Exhibit G- Instructions for Edibit I - Same Source S. Scheduled A - Equipment I ailure (Explain) 1 - N1anual Preparations ofI) ate EMtrs II - hiaintenance er Test 2 - Ntanual Scram Sheets for Licensee Esent C - Refueling 3 - Automatic Scram Report (LER) File (NUREG-0161)

D - Regulatory Restriction 4 - Other (Explain)

E - Operator Training & License lNamination F- Administrative G - Operational Error (Explain) 11 -(kher (Explain)

. _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . .___w

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