ML20129G852

Monthly Operating Rept for Mar 1985

ML20129G852
Person / Time
Site:	Farley
Issue date:	03/31/1985
From:	Mcdonald R, Woodard J ALABAMA POWER CO.
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8506070385
Download: ML20129G852 (11)

Text

,

1 OPERATING DATA REPORT 50-364 DOCKET NO.

DATE April 4, 1985 COMPLETED BY J. D. Woodard 4

TELEPHONE (205) 899-5156 OPERATING STATUS Notes

1. Unit Name:

J seph M. Farlev - Unit 2 March, 1985

1) Cuiculative data since

2. Reporting Permd:

2652 7-30-81, date of

3. IJcensed Thermal Power (MWt):

860 comercial operation.

]

4. Nameplate Rating (Gross MWe):

829

5. Demen Electncal Rating (Net MWe):

850.2

6. Maximum Dependable Capacity (Gross MWe):

i

7. Maximum Dependable Capacity (Net MWe):

an77

8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:

N/A 4

9. Power Level To Which Restricted,If Any (Net MWe):

N/A N/A i

10. Reason: For Restrictions. If Any:

4

^b O

~

This Month Yr. to Date Cumulative 744 2,160 32,185

}

11. Hours in Reporting Period 284.6 380.8 27,299.3 I

12. Number Of Hours Reactor Was Critical 138.0

13. Reactor Reserve Shutdown Hours n.n 0.0

14. Hours Generator On-Line 240.0 336.0 26,914.1 l

1

15. Unit Reserve Shutdown Hours 0.0

.0.0 0.0 368,968 608,441 67.461,189 l

16. Grom Thermal Energy Generated (MWH) 114,634 192,182 22,138,464

17. Gross Electncal Energy Generated (MWH) l

18. Net Electncel Energy Generated (MWH) 89,028 154,478 20,973,400 32.3 15.6 83.6 6

[9. Unit Service Factor 32.3 15.6 83.6

20. Unit Availability Factor l

21. Unit Capacity Factor (Using MDC Net) 14.8 8.9 80.4

22. Unit Capacity Factor (Using DER Net) la_a 8.6 78,6

23. Unic Forced Outage Rate 10.6 78 5.5

24. Shutdowns Scheduled Over Next 6 Months (Type. Date. and Duration of Eachi:

N/A T

N/A

25. If Shut Down At End Of Report Period. Estimated Date of Startup:

3

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

Forecast Achieved l

INITIAL CRITICALITY 05-06-81 05-08-81 05-24-81 05-25-81 INITIAL ELECTRICITY

)

COMMERCIAL OPERA TION nn _n t.-R 1 07 in_91 l

A 4

PDR (9/7;i g

DOCKIT NO.

sn ut.

2 UNIT DATE A2If 1 4.1985 J. D. Woodard COMPLETED BY TELEPHONE (205) 899-5156 larch, 1985 310NT11 DAY AYERACE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL OlWe Net)

QlWe-Net) 0 1

0 g7 0

0 2

gg

--~

--.0...__.

0 3

-. - --. __ _.-. g 9.

0

~"

0 4

'A 0

21 219 223 0

g 6

313 7

0 23 0

4 582 647 0

9 3

697 10 26 0

11 27 824 32 0

3 12 172 13 3

0 14 30 388 0

218 15 3g 16 0

IRTRUCEONS On this format. list the aversge daily unit power Icvelin MWe-Net for each day in the reporting month. Compute to

, the nearet whule me;swatt.

(9/77)

O

O O

O 5b-364 UNITSi4UTOOWNS AND POWER REIM)CDONS DOCKET NO.

UNIT NAME J M.

Farley - Unit 2.

DATE Anril 4. 1985 '

COMPT.ETED BY T-n Woodard REPORT MONTil Mn reb - 19Rs TEl.EPliONE (205) 899-5156 v.

's E

}

-j _e g

7 5 'j I30cn5Ce 5%

i"L c

r.

g Cause & Curreceive No.

Daic

.c g ac Event uT ju]

A.

Acikun to a

x sE j g2 g Repawa #

AG p,,,,,,g,y,,,,,c, d

I N/A N/A N/A The Cycle'III-IV refueling outage 001 850301 S

474.6 C

1 continued from 1-5-85.

002 850328 F

18.9 B

3 85-008-00 N/A N/A The reactor tripped due to 2A stemm generator low-low level caused by the 1

loss of B main feed pump control. This was due to a printed circuit card being i

removed incorrectly from the 2B steam generator feed pump control cabinet.

This event was caused by personnel error. The individual involved has been counseled.

1 003 850329 S

0.8 B

4 N/A N/a N/A Turbine overspeed trip test; maintenance testing. (Reactor power at 22%)

i i

)

I 2

3 4

i F: Forced Reason:

Method:

Exhibit G. Insieucticos S; StheJuled A-Equiper.cos Failuss(Emplain) 1 -Manual for Prepasation of D. iia B-Maintenance ad Test 2 Manual Scraan.

Entry Slicens for I.icensee C Refuchog

3. Ausonialic Scrans.

Event Repews (t.ER) File (NUREG-D-Regulatawy Resisiccion 4-(hher (Emplain) 0161) i E-Opesator Trainina A license Exandnasion l

F-Adudaisisasive 5

G Opesational Essur (Explain)

(9/77) 11 Othes (Explain)

Exhibia I - Sanw Sous.e

O O

O 5'0-364 i

UNIT SilUTDOWNS AND POWER REIMJCHONS DOCKET NO.

UNIT NAME J.M. Farley

_ Unit 2 DATE April 4, 1985 COMPI ETEE) BY J.D. Woodard t

REPORT MONTil March. 1985 TEl.EPilONE (205) 899-5156 g

3 = =$

=

r.

g,

p'IC

}

j E I'CH3CC h'.

g4 Cause & Cangective g3" es

.c E c::

Evens ay n.}

go Aciio.g to x

Ob n!

fik{

N8P'MI #

PICVcut Recusscace 8

6 4

004 850330 F

9.7 B

3 85-009-00 SG ISV The reactor tripped due to low-low level in 2A steam generator following the loss of steam generator feed pump l

2B.

During instrument calibration, an j

isolation valve leaked by causing the l

steam generator feed pump to trip due i

to an incorrectly indicated low vacuum condition. The isolation valve has l

been replaced.

4 i

1 2

3 4

F: Forced Reason:

Method:

Exhibit G. insituctions i

S: Silieduleti A-Eaguipawns Failure (Emplain)

I-Manual for Prepasalitui of Data j

B Maintenance t.iTest 2 Manual Scram.

Entry Sheces for I.icensee C-Refueling 3 Automatic Scram.

Event Repius (l.ER) file (NUREG-

~

D Regulatiny Resisiction 4 Daher (Explaio) 01611 E-Opesanor T.aining A license Emandnation 1

F Adudnistsasive 5

G Openasi mal Ensus (Explain)

Emhibit I - Same Source l')/71) 11 Othes (E aplain) 4

JOSEPH M. FARLEY NUCLEAR PLANT UNIT 2 NARRATIVE

SUMMARY

OF OPERATIONS MARCH, 1985 The Cycle III-IV refueling outage continued into the month of March.

The unit was returned to service on March 20.

There were two (2) auto-matic shutdowns which occurred on March 28 and March 30, 1985. Following the March 30 reactor trip, atmospheric relief valves lifted for all three steam generators due to the steam dumps to the main condenser being in-operable. The steam dumps were inoperable due to a leaking isolati,on valve which incorrectly indicated a low vacuum condition. The generator was taken off line for performance of the turbine overspeed trip test on March 29, 1985.

The following major safety-related maintenance was performed in the month of March:

1.

Performed miscellaneous corrective and preventive maintenance on diesel generators.

2.

Containment tendon field anchor inspection and replacement con-tinued. At the end of March, 79 of the 130 field anchors for the vertical tendons had been replaced. A visual inspection of a random sample of hoop and dome tendon field anchors was completed.

No additional problems were found.

This random sample was chosen to give a 95% confidence level that all degraded field anchors had been found.

4 L

OPERATING DATA REPORT 50-364 DOCKET NO.

DATE April 4,

1985 COMPLETED BY J. D. Woodard TELEPHONE (205) 899-5156 OPERATING STATUS

1. Unit No:ne:

J seph M. Farley - Unit 2 Nytes March, 1985

1) Cum _ulative data since

2. Reporting Pened.

2652 7-

3. Licensed Thennal Power (MWt):

c9 e ope aeion,.

860 4.' Namepiste Rating (Gross MWe):

829

5. Demen Elecincal Rating (Net MWe):

850,2 i

6. Maximum Dependable Capacity (Gross MWe):

7. Maximum Dependable Capacity (Net MWe):

an7 o

8. If Changes Occur in Capacity Ratings (Items Number 3 Thsough 7) Since Last Report. Give Reasons:

N/A

9. Power Level To Wluch Restncted. lf Any (Net MWe):

N/A I

N/A

10. Reasons For Restrictions. If Any:

This Month Yr..to.Dete Cumulative 744 2,160 32,185

11. Hours in Reporting Period 284.6 380.8 27,299.3

12. Number Of Hours Reactor Was Critical 138.0

13. Reactor Reserve Shutdown Hours n.n o.0 i

14. Hours Generator On-Line 240.0 316.0 26,914.I

15. Unit Reserve Shutdown Hours 0.0

.0.0 0.0 368,968 608,441 67,461,189

16. Gross Thermal Energy Generated (MWH) 114,634 192,182 22,138,464

17. Gross Electncel Energy Generated (MWH) t

18. Net Electncal Energy Generated (MWH) 89,028 154,478 20,973,400 32.3 15.6 83.6

19. Unit Service Factor 32.3 15.6 83.6 l

20. Unit Avadsbility Factor

21. Unit Capacity Factor (Using MDC Net) 14 8 89 80*4

22. Unit Capacity Factor (Using DER Net) to a 8.6 78.6

23. Unit Forced Outage Ratz 10,6 7.8 5.5

24. Shutdowns Scheduled Over Next 6 Months (Type. Dete.and Duration of Each t:

N/A N/A

25. If Shut Down At End Of Report Period. Estimated Date of Startup:

26. Units in Test Status iPrior to Commercial Operation):

Forecast Achieved INITIAL CRITICALITY 05-06-81 05-08-81 INITIAL ELECTRICITY 05-24-81 05-25-81 COMMERCIAL OPERATION a_nt-Al n7 in-gi P8/77 )

DOCKET NO.

sn_ua 2

UNIT DAR April 4.1985 J. D. Woodard COMPLETED BY 6

TELEPHONE (205) 899-5156 March, 1985 St0NTII DAY AVERACE DAILY POWER LEVEL DAY AVERACE DAILY POWER LEVEL plwe-Net) pgw geg)

O 0

1 g7 0

0 2

gg

-- D.._,

o 3

---. - -...._ _. g 9 0

0 4

0 5

21 219 0

223 6

g 313 7

0 23 0

8 24 582 647 0

g 9

3 697 10 3

0 11 27 824 32 0

3 12 0

172 33 3

0 l

14 30 388

'218 0

3:

15 16 0

RGTRUCT*.ONS l

l On this form:. list the averste daily unit power levelin MW'e Net for each d:y in the reporting month. Compute o the nearest whole me;swatt.

1 l

(997)

--w-

.-4

UNIT SSIU1 DOWNS AND POWER REIMMMONS DOCKET NO. 50-364 UfGT NAME J.M. Farley - LInit 2 DATE Anril 4.

1985 COMPLETED BY T-D. Woodard REPORT MONTil Mnrr-h 19R5 TELEPilONE (205) 899-5156 "L

$ sa 5 h

h_e re 5

Lkensec

[*,,

i

~

Cause & Cmreceive h%

7 g

N

g gj J: 5 ac Event g3

'g Actines to x

j12 g Reposa #

g p,,,,,,g,,,,,,,,,

u vi u o-6 a

1 N/A N/A N/A The Cycle'III-IV refueling outage 001 850301 S

474.6 C

1 continued from 1-5-85.

002 850328 F

18.9 B

3 85-008-00 N/A N/A The reactor tripped due to 2A steam generator low-low level caused by the loss of B main feed pump control. This was due to c priated circuit card being removed incorrectly from the 2B steam generator feed pump control cabinet.

l This event was caused by personnel error. Tle individual involved has been counseled.

003 850329 S

0.8 B

4 N/A N/A N/A Turbine overspeed trip test; maintenance testing. (Reactor power at 22%)

i i

l 1

2 3

4 1

F: Fusced Reason:

Mess.oJ:

Ealiibit G. Insisuctiims S: S(lieduled A-fquipmens Failwe(Emplain) 1 -Manual for Preparati<ui of Data l

B-Mainsenance of Test 2 Manual Scrasa.

Ensey sliccis for I.icensee C-Refucinig 3 Automatic Scram.

Event Repewi (1.ER) File INUREG-D-Regulasiuy Resisiccion 4-Oslier (Emplain) 01611 E-Operator Training A license Examination F-Administsasive I

5 G Opesali. mal lasur (Emplain)

Exlubit I - Same Source 19/77) 11 Othcs (Eaplain) i

5'0-364 UNITStatHDOWNS ANDPOWER REIMICHONS DOCKET NO.

UfGT NAME J.M. Farley

. Unit 2 DATE = April 4, 1985 COtrLETED BY J.D. Woodard REPORT MONTil March. 1985 TELEPilONE (205) 899-5156 w.

4E

}3mEl b3'*"888 j*k c.

~

Cause & Causective g,'

ghi, g,

I Ewns ay Aggg,, g, y

j b

jd R*Pa's #

g Pagvens Recisesence 004 850330 F

9.7 B

3 85-009-00 SG ISV The reactnr tripped due to low-low level in 2A steam generator following the loss of steam generator feed pump 2B.

During instrument calibration, an isolation valve leaked by causing the steam generator feed pump to trip due to an incorrectly indicated low vacuum condition. The isolation valve has been replaced.

l 8

2 3

4 F: Funced Reason:

Method:

Exhibh G-Insesuccions S: Sci.eduled A E.guapenens Failure (Emplain) 1 -Manual for Preparaskni of Dasa n Maintenance of Tess 2 Manual Scsaan.

Enssy $hecss for Licensee C-Refecteng 3.Ausoessasic Scrasa.

Escas Repens (i.ER) File INUREG-D iseguiasiuy Resssictina 4-Osher (Emplain) 0161)

E-Opesaion Training a license Eman.: nation F-Adannistrasive 5

G Ope 416.mial Lesos (Eng44&n)

Emlobis I - Same Sinisce (9/77) 18 Othes (Eagdain)

. ~. _ - - - - - - - -

- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ~ ~ - - ~ ~

'.h.-

~

Memng Address A! bima Power Company

- 600 North 18th Strast Post Off ce Box 2641 Birmingham. Alabama 35291

- Telephone 205 783-6090 R, o, Mcdonald Senior Vice President Flintridge Building AlabamaPower tre sautwn e a:r:c tys:#

April 10,1985 Docket No. 50-364'

~

Director, Office of Resource Management U. S. Nuclear Regulatory Commission

- Washington, D.C.

20555

Dear Sir:

4 RE: Joseph M. Farley Nuclear Plant Unit 2-Monthly Operating Data Report Attached are two (2) copies of the March 1985 Monthly Operating Report

. for. Joseph M. Farley Nuclear Plant, Unit 2, required by Section 6.9.1.10 of Appendix A of the Technical Specifications.

If you have any questions, please advise.

Yours very t

-.f l

J y/ <

G; R. P. Mcdonald C

RPM /KWM: sam 1

Enclosures

~

xc: Director, IE (10 copies)

Director, RII (1 copy) i i

b

' \\

(

i

JOSEPH M. FARLEY NUCLEAR PLANT UN'T 2 NARRATIVE

SUMMARY

OF OPERATIONS MARCH, 1985 The Cycle III-IV refueling outage continued into the month of March.

The unit was returned to service on March 20.

There were two (2) auto-matic shutdowns which occurred on March 28 and March 30, 1985. Following the March 30 reactor trip, atmospheric relief valves lifted for all three steam generators due to the steam dumps to the main condenser being in-operable. The steam dumps were inoperable due to a leaking isolation valve which incorrectly indicated a low vacuum condition. The generator was taken off line for performance of the turbine overspeed trip test on March 29, 1985.

The following major safety-related maintenarce was performed in the month of March:

1.

Performed miscellaneous corrective and preventive maintenance on diesel generators.

2.

Containment tendon field anchor inspection and replacement con-tinued. At the end of March, 79 of the 130 field anchors for the vertical tendons had been replaced. A visual inspection of a random sample of hoop and dome tendon field anchors was completed.

No additional problems were found. This random sample was chosen to give a 95% confidence level that all degraded field anchors had been found.

l I

~

- _.. _. - - - - - - _.