ML19305B291
ML19305B291 | |
Person / Time | |
---|---|
Site: | Farley ![]() |
Issue date: | 03/01/1980 |
From: | Hairston W ALABAMA POWER CO. |
To: | |
Shared Package | |
ML19305B290 | List: |
References | |
NUDOCS 8003190462 | |
Download: ML19305B291 (11) | |
Text
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..n DOCKET NO. 50 148 UNIT SilUTDOWNS AND POWER REDUCTIONS UNIT NAME 3.M. Farlev - Unit DATE 3/1/80 1 >J COMPLETED BY W C Hnirnton,III g REPORT MONTH February TELEPHONE (205)899-5156 7 M
D 1 $-
y Cause & Corrective b g ,] g 3 Licensee E.r, h". Action to %
No. Date g 5g i 2s& Event g'! gg H
f: $ jgg Report *r mU g Pievent Recurrence c5 017 800221 S 2.1 B NA NA IIA VALVEX Unit was held at 86% reactor power to perform main turbine governor control valve surveillance testing.
018 800222 F 14.6 11 3 NA Illi 7.ZZ7.ZZ Unit tripped due to trip of both SGFP's on low suction pressure.
019 800223 F 8.5 G 1 NA lill ZZZZZZ Unit manually tripped due to trip of both SCFP's on low suction pressure.
020 800223 F 16.1 B NA NA fill VALVEX Unit held at 90% reactor power to investigate low SGFP suction pressure.
Adjusted gland seal condenser bypass valve and A lleater Drain Tank dump valves.
3 4 I 2 Method: Exhibit G . Instructions F: Forced Reason:
for Preparation of Data S: Scheduled A Equipment Failure (Explain) 1-Manual -
2-Manual Scram. Entry Sheets for Licensee
. B-Maintenance of Test 3 Automatic Scram. Event Report (1 ER) File (NUREG-C-Refueling -
D-Regulatory Restriction 4-Other (Explain) 0161)
E-Operator Training & l.icense Examination 5
F-Administrative G-Operational Error (Explain) Eshibit I- Same Source O. (9/77) 11 Other (Explain)
DOCKET NO. 50-348 UNIT SIIUTDOWNS AND POWER REDUCTIONS UNIT NAME 1.M. Farley - Unit 1 DATE 3/1/80 COMPLETED fly W. G. Itairston. III REPORT MONT11 February (205)899-5156
, TELErilONE e.
w 5 E
-, .$ E 3 j .E 3 Licensee Eg En. Cause A Corrective No. Date o. i; e s jgE Event u '2 E" Action to S
N $$ 5 jgg Report # $0 Prevent Recurrence c5 014 800217 F 16.1 A 3 NA lill INSTRU Unit tripped on LO-LO Steam Generator level caus,cd by unstable feed pump control. 1 & C corrected the problem by revising the AP program in the.feci pump speed control circuit.
015 800218 F 7.8 B NA NA 1111 llTEXC11 Unit was reduced and held at 50%
reactor power to repair a leak on the shell side of SB IIcater and change oil in the feed pump oil conditioners which contained water.
016 800220 F 28.5 B NA NA EB INSTR 0 Unit was reduced and held at 86%
reactor power to investigate main generator exciter voltage regulator osci-11ations.
I 3 4 I 2 Method: Exhibit G . Instructions F: Forced Reason:
for Preparation of Data S: Scheduled A. Equipment Failure (Explain) I-Manual 2-Manual Scram. Entry Sheets for Licensee
. B-Maintenance of Test 3 Automatic Scram. Event Repor1 (LER) File (NUREG-C Refueling D-Regulatory Restriction 4-Other (Explain) 0161)
E-Operator Training & License Examination 5
F-Administrative G-Operational Error (I:xplain) Eshibit I Same Source
, (9/77) II-Other (Explain)
50-348 DOCKET NO.
UNIT SilUTDOWNS AND POWER REDUC 110NS UNIT NAME J.M. Farlev-Unit 1 DATE afi /stn COMPLETED BY W- C- HnIratnn, III REPORT MONTit February TELErilONE (205) 899-5156 w.
- E 5 jg *' Licensee E.r, gq, Cause & Corrective
}; ,
No. Date F
h 3g g= 5 3 s$3 g p3 g E Event Report at g'[2 en U Q g
% Action to Prevent Recurrence d .
011 800201 S 368.1 F 1 NA ZZ ZZZZZ7, Continuation of 1/31/80 shutdown to perform NUREG 0578 related design changes.
012 800216 F 3.8 A 3 NA lill INSTRU Unit tripped on LO-LO Steam Generator Icvel caused by unstable feed pump control. 1 & C replaced a defective control card in 'B'SGFP control systun 013 800216 F 16.8 G 3 NA - IIH ZZZZZZ Unit tripped while in Mode 2 on Steam Cencrator LO-LO level. The reactor operator did not maintain level with auxiliary feedwater flow. Reactor
~
operator was reinstructed.
i 3 4 1 2 Method: Exhibit G Instructions F: Forced Reason:
1 Manual for Preparation of Data S: Scheduled A Equipment Failure (Explain) 2 Manual Scram. Entry Sheets for Licensee
. B. Maintenance of Test Event Report (LER) File (NUREG-C-Refueling 3 Automatic Scram.
4-Other (Explain) 0161)
D-Regulatory Restviction E-Operator Training & License Examination 5
F-Administrative Estubit I - Same Source G. Operational Error IExplin)
, (9/77) Il Other (Explain)
. l AV, ERAGE DAILY UNIT POWER LEVEL ,
. p 50-348
- - DOCKET NO.
- J.M. Farley - Unit 1 '
UNIT DATE 1/1/ AO j W.G. Hairston,III l COMPLETED BY
' TELEPilONE (205)899-5156 1
February MO DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (gg,,g,,)
,,n; I. 37 gg 490 2 .
820 3 ,, .
768 4
'~
676 5 21 173 6 3
~~ 306 7 3 756 8 24 811 9 3
-0 - 818 10 26 11 27 816 813 12 814 13 30
~0~
..- 15 _3g 16 : .
l InsatUcnoNs On this format. fist the sverage daily unit power level in MWe. Net for each day in the reporting month. Compute to
, the nearest whole megswait.
. (9[77) :
O
- ~ . ~ ~ = _ . _ _ _ _
OPERATING DATA REPORT DOCKET NO. 50-348 DATE 1M/An COMPLETED BY 'A n. R#rston,III TELEPHONE (9nosco-5156 OPERATING STATUS I. Unit Name: Joseph M. Farley - Unft 1 Notes 1/ Cumulative flata since
- 2. Reporting Period: February, 1980 12/1/77, date of commercial 2652 operation.
3.' Licensed Thermal Power (MWt):
, 4. Nameplate Rating (Gross MWe): 860
- 5. Design Electrical Rating (Net MWe): 825
- 6. Maximum Dependable Capacity (Gross MWe): *N
- 7. Maximum Dependable Capacity (Net MWe): *R?9
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Throu;'s 7) Since Last Report. Give Reasons:
m o
- 9. Power Level To Which Restricted. If Any (Net MWe):
- NA
- 10. Reasons For Restrictions. If Any: NA 4
I This Month Ye,to.Date. Cumuhrbe !
II. Hours In Reporting Period 696 144'o 19.704
- 12. Number Of Hours Reactor Was Critical 314.6 1020.0 11,955.5
', 13. React.,r Reserve Shutdown Hours 381.4 420.0 1,825.3
- 14. Hours Generator On-Line 267.3 963.5 11,554.0
- 15. Unit Resem Shutdown Hours 16. Gross Thermal Energy Generated (MWH) 639,186.1 2,360,604.6 28.958,619.0
- 17. Gross Electrical Energy Generated (MWH) 205.704 / 63,1/'+ 9,287.212
- 18. Net Electrical Energy Generated (MWH) 193,464 720,372 8,779,788
- 19. Unit Service Factor 38.4 66.9
- _ 38.6 38.4
- 20. Unit Availability Factor 66.9 58.6
- 21. Unit Capacity Factor (Using MDC Net) - 33 5 -
60.1 53.7
- 3
- 22. Unit Capacity Factor (Using DER Net) 60.3 53.7
- 23. Unit Forced Outage Rate 18.3 9.9 7.6 l
- 24. Shutdowns Scheduled Over Next 6 Months (Type. Date.and Duration of Each):
Nnno 1
. 1 i
i 1
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup: NA
- 26. Units in Test Status (Prior to Commercial Operation): Forecast Achiesed I.
G 1
INITIA L CRITICALITY A/6/77 8/9/77 !
INITIAL ELECTRICITY 8/20/77 8/18/77 l COMMERCIAL OPERATION - 12/1/77 12/1/77 The Nameplate Rating / Design Electrical Rating'will be used for the Maximum Dependable Capacity until an accurate value can be determined from operatin;; experience.
(9/77)
JOSEPH M. FARLEY NUCLEAR PLANT UNIT 1 NARRATIVE
SUMMARY
OF OPERATIONS FEBRUARY, 1980 On February 1, the unit outage for performing NUREG 0578 related design changes continued. There were four (4) automatically initiated shutdowns, one (1) manual shutdown and four (4) controlled power reductions in the month of ,
February.
The following safety-related maintenance was performed in February:
- 1. Overhauled 1A and 1B Reactor Makeup Water Pumps.
- 2. Overhauled vent air particulate radiation monitor RE-21. -
- 3. Installed valve position indicators on the POR's and pressurizer safety valves.
- 4. Installed a core subcooling monitor.
- 5. Replaced a bearing on the TDAFW pump.
- 6. Repaired a casing leak and replaced bearings on "B" MDAFW pump. .
- 7. Continued installing additional instrumentation on 1B charging pump.
a mm.-_
i 1
l . . . .-
..n. .
l
s O
n O. !
- DOCKET NO.50-14R UNIT SilUTDOWNS AND POWER REDUCTIONS UNIT NAME .1. ?! . Farley - Unit 1 DATE 3/1/80 COMPLETED BY W- G . Ib i r a r on ,111 REPORT MONTII February TELEPIIONE (205)899-5156 w.
_ E E '
- ,[ g 3 yy5 U;ensee gg gn, Cause & Corrective 2ss Action to No. Date k 5g R Event g7 mO g.3 O
H fE s 3
- e. g =!
Report # o U
Prevent Recurrence t5 017 800221 S 2.1 B NA NA IIA VALVEX Unit was held at 867. reactor power to perform main turbine governor control valve surveillance testing.
018 800222 F 14.6 11 3 NA 1111 ZZZZZZ Unit tripped due to trip of both SGFP's on low suction pressure. -
019 800223 F 8.5 C 1 NA lill ZZZZZZ Unit manually ripped due to trip of both SGFP's on low suction pressure.
020 800223 F 16.1 B NA NA lill VALVEX Unit held at 907. reactor power to investigate low SGFP suction pressure.
Adjusted gland seal condenser bypass valve and A Heater Drain Tank dump valves.
I 2 3 4 Reason: Method: ' Ex!ubit G -Instrucitons F: Forced A-Equipment Failure (Explain) 141anual for Preparation of Data S: Scheduled -
B. Maintenance of 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 & Ucense Examination F Administrative ,,
5 G-Operational Error (1:xplain) Exhibii ! Same Source (9/77).. Il Other(ExpYn) 9
. . W h
- O
' DOCKET NO. 50-348 UNIT SilOTDOWNS AND POWER REDUCTIONS UNIT N AME J . 51. Fa rl ev - Unit 1 DATE 3/1/60 ,
COMPLETED BY W. G. Hairston. III REPORT MONTig February (2051899-5156-
,TELErilONE 5
n.
- B E
- EO 3 *E3 Licensee Et Evl, Cause & C errectise No. Date E N
j! il 5
3jE Event -h mO hU Actiop to Prevent Recurrence
$E j pj g Report 8 g
- 5 014 800217 F 16.1 A 3 NA 1111 INSTRU Unit tripped on LO-LO Steam Generator level caus,cd by uns table feed pump control. I & C corrected the problem by revising the AP program in the . feet pump speed control circuit.
015 800218 F 7.8 B NA NA 1111 IITEXCII Unit was reduced and held at 50%
reactor power to repair a leak on the shell side of 5B Hdater and change oil in the feed purdp oil conditioners which contained wat;er.
l 016 800220 F 28.5 B NA NA EB INSTRO Unit was reduced and held at 86%
reactor power to idvestigate main generator exciter doltage regulator osci11ations.
I I 2 3 f F: Forced Reason: Method: 4 ~ Exhibit G Instructions 1 Manual for Prephration of Data S: Scheduled A Equipment Failure (Explain)
. B-Maintenance of Test 2 Manual Scram. Entry S!jeets for Licensee 3-Automatic Scram. Event Report (LER) File (NUREG- -
C-Refueling D Regulatory Restriction .
4-Other (Explain) 0161)
E-Operator Training & License Examination F Administrative 5 G Operational Error (Explain) Exhibii I- Same Source (9/77).. Il Other (Explain)
p.
p
~'
n -
q !
50-348 UNITSIIUTDOWNS AND POWER REDUCI10NS DOCKET NO.
. UNIT NAME J .M. Farlev-t! nit 1 ;
DATE 9t / t /9n REPORT MONTil February COMPLETED BY U G- lin f ra:enn , III' TELEPflONE (205) 899-5156 .
w "t.:
a jg
- No. Date k f2
};; }Yj s&
Licensee Event E-r, 3,7 c'<!, Cause l Corrective Action to H
ff e jgg Report it in U g Prevent Recurrence 6
011 8002 1 S 368.1 F 1 NA ZZ ZZZZZZ Continuation of 1/31/80 shutdown to perform NUREG 0578 related design changes.
012 800216 F 3.8 A 3 NA lill INSTRU Unit tripped on I.0-LO Steam Generator level caused by unstable feed pump -
control. I & C replaced a defective control card in 'B'SGFP control systan 013 800216 F 16.8 G IIII 3 NA -
ZZZZZZ Unit tripped while in Mode 2 on Steam Generator LO-LO level. The reactor operator did not maintain level with auxiliary feedwater flow. Reactor operator was reinstructed. .
I i
i 2 3 F: Forced- Reason: Method: 4 ~ Exhibit G-Instructions S: Scheduled A Equipment Failure (Explain) 1 Manual for Preparation of Data B Maintenance of 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 5 G-Operational Error (Explain) Exhibit I- Same Source .
(9/77). Ilother (Explain) 9
c
.. . 4 .
AYERAGE DAILY UNIT POWER LEVEL .
,. >-.., DOCKET NO. 50-348 WT J.M. Farley - Unit 1 DATE 1/1/90 l
.b..,..,..-
W.G. Hairston,III COMPLETED BY
- .f TELEPHONE (205)899-5156
, )
1 11 0 .
February ,
DAY AVERAGE DAILY POWER LEVE . DAY AVERAGE DAILY POWER LEVEL
. (MWe-Net) (MWe Net) 1 37 -0:
2 ,
- gg 490 ,
820 3 , .
768 4
~~
5 21 676
~
173 6 g
~~
306 7 23 8 4 811 9 3
-0 -
818 10 26
!! 27 816 -
813 12 y '~
814 13 14 30
,e 15 3t .
16 -
INSTRUCDONS On this formst. list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole rnegswait.
, ~
. (987) :
D. ,
. ? . , ,
', g
. ...y.. __
T
,, .g*
OPERATING DATA REPORT DOCKET NO. 50-348 DATE 1't /90
. COMPLETED BY tJ c H,trston,III nonR00-5156
, TELEPHO.NE OPERATING STATUS *
- 1. Unit Name: Joseph M. Farlev - Unie 1 Notes 1 Cumula'tive 11ata since *
- 2. Reporting Period: _ February, 1980 12/1/77, date of commercial 2652 Operation.
- 3. Licensed Thermal Power (MWt): ,
, 4. Nameplate Rating (Gross MWe): 860
- 5. Design Electrical Rating (Net MWe): 829 r 6. Maximum Dependable Capacity (Gross MWe): *AAn
- 7. Maximum Dependable Capacity (Net MWe): *A'O
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. G;ve Reasons:
va e
- 9. Power Level To Which Restricted,1f Any (Net MWe): NA
- 10. Reasons For Restrictions,If Any: NA Uds Month Yr,to.Date. Cumubtive
- 11. Hours In Reporting Period 696 1440 19.704
- 12. Number Of Hours Reactor Was Critical 314.6 1020.0 11,955.5
~ 13. Reactor Reserve Shutdown Hours 381.4 420.0 1,825.3
- 14. Hours Generator on.Line 267.3 963.5 11,554.0
- 15. Unit Reserve Shutdown Hours -u- 639,186.1 .
- 16. Gross Thennal Energy Generated (MWH) 2,360,60 d _ 28,958,619.0
- 17. Gross Electrical Energy Generated (MWH) 205.704 ' 0J e l b* 9.287,212
- 18. Net Electrical Energy Generated (MWH) 193,464 J20,372 8,779,788
- 19. Unit Service Factor 38.4 66.9 58.6
- 20. Unit Availability Factor 38.4 66.9 56.6
- 21. Unit Capacity Factor (Using MDC Net) . 33.5 -
gn,3 g3,7 3
- 22. Unit Capacity Factor (Using DER Net) 60.3 53.7
- 23. Unit Forced Outage Rate 18.3 9.9 7.6
- 24. Shutdowns Scheduled Over Next 6 Months (Type.Date.and Duration of Each):
%nn
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup: NA
- 26. Units in Test Status (Prior to Commercial Operation): Forecast Achiesed INITIA L CRITICALITY R/6/77 8/9/77 .
INITIAL ELECTRICITY 8/20/77 8/18/77 [
COMMERC1,\L OPERATION 12/1/77 12/1/77 The Nameplate Rating / Design Electrical Rating'will be used for the Maximum Dependable Cspacity until an accurate value can be determined from operating experience.
(9/771
. O
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