ML20092M747
| ML20092M747 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 05/31/1984 |
| From: | Swindell J, Thom T TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20092M734 | List: |
| References | |
| NUDOCS 8407020378 | |
| Download: ML20092M747 (35) | |
Text
.
r N
r TENNESSEE VALLEY AUTHORITY j
DIVISION OF NUCLEAR POWER r
BROWNS FERRY NUCLEAR PLANT i
t i
r t
MONTHLY OPERATING REPORT TO NRC May 1, 1984 - May 31, 1984 F
L DOCKET NUMBERS 50-259. 50-260, AND 50-296 LICENSE NUMBERS DPR-33, DPR-52, AND DPR-68 f
Submitted by:
vt O foPlant Manager Bg7020378840611 R
ADOCK 05000259 PDR 4
9 1
4r Operations Sn= nary May 1984 The following sununary describes the significant operation activities during the reporting period.
In support of this suunnary, a chronological log of significant events is included in this report.
There 1was one reportable occurrence _and two revisions to previous
. reportable occurrences reported to the NRC during the month of May.
Unit -1 There were no scrams on the unit during the month.
Unit 2.
There were no scrams on the unit during the month.
- Unit ~4 The unit.was'in dold shutdown the entire month for the unit's end-of-cycle 5 refueling outage.
e I'
Prepared principally by B. L. Porter.
i.
,-m s
2 Ooerations Summarv (Continued)
May 1984 i
Fatigue Usage Evaluation The cumulative usage factors for the reactor vessel are as follows:
Location Usage Fact 2C Unit 4 Unit 2 Unit 9 Shell at water line 0.00598 0.00486 0.00403 Feedwater nozzle 0.28849 0.21103 0.15429 Closure studs 0.23477 0.17236 0.13233 l
. NOTE:
This accumulated monthly information satisfies Technical Specification Section 6.6.A.17.B(3) reporting requirements.
Common System
-Approximately 4.95E+05 gallons of waste liquids were discharged containing approximately 9.05E-02 curies of activities.
F
't w-y-
7 y
y-y m
er m--
w---g
--+-r---
- s','
3 Ooerations % =ary (Continued)
May 1984 Refbeling Information Unit 1 Unit :1 is scheduled for its sixth refueling beginning on or about February 8,- 1985 with a scheduled restart date of August 27, 1985. This refueling will involve loading 8x8R (retrofit) fuel assemblies into the core, replacing recirculation piping, work on "A" and "B" low-pressure turbine,
^
upgrade-hangers and anchors, and environmentally qualify instrumentations.
There are 764 fuel assemblies in the reactor vessel. The spent fuel stor-age pool presently contains 252 EOC-5 fuel assemblies, 260 EOC-4 fuel assemblies; 232 EOC-3 fuel assemblies; 156 EOC-2 fuel as'semblies; and 168 EOC-1 fuel assemblies. The present fuel pool capacity is 3,471 locations.
~
Unit 2 Unit 2 is scheduled for its fifth refueling beginning on or_about August 24. 1984 with a scheduled restart date of January 23, 1985. This refueling' outage will involve loading additional 8X8R (retrofit) fuel assemblies -into the core, finishing the torus modification, turbine Iinspection,: finishing piping inspection, finishing THI-2 modifications; post,<
accident' sampling facility tie-ins, core spray change-out, and feedwater sparger inspection.
There are 764 fuel assemblies in th3 reactor vessel. At the end of the month there were 248 EOC-4 fuel assemblies, 353 EOC-3 fuel assemblies, 156
~
EOC-2 fuel assemblies, and 132 EOC-1 fuel assemblies in the spent fuel storage pool. The-present available capacity of the spent fuel pool is 601 locations.
A v3
++A.+
w
__,m
i Operations Sn=marv (Continued)
May 1984
-Unit T
. Unit 3 shut'down for its fifth' refueling outage on September 7, 1983, with a scheduled restart date of August 1,1984. This refueling involves loading u8X8R'(retrofit) assemblies into the core, finishing the torus modifications, postaccident sampling facility tie-in, core spray change-out, finishing TMI-2 modifications, turbine inspection, piping inspections for cracks, and changeout of jet pump hold-down beams.
' There are 0 fuel assemblies presently in the reactor vessel. There are 248 new fuel asremblies, 764 EOC-5 fuel assemblies, 280 EOC-4 fuel assemblies, 124 EOC-3 fuel assemblies,144 EOC-2 fuel assemblies, and 208 EOC-1 fuel assemblies in the spent fuel storage pool. The present available capacity of the spent fuel pool is 150 locations.
t 4
g:
e 5
Significant Ooerational Events Date Time Event Unit 1 5/1 0001 Reactor thermal power at 100-percent (%), maximum flow, rod limited.
5/5 0010 Commenced reducing thermal power for control valve test and SI's.
0100 Reactor thermal power at 94% for turbine control valve test and SI's.
0330 Turbine control valve test and SI's complete, commenced power ascension.
0400 Reactor thermal power at 100%, maximum flow, rod limited.
5/12 0045 Comenced reducing thermal power for turbine control valve test and SI's.
0200 Reactor thermal power at 91% for turbine control valve test and SI's.
0325 Terbine control valve test and SI's complete, reducing themal power for control rod pattern adjustment.
0430 Reactor thermal power at 83% for control rod pattern adjustruent.
0500 control rod pattern adjustment complete, commenced power ascension.
0630 Commenced PCIOMR from 95% thermal power.
0735 Comenced reducing thermal power from 975 for SI 4.3.A.2 (Control Rod Drive Exercise).
0800' Reactor thermal power at 94% for SI 4 3.A.2.
1015 SI 4 3.A.2 complete, commenced PCIOMR from 94% power.
1300 Reactor thermal power at 100% maximum flow, rod limited.
5/13 0315.
Commenced reducing thermal power from 100%, at load dispatchers request, load not needed.
0500 Reactor thermal power at 82%, load not needed.
0630 Commenced power ascension from 825 thermal power.
+
0645 Commenced PCIOMR from 955 thermal power.
1000-Reactor thermal power at 100%, maximum flow, rod limited.
5/17 1420 Comenced reducing thermal power for a control rod pattern adjustment.
1446 Reactor thermal power at 93% for control rod pattern adjustment.
1455 Control rod pattern adjustment complete, commenced power ascension.
1500 Commenced PCIOMR from 955 themal power.
6 Significant Ooerational Events Date TLne Event Unit 1 (Continued) 5/17.
- 2105-Stopped PCIOMR at 99% power and commenced reducing power
=(Cont) to remove "B" string low-pressure heaters from service for maintenance.
.2220 "B" string low-pressure heater out-of-service for maintenance, reactor power at 65% and reducing.
5/18 0100 Reactor thermal power at 64%,
"B" string low-prese.e heaters limited.
0500 Reactor thennal power at 65%,
"B" string low-pressure heaters limited.
0545 "C" reactor feed water (RFW) pump out-of-service for maintenance, reactor power at 65%.
0800 Reactor thennal power at 66%,
"B" string low-pressure heaters and "C" RFW pump limited.
1000 Reactor thermal power at 62%,
"B" string low-pressure heaters and "C" RFW pump limited.
1115 Commenced increasing thermal power from 58%.
1500 Reactor thermal power at 645, "B" string low-pressure heaters and "C" RFW pump limited.
2215 Commenced reducing thermal power due to partial isolation on Reactor Water Cleanup (RWCU), Traversing Incore Probes System (TIPS), Drywell Floor Drain (DWFD) and Equipment Drain-(ED) sump pumps, drywell air conditioning, drywell delta pressure air compressor, Pressure System Char 51ng (PSC) supply valves, 256 continuous air monitors (CAMS) and H 0 analyzers, IP-2 22 declared.
2225 Isolation reset, electricians found a loose wire on Primary Containment Isolation System (PCIS) reset relay.
2240 Shutdown and IP-2 terminated, reactor thermal power at 60%.
2300 Commenced power ascension from 60% power.
-2343 "B" string low-pressure heaters back in service at 63%
thermal power.
5/19 0700 Reactor thermal power at 75% holding due to "A" string high-pressure heater problems, and "C" RFW pump.
1245 Commenced reducing thermal power from 75% thermal power to remove "A" string high-pressure heaters from service for maintenance.
1300 "A" string'high-pressure heaters and "C" RFW pumps out-of-service for maintenance, reactor thermal power at 71%.
1600 Reactor thennal power at 70% for maintenance on "A" string high-pressure heaters, and "C" RFW pump.
Sinnificant Ooerational Events
.Date Time Event Unit 1 (Continued) 5/19 1925 "C" R W pump back in service, commenced power ascension.
(Cont) 1930 "B" RW pump taken out-of-service for maintenance, power ascension continues from 72%.
1955 "A" high-pressure heaters back in service, power ascension continues from 73%.
2300 Reactor thermal power at 75%, "B" RW pump limited.
5/20.
'0740 "B" RW pump back in service, reactor power at 75%.
0755 "A" RW pump out-of-service for maintenance, reducing thermal power.
1200 Reactor thermal power at 74%, "A" RW pump limited.
2045 "A" RW pump back in service, commenced power ascension.
2200 Commenced PCIOMR from 84% thermal power.
5/21 2100 Reactor thermal power at 100%, maximum flow, rod limited.
2300 Reactor thermal power at 995, "R" factor out-of-limits.
5/22 0500 Reactor thermal power at 98%, "R" factor out-of-limits.
1200 Reactor thermal power at 97%, "R" factor out-of-limits.
1230 Comenced power ascension from 975 thermal power.
1300 Reactor thermal power at 1005, maximum flow, rod limited.
5/23 0200
. Reactor thermal power at 995, "R" factor out-of-limits.
1030 Commenced power ascension from 995 power.
1100 Reactor thermal power at 100% maximum flow, rod limited.
1220 Reduced thermal power to 995, "B" recirculation ptanp high vibration.
1333 Commenced power ascension from 995 power.
1400 Reactor thermal power at 100%, maximum flow, rod limited.
5/26 0015 Commenced reducing thermal power for turbine control valve test and SI's.
(-
0200 Reactor thermal power at 94% for turbine control valve test and SI's.
0300 Turbine control valve test and SI's complete, commenced power ascension.
0400 Connenced PCIOMR from 99% thermal power.
0500 Reactor thermal power _at 100%, maximum flow, rod limited.
5/31 2400 Reactor thermal power at 100%, maximum flow, rod limited.
t
8 Sinnificant Ooerational Events Date Time Event Unit 2 5/1-0001 Reactor thermal power at 61%, derated to extend full cycle.
5/2.
0728 Reactor thennal power at 60%, derated to extend full cycle.
5/4 0001 Reactor thermal power at 61%, derated to extend full cycle.
5/10 0001 Reactor thermal power at 60%, derated to extend fuel cycle and administrative hold because all Automatic Depressurization System (ADS) relief valve cables are routed through the same cable tray.
5/11 0001 Reactor thermal power at 59%, derated to exter.d full cycle and administrative hola.
5/30 0900 Reactor thermal power at 60%, derated to extend full cycle and administrative hold.
5/31 2400
. Reactor thermal power at 60%, derated to extend full cycle and administrative hold.
F 8
Significant Ooerational Events s
Date Time Event Unit 3 5/1 0001=
End-of-cycle 5 refuel outage continues.
5/31 2400 End-of-cycle 5 refuel outage continues.
t
+
m__
p 10 AVER AGE DAILY UNIT POWER LEVEL DOCKET NO.
50-259 I
UNIT o
DATE 6/1/84 COMPLETED BY Ted Thom
'd 05/729-0834 TELEPflONE M*Y l984 MONTil DAY-AVER AGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe Net)
IMWe Neti 1075 1039 3
17 5079 is '
645 i
~
(076 738 3
1090 796 4
20 1054 994 5
21 1078 1058 6
22
'1073 1070 7
23 1076 1059 g
1075 1066 9
25 1075 1048 10 26 1073 1082
'I
,7-1042 1050 32-28 1043 062
.g3 29 1064 068-30 1080 1073
+
15 1070 g6 INSTRUCTIONS On ihn Ibnnas $le nr I""' '#I '" \\f WeWet f.., each sin in s he,c;,,,eting in. nit,. (,,,,g,,,
n, ing,,
Ihe riearest *lH i
lis t ?? )
m 11 AVERAGE 94 LY UNir POWER LEVEL DOCKET No. 50-260 2
UNIT 0/I/84 DATE COMPLETED By _Ted Thom 205/729-0834 TELEPHONE
- MONTil.
May 1984 DAY AVER AGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe-Net) lMWe Net)
.I 617 607 17 615' 593 2
13 611 596 3
19 633 I
4 20 627 592 5
al 591 4
595 22
~~
618 596 7
619 591 s.
24 620 592 9
25 603 587 10 26 600 566
'I' 27
'601 622 12 28
'600 593 g3 29 589 607 14
.to 15.
002 606
+
31 16 -
597
~ INSTRi1CTioNs On thh Ihrunas.hst the.swraec a.,,q, '""' I"" I"el '" llWe Net Ibr cas h day in ilie rep,,eting en.,,idt (* gw w the ticares.gg,Ie nx g.iwaii,"
l'il77)
f[,',
- f. :
_3...'_-'/[
12 WER AGE l)All t' SIT POWER LEVEL.
3 DOCKET NO.
50-296 UNIT DA TE CO\\tPLETED BY __Ted Thom 205/729-0834 TELEPilONE Sf0 NTH
.May 1984
-DAY AVERAGE DtlLY POWER LEVEL liAY AVER AGE DAILY POWER LEVEL
- ( \\1We-Nei l -
6twe.Ner t
.i.
-1 17
-4 6
e i
_3
_3 g
.r.
-3
-2 3
,9
-3
-2 4
- o
-2
-3 5-21
-3
-3 3
-3
-3 23
-4~
-4 x-
$4
-4
-5 9
5 -4
^10 lti i1'
-4 27 _
12..
-f!.-
23
~4
-2
-4 13
-3 14
-4
.in
-4
-4 I5 ti 4
. i t.
.~.--.a_____,
INS lHl!CTIONS -
f M tlin e itrut. list t!.. : sce er.l.nts i.>ic e.
l.-
- 1. \\t,0. Vi +, t r.es 1 sta in flee ri p..itnig ni.inth. Cinnpute tii
- he nc s'e. t,s I,4 n. em..i t gisl17 )
W
13 OPERATING DA TA REPORT DOCKET NO. 50-259 DATE 6/1/84 a m-CO)lPLETED liY TELEPilONE M W R 834 OP'ER ATING STA I US
- 1. Unit Name:
Browns Ferry - 1 N"t"$
- 2. Reporting Period:
May 1984
- 3. Licenwd t hennal Power t.\\lbt):
3293 1152
- 4. Nameplate Rating (Gross al%eI:
- 5. Design. Electrical Rating (Net 31We):
1065
- 6. Stasimum Dependabic Capacity (Gron alwel:
1098.4
- 7. 31asimum Dependable Capacity (Net alwel:
1065 8 If Chances occur in Capacity Ratino sitems Number 3 Through 71 Since Last Report.Giie Reawms:
N/A
- 9. Power Lesel to which Restricted. lf Any (Net 31We):
N/A
- 10. Reawms For Restrictiom. lf Any:
N/A This 3f onth
. Yr..to.Dare Cumularise
- 11. Hours in Reporting Period 744 3,647 86,209
- 12. Number Of flours Resctor has Critical 744 3,405,28
_ 53,211.40
- 13. Reactor Newne Shutdown llours 0
225.40 6,010.42
- 14. flours Generator On Line 744-3,309.38 52,027.02
- 15. Unit Rewne Shutdown llou,,
0 0
0 16.. Grow Thermal Energy Generated (SIWH, 2,357,182 9,920,114 148,477,793 17 Grow Electrical Energy Generated l\\lkill 786.510 3,332,590 48,9/6,zlu
'14. Net Electrical Energy Generated 13tWH) 767,289 3,248,425 47,573,752
- 19. Unit Senice Factor 100 90.7 60.3 20 Unit Asailability Facto, 100 90.7 60.3
- 21.. Unit Caiucity Factor iUsing alDC Neti 96.8 83.6 51.8 2.'
Unit Capacit) Factor (Using DER Neti 96.8 83.6 51.8
- 23. Unit Forced Outage Rat, 0-8.4 23.0
.24. Shutdowm Schedulrd Oser Nest h StonthsiI3pe. Date,and Duration of Fach):
c 23, if Shut Down At End Of Report Period. Estimated Date of Startup:
2ti. Units in les Status il'r;or to Commercial Operationi:
Forecast Achiesed INill \\ L CRillCAllI Y INill \\l. ELEC TRICITY CO\\l%Il RCl \\L OPERT llON 19/771 f
14 OPER ATING DATA REPORT
. DOCKET NO. 50-260 DATE 6-1-84 COMPLETED BY _Ted Thon 1 El.l:Pil0NE
ns /779 n834 OPERAIING St A1US Br was Ferry - 2 Notes
- 1. IJnit Name:
- 2. Reporting Period:
May 1984
- 3. Liernsed 1 hennal Power t>lh e 3:
3293 1152
- 4. Nameplate Rating tGrow 51We):
1065
- 5. Design Electrical Rating INet MWep:
- 6. Masimum Dependable Capacity (Gross MWel:
1098.4 1065
- 7. Masimum Dr. ndabic Capacity (Net MWel:
- 5. If Changes (L ar in Capacity Ratings litems Number 3 ihrough 71 Since Last Report.Giie Reason :
N/A
- 9. Power Lesel lo which Restricted lf Anv iNet MWep:
60%
- 10. Reasons For Restrictions. lf Any: All Automatic Depressurization System Relief Valve Cables are routed thr'ough the same cable tray.
This Month Yr. to llate Cumularise 744 3,647 81,150 1I. Iluurs in Reporting Period 744 3,356.34 53,321.02
- 12. Number Of flours Reactor Was Critical 0
290.16 14,190.52
- 13. Reactor Resene Shutdown flours 14.' flours Generator On-l.ine -
744 3,312.14 51,804.98
- 15. Unit Resene Shutdown flour, 0
0 0
- 16. Grow Thermal Energy Cenerated MWill 1,456,390 7,943,612 146,036,63/
461,560 2,574,720 49,172,'G08 17 Grow Electrical Energy Generated (MWill lb. Net Electrical Energy Generated IMhil) 448.374 2.505.370 47.763.973
~ 19. Unit Senice Factor
_100 90.8 63.8
~
100 90.8 63.8
- 20. Unit Asailability Factor 56.6 64.5 55.3
- 21. Unit Capacity Factor (Using MDC Neil 56.6 64.5 55.3 2.'
Unit Capacity Factor (Using DER Neil 0
6.6 23.8-23c Unit Forced outage Rate
- 24. Shutdowns Scheduled ther Nest 6 Months t T y pe. Date.and lluration of I achi:
Aunust 1984 (Refuel)
- 25. If Shut Down At End Of Report Period. Estimated llate of Startup:
2h. Unih in lest Statm Prior to Umnmercial Operation' Forecast
\\ chiesed INill \\l. CRilICA til Y INillA L Ell.CIRlCIIY CO\\l\\ll:RCl gl. Ort:R g IloN 19/773
Vi
~
-.s 15 OPERATING DATA REPORT L1 DOCKET No. 50-296 DATE 6/1/s4 C0\\lPl.ETED 14Y _Ted Thom TELEPil0NE 205/729-0834 OPER ATING STATUS r
- 1. Unit Name:
Browns Ferry'- 3 yo,,,,
- 2. Reporting Period:
May 1984
- 3. Licenwd Thermal Power (Mw ti:
3293
- 4. Nameplate Rating (Grow MWe1:
1152
- 5. Design Electrical Rating INet MWe1:
-1065
- 6. Masimum Depemlable Capacity IGrow MWel: 1098.4
' 7.. Masimum Dependable Capacity INet MWel:
1065-M. If Changes occur in Capacity Ratings eitems Number 3 Through 71 Since 12: Report. Giec Reaums:
N/A N/A.
' 9; Power Lesel to which Resnieted.lf Ans INet MWei-
- 10. Reaums For Restrictions. If \\ny:
N/A' ihis Month Yr..to.D.ite Cumulatise
- 11. Hours in Reporting Period 744 3,647 63,575
- 12. Number of flours Reactor has Critical 0
0 43,087.80
- 13.. Reactor' Rewn e Shutdow n llour, 0
0 3,878.13
- 14. Iloun Generator On.Line 0
0 42,193.71
~
l$. Unit Rewne Shutdown lloun-0 0
0-
' 16. Grow Thermal Energy Generated aMwill 0
0 126,307,711
~ 17 Grow Electrical Energy' Generated lMkit, 0
0 41,597,620
- 18. Net Electrical Energ) Generated IMwil, 0
0 40,375,256
- 19. Unit Senice Factor 0
0 66.4
- 20. Unit. Asmilability Factor 0
0 66.4
-21I Unit Capacity' Facfor 't Using MDC NeiI.
0 0
59.6 22 Unit Capacity Factor IUsing DI:R Net, 0
0 59.6
- 23. Unit Forced Outage Rate 0
0 16.4
- 24. Shutdoans Scheduled User Neu ti Month ITy pe,l).ite..end lauration of Fach t:
- 25. If Shut Down \\t I:nd Of Report Period,l.stimated Date of St.artup.
August 1984
^ 26. Ifnits la less St.atus IPrior to Commercial Operationi l'orecast As hiesed P
INill \\ l. CHillCAl.ll Y INi ll AI.1-1.l C I RICII Y
. CO\\l\\ll'RCl \\l. OPI:R \\ IlON P8/77I r
p...
,p
~cn
~
4 G.
3 e
8 r
I R
0 u
i m
s t
o 9 s
N 9
4 h 2 e
e 5
8 T 7
r el e m.t e 'ie e
2
/
/
p s
a nl c
I 1
d 5
r 0
/
e 0 w
s a c u
5 6 T 2 e
e o
tD i_R o
c O.EEYE tn' c
l eufl S
I n
oL e
o e'.
re is c
g
- m. I t m
n MTBN run c i
t s :n a
r n
. u r :
I i N
S t
A A D O a eiep T N D e
r.
E H C,, R Grah e I
E i
t e K T' T P pSR E
A
,6 sc ie i
t s
t
)
E b s yt b
I C N L L e4n n
"B tuPr n1 i
s e
a tns1 s
e6 h
O U P E u
s n
s r T
a _ r D
M o
e
" e EfEE0 E
C P
O t
C rn oi 4
5 f am der t e at ra ee Dh S
N O
m)
I
. r n a
T mci
?E[L C-a 5,*
aSl U
r p
c D
4 cis E
8 StaE l l R
9
- aami 1
r
= uu oe 1
R nnt h a
',7 0 b aaut E'
y tM le4 A)
W a
.ga 8 4
O~
M M1 234 P
D l
i 3
N T
A NO S
e N
M e sn s
t W
T n
n e i e
O R
v p c
D O
iE e L
R m.
T P
i U
E ta H
R n
S im T
.EX5 j;.
s.
a I
I N
U usi5 n
w t
7 ia n
m i s.j lp l
e a
nA p
s E
oI s
E i
.74$
B c&
it t
s t
e e r
ig s
uT in o) t lif si v
ao enes n RisEi Fe a r a
r t l l
_:?3 t c yT a ap nn r
r ns ea gor
=i53 nnnt oi t
oE i
s i
I r el at nt pt el a ar
- ninu ur nr e uif geaeh m qa e e pJ p i aEMRROAO) ui~
F 4
e
- - - - - - - l RABCDIFGI 2
4 8
8'
/
7 3
1 d
/
e l
4 J u cd ce
- n. hc FS
)
\\"
7 1
8 FS 7
4 2
1
- e
- [L l
- i i
50-260 UNIT SeeUTDOWNS AND POWER RElsUrTIONS DOCET NO.
UNIT NAME 2
DATE 6/1/84 REPORT MONTH gay ggg*e COMPLETED BY Tod The'm TELN'E 205/729-0834
_E E
5?
"b j h^ '
EAcmcr
[-r,,
li<:,
Cause A C.. rectne V
Da c i
3g 4
jgi Esens
- s
[-?
A.
.n i..
r fE E'
ji-Rer : :
1 *C
,5 ~~
Picsen Recur:en.c
~
~
1 292 5/1/84 S
11 Derated to extend fuel cycle into August 198h 293 5/10/84-5 11 Derated to extend fuel cycle and ad-ministrative hold because all Automat:.c Depressurization System relief valve cables are routed through the same cable tray.
C r
1 i
2 3
4 F: Fin.cJ Reas.m:
Methi=!:
E dubit C. Inst suc 5.mi.
S. SchcJuicJ A-Eqmpenent Fadure Esplain I-Manual t..: Picpaus. 4 pasa
~
B-Maineenance or Test 2-Manual Sesam.
Ent > Shecis fus tresswe C-Refucing J-Autoenasse Scram.
Esent Rep. ee i1.1 R e I'dc t'.t HI G-D-Regulasan Resarm ths 44hher ( Esplain t Oleil i F4)perator Tsaining A Ikene I unm.at> n F-Adamnsnuss.c 5
G4)peratsuaal Esaus iE spleal ITlubis 1. Same S i.sce
- swi77, II4hher a Esplams l
l k.
9
".i 50-296 UNIT SHUTDOWNS AND FOhER REDUCTIONS DOCKETNO.
UNIT NAME 3
DATE 6/1/84 REPORT MON TH May I984 COWTED gy Ted Thom TELEPHONE 205/729-083I.
3:
g$
=_
[1 E
Cause & Castreglige
~f k
7 ).f g'
g 3
35 3
fgx Esens
?
g gaa,,,,,,
gL 32j Rep.we :
- v. w Present Recurre,we OC
=
i 140 5/1/84 S
744 C
4 End-of-cycle refuel outage continues.
(Controlled shutdown 9/7/83) co l
l i
i t
1 I
I 2
3 4
F F..recJ Reawe:
Methial:
Estubit C. Instruesi.i.is S 5 hedulcJ A-Equiprne....mrei Lsplame I.mnual t'os Pseparati.m. i 1)asa 8.Wintenance or Tess 2-mn ual Scram.
Enir> Sheets (os IAen,cc C. Refueling 3-Aut.>matic Saam.
Esen Rep.iet eI.I RI File e Nt'HI G-D Regulat.w) Restricte.m 44):her iEsplain1 01 t>I I F4)peraine Trainmg i IAenw I sanunaan.m F-Adminisssatr.c 4
G4)perati. mal Ensus IEsplam t 1:shibit I. Same S.nuce e*/77)
IIOther i Esplaml
3 O
BROCS FERRY N!*CLDJt PLA%T D;IT O.
"d " 3 BF D:SIL
...s >
CSSC EDI*IPMENT ELECTRICAL !!AINTENANCE SD0tARY 9/29/82 e
For the Month of May 19 84 Effect on Safe Action Taken Nature of l Operation of Cause.of Results of To Preclude-Dato Svste:s Component Maintenance The Reactor Malfunction Malfunction Recurrence 1984 5/25 Radiation 0-FMP-90-152A Replace fuses None Improper operation Sample pump not Task force organized monitoring operable. Low flow to resolve recurrinE alarm problem.
MR 268030 i
l 5/28 Standby 0-PX-82-00C Replace relay None Bad coil Relay inoperable Replaced bad relay.'
diesel (NVR)
MR 267385 generators t
5730 Standby 0-RLY-82-00B Replace relay None Bad relay Relay inoperable Replacedbadhelay.!
lesel MR.252792 generators i
l i
4 L
4 l
pe-
f o
PY.d.
SP%i;S FER:n* E;'C*.E*.E P:. C.T ITI*T I
SF
.;> e.s. >>
?
^
CSSC EDt IP.%. ;T ELECTRIC.it 2:.tII.TE';.J;CE SQ?.\\RY 9/29/82 For the & nth of May 19 84 j Effect on Safe,
.\\e t ion T.i.:en Nature of
[
Operation of Ca' Y
Results of To Prcelude
- Dat, Svste2 Co :enent Maintenance i The Keactor h1 function m1 function Recurrence 1984 5/9 Control 1-LA-85-855 Replace printed None Bad card Alarm Replaced bad card.
rod drive circuit card MR 265038 I
5/19 Associated 1-RLY-57-16AK2O Replace coil 2.une Bad coil Relay inoperable
. Replaced bad relay, t
electrical
. 268034 systems LER BFRO-50-259/
84023 tt N
O g
~
e I'
g Q
I I
lq___
o
=
!lflI!
'r d.
+.
y r
a e
l t
e c
n r
M ee t
e d
e Aduc a
d Il n b
ce 2
d 7
ner d 0 e 0 orr e 3 t
3 iP u c 8 n 8 t
c a 6 u 6 coe l 2 o 2 aTR p
m m
e e R 2
R R M 1
iif 2
a 5
c i.
/
o 9
r 2/
f n e
l F.
- 9 co l
o i
b r
st a
t r
n t c l n e
o p
c uu o
sf n
n e1 i
i RL y
m a
r 4
l a
8 e
l 2
R A
I, 9
9' I
1 G.
T
- 2 n
f o R
~
C
~
- .i P
L S
y t
a c
T E
M n
y C
t u
a U.
af l
a V
Ci e
v X
s r
o I
F E
n r.
T d
k a
f a
n E.
I o
B U
A C
P.
h
,Il E'
t e
n ff U.
S
- a. or o r'.
C S
o I
nt 3
R e
aoc E
T h
cia F
C t
t e E
t aR 5
L r
cr 5
E o
eee T-F f ph e
e D.
fOT n
n E
E o
o N
N e
e k
f c y
o on a
m a
l s
en e
re r
d ut er t n e
t o ai c
nt N2 a
uc M
l oe p
mt e
ee o
R Rd tnen 9
6 e
9 2
C T
Y5 2T E'.
C L -
3C RK 35 N
- A
- 0 25 21 I
1
, 9 n
n E
o o
i e
i C
e rt r
t S
t oc u
c S
s t e s
e C
v ct hset S
ao gero er irir R p H pf p e 4 t 8 4
5 a 9
/
/
D 1 5
5 5
g 1l 1
i ;
m_
-=
'* J S
_'*-55 FERIT KC.E.E :".UT t~5;;
3 EF U3i" 3.'s m
CSSC M 'I N C -
ELECTKICAL in15TE1CCE S;? a.uY D"d U 3 9/29152 For the !L nth of May 19 84 I
I Ef f *Ct on SJfe.
Acion tan 8
Nature of Operation of l Cat Results cf I TO Preclude Dato Syste=
C ;e en; I
h intentnce The Reactor I
L 1 function D1 function
! Recurre: ce 1984 3/28 Control 3-HCV-85-50-47 Replace switch None Bad switch Switch not operable Replaced bad switch rod drive
,iduring performance of. let 155983 i
EMI 50 l
l 3/28 Control 3-HCC-85-46-47 Replace switch None Bad switch lSwitchnotoperable
!Replacedbadswitch rod drive Iduring performance of ; MR 155982 21 W e
4/30 Contro'1 3-PS-65 Replace level None Bad "O"-ring' Nitrogen leaking fReplacedbad"0"-
rod drive (46-11) switch "0"-ring
} ring.
a w"
lMR 254144 4/30 control 3-LS-85 Replace level None Bad "O"-ring Nitrogen leaking Replaced had "0"-
rod drive (50-27) switch "O"-ring around "0"-ring rin g'.
MR 254161 5/1 Reactor 3-FCV-6S-33 Replace coil None Bad coil Blowing fuses on Rx Replaced bad coil, water MOV Bd 3C recircula-MR 269875 tica 2 5/7 Standby 3-FMP-82-3A Replace m tor None Bad motor bear-Pump motor making Replaced bad lube diesel ings noises oil pump motor.
E*"*f***#
MR 269873 5/7 CO2 storage 3-00-39-00 Replaced expan-None Bad valve
'Cardox unit not cool-Replaced bad expan fire Cardox unit sion valve ing sion valve.
protectica MR 147355
-i
's t
e E
f n
a
. $.,i....
5272;S FEK.iT KC*1J.' ?!.AE C';17 3
.~
3 Cssc Est!MW ELECTRICAL 2"s1!'TETJ;CE SD*".iRY 9/29/c2 For the !!enth of May 19 84 r
I j Effect on Safe,
- Ae ion Isen Nature of. [
Operation of I Cause.of Results cf
+ To Prcelude Da r'>
Swsten Ce w.ent Maintenance I The Reactor I
Malfunction I
!*tifunction
! Recurrence 1984 5/11 Air condi-3-AEU-31-0104 Replace contacts Nome Contacts not mak-Air conditioning unit; Replaced bad contact tioning ing up properly not cooling
- MR 254308 i
5/14 Reactor 3-RLY-72-K12 Replace relay None Bad relay Relay not timing Replaced bad relay.
core PNL-25-31 correctly I
MR 254305 isolation 3'
cooling g
5/18 250VDC 3-CHCA-248-Replace record-None Bad voltmeter Low reading on volt-Replaced bad volt-Systen 03EB ing voltmeter meter reter.
k u
.MR 217298 w
5/21 CO2 stor-3-TA-39-110 Replace cable None Bad heat detector Alarm will not clear Replaced cable tray, age & fire tray heat (cable found cut heat detector.
protection detector in two)
. MR 252885 5/23 Standby 3-SCD-82-3ED Replace speed None None None l Replaced old type diesel (controls) sensing switch speed sensing switcL generator with solid-state type (more reliable).
MR 254313 i
5/29 4kV shut-3-RLY-211-Replace coil None None None Replace with new
~
dowa boardu27R/53CI type coil.
& busses (EFA relay) g 73 9
9
i' II l
1 1Illi!\\lll1 l,I, lli 1i I,
~
~
J '. 4 h
h t
t i
i w
w n
N ee l
l
.d e
i i
auc o
o Tl -:
c c
ce
. 8
. 4 ner d e 5 de 6 orr ep 7 ep 7 iP u cy 4 cy 4 t
c at 5 at 5
~
ec l
2 l
2
- k. T E pw pw
.n 5 ee a ee R R n oOIP,. Rn M I
.nix 2
F f.e. 4 /
i.
9 2
7*/
f s dx. A 9
cc
[.
i st t c l n uu sf el R a*.
e e
n n
4 o
o 8
N N
3 Y
9 8
.g 3,
i 1
O'.
n f o C
- c. i t
S t
y ec r
E a
sn s.
C M
uu
- L.
2f
_ C '%
r N
E s
T e
e a1 5 f
n n
o o
o N
N m
h t
e s
n ff U.
0 aor C
- 2 S
o
. s I
nt aT e
noc R
h oia r
C t
t e E.
t aK s
I r
cr E
o eee r-T f ph e
e fOT n
n r
E o
o 3
N N
ll.
t_
e f c on l
l a
i i
en o
o re c
c ut t n e
e ai c
c N '2_
a a
l l
p p
e e
R R
g lI
- n e
1 e
1 1
1 s.
2 2
1 2
n T-Y -
LS LE i
C R
N RB RS
- A 3B 3C Ir i
o ls
. ?
d d
E r
r t as t as C
e uoe oe hbs S
t hbs S
S s
s C
w nu nu S
Vwb 7wb ko 1o 4d&
4d&
e 4
9 0
t 8 2 3
9
/
/
aD 1
5 5
l!
- l)'
l l
l
- 1 l
.v NKaE E
Am 21 4
4 3
1 Ti %
58 7
- 3 7
7 c E 34 3
7 3
0 On N
39 6
3 0
4 50 0
5
~6 6
Ie T
u 22 2
2 2
2 Co f A A-A A
A-A Ati Mm R
R R
K M
M M
M l
t i
a e
g o
vg rK n
g l n ec i
d n
ai u
l e
i vk n
p t
k a
u a
a ne
- s. m o
n e
al u t C
d l
e sr n
A t g uL m
a o
/
sn A
r t
vl N
i M
o n
ra Ck W
o ee I c C
Ss Ca R p e,
1 4
s 8
s d
=
9 u
n A
rW u.
l a
e T = 1 i
ve
=
I
=
N e1 e
o e
ic T
g g
t n e
U
=
sC a
s a
aa g
r sW i
t n a
e uC l
l ne ru c AE a
r a
et l
u=Y CI m
e n
vn a
r
=
A r
t re ei n
M M
o a
as ra re
=
N W
Ku PM o s.
n st ar =
r 1 f emo E
su h
Fr r
t AoE Y A n S
c R C o s1 R 1 M 5eC e
e e
e
=
cl4 m
m w
c E
f a
o a
F e
TmE E
N K
h
= h 5
C s
t Trm Eu EM = r c
o n
a F
uc1 g
e B
m e
b i 1
l
]
x in E
1 i
ii ae C
p oe ob ct rN u
n r
s oA o
ti t
t u t
N C
ub u
ut ud sE or o
o on mT e
u C
a uN c
et e
eI e
iI a
g go gC gs l
nI nv nR ng mM p
aC ar a
an e
hP he hn hi R
CN Cs Ci cr 1
4 0
9 0
5 1
0 0
r 0
0 0
0 1
r 0
0 0
0 0
e 0
5 3
1 1
m 8
7 7
7 1
7 m
P B
C-S V-o M
I S
E T
C r
c F
T-1 T
o 1
e1 I
a r
l e
1
{
d e a
i 1
ot s
o C
r C
r C
Bs s
n Cs I
o I
o I
m m
y e
o c
C Cn C
Cn C
lS rti rigR e
E o
E u
o Pnt) ot n(
r* g(
r i g(
C s
re acI t ain et nn ot =m s
i t v hl eC ell e thl ie t a1 e s
s ni gojP
=oot e
t cl1 t c
or i onH esos sccs aoWS s
CD ECI(
nICy e
F. scy es y
E K E RI
.a 5
5 5
1 3
2 2
2 m
1 2
5 5
5 5
5
!!llli
O g
26 h
k ul s a
i.. ;
kB 4
g j
- la:
I is a s 5
.g 3
!s j
g E5 Ii
]s aa a
a 1
i f,
$8
!a 'Igs 1 i
1, lh bl alj&
64*
O e:
g an 25 Hisil aun I
y u
M l
^
^
is i
'i l
jja!
jia!
o n3A us35 B
a n
~
A A
BROWNS FERRY NUCLt.AR ruudt unti w
4 HECHANICAL MAINTEIMNCE -SU?t!ARY -
CSSC EQUIPMENT NY
- 19. 84 For the Month of-EFFECT ON SAFE.
ACTION TAKEN DATE SYSTEM COMPONENT NATURE OF OPERATION OF-CAUSE OF RESULTS OF TO PRECLUDE.
MAINTENANCE THE REACTOR MALFUNCTION MALFUNCTION RECURRENCE 5-3 ligh Pressure 0-HCV-26-0572 Replace Valve' None Age and raw water Valve leaking thru MR A-253354.
rire Pro-g
- ection (26 5-2 High 0-SRV-26-0573 Repair Valve
'.None Age and raw water Valve leaking thru MR A-260362 Pressure Fire Protection i
N e
i
\\,;r i
1
/
9 I
b
iqb::= -
28 OUTAGE MAINTENANCE & MAJOR MODIFICATION MANAGEMENT i
MAY 1984 I.
Work Synoosis Unit 3 cycle 5 outage activities continued through day number 268 by the end of the May report period. Major emphasis areas this month have included P0392 CRD Scran Discharge Header Modification, MSIV Maintenance; 1
P0399 Instrument and Control Bus Modification, and induction heat stress improvement (IHSI) of se.l.ected weld joints, as well as work on the refuel floor and in the torus. The following is a stenmary of the major events during this work' period.'
A.
Critical Path Activities
. 1.
P0392 CRD Scran Discharge Header Modification - Piping and valve tag-ging was completed on May 5,1984. Hydrostatic test of the headers was completed on May 8,1984. Platform work is continuing.
2.
P0392 CRD Scram Discharge Header Hanger / Support Modification - Of 119 hangers, 82 have been completed with 17 having greater than 75-percent of their work complete. Many of the 37 incomplete hangers are await-ing FCR resolutions. Detailed breakdown is as fc110ws:
a..
Of twelve locations requiring inspection of existing hangers,11 are complete.
b.
Of 47 locations requiring removal only, 40 are complete.
c.
Of 18 locations requiring removal and installation of new hangers, 17 are complete.
M d.
Of 38 locations requiring new hangers,12 are complete.
~
e.
Of four locations requiring a modification to an existing hanger, two are complete.
s
.s3
.r*"
A -
c
29 OUTAGE MAINTENANCE & MAJOR MODIFICATION MANAGD4ENT MAY 1984 A.
-Critical Path Activities (Continued) 3.
P0392 (Instrumentation) - This work is continuing with pulling and terminating of cable.
4.
P0399 Instrument and Control Bus Modification - This work is continuing with the running of conduit and pulling of cable.
5.
MSIV Maintenance - This work is continuing with reassembly being started on several of the valves.
P0614 Stem Modification, was reported complete on May 20.
B.
Refbel-Floor -
P0334 Changing Air Compressor on Platform was completed.
P0027 Removal of Old Racks in Preparation for High Density Fuel Storage Rack Installation was completed on May 18. Fuel pool shuffle work began on May 22 and 351 l'
of 930 moves had been completed by month end (one shift per day). Emphasis l
has-been started on scheduling the repair of the jet pump nozzle which was found cracked during inspection. This work would invnive a possible drain down of the reactor vessel.
.C.
Balance of Plant Work continued on "C" Residual Heat Removal (RHR) heat exchanger.
Eddy 4
current testing revealed seven tubes to require plugging. The tubes were plugged and heat exchanger closed by the end of the month. Final torque and installation of drain piping are still needed to complete work. The condenser work was reported complete on May 3.
.'w
U 30 OUTAGE MAINTENANCE & MAJOR MODIFICATION MANAGENENT PAY 1984
'D.:
Turbihe The generator air test was completed on May 21. Replacement of the worn
- wheels'on unit 3 turbine building crane was begun during May. Two of the four wheels have been completed.
E.
Induction Heat Stress Tmnrovement (IHSI)
~
The IHSI process was completed during May. The final recirculation weld
-wes completed on May 15. ~The final RHR weld was treated on May.17 The final RWCU weld was completed on May 25 and the preparations for the GE contractor to move out began.
- F. :
Other Mechanical Work Diesel Generators - L.1970/P0709 - EECW piping and valve changeout was 1.
completed on "3D" and."3C" diesels. Work begarl on "3B" diesel on May 30 and is continuing. Work on "3A" scheduled to start following the completion of "3B."
- 2.. -Hydraulic Snubbers - This work continued during the month.
3.
MSRV's - Installation of valves and solenoids was completed. P0612, Installation of 1/2-inch SS flex-line, is needed for completion.. Six of.-13 hangers have been designed for P0612 while material is being
-obtained for fabrication.
4.-
.P0689 and P0691 - 64 series valves. This work is continuing and awaiting delivery of 0-rings.
5.
P0688 and P0690 Modify valves 76-18/19.This work continued during
-the month.- Both valves were electrically hooked up May 25, 1984.
l
(:
r
31 OUTAGE MAINTENANCE & MAJOR MODIFICATION MANAGEMENT MAY 1984 F.
Other Mechanical W rk (Continued) o 6.
P0695 - Modify valves 84-8A, 8B, 8C, and 8D. Thir work continued during the month.
7.
L2079 - H 0 M dification. This work began during May. Work was tem-22 pararily delayed due to need for 1/2 inch pipe caps. These caps were received May 30 and work resumed.
8.
P0684 Drywell Torus Vacuum Breakers - This work is continuing.
9.
P0569 Replace'RPV Head Vent Valves - Work continued during the month.
- 10. Repaired RHR suction valves 74-05/88. Both valves were stuck in open position.
- 11. Valves 77-2A/2B and 77-15A/15B passed Local Leak Rate Test (LLRT).
- 12. Valves 71-32/592 passed LLRT.
- 13. Valves 73-24/609 passed LLRT.
- 14. Replaced seals on unit 2 "C" RHR pump seal cooler heat exchanger.on May 3.
- 15. Repaired leakage on unit 2 "A" RHR heat exchanger. A Limiting Condition of Operation (LCO) began on May 20
- 16. P0730 Head Spray Piping Removal - Hold order established to begin-piping removal on May 28.
G.
Electrical / Instrumentation 1.
Diesel Generators - Completed modifications P0185 Rewiring of Diesel Protective Circuit, P0275 Degraded Voltage Relay Replacements, and P0585 Speed Sensing Device on "3D" and "3C" diesels. Work has started on "3B."
l'
4 32 OUTAGE MAINTENANCE & MAJOR MODIFICATION MANAGEMENT MAY 1984 G.
Electrical / Instrumentation (Continued) i' 2.
EMI-71 Motor Maintenance - Core spray "3B" and "3C" motors were com-pleted on Mey 2.
Closed Coolins Water (CCW) pump motors "3A" and "3B"
- were completed on May 5.
Raw Cooling Water (RCW) pump motors "3B" and "3C" were completed May 4.
RHR service water pump motor "3A" was completed on.May 15. High Temperature Circulation pump motors "A" and "B" were completed on May 16. Five motors remain to be tested for
~ this outage.
3.
EMI 7 Electrical Board Maintenance - Five breakers remain this outage.
4.
PO415 Reactor Pressure Vessel Feedwater Nozzles - This work is continuing.
5.
'P0322/323 Torus Level Transmitters - Work is continuing. Awaiting receipt of level transmitters.- Expected date.of delivery is June 15.
6.
P0631 RHRSW Tunnel Radiation Monitors - Work plan is in review cycle.
- 7..
P0533 Install Torus Temperature Devices - Work continued but is delayed pending the completion of P0126, installation of inverters, for power.
8.
Inspected EHC system cables for damage due to fluid spills.
9.
TIP Indexer Maintenance - Sealing started on May 13
- 10. P0284 Acoustic Monitors - This modification began during the month and is continuing.
11 1. LLRT was completed on the electrical penetrations of the TIP ball and check valves
33 OUTAGE MAINTENANCE & MAJOR MODIFICATION MANAGEMENT MAY 1984 H.
Torus i
Torus work was as follows-i.
1..
Torus attached piping support installation continued. By the end of the month, 356 of 456 supports were complete.
- 2..
Repair of valve 74-722 was completed on May 6.
3.
Touch-up painting of torus was completed.
4.
Torus fill was completed on May 26.
- 5. ' NRC 79-02 hanger irispection star'ted during the month' with 95 of 362 I
complete.
I I.
Planning and Scheduling
. Planning and scheduling efforts during this report period emphasized main-taining unit 3 cycle 5 network of activities while closely monitoring critical path activities. Unit 2 cycle 5 planning efforts are in progress.
However, lack of confimation on modifications to be worked coupled with
-lack of infomation on the scope of work involved with selected modifica-tions is hampering this c.ffort.
J.
Ariministrative The overtime percentage for the month of April was 17-percent with 115,829
.[
straight. time hours and 23,635 overtime hours. As of April 30, 1984. year-I tc,<iate overtime percentage was 20-percent, with 917,086 straight time.
I hoirs and 227,391 overtime hours. The overall goal of the overtime pePeentage is 17-percent.
l t
i b
34 OUTAGE MAINTENANCE & MAJOR MODIFICATION MANAGEMENT MAY 1984 J..
~ Administrative (Continued)
The Outage & Maintenance budget for April was $2,576,410 and the expenditures were $2,494.223 with year-to-date budget being $19,109.384 and actual year-to-date expenditures being $19,169,934.
The capital budget was $3,194.000 and-the expenditures were $6,446,281 with year-to-date budget being $24.662,900 and actual year-to-date expenditures being $25.727,507 Overall budget was $5,770,510 and the overail
~
expenditures _were 48,940,504 with year-to-date budget being $43,772,284 and actual year-to-date expenditures being $44.897,442.
L-