ML20009D435
| ML20009D435 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 07/01/1981 |
| From: | Thom T TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20009D434 | List: |
| References | |
| NUDOCS 8107240051 | |
| Download: ML20009D435 (45) | |
Text
, .,.
TENNESSEE VALLEY AUTHORITY DIVISION OF POWER PRODUCTION PROWNS FERRY NUCLEAR PLANT
- w MONTilLY OPERATING REPORT
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~. June 1, 1981 - June.30, 1981 DOCKET NUMBERS 50-259, 50-260, AND 50-296 LICENSE NUMBERS DPR-33, DPR-52, AND DPR-68
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l Submitted By: N]/f frj?fffyfy'
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Plant Super'intendent i
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"8107240051 810710 l PDR ADOCK 05000259 R PDR-L. .
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TABLE OF CONTENTS Operations Summary.. . .. . . . ... . . ... .... . .. 1 Refueling Information ... . ... ... . . - . . .. . . . . 3 Significant Operational Events . .... . .. . . .. . . . . 5 Average Daily Unit Power Level . . . . . . . . . .... . . . 11 Operating Data Peports . .. . ... . . . .. . . . . . . . . 14 Unit Shutdowns and Power Reductiona. . . .. . . .. . .. . . 17
,, Plant Maintenance . ... . . ... . . . . . .. . .. .. . 18
a 35 Outage Summary . . . . . . . . . . .>. . . .. . . .. . . . . .
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.. .* y Operations Summary June 1981 The following summary describes the significant operational activities during the reporting period. In support of this summary, a chronological log of significant events is incJuded in this report.
There were 21 reportable occurrences and eight revisions to a previous reportable occurrence reported to the NRC during the month of June.
..j - ' Unit 1
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- Unit 1 was in its EOC-4 refueling outage the entire month.
j- .A Unit 2 I
' ' There were no scrams on the unit. during the month.
Unit 3 There was one scram on the unit during the month. On June 28, the reactor scrammed from the MS1V's closing when two heaters on the B and D main steam lines.and one heater on the C main steam line were energized during a surveillance instruction on the main steam line tunnel high temperature isolation instrumenta-tion.
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_, V* 2 Operations Surmary (Continued)
June 1981 Fatigue Usage Evaluation The~ cumulative usage factors for the reactor vessel are as follows:
Location Usage Factor Unit 1 Unit 2 Unit 3 Shell at water line 0.00503 0.00405 0.00348 Feedwater noztle 0.24411 0.17393 0.13450
' O ~~ ~ Closure studs 0.19865 0.13892 0.10449
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- NOTE: 'This accumulated monthly information satisfies technical specification section 6.6.A.17.B(3) reporting requirements.
Common System Approximately 8.82E+05 gallons of waste liquid were discharged containing approximately 1.11E+00 curies of activities. .
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- 3 Operations Summary (Continued)
June 1981 Unit 1 Unit 1 began its EOC-4 refueling outage on April 11, with a scheduled restart date of August 19, 1981. This refueling will involve loading additional 8 X 8 R (retrofit) fuel assemblies into the core, the final fix on the sparger modification, power supply on LPCI modification, generator breaker and unit station transformer tie-in (requires Unit 2 to be shutdown), and torus modifi-Y
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cations.
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- There are 0 fuel assemblies in the reactor vessel. The spent fuel storage pool presently contains 764 EOC-4 fuel assemblies, 550 spent 7 X 7 fuel assemblies, five 8 X 8 spent fuel assemblics. 260 new 8 X 8 R fuel assemblies, and one' spent 8 X 8 R fuel assembly. Because of modification work to increase spent fuel pool capacity to 3471 assemblies, present available capacity is limited to 384 locations.
Unit 2 Unit 2 is scheduled for its fourth refueling beginning on or about March 26, 1982, with a scheduled restart date of August 13, 1982. Ihis refueling outage will involve completing relief valve modifications, torus modifications, "A" low pressure turbine inspection, MG set installation for LPCI modification, and loading additional 8 X 8 R fuel assemblies ic.to the core.
' There are 764 fuel assemblies in the reactor vessel. At the end of the month,'there were 132 discharged cycle 1 fuel assemblies, 156 discharged cycle 2 fuel assemblies, and 352 discharged cycle 3 fuel assemblies in the spent fuel
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4 Operations Summary (Continued)
June 1981 Unit 2 (Continued) storage pool. The present available capacity of the spent fuel pool is 160 storage locations. With present capacity, the 1979 refueling was the last refueling that could be discharged to the spent fuel pool without exceeding that capacity and maintaining full core discharge capability in the pool.
However, 949 new high density storage locations have been installed, but
..s cannot be used until Special Test 161 is completed.
h Unie 3 Unit 3 is scheduled for its fourth refueling beginning on or about September 25, 1981, with a scheduled restart date of January 23, 1982. This refueling involves loading additional 8 X 8 R (retrofit) assemblies into the core, relief valve modification, turbine inspe*ction, generator breaker and unit station transformer tie-in, and torus modifications.
There are 764 fuel assemblies presently in the reactor vessel. There are 124 discharged cycle 3 fuel assemblies, 144 discharged cycle 2 fuel asse.nblies, and 208 discharged cycle 1 fuel assemblies in the spent fuel storage pool. The present available storage capacity of the spent fuel pool is 1C52 locations.
5 Significant Operational Events Unit 1 Date Time Event 6/01 End of Cycle 4 refuel outage continues.
6/07 2230 Fuel sipping completed (11 leakers identified).
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- 6 Significant Operational Events Unit 2 Date Time Event 6/01 0001 Modifications outage on unit station service transformers continues.
6/16 1009 Commenced rod withdrawal for startup.
1100 Reactor Critical t'o. 133.
1730 Reactor pressure at 570 psi, holding for steam tunnel inspection and RFUP slinger ring adjustment.
6/17 1202 Commenced rod withdrawal.
1650 Rolled T/G.
, , - 1800 Tripped T/C (oil trip).
2040 Rolled T/G.
, 3, 2125 Synchronized generator, commenced power ascension.
~[ , 2331 Tripped turbine for transformer tap setting change, reactor thermal power at 20%.
6/18 0017 Transformer tap setting-change ccmplete, rolled T/C.
0045 Synchronized generator, coramenced power ascension.
1600 Commenced PCICMR from 63% thermal power (sequence "B").
1933 Commenced reducing thermal power from 66% to 53% for MS1V closure SI 4.7.D.1.B.2 and "A" RFUP maintenance (oil leak).
2105 MSIV closure Sl* complete, holding for RFWP "A" main-tenance.
( 2235 Maintenance completc on "A" RFRP, holding for control
, rod pattern adjustments.
I l 6/19 0300 Control rod pattern adjustment complete, commenced j power ascension from 53% thermal power.
0530 Commenced PCIOMR from 71% thermal power.
1000 Commenced reducing thermal power from 77%, (problems with "B" RFWP).
1420 "B" BFWP taken eut of service for maintenance (blown gasket on casing drain) reducing thermal power.
1500 Reactor themal power at 69%, holding for maintenance on "B" RFWP.
2200 Maintenance complete on "B" RFRP, placed in service, commenced PCIOMR.
6/21 0206 PCf0MP, stopped, APRM floe bias channel A, C, and E went high. Manual one-half scram inserted in "A"
. channel because bf APRM'w. Reducing thermal power from 93".. Running SI's on APRM's.
1740 Ccmmenced reducing thermal power from 88% for control rod pattern adjustment. ,
2030 Control rod pattern adjustment completed, commenced PCIOMR from 59% thermal power.
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. . 7 Significant Operational Events Unit 2 Date Time Event 6/22 2130 Reactor thermal power at 99%, maximum flow, rod limited.
6/26 0544 Reduced thermal power to 91% to test No. 6 intercept valve.
0600 Test completed on CIV No. 6, commenced power ascension.
0700 Reactor thermal power at 99%, maximum flow, rod limited.
, , - 6/27 2359 Commenced reducing thermal power for turbine
[,, control valve tests and SI;s.
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7[ 6'/28 0031 Turbine control valve tests and SI's complete, commenced power asccasion from 82% thermal power.
0400 Reactor thermal power at 99*, maximum flow, rod limited.
0525 Commenced reducing thermal power for main steam tunnel temperature centrol.
0545 Reactor thermal power at 957, holding for nain steam tunnel temperature control.
0600 Commenced power ascension from 95% thermal power.
0700 Reactor thermal power at 99%, maximum flow, rod limited.
6/30 2400 Reactor thermal power at 997., maximum flow, rod limited.
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8 Significant Operational Events Unit 3
_Date Time Event 6/1 0001 Reactor thermal power at 99%, maximum flow, rod limited (control cell core).
6/5 2250 Commenced reducing thermal power for turbine con-trol valve test and SI's.
6/6 0100 Reactor thermal power at 57%, holding for turbine control valve tests and SI's.
0120 Turbine control valve tests and SI's.
0430 Commenced PCIOMR from 96% thermal peuer (control
,,-- cell core).
- , _, 0600 Reactor thermal power at 99%, maximum flow, rod
, limited.
.o-6/8 2010 Reduced thermal power to 95% due to loss of plant preferred power.
2020 Commenced power ascension from 95% thermal power.
2025 Reactor thermal power at 99%, maximum flow, rod limited.
6/13 0005 Commenced reducing thermal power for turbine con-trol valve tests and SI's.
0100 Reactor thermal
- power at 85%, holding for turbine
. control valve tests and SI's.
0130 Turbine control valve tests and SI's complete, commenced power ascension.
0330 Commenced PCIOMR from 96% thermal power (control cell core).
0405 Reduced thermal power from 97% to 55%, "A" recir-culation pump tripped due to false stator high anerature indication.
0535 .. cecirculation pump back in serv;ce, commenced power ascension.
0700 Commenced PCICMR from 91% thermal power.
1400 Reactor thermal pcwer at 99%, maximum flow, rod limited.
6/19 2112 Commenced reducing thermal power for control rod pattern :2djustments.
2222 Removal "A" recirculation pump from service for MG act brush replacement.
6/20 0003 Reactor thermal power at 45%, holding for control rod p.ittern adjustments and "A" recirculation pump MG set brush replacement.
0055 Control rod pattern adjustment'and recirculation pump MG set brush replacenent complete, commenced power asccasion.
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Significant Operational Events Unit 3 Date Time Event 6/20 1437 Commenced PCIOMR from 77% thermal power (control cell core).
6/21 0700 Reactor thermal power at 99%, nn:imum flow, rod limited.
1537 Commenced reducing thermal power due to high river AT.
1740 Commenced power ascension from 75% thermal power.
6/22 0615 Commenced PCIOMR from 93% thermal power (control
..." cell core).
Reactor thermal power at 99%, maximum flow, rod 2- 1600
.. - limited.
- 1710 Reduced thermal power to 87% for removal of "B" CCW pump f rora service for maintenance.
1935 "P" CCW pump back in aervice, commenced power as-cension.
2000 Reactor thermal power at 98%, maximum flow, rod limited.
6/24 2003 Reduced thermal power to 55% when "A" recirculation pump tripaed due to false high stator temperature.
2130 "A" recirculatio'n pump back in service, commenced power ascetaion.
2230 Commenced PcIcttR from 94% thermal power (control cell core).
6/25 0600 Reactor thermal power at 99%, maximum flow, rod limited.
6/26 2125 Commenced reducing thermal power for control rod pattern adjustment and "B" recirculation pump MG set brush replacement.
2230 Reactor thermal power at 47%, holding for control rod pattern adjustment and "B" MG set brush replace-nent.
6/27 0005 ,
Control rod pattern adjustment and MG set brush re-placement complete, commenced power ascension.
0130 Commenced PCIONR from 86% thermal power (control cell core).
1243 Commenced reducing thermal power from 95% for control rod pattern adjustment.
1300 Reactor thermal power at 85%, holdinr for control rod pattern adjustment. /
1330 Control rod pattern adj"stment complete, commenced power ascension.
1410 Commenced PCIOMR from 89% thermal power (control cell core).
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~Significant Operational Events 1
Unit 3 Date Time Event
, 6/28 0511 Reactor Scram No.-99(1) from 99% thermal power due to MSIV closure during the performance of SI 4.2.A.8 (Primary Containment and Reactor Building Isolation Instrumentation Main Steam Tunnel Line High Temperature.) The MSIV closure
-was initiated from two heaters being energized on the "C" main steam line.
1418 Commenced rod withdrawal for startup.
1655 Reactor ~ Critical No. 112.
1935 Rolled T/G.
,,;, - 1955 Synchronized generator, commenced power ascension.
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Commenced PCIOMR from 79% thermal power (control
, 6/29 -0730 I'
~ 7[ cell core).
I~ '2300 . Reactor thermal power at 96%, maximum flow, rod
""' limited.
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.6/30 0100 Commenced reducing thermal power for control rod
- _ pattern adjustments.
0900 -Control rod pattern _ adjustments complete, commenced power ascension from 90% , thermal power.
1000- Reactor thermal' power at 94%, maximum flow, rod limited.
j 1500 Reactor thermal power at 93%, maximum flow, rod limited.
- 2400 Reactor thermal power at 93%, maximum flow, rod limited.
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(1)Ebuipment nalfunction.
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11 AVERAGE 1) Af LY tJN!F POh ER LEVdL DOCKET NO. 50-259 UNIT Browns Ferry - J
. Da rr . 7-1-81 COMPLETElk ilY Ted Thom
. TEl EPliONE _205-729.63_4_6 MONrli D&J AVER AGE DAILY POWEll LEVEL DAY AVER AGE t> Alt.Y POWEP LEVEL i M We-Net) t '.lWe-Net )
I -6 , l7 -5 e.*
'M 2 _5 iS --3 _
<*~ -6 19
-4
. 3
-6 -1 4 20
-6 -2 3 21-
-5 -2 6
I
-6 .
43
-2 --
g -5 -3 24 . .
9
-5 33
-3 to -6 26 -3
.ig -6 2- -4
-6 -6 33 28
-6 -6 13 79 g.: -6 -7 30 15
-b 31 16 -5 s
INS ritGCTIO?.S O.i t!us fonoat. h3' the neray daih us.n pow er lad u, ?.lWe Nel fr a cach Jo in s'ie icpoilin s in.. nth. Cionpai.- l ,
tlie naarest whoie nxramatt-j'O l M-
12 AVERAGE DAILY UNIT POWER LEVEL.
DOCKET NO. 50-260 UNIT Browns Ferry - ;
7-l~51
- DiTE CO\f PLETED itY Ted Thom
. TELE 9110N E 205-729-6846
.\l0NTil DAY AVERAGE DAILY POWER LEVEL D.tY AVERAGE D S.lLY POWER LEVEL (51We-Neu ( S1We-Neu
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4
. ,p I , 17 T' 2 -5 18 509 3 -6 19 727
-5 20 826 5
-6 7,
853
-5 873 6 22 7 -6 23 1038 g -6 1054
-5 1040
.; 's 10 -5 2.s 1054 g
-5 37 1036 I,
-5 ,...,.
1027 1.;
-5 ,9 1042
.4 -6 3a 1051 l5 -7 3, 16 . _7 INS iR UC TIONS On Ilm torrust,hst the aserage J.nly usui powei lael m \1Wc. Net for e.ich t!ay ni the et postme m. nih. c..mpuie to
!!l.* IleJtest %!)Dle f P g.1 % .s t l ,
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01177I
13 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-296 UNIT _Hrowns_Futy - 3
. DATE 7-1-81 COMPLElED BY Ted Thom
, l'ELEPilON E 205-729-68_46
.\l0NTil DAY AVfR AGE DAILY POWER LEVEL DAY AVER AGE DAILY PObER LEVEL
(.\tWe-Net i (.\lwe Nei n
, 106.' , i7 1052
,[p y 1065 g3 1063 1051 984
,;,, 3 19 _
4 1062 :o 853 5
1052 21 986 6 1013 22 1005
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7 1065 23 1042 8 1059 24 1004 __
9 1052 25 1034 IO 1053 y, 994 1047 988 1046 245 12 28 995 883 I3 29 1057 3g 992 34 15 L0li 31 16 1057 INS 1Rl!CTlONS On tlus tortnat. hst the ases. ige daily unit power lesel in MWe-Nel for cach tia in vlie ecp.u tum in. oih. (:.. nip ne t..
the tie.ucst whole toegawatt.
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- OPERATING DATA REPORT DOCKET NO.
50-259 DATE Mi-ul
- COMPLETED BY Ted Thom TELEPl!ONE 70%7.29 6846 OPER AT!NG STATUS Browns Ferry - 1 Notes
- 1. Unit Namet
'2. Reporting Period:
June 1981 3293
- 3. Licensd Thermal Power (SIWt):
1152
- 4. Nameplate Itating(Gion MWe):
- 5. Desipt Electrical Hating (Net MWe): 1065 6 Maximtun Dependable Capacity (Gross MWe):
1098.4
' f065
' 7. .ilasimum Dependable Capacity (Net SIMe):
- p.F 8. If Changes Occur in Capacity Ratinp iltems Nuinber 3 Through 7) Since Last Report. Give Reasm,:
5.+< 'NA s
NA
-9. Power Lesel To which Restriered.lf Any (Net MWe): _
-10. Reason < For Restrictions. lf Any: NA This Month Yr..t o-Da t e Cumul.; tis e
- 11. Ilours In Reporting Period 720 4j43 60,625 0 2,384.4 373, gg
.12. Number Of Il mrx Heactor Was Critical 0 16.,42_ _ 5,115.29
.13. Reactor Reserve Shutdown llours ,
-0 2,380.77 36,373.59
-14. Ifours Generator On-Line '
0 0 0 11 Unit Resene Shutdown lioots
- 16. Grow 1hermal Energy Generated (MWil) 0 7,425,495 100,717,856 0 2,474,200 33,237,490
- 17.' Grow Electrical Energy Generated (MWil) 0 2,407,849 32,271,666
- 13. Net Electrical Energy Generated (MWil) 0 54.8_ 60.0 1 19. Unit Senice Factor
- 20. IJnit Asaih.bility Fae:or 0 54.8 60.0 i
.21. Unit Capacity Factor (Using MDC Net) 0 52.1 49.t
, ' 22. Unit Capacity Factor (b.,ing DElt Net) 0 52.1 49.4
- 23. Unit Forced Outage Rate 0 0.8 28.0
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2 8. Shntdowns Scheduled Over Nest 6 Months (Type. Date.and Omation of 1.achi:
4 25.11 Shut D.mn At End Of Report Period. Estimated Date of Startup: Augnatd9.,_198.1 2 t'. . t.* nits in Tot Status tPrior !o Cmnmercial Operation). I'orecast Achiescil INITI A L CitillCAl.Il Y ,
s .-
INITIAL I:t i ClitICIT Y _ __
COM\lERCI \L OPER AIlON __
(9/77:
. 15 1 l
j^ OPERATING DATA REPORT DOCI;ET NO. 50-260 DATE 7-1-81
- CO5IPLETED BY _Tp_d_Iliqq TELEPfl0NL ?n9-129=6846 OPERATING STATUS
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Browns Ferry - 2 Notes
- 1. Unit Name:
. 2. Reporting Period: June 1981
- 3. L;cened Thennal Power (alWt1:
3293 1152
- 4. Nameplate Rating (Gns5 NIWel-
- 5. Design E!ectrical Rating tNet StWe)i 1065 2
- 6. Statimum Dependable Capacity (Gross atWe): 1098.4 2- 7. Alasimum Dependable Capacity (Net 51We):- 1065
%,f.," 8. If Changes Occur in Capacity Ratings titems Nuinber 3 Through 7) Since Last Report. Give Reasom:
- & ., NA
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m
- 9. Power Lesel To which !!cstricted,if Any(Net 31We): NA NA
- 10. Re.nons For Restrictinns. If Any:
This *..onth Yr. to.Date Cumulatise
- 11. Ilours in Reporting Period 720~ **
4,343 55,536
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349 3757.61 34,501.22
- 12. Number Of liours Reactor Was Critical
- 13. Reactor Reserve Shutdo su !!nurs .
371 557.02 13,010.5 Ii Hours Generator On-Line 313.35 3,659.79 33,400.75 f 5. " cit Reserve Shutdown llour.
0 0 0 ~
Iri. Gross Thermal Energy Generated p1Wil) 905,266 11,223,064_
92,793,407
- 17. Grow Electries! Energy Generated (',1Will 301,110 3,748,730 31,485,918 289,878 3,641,497 30,3s1,804 IS. Net Electrical Energy Generated (SIW!i)'
- 19. Unit Senice Factor '4 '4. 5 84.3 u0.1 ~
20, Unit Asail..bility Factor 43.5 84.3 60.1 21 Unit Capasily Factor (Using alDC Net) 37.8 78.7 51.7
- 22. Unit Capacity Factor (U>ing DF.R Net) 37.8 78T7 51.7
- 23. Unit Forced Outage Rate 0 4.7 30.6
- 24. ShutJou ns Scheduled Oser Nest 6 hionths (Ty pe. Date.and D..iation of Eacht:
- 25. liShut Down At 1 nd of iteport l'eriod. Estimated Date of Startup:
- 26. Umts lii Test Status (Prior to Cmnmercial Operation k Futecast As hit s td INI flA L CRllICA LITY INITIA L ELI:C I RICil Y
. CO\l%1f RCI AL OPI'R t i!ON 19/77 N
16 OPERATING DATA REPO!(T DOCKET NO.
50-296 DATE 7-1-81 CO.\lPLETED BY Ted Titoa.
TELEPil0NE .205-J29-6846 OPERATING STATUS '
Browns Ferry - 3 Notes
- 1. Unit Name:
R t Psd: June 1981 3293
~ 3. Licemed Th'ermal Power (SIWt):
- 4. Nameplate Rating (Gro>s 51We): 1152
- 5. Design Electrical Rating (Net 51We):
1065 1098.4
- 6. Staximum Dependable Capacity (Gross 51We):
1065
"' Niasimum Dependable Capacity (Net .*.lWe):
9,f 8. If Changes Occur in Capacity Ratings (Itenh Suinber 31hrough 7) Since Last Report. Give Reasom:
.A:f-.' NA
-.2- N ' -
m ..
NA
- 9. Power Level To Which Restricted,if Any (Net MWe):
NA -
- 10. Reasons For Restrictions,if Any:
This .\1onth Yr. to.Date Cumulatise
- 11. I' lours in Reportine Period' 720 -
4,343 37,991
- 12. Number Of flour,Iteactor was Critical 708.27 3,681.88 29,653.15 11.73 205.22 2,016.11
- 13. Reactor Reserve Shutdown flours
- 14. t{ours Generator On.Line 705.27- 3.588.92 28,978.92 0 0 0
- 15. Unit Reserve Shntdown'llours
.16. Grow 1hermal Energy Generated (5tWil) 951 10,871,158 85 236,186 2 221,0 78 3,621, zTO- 287r60,2W
- 17. (;ross Electrical Energy Generated (51Wil) l.'$. Net Electrical Energy Generated (ilWif) 717,194 3,512,615 27,336,938 98.0 82.6 76.3
- 19. Unit Senice Factor 98.0 82.6 76.3
- 20. Unit Asai! ability Factor
- 21. Unit Capacity Factor IUsing St!)C Net) 93.5 75.9 67.6
- 22. Unit Capadly Factor IUsin;t DER Net) 93.5 75.9 67.6
- 23. Unit Forced Ourage Rate 2.0 8.4 9.6
- 24. Simtdowns Scheduled Over Next 6 %1onths II)pc. Date.aad l>ur tie.n or rachi:
Maintenance September 1981 1
- 25. If Shut Down At End Of Reg. art Period. lkrimated Date ut Startup:-
26 Units in l'est St.itus IPrior to Commercial Operat;oni: Fin ecas: Achi,_ s ed l~ INill A L CRi t tCAl.IIY ,
I.\l I~l \ L El.1:C I!!101 IY CO'l%IERC IAL OPER A llON
' 03/773
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DOCKET NO. 50-259 __
UNIT SilUTDOWNS AND POWER REDilCTIONS UNIT NAME -Browns Forr.y.- 1
- DATE 7- h81
' COMPLETED BY Ted Thom RFPOR r MONT!! June TELEPIIONE _205-729-6846 n.
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, .5 E }4 jYR LiEeiace [-r, y'^?
g Cause A Corrective Date .;E s 5 E.ent ;y 9 Action tu -
No. i 3?
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$5 5 5 5, =
e Report = 6/L 5' O
. Prevent Recurrence
'd 172 6-1-81 S 720 C 2 EOC-4 Refuel Outage (Continued) l > !
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1 3 2 3 4 l' : Lorced Reason: Method; Exhibit G lastructiiws S Scheduleil A Equiprnent Failure (bplain) !-Manual tor Prepaiation of Data li Maintenance or Test .' Manual Seram. Entry Sheets for lacensee C Itefueling 3 Autonutic Scrain. Esont Report (1.ERI File iNUREG-D-Regulatory Restrietion 4 Other (hplain) 01til1 1 Operator Training A thense Euminat:on F- Administ r ati .e .
5 ,
G Op. ratioital Eiio iE splat;il Exhibit i S.:me Source P L/ 77 ) Il Other 4 Ex;Oin)
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t KE 260 UNIT SilUTDOWNS AND POWER REDUCTIONS , NA d Browns Ferry - 2 DATE' 7-1-81 COM!'LETEI) BY Tori Thnm REPORT MONTil Jun t TELEPilONE _205-729-6846
- E E
.5 g ; 2JYE Licenace [ 3, h, Cause & Corrective No . Date :- :s = i E E .3 Event 7. ? E ~' Action to O j$ $ 5 j, } Report : N0 !0 Prevent Recurrence
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192 - 6-1-81 S 405.42 B 2 To accommodate modifications to unit (Continued) station service transformerc I
193 6-17-81 S 1.23 B Tripped turbine for station service transformer tap setting change-s oo .
194 S B Derated for control rod pattern 6.--21_81 .
adjustment 1 2 3 4 i f.oced !<eason: M ethod: Exhibit G - Inst ructio.is 5 Scheduteit A fquipment Failure (Esplain) 1 Manu.it for Picparation.of Isata B Maintenance of Test 2 Manual Scram. Enity Sheets fot 1.ieensee C Refueling 3 Antoinatic Stram. Event Repost (1.1:R) File (NURI G.
D !;egulatory Restriction 4 Othei (Explain) 0161) 1 Operator fra:ning i !icense I samination
[ - Adi:n nist rat t.e . 5 G uperanoaal Firos (F.xplaial Exhibit I Same Source eb;77 ) Il-O:he r i L s planti
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DOCKET NO.- 50-296 UNIT SilUTDOWNS AND POWER REDUCTIONS Browns Ferry - 3 UNIT N AME .
DATE 7-1-81 COMPLETED BY- Tod Thn-REPORT MONTil June TELEPIIONE ?ns_790 AntA
, "9 .-
i jg 3 dY$ Licensee g-r, ge, Cause & Corrective N. . . Date
. #p 3E s .s s 5 Event y
.mU 9'8 Action to
-2: 5 Report c EU Prevent Recurrence
! I 5 =!
<_ u s 6
83 6-28-81 F 14.73 A 3 Scram due to MSIV closure during performance of SI 4.'2.A.8. MSIV closure initiated by two heaters on l "B" and "D" main steam lines and one i
heater on "C" main steam line being energized. 'g I 2 3 4 F: Forced Reason: Method: Exhibit G - Instructions S: Schedu!cd A Equipment Failure (Explain) 1 -Manual for Preparation of Data B. Maintenance c,i Test 2 Manual Scram. Entry Sheets for Licensee C-Refueling 3-Automatic Suam. Event Report (LER) File (NUREG-
. D-Regulatory Restriction 4 Other (Explain) 0161)
I' Operator Training & License Examination F-Adnunistrathe 5 G. Operational Error (Explain) Exhibit I Same Source (9/77) Il-Ot her ( E xplain)
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DOCKET NO. 50-296 UNIT SilulDOWNS AND POWER REDUC 110NS - UNIT NAME . Browns Ferry - 3 DATE 7-1-81
' COMPLETED BY TM Th m, REPORT MONTil' ""E TELEPilONE . _.205-J29-6844.-
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, .! E 3 4YE Licensee ,E n., 5% Cause & Corrective Action to N. . . Date g 5g 4 ji5 E.eni 77 E. ?
H fE $ ji Report h Prevent Recurrence
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6 77 6-5-81 S B Derated for turbine control valve tests and SI's ,
78 6-13-81 F A D,erated because of "A" recirculation pump trip w
79 6-19-81 S B Derated for control rod pattern ad-
- justment and "A" recirculation pump MG. set brush replacement
- Derated due to high river AT.
80 6-21-81 F D 81 6-24-81 E A Derated because "A" recirculation trippea due to false high stator temp. .,
82 6-26-81 Derated for control rod pattern ad-justment and "B" recirculation pump MG set brush replacement.
I : 3 4
! f: li.rsed Reason: Metho.1: Exhibit G - Instructions S S hsJa!ed A Equ:pment Failure (Explain) 14hnual for Preparation of Data P. Maintenance of Test 2 M.inaal Scram. lintsy Sheets for Licensee C Refueling 4 Autom.uic Scram. Event Report (LER)l'ile (NURI.G-D-I!egulatory Restriction 4 Other (l:xplain) 0101) 10;,erator Trainmg & Li.ense I: satamation F.Adnunist ratice 5 G-0,urational Livor (Explano Eshibit I Same Source ci/77 ) il-Othee (I:splain)
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BROWNS FERRY NUCLEAR PLANT UNITil,\ 2 & 3 INSTRUMENT MAINTENANCE
SUMMARY
CSSC EQUIPMENT'- . FOR IllE MONTH OF June 19 81 NATURE EFFECT ON SAFE CAUSE ACTION TAKEN
' DATE SYSTEM COMPONENT OF OPERATION OF OF RESULTS OF TO PRECLUDE MAINTENANCE THE REACTOR MALFUNCTION MALFUNCTION' RECURRENCE
- Unit.1
- 6-5 Control Rod PI-85-34 Replace None Gears Binding Indicated Pressure None Drive with Pump Off 3 6-27 Control Rod FCV-85-llA & Repair None Disconnected Feed- Valves Would Not None Drive llb back Linkage Operate Unit 2 6-2 Off-Cas ME-66-llO Repair None Faulty Hygrometer Indicated High .
None Humidity 16-3 Neutron SRM-B Repair None 'Joisy Pre-Amp Indicated High Counts None .U Monitoring ,
- 6-6 Rod Positic a 38-31 Replace None Faulty Reed Switch 8 Digit at Notch None -
Information ,
- 38 Intermittent
- 6-9 Radwaste LT-77-1A Repair. None Stuck Float Level Alarm Would Not None ,
Clear i
l Radwaste LT-77-1B Replace None Faulty Transmitter Would Not Indicate None Level
- 6-14 Reactor Pdis-71-1A Replace None Leaking Bellows Faulty Indication None Core Isol-ation Cool-i ing
!6-19 Off-Cas TIC-66-109 Repair None Faulty Amplifier. Would Not Work In None Automatic Mode
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. BROWNS TERRY NUCLEAR PLANT UNIf 1 2&3 .
INSTRUMENT MAINTENANCE
SUMMARY
CSSC r.QUTPMENT FOR ' DIE MONTil OF June 19 81 NATURE EFFECT ON StJE CAUSE ACTION TAKEN DATE SYSTDI COMPONENT OF OPERATION OF OF RESULTS OF TO PRECLUDE MilNTENANCE TIIE RFACTOR MALFITr:CTION MALFUNCTION ~ 4 RECUI,RENCE Unit 3 6-2 Reactor PI-3-207 Calibrate None Instrument Shift Rea' ding Low None Feedwater .
. ?
6-23 EECW Pds-67-8 Replace None Water in Switch Would Not Indicate None 6-24 Core Spray FI-75-21 Calibrate None -
Zero Shift Indicated Downscale None e 9
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BROWNS FERRY UUCLE!Ui PIANT UNIT 31
.- 't
\ I' ECIIAllICAL IL111;TEKiNCE SU:-:.5LkRV. \
CSFC EQi'ID:ENT 19 81 For the Month of 3""C <
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' ~
EFFECT & CM. E ACTICM TMEN DlaE SYST01 COMFONENT NATURE OF OPERATION OF CAUSE CF RESULTS OF TO PRECLUDE MAINTENANCE Tr!E REACTOR !%LFUNCTION M.iLF!NCTIO I RECURRENCE l 17-81 CRD FCV-85-11A&B Nonregulated NONI Faulty Seats Bac' Seats Replaced Seats Flow TR# 236779
$ 1 5-81 Drywell FSV-32-62 Leak NONE Unknown Solenoid leaking Replacr_d solenoid vals Control Air through TR# 203543 l
81 RiiR 1-D Seal HTX Bonne Leak NONE Unknown Bonnet leak on Outage on WP installed l
, drain valve new heat exh. with !
drain valve. l TR# 152154 l 19-81 Secondary U-l Personnel Door won't NONE Unknown Door un-functional Repaired lock , replace.
Containment. Air Lock seal seal & tightened hinge: )
TR# 235504 i w
20-81 EECW Core Spray Cooling Coil NOME Rusty Coil Col 1 dirty with Flushed coil with w l Coolers kusting rust sodium phosphate &
, then with clean water TR# 14C028 j 81 CRD valv'c 85-577 Pressure Leak NONE Valve mushroomed Seal leaking Cut 3/16" off stem, filed and cleaned up thread, polished seat TR# 234925 ,
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EROliNS FERRY 1:UCLEAR PLM:T UN,I"g ljCommon ,
- r- \t \
t.TANICAL MAI:;TEIENCE SUM:!ARY\
CFSC EOUIPMIC!T 3""" 81 .
For the Month of 19 EFFECT CN SAFE ACTION TAKEN DATE SYSTri CC:1F0: ENT UATURE OF OPERATION OF CAUSE OF RESULTS OF TO PRECLUDC VAINTENANCE THE REACI'OR MALFUNCTION MALFtRICTION RECURRE:!C,E 6-27-8A hilRSW Al Pump Broken suction None Unknown Broken suction bell Replaced suction be!'
bell & fabricated new l bushings TR# 233141
- 6-26-8
- Secondary Equip. Air Lock Door comes NONE Faulty lock & Door can be daken Adjusted lock & clos Containment door RX open wh n loose c3oser open TRv 188031
. should be closed i6-6-81 Fire ::me rgen cy Leakage NONE Unknown Water pump leaking Replaced water pump Protection Diesel Fire TR#208761 Pump f 5 81 Fire Diesel fire Leak NONE Unknown Hose Leak Repaired existing he.
Protection pump Eng. Exp. & added 2 gal. coolc tank TR# 236753 g
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11:'OW: S FERRY NUCLEAR PIA:;T UNIT 3
~
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!!EC11ANICAL 1:AI:TE ANCE SU:01ARYL \g .
CpSC EOUIP' TUT
. Tune For the I!onth of 19_ 31 .
EFFECT ON SAFE ,
ACT1G.': TAEE:3 NATURE OF OPERATION OF CAUSE OF RESULTS OF TO l'RECLUDE DATE SYSTEli COSTC::E::T I'\ INT ENA' ICE
_ THE REACTO2 MALFU':CTION !!AT.FUI!CTIGN RECU R 7F.!!CE A fuel pool Outboard I;0SE Wrong shaft on Caused bearings to Installed new shaft, 81 ruel Fool Cooling cooling H,0 bearing rt;a pump ran hot pump
~
hot sleeves, impeller,bearings,fgs,we,ar rir niceve nuts, packing s gaskets. TR# 225511 81 RCIC HCV-71-200A Steam Leak :;0NE Casket Blew Blown body gasket Replaced old gasket TR# 220342
. 81 HPCI Turbine Steam leak NONE Unknown Leak on bonnet Replaced gasket HCV-73-201A after unit 73-201A TR# 199197 scram 81 "rCI FCV-85-37A Leak-Valve NONE Cear screwed up Would not let valve Repositioned handwheel would not too high, close. & stroked valve close TR0 205924 m v
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r>R0iiNS FERRY liUCLEAR PLulT LGil'I! 3 :q.
MECILU;ICAI, It\12;TEt'aNCE SU?dt N \\ .
CSSC EOUIP::v3;- s Fer the 1:: nth of .Iune 19 81 .
EFFECT 0:3 SAFE ACTION TAKt:i 11\TE SYSTZM CCMPONENT I?ATURE OF CPERATION OF CAUSE OF RESULTS OF TO PRECLUDE inINTENANCn. ute. REACTOR MALFU:!CTICN PALF17:CTTON RECURRENCE o24-6.. LPCI 3 DN MG Set P>rcken washers 2:0NE Lock '*'ashers Broken lock-washers Replaced lockwashecs o:.
Manufactured too bearings hard at factory TRIl 137296 (
8 . liigh 3-26-587 Valve is not NONE Valve stem Closed valve Removed stem, bonnet L Pressure opening broken gate to replace bolts.
Fire Prot. TR# 227258 8 . AP Air Drywell Air Blowing air NONE Unknown Ilole in hat Replaced diaphragm Compressor Compressor TRi/ 205034 Valve 64-140 8 . AP Air valve 64-140 Blown seal NONE Unkno a Stem seal blown Replaced stem seal Compressor TR# 205386 w
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CSSC EOUYDiTNT ELECTRICAL !L\1NTEiU.NCE SMC4ARY For the Month of . Tune 19 81-g Etiect on Satc. .
Action Taken
n t e
. Systc= Cemconent- Nature of Operation'of- Cause of Results of To ?reclude.
I'.sint enance The Reactor ~ Malfunction :'alfunction Recurrence 6/3/81 Standby. Position Damper "open" None Position switch Could.not get a Adjusted position gas treat- switch on indicating was out of proper damper "open" switch,' indicating ment SBGT train B light was not adjustment o position indication lights operated outlet
- damper operating '.in the control room properly.65-38B properly TR #236852 6/10/81 CRD Scram accumu- Scheduled None, unit was While performing Eight accumulator All 185 level switche ;
- j lator level EMI-50 in refuel mode. EMI-50 it was level switches on U-1-were cleaned l
I switches CRD system was found that eight inoperative. and tested success-06-47, 10-19, tagged out for level switches fully during the 10-43, 14-Sh performing would not oper- performance of EMI-50 ,
26-03, 30-43, EMI-50 ate due to exces- as recurrence control .
38-39, 54-39 sive amounts of for previous events.
some siubstance LER-BFRO-50-259/8131 found on switch float and guide w stem which caused the floats I to stick.
3/12/81 RHR Limit switch, Valve indicat- None Bad limit switch Indicating lights Replaced limit switch,,
. for HCV 74-33 ing lights inoperable, indicating lights !
! indicated operated properly. l valve was open TR #236842 l when the valve
' was closed, l
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'ERC'.?NS FERRY NUCLEAD PLANT UNITl - I ,& Common '
CSSC roCII* INT' ELECTRICAL . :nlNTENANCE SU:W.RY. ',
For-the Month of Juno' 1981
.- EL f act. on Sate Action Taken Resultc of l.
I' .t e . Syster. Cc=ponen: Nature of' -Operation of Cause of To Preclude-I' Maintenance The Rec.ctor Malfunction- Malfunctien Recurrence
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6/13/81 Primary FCO 64-45 When FC0 64-45 None Open indicating Indicating lights Repaired broken actu i.
contain- indicating was cycled light actuator inoperable, ator, indicating ment light actua- both oren and broken. lights operate'd '
! tor' , closed indica- properly.
i ting lights TR #236777 i
i remained on.
I f6/14/81 Fire Routing valve Bad coil on .None, master FSV 39-11 coil Breaker trip Established fire j , protection :39-11 at CO 2 FSV 39-11 at valve FSV 39-11 burned occurred which re- watches, replaced
! j CO tank .is energized to moved electric the burned coil, the 2
! close, this loss power from 00 Pro- system was returned 2
l of power caused to service, w
- tected areas in the I it to open allow- TR #205708 l i
- control bay tu M ne ing pressuriza-bldg., and service I tion up to the l bldg. No valves i local man,ual with auto initia-va ves.
f tion were affected. j' t I I 6/15/81 Annuncia-Annunciator Inverter was None Bad inverter. Annunciator panel Replaced the inverter,
, tor & se- panel 55-4C continually 55-4C inoperable. annunciator panel
.l quential inverter loca- blowing fuses. operated properly. ,
t events re- ted on panel TR #236903
{ cording 9-4. .
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I1 Common ERO'.'NS r'E'bY N CLEAT PLANT k ,IT
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CSSC EOUIPMENT ELECTRICAL M\n;TENANCE SDCO.RY j For the Month of June _ 19 81
. Etiect en baic Actica Taken Nature of Operction of Cause of Recults of To Freclude N:c Sy:s t e: Cempenent Maintenance The Reactor Malfunction Malfunction Recurrence I
l 1A shutdown Did not re- None Auxiliary con- The fan indicating Adjusted the auxiliary 6/15/81 l Air Con- light circuitry was contacts, the indica-l
' ditioning board exhaust ceive a light tacts were out (Cooling- fan indicating on panel 25- of alignment, inoperable ting lights operated i Heating) light circui- 165 indicating properly. !
the fan was TR #236776 try l runnin g.
1
'1B control bay Drain valve Nore Bad drain valve Drain valve inoper- Replaced valve, new 6/16/81. Air Con-drain valve operated
. ditioning purge unit inoperable able
!(Cooling- drain valve. properly.
Heating) TR #186812 1
Air handling None I.oose' coil wire Air handling unit Tightenedtheloosh 6/19/81 Ventilat- 1B control 1B was inoperable. coil wire and the ing room air unit would handling unit not start ,
unit operated proper ,
ly. l TR #236866 l ,
' s Panel 9-7 Panel 9-7 None Loose annuncia- Received a false Tightened annunciator 6/22/81 Fire smoke annunciation card and the system ;
protection smoke alarm sn oke annun- tor circuitry
, circuitry ciator actuat- card operated properly. f
.ed with no TR #203379 ;
' smoke in panel
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ERO'.!NS FERRY NUCLEAR TLANT UN,1 .I & Common'
- CSSC EQUT!7 TENT. EI.ECTRICAL SL\INTENANCE SUM}V.RY ',
For:the Month of' ~ June 19 81 l- ETiect en Sate Action Taken l
System Ccmponent I*sture of Operation of Cause of' Results os 40 Prcclu:le Dctc. : Malfunction 'R.2currence
! Maintenance The Reactor- Malfunction i
! l l 6/23/81. l Diesel SFDl' relay on Redundant start None- While reviewing Relay operated. Adjusted " relay to- -
' generator D/G B test (EMI 3) EMI 3 it was .slightly fast but' proper setting per' s-determined that had no impact on the EMI 15 and.re-perform-i l
starting of the D/G. ed ste'p 2 & 5 of EMI l
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- SFD1 relay was:
I slightly out of 3, relay' operated i I
- tolerance. properly.
TR #225007 l
i i Replaced bell, alarm 16 Local alarm Alarm panel None Bad alarm bell Alarm bell inoper-l/23/81.l generatorDiesel panel at D/G inoperable able operated properly.
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- CSFC EOUIr!!rNT F.LECTRICAL
- nIMTENANCE SDC4ARY ,
For the :4cnth of. June 19 81-1 1 diect on Salc Actica In.cn .I.. '
b ' !9.:c .Systen Ce:penen Nature of- Operation of Cause of Results of To Freciede
,j ::aintenance 'The Reactor :4al func tion - Malfunction Recurrence H .
1 9: 5/29/81j RClC HS 3 FCV-71-3-. None-Unit was. . Contact was not HS-71-3 inoperable- Cleaned contact., .
jf . would not in cold shut- ' making connec- valve operated pro- .l ll operate from. down tion' perly by hand switch.:
il ,
control room TR #205920 ;
by HS-71-3 '
l-d:; - I i I 6/8/81 RHR # Indicating Indicating None Position switch Indicating lights Adjusted position l' j light circui- lights were was.out of would not operate: switch, indicating
) l try for FCV- not operating adjustment. properly. lights operated.
, ! 74-54 properly. properly.
!i. TR #205643
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1i6/8/81 !Unitpre- Unit preferred Breaker trip- None Bad breaker. Motor generator Replace'd breaker 1001 j! ferred MG breaker 1001 ped and would overload ' inoperable and voltage regulator,'
il set not close MG set was tested andt j'
- operated properly, u!
l 4 TR #205937 9 il
- I 1
8
'6/13/81 Fire TA-39-ll3 Annunciator None Bad circuitry TA-39-113 and Replaced bad annun-
.' , protection TA-39-120A bulbs would cards TA-39-120A inoper- clator card for TA- ,
I Annunciator not burn able 39-113 and card for l
]j , circuitry on TA-39-120A, annunci- l' J l; panel 9-8 ators operated properly.
j' i' TR #203668-
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ERO*.GS ' FERRY NUCLE!I PL32;T . UN,ITL \ 2 CSSC TOUIT*;ENT ' ELECTRICAL :nl : TEN / dice SOCuRY ',
For the Month of June 19 81 Eticct en Sate Action Takca
- v. t c
. Syste: Ccepenent Nature of .Cperation of Cauce of Results of To Preclude Maintenance The Renctor Malfunction Malfunction' ' Recurrence-
.I 6/14/81lCRD HS-85-47 Mechanical None Mechnical stop Required care to be Replaced worn stop, .l stop was bad was worn. taken while opera- switch operated. ;
on HS-85-47 ting switch to properly. I e avoid rotating TR #203683 switch past desired setting. .
i I
G/29/81 RUR FCV 2-74-57 During vibra- RHR, Loop 1 Broken contact FCV 74-57 Replaced broken tion testing suppression block on the inoperable contact block and i FCV 74-57 fail- pool cooling valve control performed EMI 18B &
ed to operate inoperable ' circuitry. 18.1 FCV operated from control properly. w room TR #239031 i
LER#BFRO-50-26 ?
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CSSC r01:TIVNT - ELECTRICAL M11NTENANCE SGEU.RY .
For the Month of June 19 81
' Action Taken
] LT:cet en Sate ~Cause of- Results of To Preclude l l'c t e 5estem Ccepenent Nature of 0::cration of Maintenance The Ronctor Malfunction Malfunction- R2currence
[
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"3A" RBCcW Excessive None Bad motor Excessive motor Replaced bearings, ;
{6/7/81 jRBCCW' bearings noise performed EMI 83, j
, pump motor pump motor l noise pump motor operated !
' s properly, l 1, TR #205382.
l '
Air con- Chilled water Temperature None Bad temperature Control bay chiller Replaced the bad f6/9/81 ditioning temperature sensor inop- sensor inoperable temperature sensor, i , (Cooling & sensor on 3A erable chiller operated I
iHeating) control bay properly.
chiller TR #220570
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1!
- 6/13/81' Air con- Spreader room Fan inoper- None Bad edil on fast Fan inoperable ditioning supply fan #2 able speed starter Replaced the bad fan operated coilfl properly'
{ (Cooling & TR #205009 Heating)
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' 6/13/81 ' Reactor 3A reactor 3A reactor 3A reactor re- MG set tripped 3A reactor recircu- Unitloadwasreducedj water recirculation recirculation circulation pump due to 2A-K45A lation pump The recirculation recircula-'MG set MG set tripped inoperable relay action inoperable pump was restarted.
I tion Unit entered initiated by RTD The high temperature !
LCO high temperature set point has been j
' trip changed on all 2A- i
! K45A and 2A-K45B i I relays. A special !
I test is being written ;
' and will be impie- +
mented to investigate-
. I this problem.
'l l8 LER-BFRO-50-296/8128 LER-BFRO-50-296/8131 i
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s CSSC E0;'II':TW : . ELECTRICAL M\I ;TE:i/0 CE SL7 CIA".Y ..
""* 19'01 For the :!onth of
- CLIuCL Cn S.1 L C - .
AC!iC3 TakCn
- sture of .Operatien ef Cnuse of F.csults of- To Prcclude
- ' :e Systc- Cenpenent
- alfunctic:t Malfunction.: Recurrence
- aintenance' The -Re,te t or
._ _ g l i Load control- None Bad controller Temperature load Replaced the tempera j 6/16/81i Air con- Temperature controller would ture load controller,*
jditioning load contro11- 1er was not controlbaychiller.f e (Cooling-& er'on 3A con- operating not operat'e proper-,
ly, operated ~ properly. .l l lIcating)
' trol bay properly TR #190627 chiller i
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i OUTAGE
SUMMARY
(Continued)
June 1981 Unit 2 was shutdown May 27, at 2217 hours0.0257 days <br />0.616 hours <br />0.00367 weeks <br />8.435685e-4 months <br /> to begin the Unit 2 station cervice transformer modification (P0275) outage, which was completed June
~
_17,1981. The unit was returned to service June 17, 1981 at 2125 hours0.0246 days <br />0.59 hours <br />0.00351 weeks <br />8.085625e-4 months <br /> allowing the outage to be completed in the original 21 day duration. The principal efforts during this outage consisted of the completion of the unit station service transformer electrical and fire protection work (ECN
.gf- ^
.dys P0275), changeout of the H2and 0 sample 2
return pumps (ECN P0315), 161 kV w .. - capacitor bank modifications (ECN P0403 - not completed) and reactor feed
-pump inspections and repair (B and C).
Raising of fan stacks on the cooling towers has been completed on all towers. Reducing the clearance of the fan tips to the stacks has been com-pleted on all towers except number 1 tower. Towers 5 and 6 only have the Hudson fans.
On June 5, members of the Water System Development Branch of the Division of Water Resources of the Office of Natural Resources performed tracer dye tests
-to determine the source of the inleakage into the Unit 1 CCW discharge tunnel.
Samples were taken from the two separate areas of inleakage into the tunnel. The tracer dye test showed that wata from the leak on the east side of the CCW tunnel was coming from the Unit 2 CCW system. The test also showed that the water from the leak on the west side of the CCW tunnel was coming from the Unit 3 CCW system. No repairs are scheduled.
I
/.
i
36 OUTAGE
SUMMARY
June 1981 The maintenance and modification activities for the month of June included continuing the Unit 1, Cycle 4 refueling / torus outage and com-pleting activities for the Unit 2 unit station station service transformer modification outage.
Major emphasis for the Unit 1, Cycle 4 refueling outage was con-centrated on the following:
"[ 1. Torus internal and external modifications.
Tj{ ' 2. LPCI modification.
- 3. H2/02 analyzer / sample pump modification.
- 4. HP turbine reassembly.
- 5. Reactor feedpunp turbine maintenance.
- 6. Cencrator breaker modifiention (P0214) .
- 7. 1B reactor feed pump reassembly.
- 8. Reactor vessel feedwater sparger changeout (Completed June 23, 1981).
- 9. Local leak rate testin. ea selected valves.
- 10. Fain steam isolation valve maintenance (repair of ID damaged stud still required).
- 11. Main steam relief valve testing - tested cff site.
- 12. CCW tunnel inspection and repairs to in]et tunnel joints.
(Completed June 21, 1981).
- 13. Fuel sipping (Completed June 21, 19dl).
- 14. Reactor building door interlocks. (Completed June 19, 1981).
- 15. Unit station service transformer modification. /
- 16. Flood up of reactor pressure vessel cavity (Completed June 25, 1981).
_