ML20053B898
| ML20053B898 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 05/01/1982 |
| From: | Jones G TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20053B890 | List: |
| References | |
| NUDOCS 8206010326 | |
| Download: ML20053B898 (42) | |
Text
.
'IENNESSEE VALLEY AU'IHORITY DIVISION OF NUCLEAR POWER BROWNS FERRY NUCLEAR PLANP e
MONIELY OPERATING REPORP April 1, 1982 - April 30, 1982 DOGET NUMBGS 50-259, 50-260, AND 50-296 LICENSE NUMBERS TR-33, NR-52, AND TR-68 Subnitted by:
e4t+o Plant rintendent 8206019 3 A
=.
TABLE OF CCNPENIS Operations Stanmary........................
1 Refueling Information......................
4 Significant Operational Events..................
6 Average Daily Unit Pcwer Level..................
15 Operating Data Reports......................
18 dnit Shutdowns and Power Reductions....
21 Plant Maintenance........................
25 Field Services Sumary...................
38 s
. - ~ -. -. -.. -..,.. - -. _ _, - - -.
1 Ooerations simunarv April 1982
%e following sumary describes the significant operation activities during the reporting period.
In support of this summary, a chronological log of significant events is included in this report.
here were 14 reportable occurrences and five revisions to previous reportable occurrences reported to the NRC during the month of April.
Unit 1 here were three scrams on the unit during the month. On April 4 and 8, the reactor scraasned from a generator load reject due to activation of the generator field ground relay.
No causes were found for either load reject, but investigations are continuing.
%e reactor scrammed on April 19, on low NPSH while being loaded to recover reactor water level. We low NPSH was caused when the RFPs exceeded the capabilities of the two hotwell pumps that were operating.
A hotwell pump was tagged for maintenance and while taking a RFP off to do maintenance at the same time, a second RFP was inadvertently tripped.
Power was reduced and the RFPs were placed back in service.
Unit 2 here were no scrams on the unit during the month.
3
2 i
I Ooerations Stmmarv (Continued)
April 1982 l
Unit 3
'1here was one scram on the unit during the month.
On April 12, the reactor was manually scrammed after the turbine was tripped when excessive vibration occurred on "C" low pressure turbine during startup.
Subsequent investigation found damage to the thirteenth stage on the "C" low pressure turbine.
'Ibe unit 3 EOC-4 tcfueling outage ended April 12, however, the unit was down the rest of the month for turbine maintenance.
l l
l l
l I
3 Ooerations Summary (Cmtinued)
April 1982 Faticue Usaae Evaluation The cumulative usage factors for the reactor vessel are as follows:
Location Usaae Factor Unit 1 Unit 2 Unit 3 Shell at water line 0.00549 0.00432 0.00375 Feedwater nozzle 0.26689 0.18768 0.14191 Closure studs 0.21353 0.14460 0.12405 NOTE:
This accumulated monthly information satisfies Technical Specification Section 6.6.A.17.B(3) reporting requirements.
Conrnon System A@roximately 6.56E+05 gallons of waste liquids were discharged containing approximately 6.60E-01 curies of activities.
1 l
l
4 Ooerations m - rv (Continued)
April 1982 Refuelina Information Unit 1 Unit 1 is scheduled for its fifth refueling beginning on or about March 18,1983, with a scheduled restart date of July 18, 1983.
%is refueling will involve loading 8 X 8 R (retrofit) fuel assemblies into the core; finishing the torus modification; turbine inspection; finishing TMI-2 modifications; post-accident sampling facility tie-ins; core spray changeout; and changeout of jet pump hold-down beams.
%ere are 764 fuel assablies in the reactor vessel.
%e spent fuel storage pool presently contains 260 ' EOC-4 fuel assemblies; 232 E00-3 fuel assemblies; 156 EOC-2 fuel assemblies; and 168 EOC-1 fuel assemblies. The present capacity is 1,148 locations.
Modification work and testing is in progress to increase the spent fuel pool capacity to 3,471 assemblies.
Unit 2 Unit 2 is schechled for its fourth refueling beginning on or about July 23,1982 with a scheduled restart date of January 31, 1983.
%is 1
refueling outage will involve empleting relief valve modifications; torus modifications; "A" low-pressure turbine inspection; generator inspection; MG set installation for LPCI modification; loading additional 8 X 8 fuel assemblies into the core; TMI-2 modifications; post-accident sampling facility tie-ins, and changeout of jet pump' hold-down beams.
Were are 764 fuel assemblies in the reactor vessel.
At the end of the month there were 160 new fuel assemblies, 353 E00-3 fuel assemblies, 156 EDC-2 fuel assemblies; and 132 EOC-1 fuel assemblies in the spent fuel storage pool. W e present available capacity of the spent fuel pool is 780
3 5
Ooerations Stmunarv (Continued)
April 1982 Unit - (Continued) locations. n ere are 169 new high-density storage locations that have been installed and can be used after they are qualified.
Unit 3 Unit 3 is scheduled for its fifth refueling on or about August 1, 1983, with a schedulcd restart date of Novenber 28, 1983.
This refueling will involve loading 8 X 8 R (retrofit) assemblies into the core; finishing the torus modifications; post-accident sampling facility tie-in; core spray changeout; finishing 'IMI-2 modifications; turbine inspection; and changeout of jet pump hold-down beams.
Unit 3 ended its EOC-4 refueling outage on April 12, 1982; however, it renained down for the rest of the month because of damage to a low pressure turbine sustained during the initial rolling of the turbine during startup.
Were are 764 fuel assemblies presently in the reactor vessel. There are 288 EOC-4 fuel assemblies; 124 EDC-3 fuel assemblies; 144 EOC-2 fuel assemblies; and 208 E00-1 fuel asseablies in the spent fuel storage pool.
The present available capacity of the spent fuel pool is 985 locations.
6 Sionificant Ooerational Events Unit 1 Date Time Event 4/01/82 0001 Reactor thermal power at 98% due to main steam pressure sensing line vibration.
1500 Reactor thermal power at 97%, holding due to main steam pressure scnsing line vibration.
4/02/82 0920 Comenced power ascension from 97% thermal power.
1000 Reactor thermal power at 99%, maximum flow, rod limited.
2345 Reduced thermal power to 97% for turbine control valve tests and sis.
4/03/82 0100 Turbine control valve tests and sis emplete, commenced power ascension.
0300 Reactor thermal power at 99%, maximtan flow, rod limited.
4/04/82 0849 Reactor Scram No.154(1) from 99% thermal power on generator load reject due to activation of the generator field ground relay (64GF).
Investigation has found no fault which could have cuased the activation of the relay.
1840 Commenced rod withdrawal for start-up.
2043 Reactor Critical No.
174.
2207 Rolled T/G.
2225 Synchronized generator, comenced power ascension.
4/05/82 0530 Commenced PCIOMR from 84% thermal power (Sequence "B").
j 0630 Commenced reducing thermal power frcxn 86% to i
remove "B"
string high pressure heaters from l
service.
0700 Reactor thermal power at 83% for removing "B"
string.high pressure heater from service.
0915 0915 Reactor thermal power at 83% holding due to need to adjust power distribution (R factor).
1110 Commenced increasing thermal power to adjust "R"
factor.
1300 "R"
factor adjusted, reactor power at 89%,
commenced PCIOMR (Sequence "B").
4/06/82 0300 Reactor thermal powr at 99%, maximum flow, rod limited.
l
7 Sionificant Ooerational Events Unit 1 Date Time Event 4/11/82 0130 Increasing thermal power from 65% for control rod pattern adjustment.
0400 Control rod pattern adjustment complete, comenced PCIOMR frm 78% thermal power (Sequence "B").
4/12/82 0600 Reactor thermal power at 99%, maximum flow, rod limited.
1141 Comenced reducing thermal power due to main steam pressure sensing line vibration.
2100 Reactor thermal power at 94% due to main steam pressure sensing line vibration.
4/13/82 0700 Reactor thermal power at 95%, due to main steam pressure sensing line vibration.
2229 Reduced thermal power to 70% when "C" condensate pump tripped.
2300 Reactor thermal power at 70% holding for "C"
condensate pump maintenance.
4/14/82 0800 Ccanenced power ascension from 70% thermal power, "C"
condensate pump maintenance continues.
1610 "C"
condensate pump back in service, power ascension in progress from 72%.
1630 ccmnenced reducing thermal power from 74% due to need to adjust R factor.
1800 Reactor thermal power at 73%,
"R" factor adjustment.
1830 Comenced power ascension from 73% thermal power.
"R" factor adjustment continues.
2011 "R" factor adjusted power ascension in progress, reactor. power at 75%.
2325 Reactor thermal power at 76%,
"R" factor adjustments required.
4/15/82 0505 "R" factor adjusted, reactor thermal power at 76%
due to "C" condensate pump being out of service for maintenance.
0700 Reactor thermal power at 75%,
"C" condensate pump maintenance.
l 1
8 Sionificant Ooerational Events Unit 1 Date-Time Event 4/17/82 1500 Reactor thermal power at 74%,
"C" condensate pump maintenance.
4/19/82 1228 Reactor Scram No.157(2) from 74% thermal power due to operator error. While "C" hotwell pump was off and tagged, "A"
RFP" was tripped for maintenance.
'Ihe operator inadvertently closed steam to "C"
RFP.
He then dropped load with recirculation pumps and reset "A" RFP.
When the RFPs were loaded up to recover reactor water level, they exceeded the two hotwell pumps capability and tripped on low NPSH. 'Ihis resulted in low reactor water level.
1931 Commenced rod withdrawal for startup.
2200 Stopped rod withdrawal due to maintenance on control rod 50-31 accumulator.
2225 Maintenance on control rod 50-31 accumulator
- complete, commenced rod withdrawal.
2253 Reactor Critical No. 176.
4/20/82 0110 Rolled T/G.
0133 Synchronized generator, commenced power ascension.
0430 Cmmenced PCIOMR from 77% thermal power (Sequence "B").
0834 Comenced reducing thermal power from 85% due to Xenon transients.
0900 Reactor thermal power at 79% (Xenon transien*.s),
0909 Cmnenced power ascension for control pattern adjustment.
1600 Camenced PCIOMR from 93% thermal power (Sequence "B").
1800 Reactor thermal power at 94%, maximum flow, rod limited.
4/ 21/82 0135 Cmnenced reducing thermal power due to computer probicms.
0700 Reactor thermal power at 88% due to computer problcms.
1500 Reactor thermal power at 86% due to computer problcus.
t 1
i l
l
9 Sionificant Ooerational Events Unit 1 Date Time Event 4/08/82 0227 Reactor Scram No.155(1) from 99% thermal pcreer when the turbine tripped on generator power load unbalance.
Operations found the generator and exciter field ground detection relays picked up.
No definite cause of the trip could be determined.
1615 Commenced rod withdrawal for startup.
1837 Reactor Critical No.
175.
~
2040 Rolled T/G.
2103 Synchronized generator, comenced power ascension.
4/09/82 0415 Stopped power ascension at 68% thermal power, computer out-of-service.
0515 Comenced power ascension from 68% thermal power.
0600 Comenced PCIOMR from 76% thermal power (Sequence "B").
4/10/82 0110 Reactor thermal power at 91%, maximum flow, rod' limited.
0400 Reactor thermal power at 90%, maximum flow, rod limited.
0500 Reactor thermal power at 89%, maximum flow, rod limited.
0700 Reactor thermal power at 88%, maxmum flow, rod limited.
0900 Reactor thermal power at 87%, maximum flow, rod limited.
1000 Reactor thermal' power at 86%, maximum flow, rod limited.
1500 Reactor thermal power at 85%, maximum flow, rod limited.
1640 Comenced reducing thermal power due to high river differential temperature.
1800 Reactor' power. at 84%, holding due to high river differential temperature.
1806 Commenced power ascension from 84% thermal power.
2000 Reactor thermal power at 85%, maximum flow, rod limited.
2200 Reactor. thermal power at 84%, maximum flow, rod limited.
2210 Comenced ~ reducing thermal power for control rod pattern adjustment.
2235 Reactor thermal power at 65%, holding for control rod pattern adjustment.
10 Sicmificant Ooerational Events Unit 1 Date Time Event 4/24/82 0950 Comenced recbcing thermal power for control rod pattern adjustment.
1100 Reactor thermal power at 72%, holding for control rod pattern adjustment.
3130 Comenced power increase for control rod pattern adjustment.
1628 Control rod pattern adjustment ccuplete, comenced PCIOMR from 80% thermal power.
4/25/82 0700 Reactor thermal power at 96%, holding due to main ste:m pressure sensing line vibration.
2200 Comenced reducing thermal power for control rod pattern adjustment.
2300 Reactor thermal power at 84% for control rod pattern adjustment.
2330 Control rod pattern adjustment complete, comenced PCIOMR from 84% thermal power.
4/26/82 0000 Reactor thermal power at 96% due to main steam pressure sensing line vibration.
1000 Reactor thermal power at 95% due to main steam pressure sensing line vibration.
4/27/82 1255 Comenced power ascension from 95% thermal power.
1315 Reactor thermal power at 99%, maximum flow, rod limited.
4/30/82 1005 Ccmnenced reducing thermal power to remove "A"
reactor feed pump from service for maintenance.
1045 "A"
reactor feed pump renoved from service for maintenance on RIM gage, reactor thermal power at 73%.
1130 "A" reactor feed pump back in service, comenced power ascension.
1230 Reactor thermal power at 99%, maximtzn flow, rod limited.
2350 Comenced reducing thermal power for turbine control valve tests and sis.
4/30/82 2400 Reactor thermal power at 975e reduction in progress for turbine control valve tests and sis.
11 Sionificant Ooerational Events Unit 2 Date
-Time Event 4/01/82 0001 Reactor thermal power at 97%, maximum flow, EOC-4 coastdown.
15'h)
Reactor thermal power at 96%, maximum flow, EOC-4 coastdown.
4/07/82 0700 Reactor thermal power at 95%, maximum flow, EOC-4 coastdown.
4/10/82 0028 Comenced reducing thermal power for turbine control valve tests and sis.
0048 Reactor thermal power at 92%, holding for turbine control valve tests and sis.
0100 Turbine control valve tests and sis complete, commenced power ascension.
0200 Reactor thermal power at 96%, maximum flow, BOC-4 coastdown.
1045 Reactor therm 1 power at 95%, maximum flow, BOC-4 coastdown.
4/11/82 1800 Comenced reducing thermal power due to high river differential temperature.
2000 Reactor thermal power at 67%, holding due to high river differential temperature.
2120 Comenced power ascension from 67% thermal power.
4/12/82 0200 Reactor thermal power at 95%, maximum flow, BOC-4 coastdown.
2200 Reactor thermal power at 94%, maximum flow, EDC-4 coastdown.
4/13/82 1515 RedJced thermal power to 85% when recirculation pump ran back while transferring boards.
1516 Comenced power ascension from 85% thermal power.
1525 Reactor thermal power at 94%, maximum flow, EDC-4 coastdown.
4/14/82 0900 Reactor thermal power at 93%, maximum flow, EOC-4 coastdown.
4/15/82 1500 Ccanenced power ascension after IMs set stops on recirculation pump MG set to prevent exceeding 105% rated core flow.
1600 Reactor thermal power at 95%, maximum flow, EOC-4 coastdown.
12 Sionificant Ooerational Events Unit 2
_Date
- Time Event -
2100 Reactor thermal power at 94%, maximum flow, EOC-4 coastdown.
4/17/82 0635 Comenced reducing thermal power due to probles with recirculation pmp MG sets (AMPS swinging).
0900 Reactor thermal power at 85% due to recirculation p mp MG set probi ms.
0920 Comenced power ascension from 85% thermal power.
1500 Reactor thermal power at 94%, maximum flow, EDC-4 Coastdown.
2230 Commenced reducing thermal power for STEAR 81-17 (Recirculation Pump MG Set Test).
2300 Reactor thermal power at 81%, holdJng for STEAR 81-17.
2320 Commenced power ascension, STEAR 81-17 in progress.
4/18/82 0005 Reactor thermal power at 91% for STEAR 81-17.
0020 Commenced reducing thermal power for STEAR 81-17.
0100 Reactor thermal power at 80% for STEAR 81-17.
0115 Ccm.nced power ascension from 80% thermal power, STEAR 81-17 in progress.
0159 STEAR 81-17 complete, reducing thermal power from 92%
for SI 4.1.A-ll (MSIV Closure).
0215 Reactor thermal power at 82% for SI 4.1. A-ll.
0237 SI 4.1. A-ll complete, commenced power ascension.
1100 Reactor thermal power at 94%, maximum flow, EDC-4 coastdown.
2300 Reactor thermal power at 93%, maximum flow, EOC-4 CoaFtdoWD.
4/20/82 2300 Reactor thermal power at 92%, maximum flow, EOC-4 coastdown.
4/21/82 1500 Commenced reducing thermal power due to "B"
recirculation pump motor amps and valves swinging.
1600 Reactor thermal power at 85%, holding due to "B" recirculation pump problems.
1730 Commenced power ascension from 85% thermal power.
2325 Reduced thermal power from 91% to 88% due to "B" recirculation pump motor amps swinging.
4/22/82 0010 Commenced power ascension from 88% thermal power.
0700 Reactor themal power at 91%, holding due to computer probi ms.
l 13 Sionificant Goerational-Events Unit 2 Date Time Event 4/ 23/ 82 0203 Reactor thermal power at 91%, maximm flow, EDC-4 coastdown.
1530 Reactor thermal power at 90%, maximm flow, EDC-4 coastdown.
4/25/82 1500 Reactor thermal power at 89%, maximum flow, EOC-4 coastdown.
4/26/82 0800 Commenced reducing thermal power for removal of "B"
condensate booster pump from service for maintenance (seal line leak).
1000 Reactor thermal power at 66% for maintenance to "B"
condensate booster pump seal line leak.
1030 Maintenance to "B"
condensate booster pump
- complete, commenced power ascension.
1500 Reactor thermal power at 93%, maximm flow, EDC-4 coastdown.
1600 Reactor thermal power at 92%, maximum flow, EOC-4 coastdown.
2300 Reactor thermal power at 91%, maximum flow, EOC-4 coast.down.
4/30/82 2400 Reactor thermal power at 91%, maximum flow, EDC-4 coastdown.
l
14 Sionificant Ooerational Events Unit 3 Date Time Event 4/01/82 0001 End-of-cycle 4 refueling outage continues.
4/06/82 1308 Startup sis in progress.
4/10/82 0805 Commenced rod withdrawal for startup.
0849 Reactor Critical No.117.
4/11/82 0150 Holding for completion of startup sis and final drywell inspections.
2236 Reactor in run mode.
4/12/82 1115 Rolled T/G.
1152 Tripped main turbine die to high vibration (cycle 4
refueling outa ends).
Reactor Manual Scram No,' 105(1) g e 1657 from 20% thermal power due to main turbine high vibration.
4/13/82 0115 Reactor in cold shutdown for "3C" low pressure turbine outage.
4/30/82 2400 Reactor in cold shutdown for "3C" low pressure turbine outage.
(1)RIuipnent Malfunction (2) Personnel Error
-a,,
- - _. _ _. - -. ~. -
15 AVERAGE DAILY UNIT POWER LEVEL l
DOCKET NO.
50-259 UNIT Browns Ferry - 1 1
DATE 5-1-82 COMPLETED BY Ted Thom TELEPilONE 205 729 0534 April SiONTil DAY AVER AGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL 151We-Net) istwe. Net,
1042 765 i
g7 2
1057 756
[
33
]
3 1066 393 39 409 847 j
20 i
921 922 5
1052 902 6
3 i
1062 7
23 131 870 g
826 982 9
5 897 1000 10 895 1043 Il 27 i
1024 1062 g,
28 13 984 1069
,9 744 1033 i.
3g 772 4
IS 31 i
16 772 l
INSTRUCTIONS On this forinat, hst the aserage dash sunt power lesel in MWe.Nei f.>r each day in the rep.isting in.inth. C.unpute to the twarest whole nwegawait.
i l
l
('8 f 77 )
l l
i L
16 4
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-260 UNIT Ilrowns Ferry - 2 DATE 5-1-82 CONIPLETED BY Ted "Thom TEl.EP110NE 205 729 0834 MONTil April DAY AVER AGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net)
I 1061 995 g7 2
1056 18 990 3
1052 1003 i9 4
1047 1003 20 5
1041 989
,I 1039 980 6
22 1035 975 7
3 1031 973 8
24 1035 937 9
25 10 1023 943 26 I
95 988 6
ii 7
1019 983 12 28 l
13 29 1004 984 998 966 j
14 3g 1005 15 1016 t
16
?
s INSTRUCTIONS On this format.!ist the average dails nmt pimer lesel m MWe Net for e.ich day m the repenting month. Compute to the nearest whole megawatt.
p;t77)
)
i
17 AVERAGE DAILY UNIT POWER LEVEL 50-296 DOCKET NO.
Browns Ferry - 3 UNIT 5-1-82 DATE COMPLETED BY Ted Thom TELEPHONE 205 729 0834 MONTil April DAY AVER AGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe-Net)
(Mwe.Neg g
-12
-13
,7
-12
-12 gg 2
-12
-13 3
39
-11
,g 20
-13
-11 21 5
-12
-12 6
22
-9
-13 7
23
-9
-l'3 8
y
-10
-12 9
25
-11 10
-13 26
~14
-12 1I 27
-14
-12 12 28
-13
-13 l
13 79 l
-12
-12 30 14
-12 15
-12 16 i
i INSTRUCTIONS On this t'orinat !ist the asera.;c daily umi power lesel in MWe-Net for.ach day in the reposting inonth. Coinpute to l
the nearest whole nwgawaii.
l r
l (0177) l I
i l
-r-
18 OPERATING DATA REPORT DOCKET NO.
50-259 DATE 5-1-82 COMPLETED BY Tod Thom TELEPl!ONE 205 729 0834 OPERATING STATUS
- 1. Unit Name:
Browns Ferry - 1 Notes
- 2. Reporting Period:
April 1982
- 3. Licensed Thermal Power (Mht):
3293
- 4. Nameplate Rating (Gross MWe):
1152
~,
- 5. Design Electrical Rating (Net MWe):
1065
- 6. Maximum Dependable Capacity (Gross MWe):
1098.4
- 7. Maximum Dependable Capacity (Net MWe):
1065
- 8. If Changes Occur in Capacity Ratings (items Number 3 Through 7) Since Last Report. Give Reasons:
NA kt
- 9. Power Lesel To Which Restricted. lf Any (Net MWe):
NA
- 10. Reasons For Restrictions.lf Any:
NA This Month Yr.-to-Date Cumulative i1. Ilours in Reporting Period 719 2,879 67,921 t
- 12. Number Of flours Reactor Was Critical 680.52 2,609.97 41,924.77 1
- 13. Reactor Reserve Shutdown flours 38.48 220.63 5,435.83 I4. Ilours Generator On Line 673.72 2,572.57 41,002.74
- 15. Unit Resene Shutdown llours 0
0 0
- 16. Cross Thermal Energy Generated (MWII) 1.967,002 7.945,651 114,820,558
- 17. Gross Electrical Energy Generated (MWil) 645,260 2,589,230 37,881,680
- 18. Net Electrical Energy Generated (MWII)
-_ 627,695 2,521,170 36,790,079
~
- 19. Unit Senice Factor 93.7 89.4 60.4
- 20. Unit Asailability Factor 93.7 89.4 60.4
- 21. Unit Capacity Factor (Using MDC Net) 82.0 82.2 50.9
- 22. Unit Capacity Factor (Using DER Net) 82.0 82.2 50.9
- 23. Unit Forced Outage Rate 6.3 10.6 26.2
- 24. Shutdowns Scheduled Oser Nest 6 Months (Type. Date,and Duration of Each):
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
- 26. Units in rest Status (Prior to Commercial Operationi:
Forceast Achies ed INITI \\ L CRITICA LITY INil'l \\L ELECTRICITY CO\\l\\lERCI \\ L OPER A TION (9/77)
19 OPERATLNG DATA REPORT DOCKET NO. 50-260 DATE 5-1-82 CO.\\lPLETED BY T-Thom TELEPilONE 70s 729 0834 OPERATING STATUS
- 1. Unit Name:
hows Feny - 2 Notes
- 2. Reporting Period:
April 1982
- 3. Licensed Thermal Power (StWt):
3293
- 4. Nameplate Rating (Gross.\\lWe):
1152 1065
- 5. Design Electrical Rating (Net 31We):
- 6. Staximum Dependable Capacity (Gross 51We):
1098.4 1065
- 7. Sf aximum Dependable Capacity (Net SIWE):
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:
NA NA
- 9. Power Level To Which Restricted,1f Any (Net 31We):
- 10. Reasons For Restrictions,If Any:
NA This 5f onth Yr to-Date Cumulative
- 11. Ilours In Reporting Period 719 2,879 62,862 I
~
- 12. Number OfIlours Reactor Was Critical 719 2,712.78 41,159.74 0
157.72 13,639.45
- 13. Reactor Reserve Shutdown llours
- 14. Ilours Generator On-Line 719 2,657.38 39,854.47
- 15. Unit Resene Shutdown llours 0
0 0
- 16. Gross Thermal Energy Generated (31WII) 2.211.221 8,395,961
_115,048,751
- 17. Gross Electrical Energy Generated (AtWil) 743 QiQ _,
2.831.750 38.264.398
- 18. Net Electrical Energy Generated (51Wil) 722.695 2.761.277 37.183,423
- 19. Unit Senice Factor 100 92.3 63.4
- 20. Unit Availability Factor 100 92.3 63.4
- 21. Unit Capacity Factor (Using atDC Neti 94.4 90.1 55.5
- 22. Unit Capacity FactorIUsing DER Net) 94.4 90.1 55.5 1
- 23. Unit Forced Ontage Rate 0
7.7
__28.1
- 24. Shutdowns Scheduled Oser Nest 6 alonths IType. Date,and Duration of Eacht:
Refuel July 1982
- 25. If Shut Down At End Of Report Period, Estimated Date of Startup:
- 26. Units in Test Status iPrior to Commercial Operationi:
Forecast Achiesed l
INITIA L CRITICALITY INITIA L ELECTRICITY CO\\l\\tERCI \\ L OPER ATION i
(9/77)
20 OPERATING DATA REPORT
~
DOCKET NO. 50-296 DATE 5-1-82 COStPLETED BY Ted Thom TELEPliONE 295 790 n834 OPERATING STATUS
- 1. Unit Name:
Browns Ferry - 3 Notes
- 2. Reporting Period: April 1982
- 3. Licensed Thermal Power (SIWt):
3293 1152
- 4. Nameplate Rating (Gross 31We):
1065
- 5. Design Electrical Rating (Net SlWe):
- 6. Stasimum Dependable Capacity (Gross SIWE):
1098.4 1
- 7. Alasimum Dependable Capacity (Net AlWe):
1065
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Gise Reasons:
NA
- 9. Power Level To Which Restricted,if Any (Net.\\lWe):
NA NA
- 10. Reasons For Restrictions,If Any:
This $1onth Yr..to.Date Cumulative 11.11ours in Reporting Pen. d 719 2,879 45,287
?
o
- 12. Number Of flours Reactor Was Critical 56.13 56.13 32,523.11 438.79 438.79 2,580.32
- 13. Reactor Reserve Shutdc wn flours
- 14. Ilours Generator On Line 0
0 31,750.78
- 15. Unit Resene Shutdown flours 0
0 0
- 16. Gross Thermal Energy Generated (51Wil) 0 0
_93,858,620
- 17. Gross Electrical Energy Generated (51Wil) 0 0
30,998,190
- 18. Net Electrical Energy Generated (51Wil) 0 e
30,088,046
- 19. Unit Senice Factor 0
0 70.1
- 20. Unit Availability Factor 0
0 70.1-
- 21. Unit Capacity Factor (Using SIDC Net) 0 0
62.4
- 22. Unit Capacity Factor (Using DER Net) 0 0
62.4
- 23. Unit Forced Outage Rate 61.6*
61.6*
10.4
- 24. Shutdowns Scheduled Oser Next 6 \\lonthqType. Date.and Duration of Eacht:
- Forced outage rate = Turbine outage 1. Turbine outage + refuel outage for this month only
^
- 25. If' Shut Down At End Of Report Period. Estimated Date of Startup:
5-13-82
- 26. Units in Test Status t Prior to Commercial Operation):
Forecast Achiesed INITI \\ L CRITICA LITY INITIAL ELECT RICITY CO\\l\\lERCI \\ L OPER TTION (9/77)
Y UNIT SilUTDOWNS AND POWER REDUCTIONS DOCKET NO.
50-259
.j UNIT N AME Browns Ferry - 1 l
DATE 5-1-82 l
REPORT MONTil April COMPLETED BY Tod Thnm j
TELEPif0NE 205 729 0834
?
I 5.a 3 5
5 -.
n E4 Licensee E.,
N C'"5e & C"'re'8ive 5E E
'2
[F y.5 3
.j s 5 Event E$
!.3 No-Date Action to 2 is =!
i'eport e AG EC Present Recurrence o
c:
6 e
6 216 4/04/82 F
13.60 A
3 Reactor scram on generator load reject due to activation of the i
g erator field ground relay.
2L7 4/08/82 F
18.60 A
3 Reactor scram when the turbine tripped on generator power load un-balance.
218 4/10/82 S
'H
'Derated for control rod pattern S
adjustment.
219 4/13/82 F
A Derated when "C" condensate pump tripped.
220 4/19/82 F
13.08 G
3 Reactor scram due.to operator error.
~
While "C" hotwell pump was off and tagged, "A" RFP was tripped for main-tenance. Th'e. operator inadvertently closed steam to "C" RFP lie then dropped load with recirculationepumps andreset "A" RFP. When the RFPs were (Continued on next page)
I 2
3 4
F: Forced Reason:
Method:
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 (l.l:R) File (NUREG-()-Regulatory Restriction 4 Other (Explain) 0161) 1:-Operator Training & License Examination F-Administrative 5
G-Operational Er ror (Explain)
Exhibit 1 - Same Source (9/77)
Il-Other ( Explain)
e 50-259 DOCKET NO.
UNtTSilUTDOWNS AND POWER REDUCTIONS Browns Ferry - 1 UNIT NAME DATE 5-1-82 REPORT MONTil April (Continued)
COMPLETED BY T-Thom j'
TELEPIIONE
?ns 729 0834 i.
n.
4.s 5 E
c,
'4 Licensee
~ -r, P.
Cause & Correctise
.5 ?
s
~?
s-?
Action to No.
Date g
g
{
,g g $
Event g
j5 5,
t5:
Report a mV 5'
Prevent Recurrence H
5 o
C 220 (Continued) loaded up to recover reactor water level they exceeded the two hotwell, pumps capability and. tripped on: low NPSH. This resulted in low water level.
221 4/30/82 F
B Derated t'o eremove "A" RFP from service for maintenance on RPM gauge, m
N 4
1 2
3 4-F: Forced Reason:
Method:
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 Refucling 3-Automatic Scram.
Esent Report (LER) File (NUREG-D-Regulatory Restriction 4-Other ( E xplain) 0161)
E-Operator Training & License Examination F Administrative 5
G. Operational Error (Explain)
Exhibit I-Same Source (9/77)
Il-Other (Explain )
o
DOCKET NO.
50-260
'j'-
UNITSilUTDOWNS AND POWER REDUCTIONS UNIT NAME Browns Ferry -2 DATE 5-1-82 COMPLETED BY Ted Thom
}l REPORT MONTH April TELEPIIONE 205,29 0834 1,
w.
E E
.] -
"h j.Y M Licensee
,E-e, K
Cause & Corrective il d,5.5 s 5 Event g
g'?
Action to No.
Date y,
3g gL Present Recurrence jE jgg Report =
t-, U H
di 233 4/11/82 F
D Derated due to high river differential temperature.
234 4/26/82 F
B Derated touremoire "B" condensate pump from service for maintenance ru w
I I
2 3
4 F: Forced Reason:
Method:
Exhibit G. Instructions S: Scheduled A Equipment Failure (Explain) 1-Manual for Preparation of Data it-Maintenance of Test 2-Manual Scram.
Entr> Sheets for Licensee C Refueling 3 Automatic Scram.
Esent Report (LER) File (NUREG.
D Regulatory Restriction 4-Other ( Explain) 0161)
E-Operator Training & Ucense Examination F Administrati.e 5
G-Operational Error (Explain)
Exhibit I Same Source (9/77)
Il-Ot her (5'.xplain)
9 DOCKET NO.
50-296 UNITSifUTDOWNS AND POWER REDUCTIONS UNIT N AME Rr nt m e Farrv -3 DATE 5-1-82
+
f COMPLETED BY Tod Thnm REPORT MONTil April TELEPl!ONE Jos 790 nntA 3
S ei 3w=
.= _e
,sa Licensee g*,
c9.
Cause & Corrective 2
=
No.
Date g
3g
,g g 5 Event s?
$?
Action to
$5 5
j di Report e
- 8. 0 y'
Prevent Recurrence O
93 4-01-82 S
275.87 C
2 Reactor scram to accommodate EOC-4 Cont refuel outage.
94 4-02-82 F
443.13 A
2 Tripped main turbine due to high sib-ration. Manually scrammed reactor due to high vibration on main turbine l
2 3
4 F: Forced Reason:
Method:
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) Fil-(NtlRI:G-D-Regulatory Restriction 4-Other ( Explain) 0161) 1:-Operator Training & License Examination F Administrative 5
G-Operational Eirur (Explain)
Exhibit I Same Source (9/77)
Il-Other (Explain)
BROWNS FERRY NUCLEAR PIANT UNIT 2
l CSSC EQUIPMENT MECHANICAL MAINTENANCE SUFD! ART Fc,r the Month of April 1982 EFFECT ON SAFE ACTION TAKEN DATE SYSTEM COMPONENT NATURE OF OPERATION OF CAUSE OF RESULTS OF IO PRECLUDE PAINTENANCE THE REACTOR MALFUNCTION MALFUNCTION RECURRENCE 4-2 High Line between Waterileak None Unknown Pin hole 3" line Welded hole in pipe, Pressure valves26-990 hydrostatic tested Fire and 26-984 to 225 PSI for a crim Protection
' period of 15 minutes.
TR 337818 4.-5 CR0 HCV 85-517 Faulty hand '
None Unknown Retaining nut broken Fabricated nut and wheel installed with hand-wheel.
TR 307412
3-8 RCIC Valve 71-570 Water leak None Worn packing Packing leak Repacked with grafoil packing.
TR 318597 4-19 RCIC RCIC turbine Possible None Possible bearings None Pulled beaking cap rotation on off to check bearing coupling end.
for anti-rotation pin, it was stilliin tact.
TR 233336 e
..+a=
'N
~ _..
e
BROWNS FERRY NUCLEAR PIANT UNIT l
CSSC EQUIPMENT MECHANICAL MAINTENANCE SUFNARY For the Month of April 19 82 EFFECT ON SAFE ACTION TAKEN DATE SYSTEM COMPONENT NATURE OF OPERATION OF CAUSE OF RESULTS OF n) PRECLUDE MAINTENANCE THE REACTOR MALFUNCTION MALFUNCTION RECURRENCE 4-19 CRD Water Water leak None Faulty Accumulator leaking Replaced accumulator Accumulator accumulator through with rebui't.
In-Module 50-31 stalled o' rings upper and lower.
TR 338934 3-22 HPCI Inboard Booster Oil added None None None Drained old oil out Pump without and cleaned sump and inhibitor bearings and added ST0-1 with inhibiter.
TR 233113 0?
e S
-mm
=
F
\\
~. - _.
e 9
13ROWNS FERRY EUCLEAR PIANT UNIT 3
CSSC EnUIPMENT MECHANICAL MAINTENANCE
SUMMARY
For the Month of April 19 82 EFFECT ON SAFE I
ACTION TAKEN DATE SYSTEM COMPONENT NATURE OF OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE MAINTENANCE THE REACTOR MALFUNCTION MALFUNCTION RECURRENCE 4-18 Diesel Air compressor Air leak None Faulty check Air leakage Replaced check valve. '
Generator
- 1 3C D/G valve TR 341599 3-31 Main Steam Block valve Valve mal-None Bad block valve Low side will not Replace block valve gT g51 on PNL function operate TR 240887 g
3-31 HPCI HPCI turbine Faulty magne-None Unknown End of magnetic pick Installed new magnetic pickup tic pickup up damaged magnetic pickup TR 337819 3-26 RHR; 3B RHR room Leakage None Unknown Cooler leaking Soldered nipple cooler around lower vent TR239295 nipple 4-2 EECW 3B control bay Faulty valve None Regulating valve Valve not operating Rebuilt valve with chiller PCV 67-79 spring weakened properly new parts (for spare from rust.
TR 327000 0
4-7 LPCI Valve 74-91 Faulty None Key was missing, Broken handwheel Installed 3/16 key handwheel handwheel fell and new handwheel e
off TR 281049 4-17 Generator A control bay Water leak None Soldered sweat Copper line leaking Resoldered sweat joint Hydrogen AHU, hotwater joint sprang TR 225782 bypas -
leakage s
4-2 HPCI HPCI turbine Missing studs None Unknown Flange inoperable Fabricated studs and flange and nut.,
nuts
~.
~
TR 233337
. 3h8 RCIC RCIC EG-R Faulty E'G-R None Bad EG-R Inoperable Replaced EG-R N
control unit TR 307703
~ 1-6 RHR 3A RHR pump Water leak None Cracked pipe Water leuage Welded pipe suction vent TR 281063 line k
BROWES FERRY NUCLEAR PLAMT UNIT 3
CSSC EQUIP >ENT MECHANICAL MAINTENANCE
SUMMARY
For the Month of April 19 82 EFFECT ON SAFE ACTION TAKEN DATE SYSTEM COMPONENT NATURE OF OPERATION OF CAUSE OF RESULTS OF 10 PRECLUDE MAINTENANCE THE REACTOR MALFUNCTION MALFUNCTION RECURRENCE 4-8 CRD Star valve Water luk None Worn packing Packing leak Replaced valve module 54-31 packing TR 281077 4-13 HPCI Barometric Seal blown None Pressure Top and bottom head Replaced gaskets and condenser gaskets blew out heads TR 225767 4-6 CRD Module 34-03 Water leak None Faulty accumula-Excessive water Changed. accumulator tor and stem leakage and replaced stem gasket gasket TR 281054 31 RHR FCV 74-74 Valve inop-None Faulty clutch Clutch gear con-Replaced clutch gear erable gear tributing to valve TR 25064 malfunction
,i c~
j' 4
1 l
1 i
~_
~
9
BROWfiS FERRY NUCLEAR PIANT UNIT COMMON CSSC EQUIP 1ENT MECHANICAL MAINTENANCE
SUMMARY
For the Month of April 1982 EFFECT ON SAFE ACTION TAKEN DATE SYSTD1 COMPONENT NATURE OF OPERATION OF CAUSE OF RESULTS OF 70 PRECLUDE MAINTENANCE THE REACTOR MALFUNCTION MALFUNCTION RECURRENCE 4-1 High A fire pump Sheared roll None Unknown Roll pins sheared on Replaced roll pins, Pressure pins gear box coupling and k key in upper Fire coupling half.
Protection TR 281019 2-iG Containment H0 Sample Faulty pump None Cams and shaft Bearings bad Replaced bearings.
Inerting Pbmh worn out cams and shaft.
a TR 337806 2-11 Containment Spare H 0 Needs Rebuild None Worn pump Bearings, cams and Replaced bearings, Inerting Samplehu$p shaft worn out cams and shaft.
TR 337809 O!
o e
e e
em e-g ew
_ e.
U e
BROWNS FERR1T NUCLEAR PLANT UNIT 1 & Common CSSC EQUIPMENT ELECTRICAL MAINTENANCE
SUMMARY
For the Month of April 19 82 Effect on Safe Action Taken Nature of Operation of Cause of Results of To Preclude Date System Component Maintenance The Reactor Malfunction Malfunction Recurrence 3/26/82 Contain-Solenoid While perform-
"A" channel Shorted bridge This electrical The solenoid ment assembly ing SI4.7.H containment rectifier in r.hort caused breaker assembly was Inerting FSV-76-51 the "A" channel atmosphere the (FSV-76-51) 224 in panel 9-9 to replaced,on containment monitor inoper-solenoid trip. This breaker FSV-76-51 and atmosphere able.
assembly.
supplies power to SI4.7.H.
monitor would Analyzer "A" pri-SI4.7.D.l.B-1(B) j not function mary containment and SMI 176 were in the drywell isolation logic and sucessfully modo.
i.
associated Analyzer completed.
"A" H 0 valves
- TR #237248 22 LER#BFRO-50-259/
8222 u>
O 3/27/82 React $r Generator "A" recircula-
"A" recircula-Relay action "A" recirculation SI's4.6.A-6 and 7 '
Water stator temp.
tion pump trip-tion pump in-was initiated pump tripped.
was performed and Recircu-relay ped due to operable.
by RTD high-the pump returned lation (2AK45A) supurious temp. trip.
to service.
generator Special Test 81-17 stator relay to study this operation.
' problem has been performed and the results are now under evaluation.
The test results will be addressed
.[
in the followup report for LER#
BFRO-50-259/8223.l i
I J
J
BROWNS FERRY NUCLEAR PLANT UNIT 1 & Common CSSC EQUIPMENT ELECTRICAL MAINTENANCE SU101ARY For the Month of April 19 82 Effect on Safe Action Taken Nature of Operation of Cause of Results of To Preclude Date System Component Maintenance The Reactor Malfunction Malfunction Recurrence 4/1/82 HPCI HPCl Turbine "open" indica-None Limit switch "open" indicating Replaced the control valve ting light mechanical light inoperable.
damaged cable, 73-19 would not cable damaged.
Indicating lights illuminate.
operated properly.
TR #25092 4/3/82 RHR 1 EA LPCI MG Output voltage None LPCI voltage Output voltage Adjustr$ents were 4/12/82 set voltage drifting.
regulator out
- drifting, made to the regulator.
of adjustment.
voltage regulator on 4/3/82 to increase vo?.tage,w the regulatnr was "
adjusted again on 4/12/82 to de-crease voltage.
At present the voltage is stable.
TR #207054 TR #314406 4/9/82 Air "lB" control Control bay Non3 Leak in the Chiller inoperable.
Repaired leak, Condition-- bay chiller.
chiller loosing chiller compres-charged chiller' ing freon.
sor discharge with freon and (cooling-line.
returned it to heating) service.
TR #187538 l
3 i
=
BROWNS FERRY NUCLEAR PLANT UNIT 1 & Common CSSC EQUIPMENT ELECTRICAL MAINTENANCE
SUMMARY
For the Month cf April 19 82 Effect on Safe Act.an Taken Nature of Operation of Cause of Results of To Preclude Date System Component Maintenance The Reactor Malfunction Malfunction Recurrence I
4/10/82 RPS CRD scram Relay was None Bad relay.
Relay was humming Replaced the relay header low-humming loudly
- loudly, per EMI-23, the pressure relay operated relay properly.
i 63X-85-35-Al TR F314401
]
(RPS channel A1) 4/19/82 Annuncia-Annunciator Panel XA-55-6C None Bad inverter.
Annunciator panel Replaced the bad tor &
panel XA fail to test.
XA-55-6C inoperable.
Inverter, the Sequent-6C on panel annu., iator panel ;
u ial 9-6.
operated properlyS)
Event TR #338945 Recording 4/24/82 RyR SBM control SBM control None Bad switch.
SBM control switch Replaced the bad switch for switch would would not operate switch per EMI-23, FCV-2-74-72.
not operate in in opening valve.
the new switch opening FCV.
operated properly.
TR #314091 I
4/24/82 RHR RHR pump A Valve inoper-hone Wire insulation Grounded circuit.
Cleared ground and shutdown cool-able.
- damaged, repaired insula-ing suction tion, the valve valve (FCV operated properly.,,
74-2)
TR #339040 lt I
D e.
BROWNS FERRY NUCLEAR PLANT UNIT 2
CSSC EQUIPMENT ELECTRICAL MAIh'IENANCE
SUMMARY
For the Month of April 19 82 Effect on Safe Action Taken Nature of Operation of Cause of Results of To Preclude Date System Component Ma in t er.anc e The Reacter Malfunction Malfunction Recurrence 4/27/82 HPCI LCV-2-73-8 Level control None Blown fuse in LCV-2-73-8 inoper-Replaced the blown valve inoper-the control able.
fuse, the valve able.
circuitry, was tested and operated properly.
TR #314089 4/28/82 4KV shut-Degraded vol-During the None "C" phase relay The relay dropped The rel'ay was cal-down tage relay on performance was out-of-cal-out at 112.64 volts.
ibrated to dropout boards &
"C" phase of of schuduled ibration.
The acceptable at ll2.04V. All buses 4KV shutdown calibration limits are 111.43 other relays on bd. D.
(S1 4.9.A.4.C) volts through 112.57 4KV shutdown bds. w to the degrad-volts.
A, B, C and D were) ed voltage fc nd within relays on 4KV tolerance.
shutdown bd. D TR #225025 the relay on LER #BFRO-50-260/
"C" phase was 8215 found slightly out-of-calibra-tion.
S 8
1 k
BROWNS FERRY WUCLEAR PLANT UNIT 3
CSSC EQUIPMENT ELECTRICAL MAINTE'WICE SLHMARY For the Month of April 19 82 9
Effect on Safe Action Taken Nature of Operation of Cause of Results of To Preclude Date System Component-Maintenance The Reactor Malfunction Malfunction Recurrence 4/8/82 Diesel D/G 3B NVR Received a None Burned NVK Received a false Replaced the bad Generator s relay.
control power relay.
power "off" alarm.
relay, the alarm "off" alarm circuitry opera-in the control ted properly.
I room and at TR #281122..
the local pane:
for D/G 3B.
+
l 4/22/82 4KV Shut-C phase de-During the per-None, unit in The relay had The minimum dropout The relay was re-l down Bds.
graded volt-formance of cold shutdown.
drifted down to voltage setting for calibrated. The and age relay on scheduled (SI a dropout volt-the relay was other relays on Busses 4KV shutdown 4.9.A.4.C) age of 111.24.
slightly low.
4KV shutdown bds$ '
board 3EA.
calibration Acceptable 3EA, 3EB, 3EC, of the degrad-limits are from and 3ED were 4
ed voltage 111.43 volts to found to be with-relays the C 112.57 volts.
in tolerance.
phase relay on TR #225026 shutdown bd, 3EA failed to operate within I
acceptable limits.
1 s
3 i
I e
.~
=
... ~
BROWNS FERRY EiUCLEAR PLANT UNIT 3
CSSC EQUIPMENT ELECTRICAL MAINTENANCE
SUMMARY
I For the Month of April 19 82 q
Effect en Safe Action Taken Nature of Operation of Cause of Results of To Preclude i
Date System Component Maintenance The Reactor Fb1 function Malfunction Recurrence 1
3/30/82 HPCI HPCI steam Steam packing None Bad motor and Steam packing Replaced the bad packing ex-exhauster in-broken wire.
exhauster inoperable, motor per EMI-33 hauster motor, operable.
and repaired the broken wire per EMI-58. The
- motor was tested for proper rota-i tion and returned i,
to service.
TR #281003 i
4/1/82 HPCI LCV 3-73-8 Control switch None Bad coil.
Level control valve Replaced the bad appeared not (LCV 3-73-8) inop-coil. The plunger j to be working.
erable.
seemed to be sticking, initiated i
TR to mechanical.
TR #25095.
4/2/82 Unit Pre-Unit preferred The MG set None Blown fuse.
Erratic voltage.
Replaced the blown ferred MG set.
voltage was fuse and checked 120 Volt erratic when the circuit.
AC..
attempt was returned the MG i
made to set to service.
i i
synchronize TR #281025 g
j the MG set to the board.
l l;'
)
i
BE0WNS FERRY EUCLEAR PLANT UNIT 3
CSSC EQUIPMENT ELECTRICAL MAINTENANCE SUM >L\\RY For the Month of_
April 19 82 Effect on Safe Action Taken Nature of Operation of Cause of Results of To Preclude Date System Coraponent Maintenance The Reactor Malfunction Malfunction Recurrence 4/6/82 Annuncia-Annunciator Annunciator None Loose flash Panel XS-55-3B Tightened the tor & Se-panel XS panel would card.
would not illuminate, loose card, tested quential 3B on panel not illuminate, panel, lights Events 9-3 operated properly.
Recording TR #227676 I
e
?
9 0
0 i
6
~
~
INSTRUMENT MAINTEMANCE SUMMA.RY
_CSSC EQUIPMENT FOR ~ DIE MONI11 OF April 19 R9 NATURE EFFECT 05 SAFE CAUSE ACTION TAKEN 1 ATE SYSTDI COMPONENT OF OPERATION OF OF RESULTS OF TO PRECLUDE MAINTENANCE THE REACTOR MALFUNCTION MALRmCTION RECURRENCE U-0 4 /02 65 FT-65-60 Repair None Paulty Amplifier Erratic Indication None U.
4/02 68 FT-68-5B Repair None Paulty Amplifier Incorrect Out'put None S
4/12 71 IS-71-2A Repair None Paulty Heater Switch would not test None U-2 4/20 73 SI-73-51 Calibrate None Instrument Drift Incorrect Indication
,None
' 4/23 73 FM-73-33 Calibrate None Instrument Drift Incorrect Output None
, 4/29 64 LI-64'-66 Calibrate None Instrument Drift Incorrect Indication
. ~
None U-3 4
4/09 74 FM-74-76 Calibrate None Instrument Drift Incorrect Output None M-4/29 67 PS-67-1 * -
Replace None Paulty Contacts Improper SW Action None pop e
G 9
N w
l k
e
~
4 9
e 5
e e
D
38 FIELD SERVICES
SUMMARY
April 1982
'Ihe refueling outage on tait 3 cycle 4 was declared officially over on April 12, 1982 after 163.5 days. 'Ihe field breaker was not closed but a forced outage declared on April 12 when the "C" low pressure turbine was damaged.
Electrical Sinmm__ry Electrical work that had been started prior to or during April and cmpleted in April included: installation of a larger pump motor for the llayes Republic H202 systems (PO315); installation of two additional MSRVs and tail pipes (P2115); installation of IIXA qualified limit switches on outboard MSIVs (PO276); all security comitments for security were empleted; feedwater nozzle taperature monitoring equignent was installed to gather information during the operating cycle; the new Bell dimensional telephone was installed in the plant and field services offices.
Work that continued through the month included: continuing the installation of alternate feeds for OC'1V cameras and diesel
'crator (PO286); support modifications in the secondary alarm sections,P0007; installation of tamper switches on Wells Fargo for non-vital doors (PO487);
dewatering pump installation (PO252) and work is close to complete on up scale and down scale trips for trip f ci a mits (PO254/Ll997). S ee of the maintenance work was cmple,e ??
. unit 3 on the ready for startup included TIP wattage tests, flamalstic inctallation, EMI-7 breaker maintenance, drywell camera installation, repair of start bus "B" connections and the removal of the diesel auto start from the start bus (PO275).
^
39 FIELD. SERVICES.
SUMMARY
April 1982 Mechanical Sumary During the month of April very little mechanical work was scheduled to be performed to support the unit 3 cycle 4 refueling outage, since most work was empleted e If.
We work that wan scheduled consisted primarily of post modification testing, leak testing, and some minor adjustments to various equipnent cmponents. We systms and cmponents were as follows: H202 syst e post modification testing and turnover to the plant; the 504 test on the.
strongback modification (PO4G2); drywell blower adjustments prior to drywell close-out; support for the HPCI and RCIC systems overspeed testing; changeout of O-rings in CRD 42-35; cooling tower #6 sergency lube oil pmp changes; and installation of cap nuts on the RWCU heat exchanger flange clamp modification.
Between outage work on snubber rebuild; post-accident sampling building pipe relocations required to pour wall and ceiling slabs; and cleanup after the refueling were underway. ne hypochlorite building is being closed in for weather proofing. Auxiliary boiler "C" was modified with the new igniter systm eliminating the need for prr> pane ignition.
Mechanical Work Note Schedule During the month several major work itms appeared that had'not been anticipated. nese itms were as follows:
l 1.
Unit 3 low pressure turbine "C" shroud damage during preparation for l
turbine overspeed test. D e shroud on the 13th stage blades (turbine end) separated from the blades at 1650 RPM causing blade and diaphragm damage. The blades had to be rmoved and shipped to General Electric
\\
l
40 FIELD SERVICES
SUMMARY
April 1982 for repair (this requires operating without 13th stage blades this cycle) which requires a pressure reducing plate to be installed where the diaphragm was located. We pressure reducing plate is currently being machined at the power service shop and is expected to be shipped to the plant on May 7, 1982.
2.
RHR Heat Exchanger 2C Leak: The field services group went into this heat exchanger and replaced a leaking gasket on the floating head.
Were were no tube leaks but the floating head gasket was changed out.
Wis work was completed within six days.
During April, the final torus cleanup was completed, a diving inspection was cmpleted and the torus closed. We latter part of the month was spent in decontamination of elevation 519 and 541.
Unit 2 Preshut Down In anticipation of the torus work for unit 2 cycle 4 the first half of
/
April drilling continued for torus tie-down anchor bolts, jacking lug removal and prefabrication of temporary ECG supports. Torus drain line and cradle extensions were started on April 6,1982. As of the end of April, the progress was as follows:
Torus tie-down drilling - 95%, jacking lug removal - 100%, fabrication of 8 temporary ECCS supports - 75%, installation of 4 temporary ECG supports - 50%, cradle extensions (32) - 62%, drain line reroute - 80%,
"G" and "H" gussets for cradle extensions (32) - 16%, and quencher end arms -
15%.
Prefabrication Writing of work plans continued during April with six out of 17 issued to the fabrication shop and 11 are in approval cycle. 15 installation workplans remain to be written.