ML20062G048
| ML20062G048 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 07/14/1982 |
| From: | Jones G, Thom T TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20062G017 | List: |
| References | |
| NUDOCS 8208120233 | |
| Download: ML20062G048 (39) | |
Text
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TENNESSEE VALLEY AUTHORITY DIVISION OF NUCLEAR POWER BROWNS FERRY NUCLEAR PLANT MONTHLY OPERATING REPORT June 1, 1982 - June 30, 1982 DOCKET NUMBERS 50-259, 50-260, AND 50-296 LICENSE NUMBERS DPR-33, DPR-52, AND DPR-68 i
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8200120233 820714 PDR ADOCK 05000259 l
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TABLE OF CONTENTS Operations Summary..
1 Refueling Information..
3 Significant Operational Instructions.
5 Averge Daily Unit Power Level.......
14 Operating Data Reports..
17 Unit Shutdowns and Power Reductions..............
20 Plant Maintenance..
23 Field Services Summary....
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1 Operations Summary June 1982 4
The following summary 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.
There were 16 reportable occurrences and one revision to previous reportable occurrences reported to the NRC during the month of June.
Unit 1 There was one scram on the unit during the month.
On June 24, the reactor scrammed in order to repair the inlet pipe to a feedwater heater after the pipe split due to steam errosion.
Unit 2 There were no scrams on the unit during the
- month, i
Unit 1 There was one scram on the unit during the month.
On June 5, the reactor scrammed after the turbine tripped when a 250-VDC supply was reenergized after a fuse was replaced and several relays did not sequence correctly.
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2 Operations Summary (Continued)
June 1982 Fatigue Usage Evaluation The cumulative usage factors for the reactor vessel are as follows:
Location Usage Factor Unit 1 Unit 2 W
Shell at water line 0.00552 0.00432 0.00381 Feedwater nozzle 0.26953 0.18769 0.14381 Closure studs 0.21420 0.14460 0.12505 j
NOTE:
This accumulated monthly information satisfies Technical Specification Section 6.6.A.17.B(3) reporting requirements.
Common System Approximately 2.00E+05 gallons of waste liquids were discharged containing approximately 1.88E-01 curies of activities.
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4 Operations Summarv (Continued)
June 1982 Refueling 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 This refueling will involve loading 8 X 8 R (retrofit) fuel assemblies into the core; finishing.the torus modification; turbine inspection; finishing THI-2 modifications; post-accident sampling facility tie-ins; core spray changeout; and changeout of jet pump hold-down
- beams, There are 764 fuel assemblies in the reactor vessel.
The spent fuel i
i storage pool presently contains 52 new fuel assemblies; 260 EOC-4 fuel assemblies; 232 E0C-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 scheduled for its fourth refueling beginning on or about July 30, 1982 with a scheduled restart date of January 31, 1983 This refueling outage will involve completing relief valve modifications; torus modifications; "A"
low-pressuN Lurtinc inspectica; gencratcr inspcction; MG set installation for LPCI modification; loading additional 8 X 8 fuel assemblies into the core; TMI-2 modifications; post-accident sampling I
facility tie-ins, and changeout of jet ' pump hold-down beams.
There are 764 fuel assemblies in the reactor vessel.
At the end of the month there were 248 new fuel assemblies; 353 EOC-3 fuel assemblies; 1
156 EOC-2 fuel assemblies; and 132 E0C-1 fuel assemblies in the spent fuel l
4 Operations Summary (Continued)
June 1982 Fefueling Information Unit 2 (Continued) storage pool.
The present available capacity of the spent fuel pool is 692 locations. There are 169 new high-density storage locations that have been installed and can be used after they are qualified.
Unit 9 Unit 3 is scheduled for its fif th refueling on or about August 1,
1983, with a scheduled restart date of November 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 TMI-2 modifications; turbine inspection; and changeout of jet pump hold-down beams.
There ere 764 fuel assemblies presently in the reactor vessel.
There are 280 EOC-4 fuel ascrablies; 124 EOC-3 fuel assemblies; 144 EOC-2 fuel assemblies; and 208 EOC-1 fuel assemblies in the spent fuel storage pool.
The present available capacity of the spent fuel pool is 993 locations.
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Significant Ocerational Event Unit 1 Date Time Event 6/01/82 0001 Reactor thermal power at 995, maximum flow, rod limited.
6/04/82 2335 Commenced reducing thermal power for turbine control valve tests and SI's.
6/05/82 0100 Reactor thermal power at 95%, holding for turbine control valve tests and SI's.
0346 Commenced reducing thermal power for removal of "A" string low-pressure heaters from service for maintenance.
0500 Reactor thermal power at 735, removed "A" string I
low-pressure heaters from service for maintenance.
0615 Commenced power ascension from 73% power.
0700 Reactor thermal power at 85%, due to "A" string low-pressure heater maintenance.
1500 Reactor thermal power at 885, due to "A" string low-pressure heater maintenance.
6/06/82 0700 Reactor thermal power at 89%, due to "A" string low-pressure heater maintenance.
6/07/82 2200 Commenced reducing thermal power for maintenance on "A" string low-pressure heaters and to place heaters back in service.
6/08/82 0215 "A" string low-pressure heaters back in service, reactor power at 75%, commenced power ascension.
0345 "A" string low-pressure heaters out of service for maintenance on drain valve 2-604.
Power ascension in progress.
1500 Reactor thermal power at 87%, holding for "A" string low-pressure heater maintenance.
2335 Commenced power ascension from 87% thermal power.
6/09/82 0240 Commenced PCIOMR from 985 thermal power (sequence "A").
-~~
0330 Reactor thermal power at 99%, maximum flow, rod limited.
0628 Commenced reducing thermal power due to 1/4 isolation on "B" main steam lino.
0700 Reactor thermal power at 975, main steam line "B" 1/4 isolation.
1000 Reactor thermal power at 96%, main steam line "B"
1/4 isolation.
1100 Reactor thermal power at 97%, main steam line "B" 1/4 isolation.
1300 Reactor thermal power at 985, main steam line "B" 1/4 isolation.
I 1745 Commenced reducing thermal power due to fuse failure in auxiliary instrument room for relay 16A-K-66D.
Reactor zone fans isolated.
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6 Significant Operational Event Unit 1 Date Time Event 1800 Reactor thermal power at 72% due to reactor zone fan isolation.
2000 Coil replaced on relay 16A-K-66 B, fuse replaced and isolation reset, commenced power ascension.
6/09/82 2300 Reactor themal power at 98% due to "B" main steac line 1/4 isolation.
6/10/82 1500 Reactor thermal power at 975, holding due to "B" main steam line 1/4 isolation.
6/12/82 0001 Commenced reducing thermal power for turbine control valve tests and SI's.
0200 Reactor thermal power at 71%, holding for turbine control valve tests and SI's.
0225 Turbine control valve tests and SI's complete, commenced power ascension.
0240 Commenced PCIOMR from 79% thermal power (sequence "A").
1200 Reactor thermal power at 97% due to main steam line low pressure 1/4 isolation.
1500 Reactor thermal power at 96% due to main steam line low pressure 1/4 isolation.
6/13/82 0100 Reactor thermal power at 97% due to main steam line low pressure 1/4 isolation.
6/15/82 1625 Commenced power ascension from 97% thermal power.
1700 Reactor thermal power at 995, maximum flow, rod limited.
6/19/82 0030 Commenced reducing thermal power for turbine control valve tests and SI's.
0100 Reactor thermal power at 91% for turbine control valve tests and SI's.
0145 Turbine control valve tests and SI's completed, commenced power ascension.
0200 Reactor thermal power at 995, maximum flow, rod limited.
6/24/82 0645 Commenced reducing power due to leak in A1 and A2 high pressure feedwater heaters.
0655 A1 and A2 heaters out of service for maintenance.
0700 Reactor thermal power at 91% for maintenance on A1 and A2 heaters.
0955 Commenced reducing thermal power for shutdown due to A1 and A2 high-pressure feedwater heater leaks.
1059 Reactor Manual Scram No. 158 from 43% thermal power for maintenance on A1 and A2 high pressure feedwater heater leaks.
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7 Significant Operational Event Unit 1 Date Time Event 6/25/82 0323 Commenced rod withdrawal for startup.
0505 Reactor Critical No. 177.
1155 Rolled T/G.
1309 Synchronized generator, commenced power ascension.
1545 Commenced reducing thermal power from 45% due to radiation increase on unit 1 effluent radiation monitors. ("C" string high-pressure feedwater heater leaks).
1600 Reactor thermal power at 38% for "C" string high-pressure feedwater heater maintenance.
2300 Reactor power at 39% for "C" string high-pressure heater maintenance.
6/26/82 0100 Reactor power at 40% for "C" string high-pressure heater maintenance.
0500 Reactor power at 425 for "C" string high-pressure heater maintenance.
0558 "C" string high-pressure heaters repaired, commenced power ascension.
1500 Commenced PCIOMR from 71% thermal power (sequence "A").
6/27/82 0700 Stopped PCIOMR at 85% thermal power for "A" string high-pressure heater maintenance.
0900 Reactor thermal power at 84%,
"A" string high-pressure heater maintenance.
6/28/82 2115 "A" string high-pressure heaters in service, commenced power ascension.
6/29/82 0015 Reactor thermal power at 88%,
"C" string high-pressure heaters out of service for maintenance.
0700 Reactor thermal power at 86%,
"C" string high-pressure heaters out of service for maintenance.
2105 "C" string high-pressure heaters back in service, reactor power at 85% (problems with C1 extraction valve).
6/30/82 0005 "C" string high-pressure heaters out of service for maintenance.
Reactor power at 85%.
2200 Commenced reducing thermal power for control rod pattern adjustment.-
2400 Reactor thermal power at 75% for control rod pattern adjustment.
8 Significant Operational Event Unit 2 Date Time Event 6/01/82 0001 Reactor thermal power at 80%, maximum flow, EOC-4 coastdown.
6/02/82 0100 Reactor thermal power at 79%, maximum flow, E00-4 coastdown.
1650 Increased recirculation flow to 80% thermal power, maximum flow, EOC-4 coastdown.
6/03/82 2300 Reactor thermal power at 79%, maximum flow, EOC-4 coastdown.
6/07/82 0700 Reactor thermal power at 78%, maximum flow, EOC-4 coastdown.
6/09/82 1500 Reactor thermal power at 77%, maximum flow, EOC-4 coastdown.
6/12/82 0700 Reactor thermal power at 76%, maximum flow, EOC-4 coastdown.
6/14/82 1500 Reactor thermal power at 75%, maximum flow, EOC-4 coastdown.
6/17/82 0700 Reactor thermal power at 74%, maximum flow, EOC-4 coastdown.
6/19/82 0030 Commenced reducing thermal power for turbine control valve tests and SI's.
0100 Reactor thermal power at 61%, holding for turbine control valve tests and SI's.
0125 Turbine control valve tests and SI's complete, reducing thermal power for recirculation pump MG set brush replacement.
0500 Reactor thermal power at 35% for recirculation pump MG set brush replacement.
0546 "B" recirculation pump MG aet brush replacement completed, "B" recirculation pump placed in service.
0555 "B" recirculation pump tripped due to controller problems.
Reducing thermal power from 35%.
0700 Reactor thermal power at 31% due to "B"
recirculation pump controller problems.
1036 "B" recirculation pump placed in service and tripped, reactor power at 31%.
1449 "B" recirculation pump placed in service, commenced power ascension.
1605 "A" recirculation pump removed from service for MG set brush replacement, reducing thermal power from 49%.
1700 Reactor thermal power at 38% for "A" recirculation MG set brush replacement.
9 Significant Operational Event Unit 2 Date Time Event 6/19/82 1720 "A" recirculation pump back in service, commenced power ascension.
2400 Reactor thermal power at 82%, maximum flow, EOC-4 coastdown.
6/20/82 0200 Reactor thermal power at 81%, maximum flow, E0C-4 coastdown.
0400 Reactor thermal power at 80%, maximum flow, E0C-4 coastdown.
0700 Reactor thermal power at 79%, maximum flow, EOC-4 coastdown.
0900 Reactor the'rmal power at 78%, maximum flow, EOC-4 coastdown.
1200 Reactor thermal power at 775, maximum flow,, EOC-4 coastdown.
1500 Reactor thermal power at 76%, maximum flow, EOC-4 coastdown.
1800 Reactor thermal power at 75%, maximum flow, EOC-4 coastdown.
6/21/82 0700 Reactor thermal power at 74%, maximum flow, E0C-4 coastdown.
2300 Reactor thermal power at 73%, maximum flow, E0C-4 coastdown.
6/24/82 0205 Commenced reducing thermal power, load not needed.
0225 Reactor thermal power at 55% holding, load not needed.
0450 Commenced power ascension from 55% thermal power.
0547 Reactor thermal power at 73%, maximum flow, EOC-4 l
coastdown.
2300 Reactor thermal power at 725, maximum flow, EOC-4 coastdown.
(
6/25/82 1500 Reactor thermal power at 71%, maximum flow, EOC-4 l
coastdown.
l 6/27/82 2300 Reactor thermal power at 70%, maximum flow, E00-4 l
coastdown.
6/29/82 2300 Reactor thermal power at 69%, maximum flow, E0C-4 coastdown.
6/30/82 0951 Increased recirculation flow, reactor thermal power at 70%, E0C-4 coastdown.
2100 Reactor thermal power at 69%, maximum flow, E00-4 coastdown.
2400 Reactor thermal power at 69%, maximum flow, E0C-4 coastdown.
10 Significant Ooerational Event Unit 3 Date Time Event 6/01/82 0001 Reactor thermal power at 70%, power ascension in progress.
0530 Commenced PCIOMR from 84% thermal power.
1840 Stopped PCIOMR at 95% when 1/2 isolation on MSL "A" low-pressure group I was received.
6/02/82 0215 Commenced PCIOMR from 95% thermal power (control cell core).
0235 Reduced thermal power from 96% when main steam line "B" low-pressure alarm was received.
0238 Reactor thermal power at 955, due to MSL "B" low-pressure alarm.
1030 Commenced power ascension from 95% thermal power.
1100 Reactor thermal power at 995, maximum flow, rod limited.
1205 Commenced reducing thermal power due to MSL "D" low-pressure 1/2 isolation.
1208 MSL "C" low-pressure, 1/2 isolation, power reduction continues.
1500 Reactor thermal power at 955, holding due to problems with main steam line pressure switches.
6/04/82 0600 Reducing thermal power for RTI-23 (Feedwater System).
0635 Reactor thermal power at 70%, holding for RTI-23 1620 Reducing thermal power for RTI-32A (Recirculation MG Set Speed Control).
2100 Reactor thermal power at 48%, holding for RTI-32A.
2115 Stopped RTI-32A when computer inoperative.
2140 RTI-32A back in progress.
2325 RTI-32A complete, commenced power ascension.
6/05/82 0445 Reactor Scram No. 106 from 65% thermal power while changing a blown fuse in 250V trip bus which caused a turbine trip.
1358 Commenced rod withdrawal for startup.-
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1635 Reactor Critical No. 119 1900 Holding startup for work on MSIVs.
6/06/82 0300 Synchronized generator, commenced power ascension.
1440 Commenced PCIOMR from 69% thermal power (control cell core).
6/07/82 1434 Reducing thermal power from 92% due to "B" recirculation pump high vibration.
1500 Reactor thermal power at 88% due to "B"
recirculation pump high vibration.
1600 Reactor thermal power at 875 due to "B" recirculation pump high vibration.
1630 Commenced power ascension from 87% thermal power.
11 Significant Operational Event Unit 3 Date Time Event t
6/08/82 0630 Commenced reducing thermal power from 89% due to problems with control rod 18-39 0700 Reactor thermal power at 74%, holding due to problems with control rod 18-39.
0750 Isolated control rod 18-39 1058 Reduced thermal power from 875 to 85% to withdraw control rod 18-39 1108 Control rod 18-39 withdrawn, J5menced power ascension.
1230 Reactor thermal power at 87% for RTI-22 (Pressure Regulator)..
1445 RTI-22 completed, commenced power ascension.
2330 Commenced reducing thermal power from 91% for control rod pattern adjustment.
2350 Reactor thermal power at 75%, holding for control rod pattern adjustment.
6/09/82 0005 Commenced power increase for control rod pattern adjustment.
0110 Control rod pattern adjustment complete, reactor power at 855, power ascension in progress.
0130 Commenced PCIOMR from 86% thermal power (control cell core).
1000 Reactor thermal power at 94% due to "3B" recirculation pump high vibration 2300 Reactor thermal power at 95% due to "B" recirculation pump high vibration.
6/10/82 0700 Reactor thermal power at 96% due to "B" recirculation pump high vibration.
6/11/82 1015 Commenced power ascension from 96% thermal power.
1115 Commenced PCIOMR from 98% thermal power (control cell core).
1220 Reactor thermal power at 99%, maximum flow, rod limited.
6/12/82 0100 Reduced reactor thermal power to 98% due to "B"
)
recirculation pump high-vibration alarm.
2105 Commenced reducing thermal power for turbine control valve tests and SI's, 6/13/82 0100 Reactor thermal power at 86%, holding for turbine control valve tests and SI's.
0155 Turbine control valve tests and SI's complete, commenced power ascension.
0800 Commenced PCIOMR from 98% thermal power (control cell core).
0900 Reactor thermal power at 99%, recirculation pump vibration limited.
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Significant Operational Event Unit 3 Date Time Event 6/ 16 /82 1500 Reactor thermal power at 985, recirculation pump vibration limited.
2300 Reactor thermal power at 995, recirculation pump vibration limited.
6/17/82 1320 Reduced thermal power to 88% when "A1" and "A2" and "C1" and "C2" feedwater heaters isolated when drain pumps tripped.
1355 Heaters back in service, commenced poder ascension.
1418 Reactor thermal power at 98%, recirculation pump vibration limited.
1600 Reactor thermal power at 995, recirculation pump vibration limited.
6/18/82 2306 Commenced reducing thermal power for turbine control valve tests and SI's.
2345 Reactor power at 71%, holding for turbine control valve tests and SI's.
6/19/82 0152 Turbine control valve tests and SI's complete, commenced power ascension.
0330 Commenced PCIOMR from 84% thermal power (control cell core).
1130 Stopped PCIOMR at 95% power until instrument mechanics checked APRM gain.
1400 Commenced PCIOMR from 955 thermal power (control cell core).
2100 Reactor thermal power at 99%,
"B" recirculation pump vibration limited.
6/20/82 1500 Reactor thermal power at 985, "B" recirculation pump vibration limited.
6/21/82 0630 Increased reactor thermal power to 995, maximum flow, rod limited.
6/23/82 1250 Commenced reducing thermal power for re= oval of "C" reactor feedwater pump from service.
1330 "C" reactor feedwater pump out of service (vibration problems).
1700 Reactor thermal power at 70% holding, "C" reactor feedwater pump out of service.
1910 "C" reactor feedwater pump back in service, commenced power ascension.
2100 Reactor thermal power at 995, maximum flow, "B" recirculation pump vibration limited.
I 13 Significant Operational Event Unit 3 Date Time Event 6/28/82 1600 Reduced reactor thermal power to 985, "B"
recirculation pump vibration's limited.
6/29/82 0700 Reactor thermal power at 995, "B" recirculation pump vibration limited.
i 6/30/82 2200 Commenced reducing thermal power for removal of 3A CCW pump from service for maintenance.
2400 Reactor thermal power at 88%, 3A CCW pump out of service for maintenance.
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l 16 AVERAGE DAILY UNIT POhER LEVEL DOCKET NO.
50-259 GIT Browns Ferry - 1 DATE 7-1-82 CO\\tPLETED llY T. Thom TELEPilONE 205 729 0834 JUNE MONTil DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL IMhe Net) otwe.Nei3 1039 1028 g
1040 1057 2
lg 1037 1015 3
39 1045 4
20 887 1031 5
21 911 1036 6
22 894 1031 7
,3 827
.435 8
984 121 9
33 10 1005 560 26 ll 992 849 7
963 853 28 1005 869 13
,9 1004 856 i.:
g 15 1013 3,
16 1044 s
INSTRUCTIONS On this f ormat !ist the avera.e daily unit p mcr lesel m \\lWe Nei t'iir each day in the reportmg mimth. Compute to the nearest whole megawatt.
Fil77) l
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15 AVER AGE DAILY UNIT POWER LEVEL 50-260 DOCKET NO.
UNIT Browns Ferry - 2 '
7-1-82 DATE COi!PLET ED I;y T. Thom 205 729 0834 T ELEPilONE Af0NTil June DAY AVER AGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (Siwe Neg)
(MWe-Nei 840 784 g
37 841 789 2
is 843 529 3
g9 842 831 4
20 832 781 5
21 834 775 6
22 825 772 7
23 821 746 g
24 815 772 9
25 10 813 26 749 811 755 11 27 821 752 g,-
23 805 750 13 29 799 748 34 30 796 15 31 16 798
.s INSTRUCIlONS Ort t'us fortnat.!ist the ascu,'e daih unit pim W m W'#.N'J' I"' ea h day in the repo, ting in.inth. Gunpute to the nearest whole nwpwaii.
19177)
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16 AVERAGE DAILY UNIT POWER LEVEL 50-296 DOCKET NO.
3.lT Browns Ferry - 3 7-1-82 DATE T. Thom COMPLETED BY 205 729 0834 TELEPilONE MONTil JUNE DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net)
(Mwe. Net ;
917 1016 i
,7 993 1033 3
18 990 945 3
39 774
-1035 4
0 122 1034 5
21 535 1037 6
902 7
23 907 1032 8
g 956 1030 9
983 1001 10 1020 1017 Il 27 983 1015 12 3
1009 1019 13 29 1024 1003 y
1023 15 l
16 1030 i
INSTRUCTIONS On this torrnat, hst the averaee daily imit pimer lesel m \\1We. Net for cash day in the icportine month. Cinnpute to the nearest whole megawari.
4 19177) l
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17 OPERATING DATA REPORT DOCKET NO. 50-259 DATE 7-1-82 C051PLETED LtY T. Thom TELEPl!ONE ZUS uv u834 OPERATING STATUS W~
- 1. Unit Name:
June 1982
- 2. Reporting Period:
- 3. Licensed Thermal Power (5 twt):
3293 1152
- 4. Nameplate Rating (Gross atWe):
- 5. Design Electrical Rating (Net alwe): 1065 1098.4
- 6. 51aximum Dependable Capacity (Gross SIWE):
1065
- 7. Sf aximum Dependable Capacity (Net alwe):
- 8. If Changes Occur in Capacity Ratings (items Number 3 Through 7) Since Last Report. Gise Reasons:
NA NA
- 9. Power Lesel To which Restricted. If Any (Net MWe):
NA
- 10. Reasons For Restrictions. If Any:
This 51onth Yr. to Date Cumulative 4
720 4,343 69,385 I1. Ilours in Reporting Pen. d o
- 12. Number Of Ilours Reactor Was Critical 701.9 4,055.87 43,370.67
- 13. Reactor Resene Shutdown llours 18.1 238.73 5,453.93
- 14. Ilours Generator On Line 693.83 4,010.40 42,440.57
- 15. Unit Resene Shutdown flours 0
0 0
- 16. Gross Thermal Energy Generated (51Wil) 2,118,593 12,456,444 119,331,351
- 17. Gross Electrical Energy Generated (5thil) 680 d20 4,053,210 39,345,660
- 18. Net Electrical Energy Generated (31Wil) 659,201 3,938,316 38,207,225
- 19. Unit Senice Factor 96.4 92.3 61.2 i
96.4 92.3 M.2
- 20. Unit Availability Factor
- 21. Unit Capacity Factor (Using SIDC Net) 86.0 85.1 51.7 86.0 85.1 51.7
- 22. Unit Capacity Factor (Using DER Net)
- 23. Unit Forced Outage Rate 3.6 7.7 2.6
- 24. Shutdowns Scheduled Oser Next 6 Stonths IType. Date,and Duration of Eacht:
l l
.s
- 25. If Shut Down At End Of Report Period. Estimated Date of Staitup:
- 26. Units in rew rotatus (Prior to Commercial Operation):
Forecast Achiesed t
INITIT L CitI TICA LITY INIII A L ELEC1 RICITY CO\\lNIERCI \\ L Ol'!:R A TION (9/77 )
=a-
18 OPERATING DATA REPORT DOCKET NO.
50-260 DATE 7-1-82 CO31PLETED BY T. Thom TELEPfl0NE ZU) /ZF0834 OPERATING STATUS I. Unit Name:
Browns Ferry - 2 Note 5 June 1982
- 2. Reporting Period:
3293
- 3. Licensed Thermal Power (5tht):
1152
- 4. Nameplate Rating (Gross SIWE):
1065
- 5. Design Electrical Rating (Net StWe):
1098.4
- 6. Stasimum Dependable Capacity (Gross $1We):
10 %
- 7. Sinimum Dependable Capacity (Net 31We):
i
- 8. If Changes Occur in Capacity Ratings litems Number 3 Through 7) Since Last Report, Giie Reasons:
NA NA
- 9. Power Lesel To which Restricted.If Any (Net 31We):
NA
- 10. Reasons For Restrictions. If Any:
This Slonth Yr..to Date Cumulative
- 11. Ilours in Reporting Period 720 4,343 64,326 0
4,1M. 76 u,6d.M
- 12. Number Of flours Reactor Was Critical 0
157.72 13.639.48
- 13. Reactor Reserve Shutdown flours
- 14. Ilours Generator on-Line 720 4,121.38 41,318.47
- 15. Unit Resene Shutdown llours 0
0 0
- 16. Gross Thermal Energy Generated ($1Wil) 1,758,588 12,239,626 118,892,416
.t
- 17. Gross Electrical Energy Generated (5thil) 591,160 4,116,560 39,549,208
- 18. Net Electrical Energy Generated 151Wil) 568,108 3,997,504 38,419,650
- 19. Unit Senice Factor -
100.0 94.9 64.2
- 20. Unit Asailability Factor 100.0 94.9 64.2
- 21. Unit Capacity Factor IUsing.\\lDC Net) 74.1 86.4 56.1 74.1 86.4 56.1
- 22. Unit Capacity Factor (Using DER Net) 0 5.1 27.3
- 23. Unit Forced Outage Rate
- 24. Shutdowns Scheduh d Oser Nest 6.'.fonths (Type. Date.and Duration of Each):
l Refueling outisge July 19u2 s
l l
- 25. If Shur Down At End Of Report Period. Estimated Date of Startup:
- 26. Units in Test Status (Prior to Commercial Operation):
Forecast Achiesed I
INI TI A L CRI TICA LITY l
lNITIAL ELECTRICITY l
CO\\l\\1ERCI \\ L OPER A IlON l
(9/77)
--.s : -
_ _ _ - - _ _ _ - _.. _ - _ _ _ _ _ _ ~.
L 19 1
i i
OPERATING DATA REPORT DOCKET NO.
50-296 DATE 7-1-82 i
CO.\\lPLETED BY T. Thom_
TELEPil0SE 205 729 0834 i
OPERATING STATUS i
- 1. Unit Name:
Browns Ferry - 3 Notes i
- 2. Reporting Period:
June 1982 f
- 3. Licensed Thermal Power (Stht):
3293
- 4. Nameplate Rating (Gross SIWel:
1152
- 5. Design Electrical Rating (Net alWe):
1065 1098.4
- 6. Stasimum Dependable Capacity IGross $1We):
1065
- 7..\\lasimum Dependable Capacity (Net SlWe):
- 8. If Changes Occur in Capacity Ratings litems Number 3 Thr'ough 7) Since Last Report. Give Reasons:
NA NA
- 9. Pt wer Lesel To Which Restricted. If Any (Net alwe):
- 10. Reasons For Restrictions.lf Any:
NA i
This alonth Yr. to Date Cumulative i
i1. Ifours in Reporting Period 720 4,343 46,751
- 12. Number OfIl<mts Reactor Was Critical 708.17 1,044.72 33,511.70
- 13. Reactor Resene Shutdown llours 11.83 914.20 2,055.73
- 14. Ilours Generator On-Line 697.75 692.72 32,713.51
- 15. Unit Resene Shutdown llours 0
0 0
- 16. Gross Thermal Energy Generated (51Wil) 2.196,804 2,747,854 96,606.474
- 17. Grow Electrical Energy Generated (.\\lWill 702,620 866,400 31,864.590
- 18. Net Electrical Energy Generated (N!Wil) 679,943 831,408 30,919,454
- 19. Unit Senice Factor 96.9 22.2 70.0
- 20. Unit Availability Factor 96.9 22.2 70.0
- 21. Unit Capacity Factor (Using MDC Neti 88.7 18.0 62.1
- 22. Unit Capacity Factor (Using DER Net) 88.7 18.0 62.1 3.1 49.3 11.3
- 23. Unit Forced Outage Rate
- 24. Shutdowns Scheduled Oser Nest 6 Stunths IT.s pe. Date.and Duration of Each t:
.s l
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
- 26. Units in Test Status il'rior to Commercial Operationi:
Forecast Achiesed INIIl \\ L CRilICA LITY INill Al.1:ll:ClRICIT Y CO\\l\\ll:RCl \\ L OPI R A TION 3~
(9/77)
.a e
Q DOCK ET NO.
50-259 UNIT SilUTDOWNS AND POWER REDUCTIONS UNil NA\\f E Browns Ferry DATE 7-1-82 JUNE CO\\f PLETED BY
?
m-REPORT 3f 0NTil TELEPflONE 205 7290834 r
4 m
E E
{g 3
4 h_" ~
1.icensee
,En, h
Cause & Currectise No.
Dare
- E 2
iE3 Event u?
F?
Attnin to 5
3 j,I Report =
A0
!C Presen: Recurrense 2
v 6
224 6/04/82 B
Derated for maintenance on "A" string low pressure heaters 225 6/09/82 11 Derated due to reactor zone fan isolating 226 6/12/82 B
Derated for turbine control valve ta t,ests and SI's o
227 6/24/82 F
26.17 A
2 Reactor scram due to A-1 and A-2 high pressure feedwater heater leaks i
2 3
4 F forted Reason :
hiethod:
Eshibit G - Inst ructio.is S Sc hed uled A l'quipment Failure (Explam)
! 41anual for Preparati..n et Data Italaintenance or Test 24f anual Scram.
I nin Sheets tor i reemee C Refueling 3 Autom.itie Stram.
I sent Report (El Rl File INtiRI G-D. Regulator) Restrietion 4-Ot her ( E splain) 01ofn i -Operater Training & 1xense Esamination F Adnunistratt.c 5
G-Operational Es tor (Explain)
Estubit I-Same Source (9/77) 11 Other (E splam)
O
. _ _ _.. = _... _ _ _ _ _ _
~
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.]
F DOCKET NO.
50-260 UNIT SilUTDOWNS AND POWER REDUCTIONS UNIT NAME Browns Ferry -2 i-I-62 DATE REPORT MONTH June COMPLETED BY T. Then TELEPif0NE 205 7290834 i,I
, j l
i i
~.
- 5. 5 e
=_
ci bi""5" 5%
$4 Cause & Currectise
's k$
? 53 b'C"'
5.?
El Action to No.
Date
,0 E2
-3 55*
3 Di j Report :
in v gL Present Recurrence O
E l
f.
236 6/19/82 B
Derated for "B" recirculation pump MG set brush replacement i
2 237 6/24/82 F
Derated for load not needed r
l i
L w
1 i
i l
i e
L 1
2 3
4 F: Forced Reason:
Method:
Estubit G-Instructions I
S: Scheduled A Equipment Failure (Explain) 1 Manual for Prepararnm of Data B-Maintenance of Test 2-Manual Seram.
Entt> Sheets or Licensee t
C Refuelmg 3 Automatic Scram.
Esent Report il I R) File (NURI G-l l
D Regulator) Restriction 4-Other ( Explain) 0161) 1 -Operator Training & License Examination i
F-Ad minist rative 5
G-Operational Er ror (Explain)
Exhibit 1 Same Source l
l (9/77)
Il-Other (Explain) i Y
9 50-296 UNIT SilUIDOWNS AND POWER REDUCTIONS DOCKET NO.
UNIT NA%f E Browns Ferry - 3 DATE 7-1-82 JUNE COMPLETED !iY T-
- Thn, REPORT 5f 0NTil TELEPl!ONE 205 729 0834 i
t g
3 u, 3 E
=_
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CJu%e d (of rett n e o u
%t.
l)Jte I""'
3?
E?
Action to A
5 2 0
55*
c:
ec 2 7, =
Repors =
vi v 5: L pf etcrit Recntrente g
6 97 6/04/82 B
Derated for RTI-23 (Feedwater System) 98 6/05/82 F
22.25 A
3 Reactor scram while changing a blown fuse in 250V trip bus causing a turbine trip 99 6/18/82 B
Derated for turbine control valve
, tests and SI's U
100 6/23/82 11 Derated to remove "C" reactor feed-pump from service (vibration pro-blems) i 3
4 Il l'orted Reason:
Afethm!:
Estubit G. Instensto is S. Ss hedulcil A I quipment Failure (i.xplain) l Manual for Preparati,in. t Dita It.Maintenante or 'lest 2%nual Scram.
1 ntey Sheets for t.isemee C Refueling 3 Autonutic Strain.
13ent ReporI t1 I 10 l'de iNtIRI G-D Regulatory Restriction 4-Olher ( f.xplain )
0161)
I ()perJtelf I'rJtillrig d 1.ltellsc I~.XJillillation I - Atlrlilflist rJfive 3
(' ()perJtiollJ1 l.t ror ll.xplJtn)
[\\\\1thit 1 Sante Sonfie s
(')/77 )
11 Ottier (l. xplain)
BR0'.J';S FERRY !!UCLEAR PLANT U:;IT 1 and Coccon CSSC Ei t'IP!!F?;T EI.ECTRICAL 11MNTE!;A: CE Sili'L1RY For t!: Month of June i r.,
i E::ce: on Sa:'c
.\\c t ica I.,;:c n
- autre cf Operation of Cauce of Results of Te Preclude
': 0 :. n ;ian
".l f - - t ic a E c e.. t r i. n e..
-:c.
c, s
. i : -:,
ce T!.e nea :: cr e
D.i t e I
6/18/82 RiiRSW Al and A3 Recoved Al None Bad motor heater:
Al and A3 Rl!RSU Replaced the Rl!RSU pump pump notor to pump motor heaters motor heaters in notors allow techani-inoperable.
R1[RSW pump motors cal repairs t.o.
Al and A3.
Also pu=p and dis-repaired broken covered the conduit at pump notor had bad A3.
heaters. This' TR #252206 resulted in TR #282688 the inspection of all RilRSW purp notors which revealed d
bad heaters in A3.
I I
I i
6/27/82 Air
'1A" Control Teeperature
- None Temperature Chiller was not l The tecperature Condition 1 Bay Chiller controller j
controller was cooling properly.
controller was ing wasnotoperai out of adjust-adjusted, chiller (cooling--
ting properly..
cent.
operated properly.
heating)
I On 6/28/82 the chiller tripped on high discharge pressure. The t
chiller was purged and re-turned to service.
TR F342882 l
TR #342884
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LROCS FERRY NL' CLEAR PLANI UNIT 2 CSSC EQt:IPMENT ELECTRICAL MAINTENANCE SD PARY For the Month of June 19 82 E!fect on Safe Actica Taken Nature of Operation of Cauce of Results of To Preclude Date S e s: ce Cor:p en en t Maint. nance The Reactor M11 function Malf tmet ion Recurrcnce 5/25/82 RliR 2-FCV-74-96 During the None, valve was Bad valve motor 2-FCV-74-96 was The bad valve performance manually and overloads.
electrically inop-motor and rc.otor of SI4.5.B.l.d operable.
- erable, overloads were the RilR Cross-replaced.
tie valve fail--
During the per-ed to elec-formance of Dil i
trically fully 18 following the open.
above, the local i.
IIS-2-74-963 was found to have water damage.
w Three switches" and two indicatin-light sockets were replaced on local 11S-2 96B and Dil 18 successfully co:nple t ed. FCV 2-74-96 was returned to service.
t f
BECit';S FERRY.rCLEAR PLA:;r U.';!T 2
CSSC Es,! !!'?!E!;T ELECTRICAL P.W;TENA::C F. SIM. : GY
- l Fer the h ath u:
June
- a S2 i
I l
E:: L:: on Sa:c
.\\ c t i '. INen
';ature ef Operation <.f C..u :: af i:e ca. : 3 nf Tc Pr.--lud.:
g Date l
"i:
nec,
IL P.ietar M ilit.n.
iin
.1i
- 1. n 7
I I
I--
I__1 c.rrer.;._.
f 6/1/82 RifRSU i"C1" RHRSU During the None Wiring error in Pucp started with The extra wire pump starting performance of pump starting FCV-67-49 closed.
was recoved, the circuitry S14.9.A.1.a circuit. A wire
, pump's starting RHRSW pump
'whichshouldhavef t circuitry was "Cl" started been removed was l ltestedand with FCV-67-49 inadvertently lSI4.9.A.I.a closed.
left in place I successfully during ECN-L1690.
completed.
- TR #314050 t
I i
6/16/82 liPCI 2-LCV-73-8 Hot well level.
None Blown fuse.
2-LCV-73-8 inoperabla Replaced the blown control 2-LCV-fuse and the LCV w operated properly."
73-8 inoper-able.
TR #340272 I
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BROL"iS FERRY NUCLEAR PLANT UNIT 3
CSSC EQUIPMENT ELECTI'ICAL MAINTENANCE Sl"D'aRY For the Month ef June 19 82 i
Effect on Safe Action Taken Nature of Operation of Cause of P.es.ults of To Preclude Date System Conpanent Maintenance The Reactor Malfunction Malfunction Recurrence 5/19/82 HPCI Inboard dis-3-FCV-73-44 None, unit down Bad valve motor.
3-FCV-73-44 The bad motor charge valve inoperable.
for turbine inoperable.
was replaced and motor repairs.
EMI 18 and 18.1 (3-FCV-73-44).
performed, valve returned to service.
TR #342727 5/31/82 Main MSIV 3-1-3S During per-None, when fuse Intermittent Intermittent trip-This problem was Steam circuitry.
formance of blows, this
- ground, ping of trip investigated and SI 2 outboard causes relay to channel.
the ground cleared MSIV 3-1-38 go into tripped while trouble-continued to condition.
shooting. Froblem blow fuse SA-recurred 6/6/S2 F3C for MS1V during the per w relay SAK3C.
formance of l
SI4.1.A-11.
On 6/12/S2 the fuse (5A-F3C) f ailure alarm failed to annunciate ou panel 9-5 due to dirty contacts en the fuse switch.
The contacts were cleaned and the t
annunciator cir-i cuitry operated properly.
TR #310323 is scheduled for work during the next unit 3 outage to
+
BIMUNS FERRY NUCLEAR PLANT UNIT 3
A CSSC EQUIPMENT ELECTRICAL MAINTENANCE
SUMMARY
For the Month of 3""C 19 82 s
l Effect on Safe action Taken Nature of operation of Cause of Results of To Preclude Date System Cormo n en t Ih in tenance The Reactor Malfunction Malfunction Recurrence
' 5/31/82 (continued)
=-
correct the intermittent ground.
TR #310310-TR #337672 6/14/82 RilR FCV-3-74-59 During the None, stroke The limit Limit switch The limit switch.
performance of time of the switch control-operating erratic.
contacts were i
SI4.5.B.1.C valve was ling the lights cleaned and the FCV-3-74-59 acceptable, used to time the valve operated was observed valve was oper-properly.
to have an ating errati-TR #337613 w*
erratic stroke cally due to the time.
contacts failing to make up properly.
6/23/82 Contain-FSV-3-76-57 During the 11,0, Analyzer FSV-3-76-57 11,0 Analyzer "A" The solenoid 2
rnent performance of "A"~ inoperable, failed to oper-was made inoperable operator for Inerting SI4.7.D.1.B-1 ate when power FSV-3-76-57 was (A) FSV-3 was applied, replaced and the 57 failed in The wire supply-FSV returned to the closed ing power to the service. This position.
FSV was found to is considered j
be burned into a random failure 1 inside the seal-and no further ing compound of recurrence the seal off control is condu i t at the planned.
I l
FSV.
TR #207387 LER#50-296/8227*
e i
1
~
ER01:i3 FERRY fiUCLEAR P1A?iT U'ilT 12CP.A:11 CAL MAINTETANCE SU1"4ARY CFSC EQUIPI'E;;7 For the Menth of June 19 82
~
EFFECT 0:1 SAFE ACTIC:I TAF.EN DATE S~lETE 1 COMPONENT NATURE OF OPERATIC:I 0F CAUSE OF EESULTS OF 10 PRECLUDE PAINTENANCE TiiE PFACTOR MALFUNCTION
'MLFl":C' IO" RECURRENCE 6-7 jet pumps flow water leak None bad tubing watcr leak in contam-Replaced 3/8" tubing transmitter inated rene TR# 342827 I
panel 3-17 Rod Monitor-CA'1 1-90-249 faulty CA>!
None 1-90-2 9 belt CAMS non-functional Replaced belt en ing 1-90-237 units had worn 1-90-249.
Tightened 1-90-257 belt belt on 1-90-257 loose T Rif 342899 3-18 Jontrol Bay lli control bay faulty chiller None had 0-rings in chiller not function-Replaced 0-rings
- lea t, Vent.
chiller blower ing TR4 339783
, A/C 6-4
')f f Gas
!!2 Stack San-pump tripping None faulty punp pump hard to turn, Installed serviceable ple Pump tripping motor out, pump TR# 342S37 w*
a 6-4
- ontrol liay 1" water piping piping needs None bad piping piping needs rewelding Replaced piping after
- ! cat, Vent to"A" control reweldinS chiller cicaning.
5 A/C bay chiller TR!: 337857
7 i }
BROWUS FERRY 1:UCLEAR PLAliI UNIT 2
J 1
MEGIANICAL IL*.INTEIRNCE SUFCIARY I
CSSC EOUIPMENT I
For the lionth of June 19 82 1
4
)
ACr10N TAKEN EFFECT ON SAFE iInTE SYSTE:1 COMPO:;ENT NATURB 0F OPERATIO:; 0F CAUSE OF RESULTS OF 10 PRECLUDE
!'AI::TE::At:CE Tl!E REACTOR MALFUNCTION P_\\T.FI"JCTION RECURRENCE
-26 RilRSW valve 23-57 lubricant None limitorque got leaking Frease Greased limitorque leaking hot & grease ran
& tightened bottomI j
out operator base bolts TR# 337850 t
I F
r P
9 L
O e
t 4
t J
l f
l 1
i G
i
3 f
BRO'a7;S FER1;Y I4UCLEAR FIANT UNIT MEGLali1 CAL PAINTEMUCE SCM:2RY cssc ErfrIPMENT June 19 82 For the Month of I.CTION TA.<E:;
EFFSCT 0:; SAFE DAl'd SYSTDi CO:iPO:;ENT I;AIURE CF OPERATIC:; 0F CAUSE OF RESULTS OF 10 FRECLUDC I:AII;TE!!A' CE THE REACTOR MALFt7:CTIO:
- AI. FIR CTIO!!
RECURRT.!!CE
-8 CRD gecumulator water Icak
!;one
' faulty accumula-.iccumulator leaking Changed out accunu-u18-39
- .o r around O' ring lator I
1R0 263391 N
e*
s
~
BRO.R.3 FERRY 1;UCLEAR FIR;r Ul:lT 3
liEGIA*i1 CAL 1:AlliTEINICE SUl! MARY CSSC EOUIPMO..f f
3"""
19 82 For the Month of EFFECT 0:; SArg ACTION TAKEN na1E SYSTui COMPONEN r NATURE OF OPERATION OF CAUSE OF RESULTS OF 10 l'RECLUDC
- nTNTEN/ dice 11!E REAC102 MALFtr:CTTOM m LFUNCTIO'!
FECDPpF'CE 5-10 Rod Moni-CX1 90-249 U\\:1 not func-None
- 90 tor & pump cump running too slow Replaced motor &
t o rint; tioning prop-pullup too small causing air flow to bt punp pulley with larger size pulley (.
2rly low TRl! 182463 5-19 D/G 3 D/G Air Faulty head None Blown head gasket Air comp. inoperable Replaced gasket Compressor #1
'Jorn bearings MG set bearings Replaced bearings Set running hot running hot
& realigned generator.
TR# 103389 5-18 LPCI 3FA LPCI MG
!G Set running None Too much grease Causing MG set to run Pulled bearings &
Set tot in bearings hot removed grease to proper Icvel w
TR/! 342019 N
'aulty Coupling None
- oupling inoper-Seals leaking &
Replaced coupling, Set ible coupling teeth rough aligned face & ran packed coupling with Ropper grease TR/! 307497 5-17 dx. Illd g.
P Air Comp.
6aptured dia-None iad diaphragm
'!alve inoperable Replaced diaphragm Vent Inlet Valve chragm TR// 337689 64-139 i-15 3/G D/G !!1 Air Air Leak None Check valve worn Air leak from llP Replaced with new Compressor out cylinder to crank check valve case IR!l 310339
-23
- RD Control Rod
- ontrol rod None Excess 0-rings Would not let pilot Iteplaced pilot stem in 46-15 aill not scram found under sole-work properly solenoid valve & also noid pilot stem put new 0 rings on pilot tubing acorn nuts TR# 311279 6
!t o-
~
BROMNS FERRY EUCLEAR FIANT UNIT _
Co=non MEGLANICAL MAlliTENANCE SUK'ARY l}
CTSC EQUIPNENT
~l For the Month of June 19 82 t-l EFFECT ON SAFE ACT10N TAKEN I ' IRTE SYSTEM COMPONENT NATURE OF OPERATION OF CAUSE OF RESULi3 0F TO raECLUDE l'AI!!TE?!ANCE THE REACTOR MALFUNCTION
?CIFUNCTION RECURRENCE'
-18 RilRSW A2 pu:tp air Yalve breken None Jalve guide broken:
Valve broken 6 non-Replaced with new release valve functional valve l
I TRE 337860
[
b i il EECW "D" EECW Broken bolts None iroken talts in Packing Leak Pulled strainer &
st raine r
>acking gland repaired broken bolts, then repacked.
TR# 316686.
L I
9
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1-
- 1. T Fex :'::. MO:.:li CF 6
19 82 r.
i
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- J'.'.5[
J.n i. J : 6:; S.C-E C.AUS 2.
%7E SY5n2:
CCa t/C;il..
or die:-3! CN CF CF RES~ CTS CF TO PFICLUCE MA !:< ;i. NAN ' '
ITF TJJ.T' TOR MALFUNCT!CN PAL ENCTION RECURRFNCE O
U-1 6-16 75 Il-75-69A Calibrate None Instrument Drift Incorrect Indication None 6-22 3
PS-3-74B Replace
!!one Instrunent Drift Incorrect set point None U-2 6-1 76 rn/PR-76-14
, Repair None Bad drive gear Loss of record None 6-10 90 10 251
' Repair
- None B t.' flow control Could not run Turbine motor Building exhaust fans.
None U-3 5-2 3
PR-3-59 Repair None Bad slidewire Loss of record None 5-17 64 PDS-64-138 Replace
. None.
Faulty contacts Switch failed to w
5-23 70 T:!-70-36 Calibrate None Instrument Dfift Incorrect Indication None operate None e
0 D
e
- 9 J
s 9
9 9
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h 4
35 FIELD SERVICES
SUMMARY
June 1982 GENERAL Major work which was completed during this reporting period is as follows:
(1) dewatering pump (P0252) commitment was met, but material problems are still hindering the completion of the automatic controls; (2) moved cardreaders on diesel-generator doors (PO465); (3) prefabricated debris screens (PO428); (4) completed assembly of one rotating element for the reactor feedpump work next outage; (5) completed instrumentation and heater work on condensate tanks (P0238); (6) EPA modifications (P0472 and PO480); (7) rerouted cables for torus temporary power supply except for routing that requires the outage to be in progress; (8) prefabrication of vacuum breaker tees (P0093); and (9) the replacement of the unit 3 turbine building overhead crane wheels.
ELECTRICAL The major work that is continuing through this report period is:
(1)
LPCI modifications (L1845) - fabricating and installing conduit 90s, conduit brackets, conduit support hangers and conduit on unit 2 elevations 621 and 639 is in progress; (2) L2052 automatic backwash system for RCW strainers units 1, 2, and 3 -installing brackets, conduit, and junction boxes.
Pulling cable on unit 2.
Completions unit 1 - 44 percent, unit -
44 percent, and unit 3 - 10 percent; (3) update CCTV System (P0287) -
pulling and splicing cables. Making terminations in CAS and SAS; (4) illuminate exterior of the protected area (P0286).- installation of the diesel-generator control wiring. Mounted transformers on lighting poles; (5) emersency lighting (PO479) - mounting lighting brackets in unit 1
36 FIFtn SERVICES
SUMMARY
June 1982 ELECTRICAL (Continued) reactor building (approximately 57-percent complete) and mounting brackets in unit 1 turbine building and control bay; (6) Inspection and tagging of conduit in reactor, diesel generator, and control bay buildings in all units (WP 5560) - inspection and tagging in unit 1 elevation 565 is approximately 75-percent complete; and (7) other electrical work, wrfting work plans for the unit 2 cycle 4 refueling outage, providing temporary classroom facilities in the hypochlorite building for operations, support work, electrical inspections of cords, tools, and lights and telephone maintenance.
MECHANICAL The major work activities in progress are:
(1) the fabrication of the strongbacks for unit 1 and 2 is nearly complete with a few welds to be verified; (2) installation of piping and drain valve for radwaste (P0178) -
delayed due to material problems; (3) prefabrication of the "N" and "M" line MSRV tailpipes is approximately 95-percent complete; (4) anubber inspections and snubber rebuild are approximately 80-percent complete; and (5) other mechanical work includes: Quadrex has completed the decontamination of one spent fuel rack, fabrication of a segregated stainless-steel work area, fabrication of welding test stations, hanger inspections (IEB 79-14 and 79-02), and instrument sensing line inspections (MMI-118).
37 FIELD SERVICES
SUMMARY
June 1982 TORUS Unit 2 torus prefabrication and selected external modifications continue in preparation for the upcoming cycle 4 outage.
(1) Tie downs - All MK IIs have been set and leveled, except number 22.
Anchor bolts have been pulled-tested for MK I.
This completes the tie-down work until the unit is shut down.
(2) Temporary ECCS supports - Completion of permanent ECCS supports number 1 percent, 4 percent, 5 percent, 8 percent, 9 -
15-percent, 13 percent, and 16 - 100-percent completed. Work has not started on number 12.
(3) External ring girder reinforcing - numbers 1, 4, 5, 8, 9, 13, and 16 are 100-percent complete.
(4) Torus snubbers - wall brackets are in transit to the site.
The work plan for installation is in the approval cycle.
(5) Quencher end-arms prefabrication - work is completed.
(6)
J, L, and N gussets: prefabrication was completed.
Installation of "J" is 95-percent, "N" is 97-percent, and "L" is 100-percent complete.
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