ML20077A775
| ML20077A775 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 06/01/1983 |
| From: | Coffey J, Thom T TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| NUDOCS 8307220433 | |
| Download: ML20077A775 (41) | |
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I TENNESSEE VALLEY AUTHORITY DIVISION OF NUCLEAR POWER BROWNS FERRY NUCLEAR PLANT A
MONTHLY OPERATING REPORT May 1, 1983 - May 31, 1983 DOCKET NUMBERS 50-259, 50-260, AND 50-296 LICENSE NUMBERS DPR-33, DPR-52, AND DPR-68 Submitted by: [.
.' Plant S6perintendent
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TABLE OF CONTENTS Operations Summary. . . . . . . ... . . . . . . . . . . . . . I Refueling Information . . . . . . . . . . . . . . . '. . . . . 3 Significant Operational Instructions. . . . . . . . . . . . . 5 Average Daily Unit Power Level. . . . . . . . . . . . . . . . .
13 Operating Data Reports. . . . . . . . . . . . . . . . . . . . 16 Unit Shutdowns and Power Reductions . . . ..... ..... 19 Plant Maintenance . . . . . . . . . . . . . . . . . . . . . . 22 Field Services Summary. . . . . . . . . . . . . . . . . . . . 31 J
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- Ooerations SunniLcI Hay 1983 The following summary describes the significant operation activities during the reporting period. In support of this summary, a chmnological log of significant events is included in this report.
There were 19 reportable occurrences and no revisions to previous reportable occurrences reported to the NRC during the month of May.
Unit 1 .
.The unit was in cold shutdown the entire month for the units' end-of-cycle 5 refueling outage.
Unit 2 There was one scram on the unit during the month. On May 30, the reactor was manually scrammed to repair a control air leak in the drywell. The unit had been in a controlled shutdown until the decision was made to scram the unit to expedite maintenance activities.
Unit ~4 There was one scram on the unit during the month. On May 28, the reactor scrammed on low reactor vessel water level when a low-pressure feedwater heater string isolated while another low-pressure feedwater heater string was isolated for maintenance, causing the reactor feedwater pumps to trip on low suction pressure.
Principally prepared by B. L. -Porter. - -
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Ooerations Sn===ry (Continued)
May 1983 Fatigue Usage Evaluation The cumulative usage factors for the reactor vessel are as follows:
Location Usage Factor Unit 1 Unit 2 Unit 9 Shell at water line 0.00583 0.00462 0.00397 Feedwater nozzle 0.28294 0.19812 0.15110 closure studs . 0.22349 0.16735 0.12839 NOTE: This accumulated monthly information satisfies Technical Specification Section 6.6. A.17.B(3) reporting requirements.
Co==an System Approximately 6.86E+05 gallons of waste liquids were discharged containing approximately 1.27E+00 curies of activities.
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Operations Su===ry (Continued)
May 1983 Refuelina Information Unit 1 Unit 1 began its fif th refueling outage on April 16, 1983.
The sched-uled restart date is October 7,1983 This refueling will involve loading 8X8R (retrofit) fuel assemblies into the core, finishing the torus modifica-tion, 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 O fuel assemblies in the reactor vessel. The spent fuel stor-age pool presently contains 216 new fuel assemblies, 764 EOC-5 fuel assem-blies, 260 EOC-4 fuel assemblies; 232 EOC-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 are in progress to increase the spent fuel pool capacity to 3,471 assemblies.
Unit 2 Unit 2 is scheduled for its fif th refueling beginning on or about June 8, 1984 with a scheduled restart date of November 8,1984. This refueling outage will involve loading additional 8X8R (retrofit) fuel assemblies into the core, finishing the torus modification, turbine inspection, finishing inspection, finishing THI-2 modifications; post-accident sampling facility tie-ins, core spray change-out, and feedwater sparger inspection.
There are 764 fbel assemblies in the reactor vessel. At the end of the month there were 248 E0C-4 fuel assemblies, 353 EOC-3 fuel assemblies, 156 EOC-2 fuel assemblies, and 132 EOC-1 fuel assemblies in the spent fuel storage pool. The present available capacity of the spent fuel pool is 861 locations.
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Operations Su===ry (Continued)
May 1983 Unit ~4 Unit 3 is scheduled for its fif th refueling on or about November 11, 1983, with a scheduled restart date of May 4, 1984. This refueling will involve loading 8X8R (retrofit) assemblies into the core, finishing the torus modifications, post-accident sampling facility tie-in, core spray change-out, finishing THI-2 modifications, turbine inspection, and change-out of jet pump hold-down beams.
There are 764 fuel assemblies presently in the reactor vessel. There are 280 EOC-4 fuel assemblies, 124 E00-3 fuel assemblies, 144 EOC-2 fuel assem-blies, and 208 E0C-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 Operational Event Unit 1 Date Time Event 5/01 0001 End of cycle 5 refuel outage continues.
5/31 2400 End of cycle 5 refuel outage continues.
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- Sinnificant Ooerational Event Unit 2 Date Time Event 5/01 0001 Reactor thermal power at 100% maximum flow, rod limited 5/04 2300 Reactor thermal power at 995, maximum flo'w, rod limited (1005 electrical) 5/05 2300 Reactor thermal power at 98%, maximum flow, rod limited (100% electrical) 5/07 2200 Commenced reducing thermal power for control rod pattern adjustment 5/08 0200 Reactor thermal power at 74% for control rod pattern adjustment 0315 Control rod pattern adjustment complete, commenced power ascension 0330 Commenced PCIOMR from 82% thermal power 5/09 1700 Reactor thermal power at 995, maximum flow, rod limited (100% electrical)
S/15 0045 Commenced reducing thermal power for turbine control valve test and SI's 0100 Reactor thermal power at 90% for turbine control valve test and SI's 0140 Turbine control valve test and SI's complete, commenced
! power ascension 0150 "A" recirculation pump tripped on high temperature when the temperature control valve on the motor-generator set stuck l closed, reducing thermal power from 91%. .
0200 Reactor thermal power at 875, "A" recirculation pump out-of-service on high temperature 0220 "A" recirculation pump back in service, commenced power ascension 0400 Commenced PCIOMR from 975 thermal power 1800 Reactor thermal power at 100% maximum flow, rod limited 5/16 1600 Reactor thermal power at 995, maximum flow, rod limited (100% electrical) 5/19 0530 Commenced reducing thermal power due to CMFLPD limits 1000 Reactor thermal power at 97%, CHFLPD limited l
5/20 2220 Commenced reducing thermal power for a control rod sequence exchange from A to B e e
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Sinnificant Coeraticnal Event Unit 2 Time Date Event (Continued) 5/21 0300 Reactor. thermal power at 54%, control rod sequence exchange in progress, increasing power .
0610 Control rod sequence exchange complete, commenced PCIOMR from 72% thermal power 0645 "C" string high-pressure heater out-of-service, PCIOMR continues 5/22 0930 Reactor thermal power at 94%, holding for maintenance on "C" string high-pressure heaters 1253 "C" string high-pressure heaters back in service, commenced PCIOMR from 945 thermal power 1400 Commenced reducing thermal power from 95% for backwash and precoat of condensate demineralizers 1800 Reactor thermal power at 815 for backwash and precoat of condensate demineralizers 5/23 0500 Backwash and precoat of condensate demineralizer complete, commenced power ascension 0700 Commenced PCIOMR from 89% thermal power 2300 Reactor thermal power at 1005, maximum flow, rod limited
,- 5/24 0500 Reactor thermal power at 99%, maximum flow, rod limited (100% electrical) i 1500 Reactor thermal power at 98% maximum flow, rod limited (100%
electrical) 2000 Reactor thermal power at 995, maximum flow, rod limited (1005 electrical) 2200 Reactor thermal power at 1005, maximum flow, rod limited 5/25 2200 Reactor thermal power at 995, maximum flow, rod limited (1005 electrical) 5/26 0700 Reactor thermal power at 1005, maximum flow, rod limited 5/27 2325 Commenced reducing thermal power for removal of "B" reactor '
feedwater pump from service for maintenance 5/28 0005 Reactor thermal power at 72%, holding for removal of "B" reactor feedwater pump from service for maintenance 0027 "B" reactor feedwater pump out-of-service for maintenance, reactor power at 72% ~
0800 "B" reactor feedwater pump out-of-sevice for maintenance, increasing thermal power 2025 "B" reactor feedwater pump back in service, commenced power ,
ascension from 77% thermal power !
Commenced PCIOMR from 96% thermal power 2300 )
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. Sinnificant Ooerational Event Unit 2 Date Time Event (Continued) 5/29 0030 Stopped PCIOMR at 98% thermal power due to CHFLPD limits, decreasing thermar power ,
~0110 Reducing thermal power from 97% due- to control air leak inside drywell 1450 Commenced reducing thermal power from 95% for a controlled shutdown to identify and repair control air leak inside drywell 2250 Tripped turbine, generator off-line, reactor power at 165, controlled shutdown continues 5/30 0134 Manually scrammed reactor, Scram No. 141, from 2% thermal power to identify and repair control air leak inside drywell. (Investigation revealed that the control air leak was caused by a stuck steam seal regulator on MSIV-1-37.)
1445 Reactor in cold shutdown 5/31 2400 Reactor remains down for maintenance on MSIV-1-37
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J Sinnificant Ooerational Event Unit 3 Date Time Event 5/01 0001 - Reactor thermal power at 935, PCIOMR in progress 0600 Reactor thermal power at 975, holding due to computer problems .
1130 Computer back in service, commenced PCIOMR 1730 Reactor thermal power at 100%, maximum flow, rod limited 5/07 0001 Commenced reducing thermal power for turbine control valve test'and SI's 0030 Reactor thermal power at 93% for turbine control valve test and SI's 0157 Turbine control valve test and SI's complete, commenced power ascension 0230 Reactor thermal power at 100%, maximum flow, rod limited 5/13 1200 Reactor thermal power at 99%, maximum flow, rod limited 1600 Reactor thermal power at 100%. maximum flow, rod limited 5/15 0245 Commenced reducing thermal power for turbine control valve test and SI's 0300 Reactor thermal power at 89% for turbine control valve test and SI's 0348 Turbine control valve tests and SI's complete, commenced power ascension-0404 Reactor thermal power at 100% maximum flow, rod limited 5/18 2400 Reactor thermal power at 100% maximum flow, rod limited 5/19 1325 Commenced reducing thermal power to insert control rod 34-51 to 00 for maintenance 1400 Reactor power at 97% for maintenance on control rod 34-51 -
1630 Reducing thermal power for scram testing control rod 34-51 1700 Reactor power at 86% for scram testing control rod 34-51 1725 Scram testing complete on control rod 34-51, commenced power ascension 1900 Reactor thermal power at 100%, maximum flow, rod limited J
5/22 0030 Commenced reducing thermal power for turbine control valve
- test and SI's l 0040 Reactor thermal power at 95% for turbine control valve test and SI's 0050 Turbine control valve test and SI's complete, commenced power ascension 0100 Reactor thermal power at 100%, maximum -flow, rod limited 0630 Lost bus duct cooling fan, commenced reducing thermal power 0745 Reactor thermal power at 53% .due to loss of bus duct cooling fan -
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.Sinnificant Ooerational Event Unit 3
-Date Time Event (Continued) 5/22 0950 Bus duct cooling fan out-of-service for maintenance, increasing thermal power 1020 Reactor thermal power at 58%, holding for maintenance on bus duct cooling fan 1400 Increasing thermal power, bus duct cooling fan out for maintenance 1900 Reactor power at. 61%, bus duct cooling fan limited 5/23 0320 Bus duct cooling fan back in service, commenced power ascension 1830 Commenced PCIOMR from 75% thermal power 5/24 1230 Stopped PCIOMR at 935 power due to maintenance on "C" string high-pressure heaters channel relief valve 2300 Reactor power at 92% and decreasing due to maintenance on "C" string high-pressure heater channel relief valve 5/25 0600 Reactor power at 91% for maintenance on "C" string high-pressure heater channel relief valve 1120 "C" string high-pressure heaters in service, commenced PCIOMR 1840 Stopped PCIOMR at 93% power, removed "C" string high-pressure heaters from service for maintenance on channel relief valve 5/26 0145 "C" string high-pressure heaters in service, holding reactor power at 93% for removal of "A" string high-pressure heaters from service for maintenance on channel relief valves .-
0415 "A" string high-pressure heaters out-of-service for maintenance on channel relief valves, reactor power at 935 0535 "A" string high-pressure heaters in service, reactor power at 935, holding for removal of "B" string high-pressure heaters from service for maintenance on channel relief valves 0545 "B" string high-pressure heaters out-of-service for maintenance on channel relief valves, reactor power at 935 0600 "B" string high-pressure heaters in service, holdf ug at 935 power for removal "A" string high-pressure heatcra from service for maintenance on channel relief valves 0615 "A" string high-pressure heaters out-of-service for maintenance on channel relief valves, reactor power at 92%
2015 "A" string high-pressure heaters back in service, commenced PCIOMR from 92% thermal power O
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Unit 3 Date Time Event (Continued) 5/27 - 0045 Commenced reducing thermal power from 95% per load dispatchers request, load not needed 0200 Reactor power at 75% due to load dispatchers request 0355 Commenced power ascension from 7.5% thermal power 0530 Commenced PCIOMR from 96% thermal power 1200 Reactor thermal power at 100%, maximum flow, rod limited 5/28 0130 Commenced reducing thermal power for turbine control valve '
test and SI's 0200 Reactor thermal power at 935 for turbine control valve test and SI's 0250 Turbine control valve test and SI's complete, commenced power ascension 0300 Reactor thermal power at 100%, maximum flow, rod limited 2110 Received C5 heater high-level alarm 2112 "C" low-pressure heaters isolated 2114 "C" low-pressure heaters in service 2120 Commenced reducing thermal power for removal of "C" string low-pressure heater to check for water hammer in drain lines 2130 "C" string low-pressure heaters out-of-service, reactor power at 90%
2133 "B" string low-pressure heaters isolated automatically 2134 Reactor Scram No.111 from 90% thermal power when "B" string low-pressure heaters isolated while "C" etring low-pressure heaters were being removed from service to check for water hammer in drain lines. Unit remains offline for maintenance on "A" and "B" string high-pressure heaters and "C" str ing l low-pressure heaters l
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l 5/29 1330 "B" string high-pressure heaters maintenance complete 1345 "A" string high-pressure heaters out-of-service for maintenane 1800 "A" string high-pressure heaters maintenance complete 2330 Commenced rod withdrawal for startup 5/30 0125 Reactor Critical No. 125 0340 Rolled turbine-generator 0347 Synchronized generator, commenced power ascension 1600 Commenced PCIOMR from 845 thermal power 2135 Stopped PC10MR at 81% thermal power and commenced withdrawing rods,for power ascension 2300 Commenced PCIOMR from 87% thermal power i
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Unit 3 Date Time Event (Continued) 5/31 0220 Stopped PCIOMR at 86% power and commenced withdrawing control rods for power ascension 0300 Commenced PCIOME from 88% thermal power 1350 Commenced reducing thermal power from 90% due to an oil leak on "A" reactor feedwater pump 1555 "A" reactor feedwater pump out-of-cervice for maintenance (broken oil line), reactor power at 74% and decreasing 1700 Reactor thermal power at 72% for maintenance on "A" reactor feedwater pump oil line 2220 "A" reactor feedwater pump in service, commenced withdrawing control rods for control rod pattern adjustment 2400 Reactor thermal power at 73%, control rod pattern adjustment i in progress l
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. AVERAGE DAILY UNIT POWER LEVEL _
DOCKET NO. 50-259 r ms Ferry.-l UNIT 6-1-83 COMPLETED BY T. Thom TELEPHOh'E 205/729-0834 MONTH _ May DAY " AVERAGE DAILY POWER LEVEL DAY AVER AGE dilly POWER LEVEL (MWe-Net) (MWe-Net) g'
-9 -4 17
-10 .
-4 IS
-9 '
-6 3_ 19 4
-7 -5 20
-0 -4 5' 3
-6 _4 22 7 -6 -4 23
-6 4 8
-6 _4 -
9 _
10 -4 26 -4 11
-4 p -4 12
-4 ~4 28 -
-4 _4
- ,3 29
-4 -4 -
I4 30
-4 -6 15 3, 16 -4 5
INSITIUCTIONS On this format.!ist the average daily unit power leselin Mwe. Net for each day in .the reportism month. Compute o' the nearest whole megawatt.
(9/77)
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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-260 UNIT r u s Ferry-2 DATE COMPLETED BY T. Thoni TELEPIIONE 205/729-0834 MONTH May DAY AVERAGE DAILY POWER LEVEL DAY AVE'R AGE DAILY POWER LEVEL
, (MWe-Net) (MWe.Neti 1
1095 1063
,7 1077 1070.
2 3 1081 1063 3 -
g9 4, 1091 1031 20 5
1077 ,, 775 1075 933 6
7 1058 23 990 8 951 1070 34 9
1066 1075 -
10 1088 36 1072 Ii 1059 27 1074 12 1070 855 33
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13 29
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14 1082 30 -17
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iS 1053 3,
-14 l6 1085 i
INSTRUCTIONS On this fortnat.!ist !he average daily unit p.mer leselin MWe. Net for each day in the reporfine month. Compute io the nearest whole nwgawatt.
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AVERAGE DAILY UNIT POWER LEVEL .
DOCKET NO. 50-296 UNIT Browns Ferry-3 DATE COMPLETED BY T._Thom TELEPHONE 205/729-0834 i MONTH. May DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL
. (MWe-Net) (MWe-Net t i 995 1055
,7 1039 1051 2 3 1042 1057 3 -
39 4, 1052 1058 20 5
1002 1059 21 1060 728 6 22 1046 760 7 23 8 1050 951 24 9
1051 963 3
1056 972 10 26
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.Ii 1059 27 998 12 1052 950 3
13 1057 -14 ."'
1051 588 14 30 1061 849 I5 31 16 1051
.s INSTRUCTIONS Oit this fonnat,!ist the average daily unit pinve leselin Mwe. Net for each day in the seporting month. Compute to
- the nearest whole megawatt.
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UPERATING DATA REPORT DOCKET NO. 50-259 DATE 6-1-83 COMPLETED BY T. Thom .
TELEPHONE 205//29-0834 OPERATING STATUS Browns Ferry - 1 Notes
- 1. Unit Name:
. 2. Reporting Period: May 1983 3293
- 3. Licensed Thennal Power (MWt):
- 4. Nameplate Rating (Gross MWe):
- 5. Design Electrical Rating (Net MWe):
- 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 .
- 9. Power Level To Which Restricted.If Any (Net MWe): NA
- 10. Reasons For Restrictions,If Any: NA This Month Yr to-Date Cumulative
- 11. Hours In Reporting Period - 744 3,623 77,425
- 12. Number Of ilours Reactor Was Critical 0 2,363.25 49,752.79
- 13. Reactor Reserve Shutdown llours 0 47.71 5,785.02
- 14. Hours Generator On-Line 0 2,317.52 - 48,717.64
- 15. Unit Reserve Shutdown flours 0 0 0
- 16. Gross Thermal Energy Generated (MWil) 0 6.784.675 138.557,679 .
- 17. Gross Electrical Energy Generated (MWil) 0 ,___,,,, 2,244,900 45,645,620 -
- 18. Net Electrical Energy Generated (MWil) 0 2,175,548 44,325,327 64.0
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- 19. Unit Service Factor 0 63.1
- 20. Unit Availability Factor 0 64.0 63.1
! 21. Unit Capacity Factor (Using MDC Net) 0 56.4 53.8 l 22. Unit Capacity Factor (Using DER Net) 0 56.4 53.8 l
- 23. Unit Forced Outage Rate 0 8.1 23.8
- 24. Shutdowns Schedulcd Over Next 6 Months IType. Date.and Duration of Each):
.a
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup: October 7, 1983
- 26. Units in Test Statm IPrior to Commercial Operation). Forecast -Achieved i
INITIA L CRITICA LITY INITIAL ELECTRICITY COMMERCIAL OPER ATION '. .
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(0/77) f -
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OPERATING DATA REPORT DOCKET NO.
50-260 -
DATE D-1-0
- COMPLETED BY T. Thom TELEPil0NE 205/729-0834
. OFERATING STATUS
- 1. Unit Name: Browns Ferry - 2 N tes
- 2. Reporting Period: May 1983 -
- 3. Licensed Thermal Power (MWt):
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 31arough 7) Since Last Report. Give Reasons:
NA
- 9. Power Level To Which Restricted,if Any (Net MWe): NA
- 10. Reasons For Restrictions.If Any: NA This Month Yr..to.Date Cumulative
- 11. Ilours in Reporting Period 744 3,623 72,366
- 12. Number Of flours Reactor was Critical 697.57 1,687.04 44,980.51
- 13. Reactor Reserve Shutdown flours 46.43 62.21 13, M 7. 03
- 14. Ilours Generator On.Line 694.84 3,614.48 43.589.93
- 15. Unit Reserve Shutdown llours 0 0 0
- 16. Gross Thermal Energy Generated (MWil) 2,169,799 4,517,028 124,926,875 '.
- 17. Gross Electrical Energy Generated (MWil) 735,440 _ _ 1,529,680 41,554,588 -
- 18. Net Electrical Energy Generated (MWil) 716,352 1,485,538 40,358,613
- 19. Unit Service Factor 93.8 44.6 60.2
- 20. Unit Availability Factor 93.8 44.6 60.2
- 21. Unit Capacity Factor (Using MDC Net) 90.4 38.5 3z.4
- 22. Unit Capacity Factor (Using DER Net) 90.4 38.5 52.4
- 23. Unit Forced Outage Rate 6.6 7.1 26.5
- 24. Shutdowns Scheduled Oser Next 6 Months (Type. Date and Duration of Each):
a
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
- 26. Units in Test Status (Prior to Commercial Operation): Forecast Achiesed INl f!A L Cit lTICA LITY INITIAL ELECTRICITY
, COMMERCIA L OPER A TION _
(4/77)
18 .
OPERATING DATA REPORT DOCKET-NO. 50-296-DATE D~ M 5
. COSIPLETED BY T. Thom TELEPIIONE 205//z9-0834 OPERATING STATUS
- 1. Unit Name: Browns Ferry - 3 Notes
- 2. Reporting Period: May 1983 -
3293
- 3. Licensed Thermal Power (51Wt):
- 4. Nameplate Rating (Gross 5!We):
- 5. Design Electrical Rating (Net SIWE): 1065
- 6. Slaximum Dependable Capacity (Gross alWe): 1098.4
- 7. Alaximum Dependable Capacity (Net AlWe): 1065
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7)Since Last Report. Give Reasons:
N/A
- 9. Power Level To Which Restricted,If Any(Net SIWE): N/A
- 10. Reasons For Restrictions.If Any: N/A This alonth Yr..to-Da t e Cumul.itive
- 11. Ilours in Reporting Period 744 3,623 54,791
- 12. Number Of flours Reactor Was Critical 716*15 3'132.67 4,074.95
- 13. Reactor Reserve Shutdown llours 27.85 490.33 3,862.48
- 14. Hours Generator On-Line 713.78 3,087.28 -39,861.34
- 15. Unit Reserve Shutdown flours 0 0 0
- 16. Gross Thermal Energy Generated (51Wil) 2.259.677 9.756.178 119.092,282 .
- 17. Gross Electrical Energy Generated (MWil) 733.660 _._ ,_, 3.226,180 39,265,970 ~
- 18. Net Electrical Energy Generated (MWil) 714.985 3.139.'.62 38.120.066
- 19. Unit Service Factor 95.9 85.2 72.8
- 20. Unit Availability Factor 95.9 85.2 72.8
- 21. Unit Capacity Factor (Using MDC Net) 90.2 81.4 65.3
- 22. Unit Capacity Factor (Using DER Net) 90.2 81.4 65.3
- 23. Unit Forced Outage Rate 4.1 14.8 17.2
- 24. Shutdowns Scheduled Oser Ne.st 6 MonthsIType. Date.and Duration of Eachl:
s
- 25. If Shut Down At End Of Iteport Period. Estimated Date of Startup:
- 26. Units In Test Status IPrior io Commercial Operation): Forecast Achiesed INITIA L CltlTICALITY INITIA L I?!.ECTRICITY COMM ERCIA L OPER A IlON (9/77)
n 3
j' UNIT SIIUTDOWNS AND POWER REDUCTIONS DOCKETNO. 50-259
- UNIT NAME Browns Ferry-1 "
i DATE 6/1/63 -,_ '
COMPLETED BY T. Thorn REPORT MONTil May
.TELEP110NE 205/729-0834 !
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.,- 5g 'h 4.Ei Licensee ,E3, $4 Cause & Corrective Eg .555 gg No. Date g, @ Event g.E Action to H j= $ gg Report 2 mV jU Prevent Recurrence
- 6 .
264 5/1/83 S 744 C 4 EOC-5 refuel outage continues .
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- 2 3 4 ,
. F: Forced Reason: Method: Exhibit G - Instructions
. . S: 5cheduled A. Equipment Failure (Explain) 1 -Manual for Preparation of Data B-Maintenance of Test 2-Manual Scram- Entry Sheets for Licensee C Refueling 3-Autom.nic Scrami E.ent Report (LER) File (NUREG-D Regulatory Restriction 4 Other (Explain) 0161)
E-Operator Training & License Examination F-Administrative 5 G-Operational Error (Explain) Exhibit I Same Source
- W/77) ll Other (Explain)
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- I DOCKET NO.
50-260 .-
UNIT SilUTDOWNS AND POWER REDUCTIONS UNIT NAME Browns Ferry-2 ,.
DATE 6-1-83 "
May COMPLETED BY . T. Thom
- REPORT MONTil TELEPif0NE ?ns/779-nR w i '
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- i" E Licensee ,E-r, ym, Cause & Corrective No. Date g 3s s .g g 5 . Event g 'g el Action to H jE 5 5 ;2 g
<- g Report : in U 5' v
Prevent Recurrence O
253 5/7/83 S H Derated for control rod pattern adjust -
ment 254 5/20/83 S H Derated for control rod sequence
, exchange 255 5/27/83 F B Derated for maintenance on'"B" reactor feed water pump w
256 5/29/83 F 2.73 H Turbine trip due to control air leak ,
inside drywell 257 5/30/83 F 46.43 H 2 Reactor scram due to control air leak inside drywell e
I 2
- 3 4 .
F: Forced Reason: Method: Exhibit G. Instructions
, S: Scheduled A.Ecluipment Failure (Explain) ! Manual for Preparation of Data B-Maintenance of Test 2-Manual Scram. EntriSheets for Licensee C Refueling . 3 Automatic Scram. Event Repoit (LER) File t NURI'G-D Regulatory Restriction 4-Other (Explain) 0161)
E-Operator Training & License Examination .
F-Administrative 5 G-Operational Error (E.4 plain) Exhibit I same Source .
(9/77) li Other (Explain) *'
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1
- 1 I!
DOCKET NO. 50-296 .,
UNIT SilUTDOWNS AND POWER REDUCTIONS '
- UNIT NAME Browns Fet rv-3 * ,
DATE D-1-33 May COMPLETED BY ' T. Thom .
REPORT MONTil TELEPilONE 205/729-0834 l t
-_ = c
, 5? 3 $Yi Licensee [-r, Ng Cause & Corrective .
No! Date g 3g ( .g g 5 Event ti ? 5-? Action to H
$~ 5 3< dj g Report : NU 5' Prevent Recurrence
- v Q
132 5/22/83 F A Derated due to loss of bus duct cool-ing fan.
133 5/28/83 F 30.22 H 3 Reactor. scram when '!B" string low-pressure heaters isolated while "C" string low-pressure heaters were being removed from service to check for water hammer in drain lines. -
i I 2 3 4 F: Forced Reason: Method: Exhibit G-Instructions S: Scheduled A Equipinent Failure (Explain) ! Manual for Preparation of Data .
B-Maintenance of Test 2-Manual Scram. Entry Sheets for Licensee C-Refueling 3 Autom:itic Scram. Event Report (LER) Fife iNUREG- -
D Regulatory Restriction 4 Oiher (Explain 1 0161) -
E-Operator Training & License Examination F-Administrative 5 G Operational Error (Explain) Exhibit I- Same Source (9/77) Il-Other (Explain) ,
4
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Pg 3 BROWNS FERRY NUCLEAR PLANT. UNIT 1 cnd Common .
CSSC EQUIPMENT Appendix B ELECTRICAL MAINTENANCE SU MARY '
'9 ,, 9
~
9/29/82 .
For the Month of May. -19 83 . } ', .
'\
's
' Effect on Safe i Action Taken Nature c: Operation of Caese of -
Results of To Prec1Ude .
Date System Component Ma in t enance The Reactor Malfunction Malfunction -Recurrence . .
5/10/82 RBCCW "Al" drywell Drywell blower None Bad motor. Drywell blower "Al" The motor was 5/16/83 blower motor. motor "Al" inoperable. repaired and ,
tripped. replaced per EMI *
1 . y i MR #A-061300 .
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- 5/24/83 Air Con- Auxill~rya Chilled water None Auxillary core Chilled water pump Cleaned the
, ditioning contacts on pump "A" hg* 'j tacts on pump "A" would not start. auxillary contacts
. (Cooling- "B"; chilled would not "B" motor, starter g and the' pump 3, catjsg) water pump start. stuck and would ,/ . operated properly.
1 '. < /. ; motor starter , ' f', not allow "A" MR #A-148764 j
d /, pump motor to f 3,f , start.
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~
.3/28/83 Air 'Un ts 1.and Bad oil None Oil pressure Chiller taken out of The.oilrpressure Condition- 2jcontrolbay' ' pressure - switch worn. service to replace switch' was ing emergency switch. , the oil pressure replaced and the (Cooling- chiller oil -
switch. chiller returned
.' .llea t ing) pressure ;, ' '
, to service.' ,i switch. '
o, r, U MR #A-074183 ' ,,
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E}:5IL 30. , .e Appendix B ' . T, " , ,-
, - 'OSSC'EQUIPMEN , ELECTRICAL't INTENANCE
SUMMARY
., a 3 4 - 9/29/82 ,
For the Montti of
~
May~
T,_ Q. , .
J 9 " 83 '
J Effect en Safe . Action Taken j gature of . Operation of- Cau'se' of Results of To Preclude jlde System Component Milntenance The Reactor Malfunction Malfunction Redurrence
./5/83 Radiation Radiation RE '30-126 None Bad cam mtor. RE 90-126: inoperable. Replaced the bad Monitoring Monitor inot"t rabic. motor and returned RE 90-126 RE 90-126 to service.
MR #A-135736 ,
i/5/83 Vent 11at- Diesel Gener- The inlet None Bad damper motor. Damper inoperable. Replaced the bad ing ator "C" room damper failed -damper motor.
inlet air to open when MR #A-148496 damper on "B" exhaust ,
"B" exhaust fan was fan s ta r t. ed . .
U 2/22/ Neutron Neutron Broken battery None During mainten- Required temporary Replaced the'c' ell 82 Monitoring monitoring terminal on ance the cell flag terminal to be per SEMI 39. -
./6/83 battery lA. celt 1-3 of 1-3 flag terminal fabricated and used MR #A-061289 h channel A unit was broken while until a replacement neutron cable connections cell for 1-3 could f
, mon t r o:-ing were being made. be obtained.
- battery.
L
./10/83 CRD 11S-85-47 Iland switch None Broken stop. Required care to be Replaced broken (ggs _:45-47) taken by operator to stop, hand switch stoi broken, avoid turning hand operated properly. ,
switch past desired MR #A-148694 *
, setting.
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2 BRO'cS I'ERRY NUCI. EAR PLANT UNIT Eh3g 33
- Appendix B
_CSSC EQUIPMENT ELECTRICAL' MAINTENANCE UNMARY '
9/29/82 .
19 83~
For the Month of May .
.N *' V r Effect on Safe . _ . , Action Taken Cause of Nature of Operation of -
Results of To Preclude .
Dn:e Systen Component Maintenance The Reactor Malfunction Mplfunction Recurrence . .'
~~,
, s. .
./5/83 Contain- Relay 84K3B Received a None Bad coil on Relay contacts closed, The relay. coil was ment false SGT duct relay 84K3B, thus giving a false: rgplaced and the.
Atmosphere pressure alarm. relay returned to-Diltition abnormal alarm. service.
MR JA-148533
- 3 t ,
N i/10/83 Fire Fire protec- Received a None Relay coil Power supply low Replaced the relay Protection tion DC power " Auto fire pro- burned. voltage / ground fault per EMI 23 and
vol tage/grounc. power supply . , able. MR #A .148563 fault meter / trouble" alarm x relay. on panel 9-8. s i N *
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./13/83 TIP "2D" TIP Ball valve None Blown fuse. Ball valve would nest Replaced 'the blown machine ball would not open. open. fuse, TIP machine ,
valve "2D" operated- l
, circuitry. properly. i MR #A-148595
. ~
, {
./26/83 IIPCI ~ HPCI inverter < Blown inverter llPCI inoper- Blown fuse. HPCI inoperable.
fuse. . fuse was replaced
, , able.
Theblowninvert and the HPCI
, returned to .
s service.
MR #A148095 LER#BFRO-50-260/
83028 e
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BROk"1S FERRY MUCLEAR PLANT UNIT 1 EMSIL 30 f Appendix B '
CSSC EQUIPMENT ELECTRICAL MAINTENANCE SNDIARY : .
9/29/82 For the Month of hy 19 83 . .
- 1 Effect on Safe Action Taken Nature of Operation of Cause of -
Results of; To Preclude Dh.:e System Component Maintenance The Reactor Malfunction Malfunction Recurrence
/17/83 Contain- "B".0xygen H0 analyr r None Oxygen sample Oxygen inlet pump The oxygen inlet sample inlet 22 was not showing inoperable. pump assembly was ment. inlet pump was Incrting pump. oxygen flow. locked up. replaced and re-
- ~
turned to service.
MR #A-149554 '
/29/83 Sampling & Relay 16A-K79 While invest- 3-FCV-43-13 The relay coil The armature being The relay was Water igating a " Fuse 'was inoperable. had overheated- stuck in the energiz- replaced, SI Quality Blown" annun- and melted the ed position prevented 4.7.D.1.a-1 per-ciation' relay coil spool FCV-43-13 from formed and the 16A-K79 was material, thus clesing. valve returned to found to have sticking the -
service. w failed. armature in the MR #A-147210 energized posi- LER #BFRO-50-296/
tion. 83028 "B" hydrogen The "B" hydro-
~
/4/83 Contain- Hydrogen The end bell of Hydrogen analyzer "B" The hydrogen sam-
"B"
~
ment sample inlet gen sample analyzer the hydrogen sam- was removed from ple inlet pump and
, Inerting pump motor. Inlet pump was was removed ple inlet pump service. motor assembly was making abnor- from service. motor was worn -
replaced and the mal noise. apprerimately analyzer returned
.C03 inches, to service. '
allowing exces- MR #A-147629 sive vibration of LER#BFRO-50-296/
the rotor of the 83030 motor. The apparent cause of wear in the end -
bell was improper bearing clearance ,
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F.A D~.'-:NANC2 TiiE 15. ACTOR '
2'.5.FC CTION y_\'.:.1 Mc;;p .I R E C"? ?.:
- U-l t-9 90 RR-90-249 Repair None Age Loss of Record None
.-11 90 RR-90-101 Repair None Ag'e Loss of Record None
- -13 90 RM-90-249 Repair None Age Loss of Indication None i-18L 63 -
FIS-63-11 Replace None ,
End of Life Loss of Indication None l7-2 *
-20 73 TR-73-54 Repair None Age . Loss of Record
- J -
i-18 90 RR-90-135 Repair None Age -
Loss.^of. Record None w I-23 90 RR-90-249 Repair None Age e
Loss of Reco'rd None'
- -24 68 -
PDT-68-19 Replace None 4 Age Loss,of Indication None ..
l-25 1 PDIS-1-12B Replach None Age Loss of Indication None? - -
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cSSC EOUIIMENT MECl!ANICAL MAINTE!%NCE SUlt!ARY ,
For the Month of May 19 83 .
EFFECT ON SAFE ACTION TAKEN -
DATE , SYSTEM COMPONENT NATURE OF OPERATION OF - CAUSE OF RESULTS OF 'TO PRECLUDE MAINTENANCE THE REACTOR MALFUNCTION MALFUNCTION RECURRENdE 5-4 23 air release replaced valve s- none NA . hA NA valves C1, B3, & D3 l'
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BROWNS FERRY NUCLEAR PIANT UNIT 1 MECHAWICAL MAINTEENCE
SUMMARY
CSSC ECUIPMENT
- For the Month of - May 19 83 - '
] ,
EFFECT ON SAFE ACTION TAKEN -
.DATE ,' SYSTEM COMPONENT NATURE OF OPERATION OF CAUSE OF -RESULTS OF TO PRECLUDE MAINTENANCE THE REACTOR MALFUNCTION MALFUNCTION RECURRENCE 35-4 74 seal heat preventative none normal use NA NA ,
exchangers maintenance cleaned heat l*
exchangers j5-8 91 - control bay preventative none normal use NA NA 1 chillers. maintenance
- cleaned cooler
- s l and rebuilt ,
i compressor -
i5-12 67 core spray preventative none normal use NA NA-I room coolers maintenance ,
flushed cooler s t
- 75-22' 86 directional replaced valve none (unit in not known rod inserting post none w control valve outage) "00" on HCU e
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BROWNS FERRY NUCLEAR PIANT UNIT 2 . .
.c .
MECHANICAL MAINTE!RNCE
SUMMARY
CSSC EOUIPMENT *
- For the Month of May 19 83 EFFECT ON SAFE ACTION TAKEN DATE , SYSTEM COMPONENT NATURE OF OPERATION OF CAUSE OF RESULTS OF 10 PRECLUDE NAINTENANCE THE REACTOR MALFUNCTION MALFUNCTION RECURRENCE FCV 10-500 replaced valve none. normal age increased leakage in NA
- 5-31 10 during short drywell outage in l-drywell l5-31 32 -
manifold assem- replaced mani- leak resulted in not known unit shutdown none bly on C inboard fold assembly. a manu d shut-MSIV down of the reac-- -
tor because of increasing 0 2
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levels in
- i primary contain-i ment ,
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BROWNS FERRY NUCLEAR PIANT UNIT 3 -
i c.iSC EOUIIHENT MECHANICAL MAINTENANCE
SUMMARY
For the Month of May 19 83 EFFECT ON SAFE ACTION TAKEN DATE , SYSTEM COMPONENT ' NATURE OF :0PERATION OF CAUSE OF RESULTS OF- TO PRECLUDE MAINTENANCE Tile REACTOR MALFUNCTION MALFUNCTION RECURRENCE 5-8 91 control bay preventative none. normal age NA NA chiller 3A maintenance cleaned coolers' f 5-16 90 CAM 90-251' replaced puller none pulley worn CAM temporarily out none on pump motor of service 5-29 73 gland seal replaced HPCI none pressure surges condenser gland seal HPCI removed from an initial inv'esti- ,
service during gation to determine '
condenser replacement of gasket cause of surges is gasket being undertaken 5-30 73 gland seal replaced HPCI none pressure surges HPCI removed from
~1 an initial investi-.
condenser gland seal service during gation to determine condenser replacement of gasket cause of. surges is gasket being undertaken g 5-12 74 LFCI MG set replaced entered LCO not known none none 3EA bearing ' '
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~
FIRLn SERVICES
SUMMARY
May 1983
~
MAJOR WORK AREAS A. Refuel Floor - On May 2,1983, core unload was completed and the critical path work continued with LPRM changeout, which was completed on May 4, followed by fuel pool gate installation on same day at 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br />.
Invessel inspection was completed on May 5,1983 at 0400 hours0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br />.
Control roc drive (CRD) uncoupling started on May 6 and was completed on May 13. After initial tryout and learning, the new uncoupling tool for unlatching CRDs from top proved itself very effective and reduced exposure rates greatly. In parallel with unlatching, the rod position indication system (RPIS) probes were removed in preparation for CRD changeout. The first CRD was changed out on May 10. A total of 100 were scheduled for changeout, and at the end of May were completed.
Fuel sipping started on May 17, and on May 31, 615 bundles were completed out of 764.
B. Turbine - During May, all components that required disassembly were disassembled. Radiation levels on the low-pressure turbine "A" and "B" inner cylinders was high, and the turbine decontamination room was required to decontaminate the inner cylinders. One inner cylinder has been deconned. In addition to the inner cylinder, the "B" and "D" control valves have been sent to turbine decontamination due to radiation levels.
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FIELD SERVICES
SUMMARY
May 1983 MAJOR WORK AREAS (Continued)
B. Turbine - (Continued)
All sandblasting was completed in May.
The inspection of the "B" rotor revealed that the. blades from the 13th stage turbine end would require removal and shipment to the General Electric Service Shop in New-York for repair. Currently, methods are being reviewed for deconning blades to an acceptable level for
. shipment into the state of' New York. It was also discovered that low-pressure "A" rotors 13th stage blades would require repair, but this repair can be accomplished onsite. At this writing, no definite i schedule has been developed to access the schedule impact of these I repairs due to lack of sufficient scheduler-type information.
i l The reactor fe- Jump turbine "C" is being assembled at this time with 1
~'
no major repairs required.
l The main turbine bypass control and intercept valve maintenance was completed in Hay.
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FIRtn SERVICES
SUMMARY
May 1983 MAJOR WORK AREAS (Continued)
B. Turbine - (Continued)
An inspection of the front standard revealed that the bull gear, turbine oil pump gear and bearing had acquired damage. Paperwork is in process to award a contract for repair.
The "B" and "D" control valve maintenance will continue upon completion of deconning the valves.
C. Drywell - During the first week in May, all 13 main steam relier valves (MSRV) were removed and blanks installed, started preparatory work for installation of snubbers at Yarway column, and prefabrication of MSRV control air piping. Fabrication of vacuum breaker parts started and one was completed and assembed on May 19 for testing at Wyle Laboratories; however, extremely slow progress in getting contracts issued to Wyle Lab prevented shipment of both MSRVs and vacuum breakers.
Main steam isolation valve work consisted of further testing, and by the end of May, seven out of eight were found to require rebuild; four were disassembled and lapping started on valveseats after long and extensive decontamination work, which had not been expected.
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34 * *
- FIELD SERVICES
SUMMARY
May 1983 MAJOR WORK AREAS (Continued)
D. Electrical - During the month of May, most of the electrical work plans were issued for review and approval. All of the work plans that require significant manpower and duration were released for work during May except for P0126. The most significant work items are l'isted below:
- 1. P0399 Long Term Solution to Instrument and Control Bus Problems -
All the conduit has been installed, and the associated equipment has been installed except for one disconnect switch which cannot be installed until an outage is available on the "Tr bus. In addition, a procedure was written which identifies the steps required to perform the tie-ins to the "A" and "B" bus.
Currently, operations is reviewing the tie-in procedure.
- 2. PO422 Provide Redundant Class IE Protection at Interface of Non-l class IE Power Supplies and the RPS percent of the conduit
~
has been installed and five of the six protective circuit cabinets have been installed. The sixth cabinet must be i installed on P0399 outage.
l 3 P0533 Torus Temperature Monitoring System - Started conduit installation and currently installing cabinets 9-87 and 9-88 in l
l the auxiliary instrument room.
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' 35 ^
> = -
FIELD SERVICFS
SUMMARY
.. May 1983 M?iJOR WORK AREAS (Continued)
D. Electrical - (Continued)
- 4. PO451 Add a three-second Time Delay Pickup to the RCIC High-Differential Pressure Steam Line Isolation - The modification was completed during May. Currently in the process of closing out the work plan.
Near the end of May, the work plans for the following modification were released for work: -
P0322 Replace existing containment pressure maintenance system with one capable of measuring from five psig to at least 225 pais.
P0232 Replace present torus level transmitter with ones capable of measuring from bottom of torus to five feet above normal water level.
P0324 Supplement existing containment radiation monitors with redundant instruments capable of monitoring radiation levels up to ten Rad /M.
Other electrical work: started maintenance on recirculation pump motor motor-generator set 1A during May. This work was halted when CRD changeout started due to the requirements for machinist to support drive changeout.
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- 36 ,
a . .
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FIELD SERVICES
SUMMARY
May 1983 MAJOR WQRK AREAS (Continued)
D. Electrical - (Continued)
EMI-71 on' pump motors continued in May,and currently 22 of 48 motors have been checked out. The check on the condenser circulating water pump motor 1C required that the motor be pulled and sent to Power Service Shop for repir.
EMI-7 on breakers started during May, and 12 of 60 are complete. No
, problem breakers have been found to date.
The electrical group supplied manpower to support cable pulling for the new buildings being constructed onsite.
Supported the torus group by installing cable trays and welding leads l- inside the torus. Electrical support was also required on the torus
! ~
vent fans and temporary power supplied to the torus.
Special training classes for the electricel group were conducted on EMI-18, EMI-7, and EMI-71.
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FIRtn SERVICES
SUMMARY
May 1983 MAJOR WORK AREAS (Continued)
E. Mechanical - By mid-May drawings were received for duct work at diesel generators. By the end of May, virtually all overhead duct supports were installed; 80-percent of ducting for one unit was prefabricated by Power Service Shops, when material delivery problems shutdown duct p'refabrication.
ISI work on recirculating system rapidly increased from 29 welds to 61; requiring inspection, of which 15 were completed in May with seven rejects and two under evaluation.
Probolog contractor moved onsite on May 9 and started work on heat exchangers; completing stator, hydrogen, exciter, EHC, and portions of the turbine lubrication oil coolers by month end.
ANI Requirements - P0392 Scram Discharge Header prefabrication and its flush connections on P0538 required ANI involvement; also P0361, torus attached piping and nozzle reinforcing. Hold points have been established in work plans. Maintenance items under Section XI during the mor.th of May did not require any welding work.
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FIELD SERVICES
SUMMARY
May 1983 MAJOR WORK AREAS (Continued)
E. Mechanical - (Continued)
ALARA: During the month of May the primary ALARA concerns, other than routine work items, were as follows:
- Installation of shielding around the recirculation system to support the in-service inspection, Shielding of the CRD north header, Numerous deconning of the following:
RWCU heat exchange rooms Basement in drywell TIP indexes CRD rebuild room MSIV poppets and internals LP turbine inner cylinders
- Extensive beta surveys were conducted Evaluation of CRD changeout crews' TLDs on a daily basis Flushing of system to reduce radiation levels Pre-work briefings on selected deconning/ transporting efforts F. Planning and Scheduling - During the month of May, one schedule evaluation was made and numerous mini-schedules were developed to l support critical activities. Development of detailed tracking sheets for electrical, mechanical and piping progress reporting continues.
Status reports from foremen in field and engineers continue to support overall planning activities. Computer system PROJECT /2 and INFO are being utilized more than any previous outage.
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- 39 ,-
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FIELD SERVICES
SUMMARY
May 1983 MAJOR WORK AREAS (Continued)
F. Planning and Scheduling - (Continued)
Drywell work and ISI work at recirculation system with expected weld repairs are being closely monitored as to impact on schedule.
G. Torus - With fuel pool gates in place, the torus drain down and decon-tamination work inside was started on May 5 at 0910 hours0.0105 days <br />0.253 hours <br />0.0015 weeks <br />3.46255e-4 months <br />. During the second half of May sandblasting, ductwork, airheaders, welding. leads and scaffolding for modifications were completed; and on May 24, actual modification work was started. Requirements of facemasks slowed progress and by the end of May tie-bars, X, Y, Z gussets, and 24" high-pressure coolant injection, and 18" residual heat removal modifications were approximately 8-percent complete.
Until mid-May, outside torus modifications continued with 11 out of 16 anubber wall brackets installed; N, J, and L lapplates completed.
~
Work inside of vent headers consisted of installing safety relief valve restraints, which progressed to 85-percent complete by month end.
Attached piping efforts continued throughout the month. A total of 123 pipe supports of 358 were completed during the month, boosting the total to 130 of 358. By system the following progress was made:
HPCI - 65%, RCIC - 705, RHR Loop 1 - 30%, RHR Loop II - 755, CS Loop I - 30% and Loop II - 255, drywell and torus purge - 155 and i
~ '
PSC ringheader - 0% complete. '
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- 40
, .l- * .
FIELD SERVICES
SUMMARY
tiay 1983 MAJOR WORK AREAS (Continued)
H. Administrative - The overtime percentage for the month of April was 23-percent with 119,611 straight time hours and 35,570 overtime hours.
As of April 30, 1983, year-to-date overtime percentage was 20-percent, 922,490 straight time hours and 232,946 overtime hours. The overall goal of the overtime percentage is 17-percent.
The O&M budget for April was $2,561,269 and the expenditures were I
. $1,654,815 with yean-to-da'te budget being $19,485,364 and actual year-to-date expenditures being $18,212,795. The capital budget was
$3,154,578 and the expenditures were $2,085,439 with year-to-date budget being $26,361,800 and actual year-to-date expenditures being
$10,936,120. Overall budget was $5,720,847 and the overall expenditures were $3,720,254 with year-to-date budget being
$45,847,164 and actual year-to-date expenditures being $29,148,814.
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TENNESSEE VALLEY AUTHORITY Browns Ferry Nuclear Plant P. O. Box 2000 Decatur, Alabama 35602 fJUN 101983 Nuclear Regulatory Commission Office of Management Information and Program Control Washington, DC 20555 Gentlemen:
Enclosed is the May 1983 Monthly Operating Report for Browns Ferry Nuclear Plant Units 1, 2, and 3 Very truly yours, TENNESSEE VALLEY AUTHORITY
,9 _A ll
, K. N
. A. Coffey Acting Power Plant Superintendent Enclosures cc: Director, Region II Mr. Bill Lavalee Nuclear Regulatory Commission NSAC Office of Inspection and Enforcement P. O. Box 10412 101 Marietta Street Palo Alto, CA 94303 Atlanta, GA 30303 (1 copy)
Director, Office of Inspection f
and Enforcement Nuclear Regulatory Commission Washington, D. C. 20555 (10 copies)
Mr. A. Rubio, Director Electric Power Research Institute P. O. Box 10412 l Palo Alto, CA 94304 l
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An Equal Opportunity Employer
$>[i(s