ML20065D157
| ML20065D157 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 08/01/1982 |
| From: | Thom T TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20065D138 | List: |
| References | |
| NUDOCS 8209240410 | |
| Download: ML20065D157 (44) | |
Text
9 TENNESSEE VALLEY AUTHORITY DIVISION OF NUCLEAR POWER BROWNS FERRY NUCLEAR PLANT MONTHLY OPERATING REPORT July 1, 1982 - July 31, 1982 DOCKET NUMBERS 50-259, 50-260, AND 50-296 LICENSE NUMBERS DPR-33, DPR-52, AND DPR-68 Submitted by:
A~ ccm Plant Su[elintendent khj9 042o g20018 R
OCK 03000259 PDR 4
... _. =. _
i TABLE OF CONTENTS i
I J
.t Operations Summary...
1 Refueling Information....................
4 Significant Operational Instructions.....
6 Averge Daily Unit Power Level.
17 Operating Data Reports.
20 i
Unit Shutdowns and Power Reductions.............
23 Plant Maintenance......................
26 Field Services Summary....................
38 9
?
k 1
i i
. _. _ _,, _ _ _,.. _.,, _. _ _ _ _ _ _ _ _ ~ _
1
_ Operations Summary July 1982 The following summary describes the sigrificant operation activities during the reporting period.
In support of this summary, a chronological log of significant events is included in this report.
There were 14 reportable occurrences and three revisions to previous reportable occurrences reported to the NRC during the month of July.
Unit 1 There were no scrams on the unit during the month.
Unit 2 There were five scrams on the unit during the month.
On July 19, the reactor scrammed on high APRM signals caused by a pressure transient when a main steam pressure sensing line for the EHC system failed.
The reactor scrammed on July 20 when a boot was not removed from a MSIV relay during an instruction which gave the RPS logic a false signal of tvo MSIVs going closed.
On July 21, the reactor scrammed when the turbine tripped on low condenser vacuum caused by a SJAE third stage isolating due to an increase in discharge pressure.
The reactor scrammed again on July 21 after the turbine tripped from low condenser vacuum caused when the unit was placed in the run mode at less than optimal conditions on the SJAEs.
On July 30, the reactor was manually scrammed when power dropped to less than 30 percent and RWM/RSCS had not and could not be proven operable.
Power dropped to less than 30 percent when a feedwater signal dropped out because of a leak at the feedwater flow transmitter which caused the recirculation pumps to run back to minimum speed. The last scram began the unit 2, E0C-4 refuel and maintenance outage.
/
2 Operations Summary July 1982
~
Unit "4 There was one scram on the unit during the month.
On July 31, the reactor was manually scrammed to comply with a limiting condition for operation (LCO) when secondary containment could not be verified.
D
2 3
N Coerations Summary (Continued)
July 1982 Fatigue Usane Evaluation The cumulative usage factors for the reactor vesse] are as follows:
Location Usane Factor Unit 1 Unit 2 Unit 3 Shell at water line 0.00552 0.00448 0.00383 Feedwater nozzle 0.26960 0.19544 0.14503 Closure studs 0.21420 0.14759 0.12539 NOTE:
This accumulated monthly information satisfies Technical Specification Section 6.6. A.17.B(3) reporting requirements.
Common System Approximately 2.40E+05 gallons of waste liquids were discharged containing approximately 1.81E-01 curies of activities.
9 i
I
V, e
s 4
s Ooerations Su==arv (Continued)
July 1982 Refuelina Information Unit 1 Unit 1 is scheduled for its fif th 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 inte the core; finishing the torus modification; turbine inspection; finishing TMI-2 modifications; post-accident sampling facility tie-ins; core spray changeout; and changeout of jet pump hold-down beams.
There are 764 fuel assemblies in the reactor vessel.
The spent fuel storage pool presently contains 52 new fuel assemblies; 260 EOC-4 fuel assemblies; 232 EOC-3 fuel assemblies; 156 EOC-2 fuel assemblies; and 168 EOC-1 fuel assemblies.
The present ccpacity 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 began for its fourth refueling on 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-pressure turbine inspection; generator inspection; MG set installation for LPCI modification; loading additional 8 X 8 fuel assemblies ir.to the core; THI-2 modifications; post-accident sampling 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 assem]l1es; 353 EOC-3 fuel assemblies; 156 EOC-2 fuel assemblies; and 132 EOC-1 fuel assemblies in the spent fuel
5 Ooerations Sn===ry (Continued)
July 1982 Fefueling Information Unit 2 (Continued) storage pool. The present available capacity of the spent fuel pool is 861 locations.
Unit 3 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) as.semblies into the core; finishing the torus modifications; post-accident sampling facility tie-in; core spray changeout; finishing THI-2 modifications; turbine inspection; and changeout of jet pump hold-down beams.
There are 764 fuel assemblies presently in the reactor vessel.
There are 280 EOC-4 fuel assemblies; 124 EOC-3 fuel assemblies; 144 EOC-2 fuel assemblies; and 208 EOC-1 fuel assemblies in the spent fuel storage pool.
The present available capacity of the spent fuel pool is 993 locations.
6 Significant Ooerational Eigni Unit 1 Date Time Event 7/01/82 0001 Reactor thermal power at 75% for control rod pattern adjustment.
0100 Reactor thermal power at 72% for control rod pattern adjustment.
0130 Commenced power ascension from control rod pattern adjustment.
0400 Commenced PCIOMR from 77% thermal power (Sequence "A").
1620 Commenced ~ educing thermal power from 86% to place "C" string high-pressure heater in service.
1715 Reactor thermal power at 79%,
"C" high-pressure heaters in service, commenced PCIOMR (Sequence "A").
1930 Stopped PCIOMR to remove "B" string high-pressure heaters from service for maintenance, reactor power at 87%.
2300 Commenced PCIOMR from 67% thermal power (Sequence "A").
7/02/82 0700 Reactor thermal power at 935, for "B" string high-pressure heater maintenance.
1400 Reactor thermal power at 925, for "B" string high-pressure heater maintenance.
2200 "B" string high-pressure heaters in service, commenced power ascension.
7/03/82 0001 Commenced PCIOMR from 945 thermal power (Sequence "A").
0800 Reactor thermal power at 995, maximum flow, rod limited.
7/04/83 0300 Commenced reducing thermal power for SI 3.4.3.A.2 (CRD Exercise).
0400 Reactor thermal power at 96% for CRD exercise.
0440 CRD exercise complete, commenced power ascension.
0500 Reactor thermal power at 995, maximum flow, rod limited.
7/05/82 0230 Commenced reducing thermal power for control rod pattern adjustment.
0400 Reactor thermal power at 76% for control rod pattern adjustment.
0452 Control rod pattern adjustment complete, commenced power ascension.
0700 Commenced PCIOMR from 845 thermal power (Sequence "A").
2200 Reactor thermal power at 995, maximum flow, rod limited.
7 fignificant Operational Event Unit 1 Date Time Event 7/09/82 2133 Commenced reducing thermal power for removal of bus duct cooling fan from service for maintenance.
7/10/82 0300 Reactor thermal power at 525 for maintenance to bus duct cooling fan.
0350 Bus duct cooling fan back in service, commenced power ascension.
0630 Commenced PCIOMR from 88% thermal power.
0800 Reactor thermal power at 995, maximum flow, rod limited.
1130 Adjusting control rods to clear rod blocks, reactor power at 995 1500 Reactor power at 98% due to rod adjustment to get off of rod blocks.
1835 Commenced power ascension from 98% thermal power.
1900 Reactor themal power at 995, maximum flow, rod limited.
7/15/82 0930 Commenced reducing thermal power to remove "B" CCW pump froms service (high backpressure).
1500 Reactor thermal power at 86%, holding due to high backpressure.
1855 "B" CCW pump back in service, commenced power ascension.
2000 Commenced PCIOMR from 95% thermal power.
2300 Reactor thermal power at 735 for control rod pattern adjustment.
2220 Commenced reducing thermal power from 98% for cortrol rod pattern adjustment.
7/16/82 0050 Commenced PCIOMR from 73% thermal power (Sequence "A").
1630 Stopped PCIOMR at 935 due to high backpressure.
2330 Reduced thermal power to 90% for control rod exercise, turbine control valve tests and sis.
7/17/8?
0210 Control rod exercise, turbine control valve tests and sis cosplete, commenced power ascension.
0220 Commenced FCIOMR (Sequence "A").
0700 Reactor thermal power at 975, limited by high backpressure.
1500 Reactor thermal power at 95% due te high back-pressure.
8 Sinnificant Operational Event Unit 1 Date Time Event 7/18/82 0700 Reactor thermal power at 99%, high backpressure limited.
0920 Reduced thermal power to 65% due to loss of reactor zone ventilation (main steam tunnel temperature increase)(bad coil found on relay K-73 in panel 9-42).
0940 Reduced thermal power to 57% due to loss of reactor zone ventilation. (Main steam tunnel temperature increase).
1040 Commenced PCIOMR from 57% power (Sequence "A").
1500 Reactor thermal power at 995, maximum flow, rod
. limited.
1600 Reduced thermal power to 90% due to high back-pressure.
1800 Commenced PCIOMR from 905 thermal power (Sequence "A").
2330 Reactor thermal power at 955, holding due to high backpressure.
7/19/82 0145 Reduced thermal power to 86% due to high back-pressure.
0652 Commenced power ascension from 85% thermal power.
0730 Reactor thermal power at 955, holdig due to high backpressure.
7/20/82 1310 Commenced reducing thermal power due to high back-pressure.
1500 Reactor thermal power at 91% due to high back-pressure.
7/21/82 0700 Reactor thermal power at 925 due to high back-pressure.
1500 Reactor thermal power at 91% due to high back-pressure.
7/22/82 0130 Commenced reducing thermal power to backwash and precoat condensate demineralizers.
0400 Reactor thermal power at 82% for backwash and precoat of condensate demineralizers.
0500 Backwash and precoat of condensate demineralizers complete, commenced power ascension.
0800 Reactor thermal power at 94% due to high back-pressure.
1327 Commenced reducing thermal power to backwash and precoat condensate demineralizers.
1900 Reactor thermal power at 83% for backwash and precoat or condensate demiacralizers.
9 Significant Operational Event Unit 1 Date Time Event 7/23/82 0555 commenced power ascension from 83% thermal power.
1500 Reactor thermal power at 90%, high backpressure limited.
2300 Reactor thermal power at 89%, high backpressure limited.
7/24/82 1005 commenced power ascension from 89% thermal power.
1100 Reacter thermal power at 905, high backpressure limited.
1437 Reducing thermal power due to high temperatures in cooling towers.
1500 Reactor thermal power at 85% due to cooling tower high temperatures.
1600 Commenced power ascension from 85% thermal power.
2300 Reactor thermal power at 89%, high backpressure limited.
7/26/82 0400 Reactor thermal power at 90%, high backpressure limited.
7/27/82 0700 Reactor thermal power at 895, high backpressure limited.
1500 Reactor thermal power at 88%, high backpressure limited.
1640 Reduced thermal power to 86% due to high back-pressure.
(
7/28/82 0435 commenced power ascension from 86% thermal power.
0700 Reactor thermal power at 915, high backpressure limited.
0800 Reactor thermal power at 90%, high backpressure limited.
1000 Reactor thermal power at 895, Ligh backpressure limited.
1100 Reactor thermal power at 88%, high backpressure limited.
l 2005 Reduced thermal power to 82% due to high back-pressure.
7/29/82 0200 Reactor thermal power at 835, high backpressure l
limited.
0640 commenced power ascension from 835 thermal power.
0700 Commenced reducing thermal power from 94% for maintenance on "B" string high-pressure heaters.
0715 Reactor thermal power at 895 for maintenance on "B" string high-pressure heaters.
10 Significant Operational Event Unit 1 Date Time Event 0730 Commenced PCIOMR from 89% thermal power (Sequence "A").
1500 Reactor thermal power at 94%,
"B" string high-pressure heater maintenance limited.
1635 Reduced thermal power to 90% to remove "B" CCWP from service for cooling tower level control.
2050 Commenced reducing thermal power due to high back-pressure.
7/29/82 2300 Reactor thermal power at 85%, high backpressure limited.
7/30/82 2345 Commenced power ascenison from 85% thermal power.
7/31/82 0600 Reactor thermal power at 91%, high backpressure limited.
0720 Commenced reducing thermal power to remove "B"
string high-pressure heaters from service for maintenance.
1015 "B" string high-pressure heaters out of service for maintenance, reactor power at 85%.
1200 "B" string high-pressure heaters back in service, reactor power at 85%, holding to remove "A"
string high-pressure heaters from service for maintenance.
1445 "A" string high-pressure heaters out of service for maintenance, reactor power at 855.
1715 "A" string high-pressure heaters back in service.
1855 "B" string high-pressure heaters out of service for maintenance, reactor power at 85%.
7/30/82 2400 Reactor power at 86%.
7/31/82 1250 "B" string high-pressure heaters back in service, reactor power at 855 1400 Commenced PCIOMR from 85% thermal power (Sequence "A".
1500 Stopped PCIOMR at 88% thermal powwer due to "B" string feedwater heater problems.
2010 "B" string high-pressure heaters out of service for maintenance on channel relief valve.
2400 Reactor thermal power at 88% due to maintenance on "B" string high-pressure heaters channel relief valve.
11 Significant Ooerational Event Unit 2 Date Time Event 7/01/82 0001 Reactor thermal power at 74%, maximum flow, E00-4 coastdown.
7/19/82 0352 Reactor Scram No.135(1) from 67% thermal power on APRM high from a pressure transient caused by failure of the main steam pressure sensing line for the EHC system.
2148 Commenced rod withdrawal for startup.
7/20/82 0052 Reactor Critical No. 146.
0304 Rolled T/G.
0333 Synchronized generator, commenced power ascension.
1000 Reactor thermal power at 87%, EOC-4 coastdown (Xenon transient).
1315 Reactor Scram No.136(2) from 84% thermal power while performing SI 4.1. A.11 (Main Steam Isolation Valve Closure).
1815 Commenced rod withdrawal for startup.
2140 Reactor Critical No. 147 2220 Stopped rod withdrawal due to maintenance on "B" and "E" IRMs.
2300 Commenced rod withdrawal for startup.
7/21/82 0110 Rolled T/G.
0145 Synchronized generator, commenced power ascension.
0630 Reactor Scram No. 137(1) from 79% thermal power on condenser low vacuum.
1402 Commenced rod withdrawal for startup.
1630 Reactor Critical No. 148.
1740 Reactor Scram No. 138(2) from 4% while going into run mode, on condenser low vacuum.
2205 Commenced rod withdrawal for startup.
7/22/82 0015 Reactor Critical No. 149.
0300 Rolled T/G.
0316 Synchronizd generator, commen'ced power ascension.
0348 Reactor power at 19% due to isolation of third l
stage SJAE "B".
0410 Reactor thermal power at 23% going on bypass l
valves due to SJAE "B" problems.
0437 Generator offline, due to problems with SJAE "B",
i reactor power at 23%.
0525 Reducing thermal power by inserting control rods.
0603 Rolled T/G, reactor thermal power at 225.
0625 Synchronized generator, commenced power ascension from 22% thermal power.
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12 Significant Operational Event Unit 2 Date Time Event 7/22/82 1300 Reactor thermal power at 885, maximum flow, E0C-4 coastdown (Xenon transient).
7/25/82 0335 Commenced reducing thermal power from 69%, load not needed by system.
0500 Reactor thermal power at 65%, ho' ding, load not needed by system.
7/25/82 0635 Commenced powar ascension from 64% thermal powc'.
1200 Reactor thermal power at 69%, maximum flow, 'EOC-4 coastdown.
7/28/82 1125 Commenced reducing thermal pceer from 59% due to high backpressure.
1500 Reactor thermal power at 63% due to high back-pressure.
7/29/82 0632 Commenced power ascension from 63% thermal power.
0652 Reactor thermal power at 685, maximum flow, EOC-4 coastdown.
7/30/82 1336 Commenced reducing thermal power from 67% due to high backpressure.
1500 Reactor power at 61% due to high backpressure.
1700 Commenced reducing thermal power for shutdown for E00-4 refuel outage.
1944 Reactor manual Scram No. 139(1) from 28% thermal power on loss of feedwater signal which caused recirculation pump runback, power reduced to 28%
without proving RWM and RSCS; therefore a manual scram was initiated in order to control reactor.
The unit remains offline for E00-4 refuel outage.
7/31/82 1215 Reactor in cold shutdown.
2400 EOC-4 refuel outage.
13 I
Significant Ooerational Event Unit 3 Date Time Event 7/01/82 0001 "A" CCW pump back in service, commened power ascension from 885 thermal power.
0200 Reactor thermal power at 995, maximum flow, rod limited.
7/02/82 0600 Reactor thermal power at 995, maximum flow, "B"
recirculation pump vibration limited.
7/04/82 0555 Commenced reducing thermal power for control rod pattern adjustment.
0700 Reactor thermal power at 79% for control rod pattern adjustment.
0730 Control rod pattern adjustment complete, commenced PCIOMR (control cell core).
7/05/82 0500 Reactor thermal power at 995, maximum flow, rod limited.
7/08/82 0950 Reduced thermal power to 97% to decrease load line due to "B" recirculation pump vibration limits.
2300 Reactor thermal power at 985, maximum flow, "B"
recirculation pump vibration limited.
7/09/82 2325 Commenced reducing thermal power for turbine control valve tests and sis.
2335 Reactor thermal power at 90% for turbine control valve tests and sis.
7/10/82 0015 Turbine control valve tests and sis complete, l
commenced power ascension.
0035 Reactor thermal power at 995, maximum flow, "B"
recirculation pump vibration limited.
7/15/82 1145 Reduced thermal powr to 90% due to high back-pressure.
1230 Reduced thermal power to 86% due to high back-pressure.
l 1832 Commenced power ascension from 86% thermal power.
2300 Reactor thermal power at 995, maximum flow, rod j
limited.
l 7/16/82 0902 Commenced reducing thermal power due to high back-pressure.
0915 Reactor thermal power at 90% due to high back-pressure.
l
14 Significant Ooerational Event Unit 3 Date Time Event 7/16/82 0930 Increased thermal power to 955, holding due to high backpressure.
1650 Reduced thermal power to 92% due to high back-pressure.
7/18/82 1500 Increased thermal power to 935, high backpressure limited.
2300 I. creased thermal power to 945, high backpresaure limited.
7/19/82 0645 commenced power ascension from 94% thermal power.
0830 Commenced PCIOMR from 955 thermal power (control cell core).
1500 Reactor thermal power at 99%, maximum flow, "B"
recirculation pump vibration limited.
2300 Reactor thermal power at 98%, maximum flow, "B"
recirculation pump vibration limited.
7/22/82 1020 Commenced reducing thermal power due to high back-pressure.
1340 Reactor thermal power at 82% due to high back-pressure.
2300 Reactor thermal power at 83% due to high back-pressure.
7/23/82 0905 commenced power ascension from 83% thermal power.
1000 Reactor thermal power at 90%, holding due to high backpressure.
1945 Reducing thermal power due to problems with "B" recirculation pump.
2100 Reactor thermal power at 85%, problems with "B" recirculation pump.
7/24/82 0034 commenced power ascension from 85% thermal power.
0130 commenced pulling rods for control rod pattern adjustment from 87% thermal power.
0522 Reactor thermal power at 915, holding due to high backpressure.
1440 Commenced reducing thermal power due to high back-pressure.
1500 Reactor thermal power at 87% due to high back-pressure.
1635 commenced power ascension from 87% thermal power.
1700 Reactor thermal power at 915, holding due to high backpressure.
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~-
15 Significant Ooerational Event Unit 3 Date Time Event 7/25/82 0010 Commenced power ascension from 91% thermal power.
0100 Reactor thermal power at 96%, hodling due to high backpressure.
0338 Reduced thermal power to 92%, load not needed by system.
0635 Commenced power ascension from 92% thermal power.
0700 Reactor thermal power at 95% due to high back-pressure.
2300 Reactor thermal power at 945 due to high back-pressure.
7/26/82 1820 Commenced reducing thermal power due to high back-pressure.
1900 Reactor thermal power at 90% due to high back-pressure.
7/27/82 1647 Reduced thermal power to 86% due to cooling tower high temperatures.
7/28/82 0438 Commenced power ascension from 86% thermal power.
1000 Reactor thermal power at 93%, due to high back-pressure.
1140 Commenced reducing thermal power due to high back-pressure.
1500 Reactor thermal power at 89% due to high back-pressure.
7/29/82 0640 Commenced power ascension from 89% thermal power.
0700 Commenced PCIOMR from 92% thermal power (control cell core).
1728 Commenced reducing thermal power from 97% to remove "B" CCWP from service due to high level in cooling towers hot water channel.
2300 Reactor thermal power at 90% due to high level in hot water channel.
7/30/82 2000 3B CCWP back in service, reactor thermal power at 90%, holding due to high backpressure.
16 Sinnificant Ooerational Event Unit 3 Date Time Event 7/31/82 2000 Commenced reducing thermal power from 90% to remove unit from service due to failure of SI 4.7.C.1 (Secondary Containment Capabilities).
2132 Reactor Scram Manual No. 107(1) from 38% thermal power due to failure of SI 4.7.C.1.
2400 Unit offline to investigate problems with secondary containment.
(
(1) Equipment Malfunction (2)0perator Error I
1
.=.
17 4
AVERAGE DAILY UNIT POWER LEVEL 50 259 DOCKET NO.
Browns Ferry - 1 g.lT DATE 8-1-82 T. Thom COMPLETED BY 205/729/0834 TELEPilONE "Y
MONTil DAY AVER AGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL IMWe Net) 1MWe-Net) 1 826 949
,7 944 946
,3 1012 939 3
,9 1023 933 4
g 5
933 920 21 1029 871 6
7 1015 876 23 1016 881 8
3 901 9
979 25 909 865 10 3
i ii 1021 872 27 1023 61 12 28 1027 885 13 29 1024 885 34 30 943 867 15 3,
07I 4
16 i
INSTRUCTIONS On this fonnat.!ist the aser. ige.Jaih unit powei lesel in MWe. Net for e.ich da) in the repoinng snienth. Cinnpure to the nearest whole megawatt.
08/77)
18 l
- AVERAGE DAILY UNIT POWER LEVEL DOCKET NO, 50-260 g3,7 Browns Ferry - 2 8-1-82 DATE CONfPLETED BY T. Thom TELEP110NE 205/729/0834 310NTil 3"1Y DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (51We-Neu (StWe Net) 746 676
,7 3
737 691 g
731 86 3
,9 728 256 4
20 723 80 5
6 723 509 7
7_12 701
,3 8
730 669
,4 l
719 665 9
25 714 645 10 711 664 Il 707 632 12
,3 l
13 700 653
,9 706 g4 30 687
-20 15 y,
bO7 16 1
INSTRUCTIONS On this format.hst the aserage d.nh umt power lesel in \\lWe Net for each da) in the seportmg inonth. Coinpute to t he 11eafe51 whole !!1egawat t, 1
(9177) 4 m,-.
- +,.,
-.r--e.,~
e-c.
w,,
-we-.,... -,_. -. -,
e,.. -.... -,., - -.
-.v.----.-,..
. -. - - ~,, - + - - -. - - -,
rw.,.
-. - - - -e
19 AVERAGE DAILY UNIT POWER LEVEL 50-296 DOCKETNo.
Browns Ferry - 3 UNIT 8-1-82 DATE T. Thom COi!PLETED fly TELEPflONE 205/729/0834 MONTil July DAY AVER AGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe-Net I (MWe Net) 1020 931
,7 1018 960 18 1021 971 3
,9 913 1015 20 1009 1013 3
1030 909 6
1024 875 7
33 8
1011 911 34 9
1011 981 25 10 1021 26 918 Ii 1020 891
,7 1022 12 28 1027 935 13 1024 30 g,g 993 791 15 3,
16 976 INSTRUL710NS On this format.!ist the : verage daily unit power lesci in \\lWe Net los cach day in the sepoitine nionth. Geinpute to the nearest whole negr.vart.
pif77)
.=
20 T
OPERATING DATA REPORT 50-259 DOCKET NO.
DATE 8-1-82 CO.\\lPLETED BY T. Thom TELEPil0NE 205-729-0834 OPERATING STATUS i
- 1. Unit Name:
Browns Ferry - 1 Notes i
- 2. Reporting Period:
July 1982 3293
- 3. Licensed Thermal Power (5tht):
1152
- 4. Nameplate Rating (Gross 31We):
1065
- 5. Design Electrical Rating (Net SlWe):
1098.4
- 6. Staximum Dependable Capacity (Gross SlWe):
1065
- 7. Stasimum Dependable Capacity (Net 31We):
1
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report.Give Reasons:
NA i
- 9. Power Lesel To which Restricted. lf Any (Net 31We):
NA NA
- 10. Reasons For Restrictions,if Any:
i This 31onth Yr to.Date Cumulative 744 5,087 70,129
- 11. Ilours In Reporting Period
- 12. Number Of flours Reactor Was Critical 744 4799.87 44114.67
- 13. Reactor Resene Shutdown llours 0
238.73 5453.93
- 14. Ilours Generator On-Line 744 4754.4 43164.>/
- 15. Unit Resene Shutdown flours 0
0 0
i
- 16. Gross Thermal Energy Generated (SIWil) 2,177,750 14,634,194 121,509,101
- 17. Gross Electrical Energy Generated (AlWil) 720,160 4,773,370 40,065,820
- 18. Net Electrical Energy Generated (SlWil) 697.038 4,635,354 38,904,263
- 19. Unit Service Factor 100 93.5 61.6
- 20. Unit Availability Factor 100 93.5 61.6
- 21. Unit Capacity Factor (Using.\\tDC Net) 88.0 85.6 52.1
- 22. Unit Capacity Factor (Using DER Net) 88.0 85.6 52.1
- 23. Unit Forced Outage Rate 0
6.5 25.3
- 24. Shutdowns Scheduled Oser Next 6 Slonths IType.Date.and Duration of Each t:
t s
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
- 26. Units in Test Status t Prior io Commercial Operationi:
Forecast Achiesed INITI A L CRITICA LI TY INITI \\ L 1:LECTRICITY CO\\l\\ll:RCI \\L OPER \\ TION Pl/77)
- ~ -. -, - _ _ _ _ _ _
21 OPERATING DATA REPORT DOCKET NO. 50-260 DATE 8-1-82 CO.\\lPLETED BY T om TELEPflONE 834 OPERATING STATUS Bmes Feny - 2
.No tes
- 1. Unit Name:
- 2. Reporting Period:
July 1982 3293
- 3. Licensed Thermal Power (Stht):
1152
- 4. Nameplate Rating (Gross.\\lWe):
1065
- 5. Design Electrical Rating (Net 51We):
1098.4
- 6. Staximum Dependable Capacity (Gross 31Wel:
1065
- 7. 3!aximum Dependable Capacity (Net SIWE):
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7iSince Last Report.Give Reasons:
NA NA
- 9. Power Level To which Restricted,If Any (Net.\\lWe):
NA
- 10. Reasons For Restrictions.If Any:
This alonth Yr..to Date Cumulative 744 5,087 65,070
- 11. Ilours in Reporting Period
- 12. Number Of Ilours Reactor Was Critical 669.73 4,846.51 43,293.47
- 13. Reactor Reserse Shutdownllours 45.34 203.06 13,684.82
- 14. Ilours Generator On Line 656.98 4,778.36 41,975.45
- 15. Unit Reserve Shutdown flours 0
0 0
- 16. Cross Thermal Energy Generated (51Wil) 1,517,431 13,827.550 120,480,340
- 17. Gross Electrical Energy Generated t.\\lWil) 475,700 4,592,260 40,024,908
- 18. Net Electrical Energy Generated (atWII) 453,425 4,450,929 38,873,075
- 19. Unit Senice Factor 88.3 93.9 64.5 88.3 93.9 64.5
- 20. Unit Asailability Factor
- 21. Unit Capacity Factor (Using AIDC Net) 57.2 82.2 56.1 57.2 82.2 56,1
- 22. Unit Capacity Factor iUsing DER Net) 8.2 5.5 27.1
- 23. Unit Forced Outage Rate
- 24. Shutdowns Scheduled Oser Next 6 Slonths (Type. Date,and Duration of Each):
Unit 2 Refuel Outage EOC-4 began July 30, 1982
.s
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
- 26. Units in rest Status (Prior to Commercial Operations:
Forecast Achiesed INITIT L CitlT ICA LITY INITI AI. ELECT RICITY CO\\l\\lERCIAL OPER ATION (9/77)
22 l
OPERATING DATA REPORT DOCKET NO. 50-296
.t DATE 8-1-82 COSIPLETED BY T. Thom TELEPil0NE 205/729/0834 OPERATING STATUS
~
- 1. Unit Name:
- 2. Rcporting Period:
July 1982 3293
- 3. Licensed Thermal Power (Stht):
1152
- 4. Nameplate Rating (Gross 31We):
1065
- 5. Design Electrical Rating (Net 31We):
- 6. Stasimum Dependable Capacity (Gross SlWe): 1098.4
- 7. Stasimum Dependable Capacity (Net alwe):
1065
- 8. If Changes Occur in Capacity Ratings titems Number 3 Through 7) Since Last Report.Give Reasons:
NA NA
- 9. Power Level To Which Restricted. If Any (Net alWe):
NA
- 10. Reasons For Restrictions,if Any:
This alonth Yr..to-Date Cumulatise 744 5,087 47,495
- 11. Ilours in Reporting Period 741.53 1,786.25 34,253.23
- 12. Number Of Ilours Reactor Was Critical
- 13. Reactor Reserve Shutdown flours 2.47 916.67 3,058.20
- 14. Ilours Generator On-Line 741.53 1.704.26 33,455.04 0
0 0
- 15. Unit Reserse Shutdown flours
- 16. Gross Thermal Energy Generated (Slwil) 2,311,452 5,059,306 98,917,926
- 17. Gross Electrical Energy Generated (.\\lWill 745,650 1,612,050 32,610,240 721,5ITf-~ ~
1,552,917 31,640,963
- 18. Net Electrical Energy Generated I.\\lWil) 99.7 33.5 70.4
- 19. Unit Service Factor 99.7 33.5 70.4
- 20. Unit Asailability Factor
- 21. Unit Capacity Factor (Using.\\lDC Net) 91.1 28.7 62.6 91.1 28.7 62.6
- 22. Unit Capacity Factor (Using DER Net)
- 23. Unit Forced Outage Rate 0.3 35.7 11.1
- 24. Shutdowns Scheduled Oser Nest 6 Months (Type. Date.and Duration of Each t:
s
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
- 26. Units in rest Status tPrior to Commercial Operations:
Forecast Achiesed INITI \\ L CRITICALITY INi rt \\ L ELEC TRICITY CO\\l\\lERCI A L OITR A TION
('8/77 )
W i
4 50-259 i
DOCKETNO.
UNITSilOTDOWNS AND POWER REDUCTIONS
- ~
UNil NAME Browns Ferry - 1 DATE 8-1-82 COMPLETED BY T. Thom REPORT MONTII
. July TELEP!!ONE 205/729/0834 c:
5 ?
3 4Y]
Licensee
[-t,
$#t Cause & Corrective No.
Date g
3g d
,5 y $
Event
?'y
$3 Action to E
5 I g =!!
Report =
nu E'
Present Recurrence A
u 6
228 7/05/82 S
11 Derated for control' rod pattern adjustment 229 7/09/82 F
B Derated to remove bus duct cooling fan for maintenance g
230 7/15/82 S
11 Derated for control rod pattern adjustment 1
231 7/18/82 F
II Derated due to loss of reactor zone ventilation 4
I 2
3 4
F: Forced Reason:
Method:
Exhibit G. Instructions S: Scheduled A Equipment Failure (Explain) 1-Manual for Preparation of Data 1
- 11. Maintenance of Test 2-Manual Scra m.
Entr.s Sheets for I.icensee C. Refueling 3-Automatic Scram.
Event Report (1.1:R t File (NURI G-D-Regulatory Restriction 4-Ot her ( Explain) 0161)
E-Operator Training & License Examination F Administrative 5
G-Operational Eiror (Explain)
Exhibit 1 - Same Source (9/77)
Il-Ot her (E xplain)
50-260 DOCKET NO.
UNIT SilUTDOWNS AND POWER REDUCTIONS UNIT NA%!E Browns Ferry -2 DATE 8-1-82 COMPLETED BY T. Thom REPORT MONTil July TELEPilONE 205 / 7? o /O R'M n.
5g 3
y)
I.icensee
[= -r, b
Cause & Corrective No.
Date i
3g 4
js5 Esent gg
!L?
Action to j=
5 5 gjE, =
Repori e mu 5'
Present Recurrence H
e f
G 6
238 7/19/82 F
23.68 A
3 Reactor scram due to failure of the main steam pressure sensing line for the E!!C system 239 7/20/82-F 12.50 11 3
Reactor scram while performing SI 4.l.A.11 (MSIV Isolation Valve Closure) y w
240 7/21/82 F
11.17 11 3
Reactor scram on condenser low vacuum (no generator synch) 241 7/21/82 F
9.60 11 3
Reactor scram on condenser low vacuum 242 7/22/82 F
1.80 H
Turbine tripped due to isolation of 3rd stage SJAE "B" (no reactor scram)
(generator offline) 243 7/30/82 S
28.27 11 2
Reactor scram to accommodate EOC-4 refuel outage 1
2 3
4 F: Forced Reason :
Method:
Exlubit G - Instructio.is S: Scheduled A-Filuipment Failure (Explain)
- Manual for Prep.uation of Data B. Maintenance of Test 2-Manual Scram.
Ent:) Sheets for I.icensee C-Refueling 3 Autom.itic Ss ram.
Esent Report (l.I:R)I de (Nt1RI G.
D Regulatory Restriction 4-Other ( E xplain) 0161)
I'.-Operator Training 1 Licensa Examination F-Administ rative 5
G-Operational 1: rus (Explain)
Eshibit ! - Same Source 19/77)
Il-Other ( E xplain)
w 4
a..A,,
m.
a am.-.+'
s
.+w.
4a 4
m.
e.
a b
4.-
4 m_,,
_AA_,,
'i y,
50-296 J
UNITSilUTDOWNS AND POWER REDUCTIONS DOCKET NO.
_.3 UNIT NAME Browns Ferry DATE 8-1-82
+
REPORT MONT!!
July COMPLETED BY.
T-Thn TELLrlf0NE 205/729/0,8.3L c
.5 g 3
4Y2 Licensee
,E n, h
Cause & Corrective No.
Date i
5=
5 5sE Event g?
s1 Action in jE 55g Report 2 mV E'
Present Recurrence H
O C
.i 101 7/04/82 S
11 Derated for control rod pattern adjustment 102 7/31/82 F
2.47
'll 2
Reactor scram due to failure of SI 4.7.C.1 (Secondary Containment j
Capabilities) y i
l
?
b 4
l I
2 3
4 F: Forced Reason:
Method:
Exhibit G -Instructions 5: Sdieduled A Equipment Failure (Explain)
! Manual for Preparation of Data ll Maintenance of Test 2 Manual Scram.
1:ntry Sheets for 1.ieensee C Refueling 3 Autonutie Scran.
Event Report (LER) Fde (NURI:G-D Regularory Restriction 4-Other ( Explain) 01611 E-Operator Training & License Examination F Administrative 5
G Operational Eiror (Explain)
Exhibit I - Same Source (9/77)
II Other (Explain) d
INSTRUMENT l'AINTESMiCE SU}MA.*G CSSC EQUIND'T FOR nlE MO:iTil OF July 19 82 NAI'.,'FI EFFECT 0:; SAFE CAUSE ACTION TAKEi WDE SYSTD!
CO!!?CNE.7 OF OPERATION OF OF RESULTS OF TO PFICLUDE MAIhTENANCE E!E REACTOR MALFUNCTION MALFUNCTION RECURRENCE U-l 7-6 74 FR-74-64 Repair None Faulty slide wire Erratic indication None contact 7-14 65 FIS-65-70B Repair None Faulty photocell Improper switch None
?
opera tion 7-20 73 VR-73-50 Repair None Fault'y' Switch Loss of channel None U-2 7-12 90 RM 249 Repair None Faulty flow contfo] Improper sample flow None motor control 7-19 46 LC-46-9A Repair None Failed capicators Erratic control None N
es 7-20 64 TIS-64-55 Replace None Instrument drift Incorrect indication None
" ~
U-3 7-4 90 RM-90-142B Repair None Fail,ed relay Invalid alarm
- None 7-15 77 ET-77-16 Replace None Instrument drift Incorrect output None t
e 0
e o
e d
y cw
BROWNS FERRY fiUCLEAR PLANT UNIT 1 & Common CSSC EQUIPMENT ELECTRICAL MAINTENANCE
SUMMARY
For the Month of July 19 82 Effect on Safe Action Taken Nature of Operation of Cause of Results of To Preclude i
Component Maintenance The Reactor Malfunction Malfunction Recurrence Date 4, System 6/23/82 Air Condi-Shutdoan board - Exhaust fan None Bad fan motor IA exhaust fan The fan motor was tioning room exhaust feeder breaker inoperable repaired at PSS (Cooling-fan 1A breaker was and re-installed l Ileating) tripping per EMI 33.
The fan operated 3
properly.
TR #342871 I
7/1/82 Fire Pro-Fire protec-Recejved a None The trouble alarr All smoke detectors Patrolling fire tection tion panel trouble alarm resulted from a associated with panel watch was estab-l 1-25-325 for panel power failure to 1-25-325 was inoper-lished. The 'EE' 1-25-325 the smoke detec-able circuit board tors connected assembly was tj to the panel.
replaced and The circuit tested per SI breaker which 4.11.3 & 4, then feeds power to returned to j
the smoke detec-
- service, tors is soldered TR #310500 to the 'EE' cir-LER-BFRO cuit board in thc 259/8245 control panel.
These soldered connections fail-ed as a result of mechanical stress normally associa-ted with reset-ting the breaker.
7 i
BROWNS FERRY NUCLEAR PLAMT UNIT 1 & Common l
CSSC EQUIPMENT ELECTRICAL MAINTENANCE
SUMMARY
For the Month of July 19 82 Effect on Safe Action Taken Nature of Operation of Cause of Results of To Preclude Date System Component Maintenance The Reactor Malfunction Malfunction Recurrence 7/3/82 Fire Pro-Fire protec-Received a None Bad " zone" cir-Required fire zone Fire watch was tection tion panel trouble alarm cuitry card circuits to be taken established, 1-25-311 for panel out of service in circuit card l
1-25-311 order to replace the replaced, SI bad card 4.ll.C. 3 & 4 i
successfully per i formed and the zones returned to service. On 7/5/82 a trouble alarm for panel i
1-25-311 re-occurred. Them main circuitry a
card for the l
panel was replac-ed, SI 4.ll.C.3 &
4 successfully performed and panel returned i
to service.
TR #310419 TR #342896 LER-BFRO 2 259/8246 e
e 4
BR0kmS FERRY NUCLEAR PLANT UNIT 1 & Common CSSC EQUIPMENT ELECTRYCAL MAINTENANCE
SUMMARY
For the Month of July 19 82 Effect on Safe Action Taken Nature of Operation of Cause of Results of To Preclude Date System Component Maintenance The Reactor Malfunction Malfunction Recurrence 7/13/82 Air Con-1A control bay Chiller temp-None Bad proportional Temperature control-Replaced the pro I ditioning chiller erature con-controller ler inoperable portionalcontrol-f (Cooling-troller failed module ler module and l
lleating) to operate performed EMI 60. -
properly The chiller opera-ted properly, i
TR #282468 I
7/14/82 EECW PS-67-55 Breaker #305 None Ground wire at EECW south header Cleared ground, circuitry in panel 9-9 cable strap and indications replaced relays 1 & C tripped screw in PS inoperable AB3X and AD3X in when D-1 RilRSW 55
' panel 9-36 which pump was run were damaged as y a result of grounded circuit.
7/18/82 Contain-Relay 16A-K37 Partial pri-11,0 Analyzer The coil for Partial primary con-The bad relay 2
ment
. mary contain-
"X and "B" relay 16A-K37 tainment isolation.
coil was replaced Inerting ment isola-inoperable burned out The isolation result-
'and the 110 22 tion causing the ed in the closure of analyzers and relay to fail the isolation valves other systems for "A" and "B" 11 0 affected by the 22 Analyzers, thereby partial primary preventing sampling containment iso-of the Torus and lation were drywell atmospheric returned to conditions normal.
TR #273285 LER-BFRO-50 259/8248
BROWNS FERRY EUCLEAR PLANT UNIT 1 & Common ELECTRICAL MATWTENANCE SDD!ARY CSSC EQUIPMENT For the Month of July 19 82 Action Taken Effect on Safe Nature of Operation of Cause of Results of To Preclude 3 ate Svstem Component Maintenance The Reactor Malfunction Malfunction Recurrence 7/27/8:
4KV Shut-Degraded During the None, setpoint Increased temp-All 4 relays' trip The relays were down voltage performance drifts were in erature in the setpoints were recalibrated to l and Buses control cal-the conserva-boardrooms is I
found to operate at the correct set-;
Boards relays of recurrence tive (higher suspected 3941.7 as opposed point. The set-+
ibration voltage) range to the required point drift i
(BFRO-50-296/
3900 to 3940 volt problem is now 8213) of de-
- range, being evaluated graded volt-by TVA Engineer-age relays ing Design.
(SI 4.9.A.4.C; TR #342718 1 degraded LER-BFRO '
voltage on 259/8250 4KV shtd. bd.
A, 1 on 4KV shtd. bd. B, and 2 on 4KV shtd. bd. C were found I
to operate slightly abovc the required 3900 to 3940 volt range.
9
BROWNS FERRY NUCLEAR PLANT UNIT 2
CSSC EQUlPMENT ELECTRICAL MAINTENANCE sum 1ARY For the Month of July 19 82 t
l Effect on Safe Action Taken Nature of Operation of Cause of Results of To Preclude Date Systen Component Maintenance The Reactor Malfunction Malfunction Recurrence J
7/1/82 Radiation RA 90-272 "Drywell Radi-None Wire 2M610 in Received a false Used spare cable Monitoring circuitry ation High" cable 2A2369 "Drywell Radiation to replace cabic (RA 90-272) shorted to High" annunciation 2A2369. Returned I annunciation shield RA 90-272 to came in and service.
would not TR #170902 clear TR #252221 i.
7/20/82 Contain-FSV-2-76-65 During the H m nit r "B" Bad solenoid H, monitor "B" was The solenoid 2
ment performance was made incap-valve (FSV-2 i6-ride incapable of assy was replaced, Inerting of SI 4.7.D.1.
able of monitor-65) monitoring the torus The valve failed B.1-(A) H, ing the torus again during the monitor "B" performance of (FSV-2-76-65)
SI 4.7.D.l.B.1-(A) failed The solenoid valve will be u
~
repaired during the refueling outage.
TR #282482 LER-BFRO 260/8221
BROWNS FERRY NUCLEAR PLANT UNIT 3 CSSC EQUIPMENT-ELECTRICAL MAINTENA' ICE SLW1ARY For the Month of July 19 82 Effect on Safe Actic. Taken Nature of Operation of Cause of Results of To Preclude Date Systen Component Maintenance The Reactor Malfunction Malfunction Recurrence l
7/1/82 Diesel 3D diesel gen-Low water an-None LWD relay con-Low water annuncia-Replaced the bad Generators erator relay nunication tacts (bad) tion would not clear relay per EMI 23.
LWD would not stuck SI 4.9.A.1.d was U clear during successfully annual inspec-completed.
1.d)
TR #200626 3
7/15/82 RHRSW "Dl" RHRSW Bad relay None Relay was dam-Bad relay Replaced relay per:
pump " running" aged due to EMI 23, ran pump, l auxiliary ground.
(See relay operated relay (ADIX) 7-14-82 on U-1, properly.
g TR #310482)
TR #282472 7/16/82 4KV Shut-Degraded While perform-None, loss of The degraded volt-Three degraded volt-The timers were down voltage relay ing SI 4.9.A 4, voltage relays age timer set-age relay timers adjusted to bring j,
Boards timers C 2 degraded were operable points were chang-were found slightly within tolerance.
and Buses voltage relay ed slightly in a out of new setpoint and returned to timers, 1 each 3/29/82 unit 3 range
- service, on 4KV shtd.
Tech. Spec. re-TR #196525 bd. 3EC and vision. S1 4.9.A.
LER-BFRO 3ED, were 4.C was revised 296/8231 found set at to incorporate 0.26 second as these minor set-opposed to 0.2:
point changes and to 0.33 second, performed to as-One timer on sure timer set-4KV shtd. bd.
tings were in con-3EC was found formance with new set at 7.63
- settings, seconds as opposed to 6.21 i
to 7.59 seconds l
BROT;S FERRY TEUCLEAR PLANT UN8T 3
CSSC EQUIP!!ENT ELECTRICAL MAINTENANCE
SUMMARY
For the !!onth of July 19 82 Effect on Safe Action Taken Nature of Operation of Cause of Results of To Preclude Date Systen Component Maintenance The Reactor Malfunction
!!al f unc t ion Recurrence 7/19/82 liigh-Pres- "A" Fire pump Bad "2T" relay None Relay coil "A" fire pump Replaced the bad sure Fire strainer coil burned strainer inoperable relay per D!I 23 Protec-circuitry and timed per I
tion Dil 15.
TR #273291 t
7/22/82 4KV Shut-Degraded volt-During the per-- None, setpoint Increased temp-These relays' trip The relays were down age relays formance of re-- drif ts were in erature in the setpoints were found recalibrated to Boards and currence con-the conserva-bot trooms is to range from 3940.3 the correct set-Buses trol calibra-tive (higher suspected to 3944.15 volts as point. The set-tion (BFRO voltage) range opposed to the re-point drift prob-296/8213) of quired 3900 to 3940 1em is now being degraded volt-volt range.
evaluated by TVA age relays Engineering g
(SI 4.9.A.4.C)
Design.
l 2 degraded TR #225034 voltage relays LER-BFRO on 4KV shut-296/8232 down bd. 3EB and 1 on 4KV shutdown 3ED were founct to operate slight-ly above the required 3900 to 3940 volt range.
t a
~
BROWNS FERRY NUCLEAR FIANT UNIT comfoN CSSC FOUIPMEitT -
MECHANICAL MAINTENANCE
SUMMARY
For the Month of July 19 82
~
i
)
EFFECT ON SAFE ACTION TAKEN:
l DATE SYSTEM COMPONENT NATURE OF OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE MAINTENANCE THE REACTOR MALFUNCTION MALFUNCTION RECURRENCE 7-13 D/G C Engine U-l&2 change oil in None Unknown None Changed oil in governor governor TRf 337840 i
7-20 D/G D Engine U-162 oil needed None oil needed None Changed oil
^
changing changing TR# 337841 I 7-20 D/G Diesel Fire radiator cap None diesel fire pump cap was beyond repair Replaced radiator cap Pump blew & needs hot & blew TR# 207167 replacing cap 8
o O
3 i.
I 2
C
~
BROWNS FERRY NUCLEAR PIldiT UNIT 1
CSSC EQUIPMENT MEQIANICAL MAINTENANCE
SUMMARY
For the Month of July 19 82 EFFECT ON SAFE ACTION TAKEN DATE SYSTEM COMPONENT NATURE OF OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE MAINTENANCE THE REACTOR MALFUNCTION MALFUNCTION RECURRENCE 7-2 HPCI IIPCI turbine water in oil.
None Unknown water in oil.
Pumped old oil out, clear d sump 6 added new oil.
I TP.# 311939 7-6 HPCI pipe hanger on faulty hanger None Unknown loose pipe Tightened pipe hanger fire protection on line on line line TR# 310432 7-19 HPCI HPCI turbine drain water from bottom of hyd. oil tank 7-14 RHR check valves faulty valves None worn gaskets &
valve not operating Cleaned piston &
dirty piston properly installed new gasket TR# 315960 w
V 7-23 RHRSW pump B-1 leak None faulty valve vacuum breaker Replaced air release leaking thru valve 4" & 1" TR# 316090 7-3 LPCI MG LPCI MG Set high vibration None bad bearings flywheel bearings Changed bearings lEN noisey & vibrating TP# 311938 7-7 RCIC LCV-71-5 leak None worn packing steam leak Replaced valve TR# 338917 7-8 Control 1B control bay faulty chiller None rnetal around chiller would not Replaced filter, o' ring Air chiller flange bolt holes function properly
& psi gauge breaking away TR# 316060
~
C
2
- o BROWNS FERRX NUCLEAR PIANT UNIT CSSC EQUIPMENT MECHANICAL NAINTENANCE SU1 NARY For the Month of July 19 82 DATE SYSTEM COMPONENT NATURE OF OPERATION OF
'l ACTION TAKEN EFFECT ON SAFE CAUSE OF RESULTS OF TC PRECLUDE MAINTENANCE 1RE REACTOR MALFUNCTICN MALFUNCTION RECURRENCE 7-8 IIPCI IIPCI turbine moisture anal-None None oil sample taken Took oil sample &
l ysis reinstalled drain lug TR# 216478 7-6 Fuel Pool pumps A & B lubricate None None bearings needed Lubricated bearings on Cooling bearings lubrication A 6 B pumps C-P TR# 170912 4
i g
+
l
J
~
BROWUS FERRY NUCLEAR FIANT UNIT MECIIANICAL MAINTE%iNCE
SUMMARY
l CSSC EQUIPMENT For the Month of July 19 82 EFFECT ON SAFE ACTION TAKEN DATE SYSTEM COMPONENT NATURE OF OPERATION OF CAUSE OF RESULTS OF IU PRECLUDE j
MAINTENANCE Tile REACTOR MALFUNCTION MALFUNCTION RECURRENCE 7-8 IIPCI IIPCI turbine moisture analy-None None check for water in Took sample of lube sis oil oil & replaced plug TR# 216477 I
j.
I 7-6 D/G B engine stand-oil needed None None changed oil &
Changed oil in governor by changing refilled with MO-3 TR# 337837 7-8 D/G
- 1 air compres-blown head None Unknown blown head gasket Replaced head gasket TR# 273349 sor gasket 7-8 D/G
- 2 air compres-. blown head None Unknown blown head gasket Replaced h.ead gasket TR# 315950 sor on 3EA D/G gasket e
9 C
9
38 FIELD SERVICES
SUMMARY
July 1982 WORK SYNOPSIS Work completed during this monthly period: completed EPA modifications, prefabrication of the "N" and "M" MSRV tailpipes, and preparing the fabrication shop with a stainless steel work area for the unit 2 cycle 4 refueling outage. Work that is continuing: prefabrication work on the scram discharge header modification (P0392); rebuild of Atwood Morrel 26-inch valve manifold and air operator; set up of Field Services welding facility; provide temporary operations training facility in the hypochlorite building; security diesel generator building (P0286); update of the CCTV system (P0287); post accident sampling facility (P0314);
installation of temporary power feeders for power pack supplies for Field Services outage work; LPCI MG set (L1845); automatic backwash modification (L2052); and emergency lighting installation (P0479). The unit 2 cycle 4 refueling and major modification outage started at 1944 hours0.0225 days <br />0.54 hours <br />0.00321 weeks <br />7.39692e-4 months <br /> on July 30, 1982.
REFUEL AREA Quadrex completed decontamination of the old spent fuel racks.
The repair of the hydrolazer machine was completed.
The reactor building overhead crane 125-ton wire rope was replaced and tested satisfactorily.
TURBINE The IQT contract for sandblasting was let to Newsom and Work Meta 111 zing Company.
The materials were ordered the reactor feed pump rotating elements were received this month. Preparations for turbine disassembly have been completed.
~
39 FIFI.n SERVICES
SUMMARY
July 1982 ELECTRICAL The major work during the past month has been: (1) LPCI modifications (L1845) - installation of conduit and hangers on elevation 621 and 639 is continuing. (2) L2052 automatic backwash system for RCW strainers unit 1, 2, and 3 - installing brackets, conduit, and junction boxes.
Completion:
unit 1 - 525, unit 2 - 54%, and unit 3 - 26%. This modification has suffered gaps in work continuity due to manpower availability. (3) Update CCTV System (P0287) - continued power and control wiring at various cameras and wiring at CAS. (4) Illuminate exterior of the protected area (P0286) - installation of the diesel generator control wiring, doors, and locks is continuing. (5) Install emergency lighting (PO479) - mounting lighting brackets in all three units was completed and review of these work plans is in progress. Work plan 8539 for the electrical connections is in the approval cycle.
(6) Other electrical work: torus feeder preparations, support work, electrical inspections of cords, tools, and lights and telephone maintenance.
MECHANICAL During the month of July, the Field Services Group Mechanical Section devoted most of its time to preparing for the unit 2 cycle 4 refueling outage. This work primarily consisted of prefabrication work for modifications such as the scram discharge header, tailpipe installations, and various TRs which support the unit 2 cycle 4 outage.
The major work activities in progress are:
(1) replace automatic deluge valves to the
40 FIELD SERVICES
SUMMARY
July 1982 MECHANICAL (Continued) unit 1 HPCI fire protection (P0520), (2) prefabrication of CRD scram discharge header materials (P0392).
Other mechanical work includes:
fabrication of segregated stainless steel work area, fabrication of weld stations, and hanger inspections (IEB 79-14 and 79-02).
MODIFICATIONS Review of unit 2 cycle 4 modification work and processing work plans.
PLANNING AND SCHEDULING The unit 3 cycle 4 outage report is being written and assimilated.
Development of the computerized project management program and the overall modification and maintenance planning effort has suffered from lack of a firm modification listing and frequent changes to the outage work scope.
Changes to the outage work scope at this late date will have a significant impact on the quality of the planning effort.
TORUS During the first week of July all torus tie-down work was completed with the exception of weldout of HKIIs which.will be accomplished during the outage.
Temporary ECCS Supports: Work continued with the installation of the temporary ECCS supports followed by permanent ECCS header support. By the end of the month the status was as follows:
- 2 - 15%, 3 - 10%, 6 - 20%,
7 - 05, 8 - 90%, 10 - 05, 11 - 105, 12 - 955, 14 - 105, 15 - 05, and 1, 4, 5, 9, 13 and 16 are 100% complete.
External Ring Reinforcing: # 1, 2, 3, 4, 5, 8, 9, 12, 13 and 16 are complete with partial weldouts until shutdown.
41 FIm n SERVICES
SUMMARY
July 1982 TORUS (Continued)
Torus Snubbers: Installation of brackets for torus snubbers started the first week of July. Anchor bolt drilling for wall brackets was completed at RG #1 and 13 and RG #4 and 5 are 50 percent completed.
RG lugs and gussets were installed on external RG reinforcing #1 - 905, 2 - 20%, 3 -
20%, 4 - 85%, 5 - 85%, 8 - 905, 9 - 855, 12 - 80%, 13 - 80%, and 16 - 25%
complete.
Preparatory work for the scheduled shutdown on July 30, 1982 contiued throughout the month of s'uly.
SPECIAL PROJECTS (1) Dewatering pump modification (P0252) - the vendor was onsite last week a
and the diesel pump was satisfactorily functionally tested. (2) Hypo-chlorite building - The construction work on the operations classroom I
facilities is essentially completed with the exception of some interior f
finish work.
ADMINISTRATIVE As of June 6,1982, fiscal year-to-date. straight-time hours worked were 1,443,938 and overtime hours worked were 360,868.5. The overtime percentage is 20 percent.
The overtime percentage for month of June was 3 percent 1
based on 91,119 straight time hours and 3,215.5 overtime hours. The overtime percentage for July is approximately 9 percent.
The O&M budget through June 30 was $23,657,564 and expenditures were
$21,755,657. The capital budget through June 30 was $25,471,420 and expenditures were $24,556,590. Overall budget was $49,074,984 and expenditures were $46, 312,247.
Overall actual expenditures on the budget were $2,762,737 less than the YTD estimate.
1, 42 FIELD SERVICES
SUMMARY
July 1982 ADMINI**'ATIVE (Continued)
On July 12, 1982 staffing for the unit 2 cycle 4 refueling / torus outage began. During the period from July 12 through July 31, 144 additional employees were hired.
Two payroll clerks were reassigned to better utilize personnel.
l Plans were implemented to conduct initial employee training outside the security area to reduce escort requirements, i
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