ML20071C727
| ML20071C727 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 01/01/1983 |
| From: | Thom T TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20071C724 | List: |
| References | |
| NUDOCS 8303080021 | |
| Download: ML20071C727 (40) | |
Text
_ - - _
a TENNESSEE VALLEY AUTHORITY DIVISION OF NUCLEAR POWER BROWNS FERRY NUCLEAR PLANT MONTHLY OPERATING REPORT December 1, 1982 - December 31, 1982 DOCKET NUMBERS 50-259, 50-260, AND 50-296 LICENSE NUMBERS DPR-33, DPR-52, AND DPR-68 g
n>A Submitted by:
K-W Plant Superintendent S
8303080021 830111 DR ADOCK 05000
\\
TABLE OF CONTENTS Operations Summary......................
1 Refueling Information....................
3 Significant Operational Instructions.............
5 Averge Daily Unit Power Level................
13 Operating Data Reports....................
16 Unit Shutdowns and Power Reductions.............
19 Plant Maintenance......................
22 Field Services Summary..........
33 P
.+
l l
.J
1 0
Ooerations Summarv November 1982 The following summary describes the significant operation activities during the reporting period.
In support of this summary, a chronological log of significant events is included in this report.
There were 17 reportable occurrences and one revision to previous reportable occurrences reported to the NRC during the month of December.
Unit 1 There were two scrans on the unit during the month.
On December 6, the reactor was manually scrammed to repair a crack on a reactor feed pump's discharge line.
The reactor scrammed on December 6 when a control rod double-notched during startup and caused two IRMs to reach their trip setpoints.
Unit 2 l
The unit was in its EOC-4 refueling outage the entire month.
Unit 't There was no scrans on the unit during the month.
1 Principally prepared by B. R. McPherson.
6
2 I
Doerations Summary (Continued)
December 1982 Fatinue Ussne Evaluation The cumulative usage factors for the reactor vesse7 are as follows:
Location Usan* Factor Unit 1 Unit 2 Unit 3 Shell at water line 0.00564 0.00448 0.00388 Feedwater nozzle 0.27594 0.19544 0.14705 Closure studs 0.21688 0.15641 0.12638 NOTE:
This accumulated monthly information satisfies Technical Specification Section 6.6.A.17.B(3) reporting requirements.
Common System Approximately 9 09E+0.5 gallons of waste liquids were discharged containing approximately 1.55E+00 curies of activities.
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1
3 Doerations Summarv (Continued)
December 1982 Refueling Information Unit 1 Unit 1 is scheduled for its fifth refueling beginning on or about i
March 18, 1983 with a scheduled restart date of July 18, 1983 This refueling will involve loading 8 I 8 R (retrofit) fuel assemblies into the l
core; finishing the torus modification; turbine inspection; finishing THI-2 modifications; post-accident sampling facility tie-ins; core spray changeout; and changeout of jet pump hold-down beams.
There are 764 fuel assemblies in the reactor vessel. The spent fuel 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 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 began its fourth refueling on July 30, 1982 with a scheduled restart date of February 14, 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 R fuel assemblies into the core; THI-2 modifications; post-accident sampling facility tie-ins; and changeout of jet pump hold-down beams.
4
- a
l 4
Doerations Summary (Continued)
December 1982 Refueling Information En11_2 (Continued)
There are no fuel assemblies in the reactor vessel. At the and of the month there were 248 new fuel assemblies; 764 EOC-4 fuel assemblies; 353 BOC-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 97 locations.
Unit 9 Unit 3 is scheduled for its fif th refueling on or about October 1, 4
j 1983, with a scheduled restart date of January 31, 1984. This refueling will involve loading 8 I 8 R (retrofit) assemblies 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 E00-3 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.
5 Sinnificant Operational Event Unit 1 Date Time Event 12/01/82 0001 Reactor thermal power at 995, maximum now, rod limited.
12/03/82 0325 Commenced reducing thermal power for turbine control valve test and SI's.
0330 Reactor thermal power at 955 for turbine control valve test and SI's.
0340 Turbine control valve test and SI's complete; commenced powcr ascension.
0400 Reactor thermal power at 995, maximum flow, rod limited.
12/04/82 1645 Commenced reducing thermal power for shutdown due to a leak on discharge of "B" reactor feed-water pump.
1718 Reactor scram manual No.162 from 425 thermal power to repair leak on discharge line of "B" reactor feedwater pump.
12/ 06/ 82 1915 Commenced rod withdrawal for startup.
2118 Reactor critical No. 181. Inserted rod 18-51 back to 00 to bring reactor sub-critical.
2119 Reactor sub-critical.
2253 Reactor critical No. 182.
2316 Reactor scram No.163, from 05 thermal power on "A" and "F" IRM spike when control rod 18-51 double-notched.
12/07/ 82 0145 Commenced rod withdrawal for startup.
0250 Reactor critical No. 183 0545 Rolled T/G.
0607 Synchronized generator, commenced power ascension.
2330 Commenced reducing thermal power from 845 for control rod pattern adjustment.
2400 Reactor thermal power at 805 for control rod pattern adjustment.
12/08/82 0001 Control rod pattern adjustment complete, commenced power ascension.
0200 Commenced PCIOMR from 885 thermal power (sequence
'*B").
l 2200 Commenced reducing thermal power from 965 thermal power for removal of "A" recirculation pump from service to repair an oil leak on recirculation pump M-G set.
2300 Reactor thermal power at 515 for "A" recirculation pump M-G set oil leak repair.
'o
6 Sinnificant ODerational Event Unit 1 Date Time Event i
12/09/82 0021 "A" recirculation pump in service, commenced power ascension.
0230 Commenced PCIOMR from 845 thermal power (Sequence "B").
1200 Reactor thermal power at 995, maximum flow, rod limited.
12/17/ 82 2323 Commenced reducing thermal power for control rod pattern adjustment and turbine control valve test and SI's.
2400 Turbine centrol valve test and SI's complete reactor power at 83%, increasing power for control rod pattern adjustment.
12/18/82 0100 Reactor power at 84% control rod pattern adjust-ment in progress.
0120 Control rod pattern adjustment complete, holding at 845 for SI 4.1. A-10 (main staanline radiation).
0230 SI 4.1.A-10 complete. Commenced PCIOMR from 845 thermal power.
1730 Reactor thermal power at 995 maximum flow, rod limited.
12/20/82 2140 Commenced reducing thermal power for MSIV 10% clo-sure SI 4.1. A.11 and MSIV full closure SI 4.7.D.1.b-2.
2150 Reactor power at 905. SI 4.1. A-11 oonplete, reducing power for SI 4.7.D.1.b-2.
2305 Reactor thermal power at 69%, SI 4.7.D.l.b-2 com-plate. Commenced power ascension.
12/21/82 0100 Commenced PCIOMR from 97%* (Sequence "B").
0300 Reactor thermal power at 995, mari=um flow, rod limited.
12/25/82 0130 Commenced reducing thermal power for turbine control valve tests and SI's.
0140 Reactor power at 95% for turbine control valve tests and SI's.
0150 Turbine control valve test and SI's complete, commenced power ascension.
0200 Commenced PCIOMR from 98% thermal power.
(Sequence "B").
0300 Reactor thermal power at 995, maximum flow, rod limited.
12/31/82 2400 Reactor thermal power at 995, maximum flow, rod limited.
7 Sienificant Ooerational Event Unit 2 Date Time Event 12/01/82 0001 End of cycle, refuel outage continues.
12/31/82 2400 End of cyce, refuel outage continues.
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8 Sinnificant Operational Event Unit 3 Date Time Event 12/01/83 0001 Reactor thermal power at 995, maximum flow, rod limited.
12/03/83 2130 Commenced reducing thermal power for removal of "A" reactor feedwater pump from service for main-tenance.
2250 Reactor. thermal power at 655 "A",
reactor feedwater pump out of service for maintenance.
12/04/83 0025 started SI 4.3.B.l.a scram testing control rods, reactor thermal power at 635.
0135 SI 4.3.B.l.'a complete.
Commenced power ascension from 635 thermal power.
0930 Reactor thermal power at 785. Commenced control rod pattern adjustment.
1105 Reducing thermal power for control rod pattern adjustment.
1400 Reactor thermal power at 71% for control rod pattern adjustment.
1440 Control rod pattern adjustment complete.
Commenced power ascension from 715 thermal power.
1800 Reactor thermal power at 75% for "A" reactor feedwater pump maintenance.
2200 Reactor thermal power at 765 for "A" reactor feedwater pump maintenance.
12/05/83 0600 "A" reactor feedwater pump back in service.
Commenced power ascension from 76% thermal power.
0630 Commenced PCIOMR from 775 thermal power.
0835 Stopped PCIOMR at 795 for tip set run.
1105 Tip set complete.
Commenced PCIOMR from 795 thermal power.
12/06/83 1110 Stopped PCIOMR at 965, computer out of service.
1300 Commenced PCIONR from 965 thermal power.
1600 Reactor thermal power at 995, maximum flow, rod limited.
1958 Commenced reducing thermal power due to 1/4 iso-lation from "C" sain steamline low-pressure switch.
e 6
9 Sinnificant Ooerational Event Unit 3 Date Time Event 12/07/83 0100 Reactor thermal power at 965, "C" sain steam-line low-pressure switch.
A340 Commenced PCIOMR from 965 thermal power.
(Sequence "B").
1800 Reactor thermal power at 995, maximum flow, rod limited.
12/07/83 2020 Received 1/4 isolation from "C" sain steamline low-pressure switch. Commenced reducing thermal power.
2300 Reactor thermal power at 965 due to 1/4 isola-tion from "C" sain steamline low-pressure switch.
12/10/83 0945 Commenced power ascension from 965 thermal power.
1000 Reactor thermal power at 995, maximum flow, rod limited.
2330 Commenced reducing thermal power for control rod pattern adjustment and turbine control valve test and SI's.
2400 Reactor thermal power at 885, turbine control valve test in progress.
12/11/83 0021 Turbine control valve test complete, dropping load from 885 for control rod pattern adjustment.
0045 Reactor thermal power at 645 for control rod pat-tern adjustment.
0238 Control rod pattern adjustment complete.
j Commenced power ascension.
0810 Reduced thermal power from 815 to 775 for control rod pattern adjustment.
1100 Commenced PCIONR from 775 thermal power.
(Control cell core).
l 2330 Stopped PCIONR at 915, computer out of service.
12/12/83 1215 Computer back in service. Commenced PCIONR from 915 thermal power.
2111 Received 1/4 isolation from "C" sain steam-line low-pressure switch. Commenced reducing thermal Power from 985.
2200 Reactor thermal power at 965 due to "C" sain steamline low-pressure.
12/13/83 0700 Reactor thermal power at 955 due to "C" sain steam line low pressure switch.
10 i
m nificant Operational Event Unit 3 Date Time Event 12/15/83 2105 Commenced power ascension from 955 thermal power.
2130 Commenced PCIOMR from 965 thermal power (control cell riore.)
2230 Reactor thermal power at 995 maximum flow, rod limited.
12/18/83 0210 Reducing thermal due to loss of RSCS.
0500 Reactor thermal power at 905 due to RSCS problem.
0545 RSCS repaired. Commenced PCIOMR (control cell core).
l 0900 Reactor thermal power at 095 maximum flow, rod limited.
12/19/83 1728 Reduced thermal power to 815 when "A" feedwater pump tripped while injection water was being adjusted.
i 1750 "A" reactor feedwater pump reset and placed back in service, holding at 815 for removal of "C"
string low-pressure heaters from service for main-tenance.
(Bottom head leaking.)
1804 "C" low-pressure heaters out of service, reactor power at 815.
1910 Commenced power ascension from 815 thermal power.
("C" low-pressure heators out of service for main-tenance).
12/20/83 0850 Commenced reducing thermal power from 935 when "C" string high-pressure heater isolated, on C1 and C2 moisture-separator drain pump high level.
0910 "C" string high-pressure heaters back in service.
Reactor power at 895 for "C" string low-pressure heater maintenance.
1900 Reactor thermal power at 905 for "C" string low-pressure heater maintenance.
12/21/83 1110
~"C" string low-pressure heater maintenance com-plete. Heater back in service; commenced power ascension.
1400 Reactor thermal power at 995, maximum flow, rod limited.
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,._. _.. ~
11 p.
Sienificant Operational Event Unit 3 Date Time Event 12/23/83 1042 "A" reactor feedwater pump tripped on high vibra-tion, commenced reducing thermal power.
1400 Reactor thermal power at 815, "A" reactor feed-water pump off line due to high-vibration trip.
l 1405 Rolled 3A reactor feedwater pump.
I 1407 3A reactor feedwater pump tripped on high vibra-tion.
Reactor power at 815.
1408 Rolled 3A reactor feedwater pump.
1438 3A reactor feedwater pump tripped on high vibra-tion.
Reactor power at 815.
1510 3A reactor feedwater pump back in service.
1548 3A reactor feedwater pump taken out of service to replace cable on turbine and Indikon.
Reactor power at 815.
1630 Cable replaced on 3A reactor feedwater pump turbine end Indikon.
Commenced power ascension.
1800 Reactor thermal power t 995 maximum flow, rod limited.
12/24/83 2344 commenced reducing thermal power for turbine con-trol valve test and SI's.
2359 Reactor thermal power at 935 for turbine control valve test and SI's.
12/25/83 0115 Turbine control valve test and.SI's complete.
menced power ascension.
0130 Reactor thermal power at 995, maximum flow, l
rod limited.
12/28/83 2030 Commenced reducing thermal power for removal of 3A reactor feedwater pump from service for main-tenance.
2110 Reactor thermal power at 735, 3A reactor feedwater l
pump out of service for maintenance.
2206 Maintenance complete on 3A reactor feedwater pump, placed pump in service, commenced power ascension.
2300 Commenced PCIONR from 985 thermal power (control cell core).
(
2400 Reactor thermal power at 995, maximum flow, rod L
limited.
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12 Sinnificant Ooerational Event Unit 3 Date Tina Event 12/29/83 1015 commenced reducing thermal power for removal of 3c reactor feedwater pump from service for maintenance.
1100 3c reactor feedwater pump out of service for main-tenance, reactor thereal power at 745.
1940 3c reactor feedwater pump maintenance complete, placed pump in service, commenced power ascension.
2200 Reactor thermal power at 995, maximum flow, rod limited.
12/31/83 0628 commenced reducing thermal power for removal of 3c reactor feedwater pump from service for maintenance.
0730 3C reactor feedwater pumps out of service for maintenance. Reactor power at 765, 0800 Peactor power at 755, 3c reactor feedwater pump maintenance.
1000 Reactor power at 775, 30 reactor feedwater pump maintenance.
1400 Reactor power at 785, 3c reactor feedwater pump maintenance.
1800 Reactor power at 795, 3c reactor feedwater pump maintenance.
1840 Maintenance complete on 3c reactor feedwater pump.
placed pump.in service, commenced power ascension.
2100 Reducing thermal power from 985 for maintenance to change oil filter on 3A reactor feed pump and tur-bine control valve tests and SI's.
l 2200 Reactor thermal power at 965 for oil filter change on 3A reactor feedwater pump and turbine control l
valve tests and SI's.
2400 Reactor thermal power at 965 for oil filter change on 3A reactor feedwater pump and turbine control valve tests and SI's.
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13 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-259 UNIT Browns Ferry 1 I!1!O DATE COMPLETED BY TELEPHONE 205/729-0834 MONTH DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe Neti iMWe-NetI 1060 1067 i
g7 1063 982 2
33 1071 3
39 4
754 20 1041
-16 1061 5
33
-12 1066 6
7 23 8
962 1089 24 984 1064 9
25 1069 1041 10
'6 1062 1064 II 27 12 1063 1066 73 1066 1068 13 1068 1067 g4 9
1064 1051 15 3g 1067 16 s
INSTRUCTIONS l
On this fonnat hst the.nerage daily unit pimer lewi ni Mwe. Net for each day in the ieporting inanth.Coinpute o l
the nearest whole nwpwait, l
(9/77)
J
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14 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-260 UNIT Browns Ferry 2 l-1-83 DATE T. Thom COMPLETED BY TELEPHONE 205/729-0834 December MONTH DAY AVERAGE DAILY POWER LEVEL DAY AVER ACE DAILY POWER LEVEL (MWe-NetI (MWe-Net)
I
-2 17
-2
-2
-2 2
I8
-2
-3 3
9
-2
-2 4
5
-3
-2
-2
-2 6
22
-2
-2 7
33
-2
_3 8
-6
~
l 9
,5
(
-2
-7 10 6
-2
-6 j
II 27 1
12
-2
-6 28
-2
-7 l
I3 29
-2
_7 l
I4 30 15
-2 3I
-6 I6
-3 l
INSTRUCTIONS On this forinat, list the averaec daily unit power lesel in Mwe. Net for each day '"'I'# '#P""I"E '"" nth. Onnpute io the nearest whole mea awan.
g 1
1 b 77I b
15 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO, 50-296 Browns Ferry 3 WIT
~
DATE COMPLETED BY T. Thom 205/729-0834 TELEPHONE MONTH December DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe Netl g y g,,3,,,
i 1054 7
1070 2
1058 1050 i3 1031 1029 3
,9 775 9.16 4
g 5
850 21 997 6
1015 1054 y2 1027 1018 7
23 1018 1037 8
9 1019 1056 25 10 1046 1049 3
813 1059 i
1014 1043 12 28 1008 993 13 29 1065 14 1013 30 I5 1015 917 s
33 1064 I
16 i
INSTRUCTIONS On this format !:st the aserage daif> unit power lesel ni MWe Net for each day in the seportmg snonth. Compute to the nearest whole nwgawaii.
p177) o
16 OPERATING DATA REPORT DOCKE T NO. 50-259 DATE 1-1-83 COMPLETED BY T. Thom TELEPHONE ?ns/7?o-0834 OPERATING STATUS Notes
- 1. Unit Name: Browr s Ferry - 1 December 1982
- 2. Reporting Period:
3293
- 3. Licensed Thermal Power (Mht):
1152
- 4. Nameplate Rating (Gross MWe):
- 5. Design Electrical Rating (Net MWe): 1065
- 6. Maximum Dependable Capacity (Gross MWe): 1noR.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:
N/A
- 9. PoweiLevel To Which Restricted.lf Any(Net MWe):
N/A
- 10. Reasons For Restrictions.lf Any:
N/A This Month Yr to Date Cumulatise 744 8,760 73,802
- 11. Hours in Reporting Period 686.87 8,074.74 47,389.54
- 12. Number Of Hours Reactor Was Critical 57.13 522.11 5,737.31
- 13. Reactor Reserve Shutdown Hours
- 14. Hours Generator On-Line 683.18
/,969.93 46,400.12
- 15. Unit Reserve Shutdown flours 0
0 0
- 16. Gross Thermal Energy Generated (MWH) 2,196,238 24,898,097 131,773,004
- 17. Gross Electrical Energy Generated (MWH) 729.940 8,108,270 43,400,720
- 18. Net Electrical Energy Generated (MWH) 711,479 7,880,870 42,149'779
- 19. Unit Service Factor 91.8 9?.?
610
- 20. Unit Availability Factor 41.8 92.2
-63.0
- 21. Unit Capacity Factor (Using MDC Net) 89.8 84.5 53.6
- 22. Unit Capacity Factor IUsing DER Net) 89.8 84.5 53.6 8.2 8.5 24.4
- 23. Unit Forced Outage Rate
- 24. Shutdowns Scheduled Oser Next 6 Months aType. Date,and Duration of Eacht:
1
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
- 26. Units In Test Status IPrior io Commercial Operation):
Forecast Achiesed INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCI AL OPER ATION (9/77) s I'
17 OPERATING DATA REPORT DOCKET NO. 50-260 DATE 1-1-83 COMPLETED BY T.
Thom TELEPHONE 205/729-0834 OPERATING STATUS Browns Ferry - 2 Notes
- 1. Unit h December 195Z
- 2. Reporting Period:
- 3. Licensed Thermal Power (MWt): 3293 1152
- 4. Nameplate Rating (Gross MWe):
- 5. Design Electrical Rating (Net MWe):
1065 1098.4
- 6. Maximum Dependable Capacity (Gross MWe):
1065
- 7. Maximum Dependable Capacity (Net MWe):
- 8. If Changes Occur in Capacity Ratings (items Number 3 Through 7) Since Last Report.Give Reasons:
N/A
- 9. Power Level L Which Restricted,if Any (Net MWe):
N/A
- 10. Reasons For Restrictions.lf Any:
N/A This Month Yr.-to-Date Cumulative 744 8,760 68,743
- 11. Hours In Reporting Period 0
4.846.51 43,293.47
- 12. Number Of Hours Reactor Was Critical 0
203.06 13,684.82
- 13. Reactor Reserve Shutdown Hours U
- 14. Hours Generator On-Line 4.778.36 41,975'.45
- 15. Unit Reserve Shutdown Hours 0
0 0
0 13,827,jj0
- 120,480,340
- 16. Gross Thermal Energy Generated (MWH) 0 4,592,260 40,024,908
- 17. Gross Electrical Energy Generated (MWH) 0 4,450,929 38,87),075
- 18. Net Electrical Energy Generated (MWH) 0
- 19. Unit Senice Factor 54.5 61.1 U
54.5 61.1
- 20. Unit Availability Factor
- 21. Unit Capacity Factor (Using MDC Net 1 0
47.7 53.1 0
47.7 27.1
- 22. Unit Capacity Factor (Using DER Net) 0 5.5 27.1
- 23. Unit Forced Outage Rate
- 24. Shutdowns Scheduled Oser Next 6 Months (Type. Date.and Duration of Eacht:
3
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
February 1983
- 26. Units in Test Status tPrior to Commercial Operation):
Forecast Achiesed INITIA L CRITICALITY INITI A L ELECTRICITY CO\\tMERCI A L OPER ATION (9/77)
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18 OPERATING DATA REPORT DOCKET NO. 50-296 DATE l-1-83 COMPLETED BY T.
Thnm TELEPHONE 205/729-0834 OPERATING STATUS
- 1. Unit Name: -Browns Ferry - 3 Notes December 1982
- 2. Reporting Period:
3293
- 3. Licensed Thermal Power (MWt): 1152
- 4. Nameplate Rating (Gross MWe):
- 5. Design Electrical Rating (Net MWe): 1065 1098.4
- 6. Maximum Dependable Capacity (Gross MWe):
1065
- 7. Maximum Dependable Capacity (Net MWe):
- 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 MWe):
N/A
- 10. Reasons For Restrictions. If Any:
N/A This Month Yr..to-Date Cumulative i1. Hours In Reporting Period 744 8.760 51.168
- 12. Number Of Hours Reactor Was Critical 744 5,145.30 37,612.28
- 13. Reactor Reserve Shutdown flours 0
1,230.62 3,372.15
- 14. Hours Generator On-Line 744 5,023.28 36,774.06
- 15. Unit Reserve Shutdown flours
.0 0
0
- 16. Gross Thermal Energy Generated (MWil) 2,326,246 15,477,484 109,336,104
- 17. Gross Electrical Energy Generated (MWH) 7 6 6, _7_9_0_, _,
5.041.600 36.039.790
- 18. Net Electrical Energy Generated (MWH) 748,175 4,892.858 34,980.904
- 19. Unit Service Factor 100 57.3 71.9
- 20. Unit Availability Factor 100 57.3 71.9
- 21. Unit Capacity Factor (Using MDC Net) 94.4 52.4 64.2
- 22. Unit Capacity Factor (Using DER Net) 94.4 52.4 64.2
- 23. Unit Forced Outage Rate 0
20.6 17.4
- 24. Shutdowns Scheduled Oser Next 6 Months IType. Date,and Duration of Each t:
- 25. If Shut Down At End Of Report Period. Estimated D.ite of Startup:
- 26. Units In Test Status IPrior to Commercial Operationi:
Forecast Achiesed INITIA L CRITICALITY INITIAL ELECTRICITY CO\\lMERCI AL OPERATION (9/77)
{
essP i
a 50-259 DOCKET NO.
UNIT SilUTDOWNS AND POWER REDUCTIONS UNIT N AME Browns Ferry 1_
DATE 1-1-83 December COMPLETED BY T.
Thnm REPORT MONTil TELEPif0NE 205/729-0834
=
c 5g 3
j E5 Licensee
,E-r,
,E g Cause & Corrective No.
Date g
3g j
,3 g 5 Event g?
El Action to Report 2r mO 5'
Prevent Recurrence H
jE d
35g e
o O
249 12/04/82 F
53.97 B
1 Reactor scram to repair leak on dis-charge line of "B" reactor feedwater pump.
250 12/06/82 F
6.85 A
3 Reactor scram on "A" and "F" IRM spike when control rod 18-51 double notched.
251 12/08/82 F
B Derated to repair an oil leak on "A" 5
recirculation pump M-G set.
252 12/20/82 S
B Derated for MSIV 10% and full closure SI's.
l 1
2 3
4 l
F: Forced Reason:
Method:
Exhibit G - Inst ructions S: Scheduled A Equipment Failure (Explain) 1-Manual for Preparation of Data 11 Maintenance of Test 2-Manual Scram.
Entry Sheets for Licensee C-Refueling 3-Automatic Scram.
Event Report (1.1:R) File (NtlRI.G-D-Regulatory Restriction 4-Ot her ( Explain) 0161) 150perator Training & License Exaipination F Administrative 5
G-Operational Error (Explain)
Exhibit I - Same Source (9/77) ll-01her (E xplain)
- I DOCKET NO.
50-260 UNIT SilUTDOWNS AND POWER REDUCTIONS UNIT NAME Browns Ferry 2 DATE 1-1-83 COMPLETED BY T. Thom December REPORT MONTil TELEPHONE 205/729-0834 c
, t, K
Cause & Corrective jg 3
j h#5 Licensee E
No.
Date i
d 3s5 Event 37 9?
Action to
-=
~ ji =y Report a mV EO Prevent Recurrence j=
5 H
=;
v e
6 243 12/1/82 S
744 H
2 EDC-4 Refuel Outage Continues S$
I 2
3 4
F: Forced Reason:
Method:
Exhibit G -Instructions S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance of Test 2-Manual Scram.
Entry Sheets for Licensee C Refueling 3 Automatic Scram.
Event Report (i.ER) File (Ntf RI:G-D Regulatory Restriction 4 Other (Explain) 0161) 150perator Training & License Examination F-Administrative 5
Exhibit I Same Source G Operational Error (Explain t (9/77)
Il-Other (Explain)
__n____-___
s 9
50-296 DOCKET NO.
UNITSIIUTDOWNS AND POWER REDUCTIONS UNIT NAME Browns Ferry 3 DATE 1-1-83 December COMPLETED BY T-Thn=
REPORT MONTH TELEPliONE ?n s 17? o_nnu w.
E E
.5 g 3
j E~
Licensee
,E-t,
%'?
Cause & Corrective No.
Date g
~g d
.;; j 5 Event p
e-Action to f-5 35e Report a mO E'
Prevent Recurrence H
g o
e O
117 12/3/82 F
B Derated to remove "A" reactor feed pump from service for maintenance.
118 12/11/82 S
H Derated for control rod pattern adjustment.
119 12/28/82 F
B Derated to remove "A" reactor feed-water pump from service for main-tenance.
O 120 12/29/82 F
B Derated to remove "C" reactor feed-water pump from service for main-tenance.
121 12/31/82 F
B Derated to remove "C" reactor feed-water pump from service for main-tenance.
I 2
3 4
F:. Forced Reason:
Method:
Exhibit G. Instructions S: Scheduled A Equipment Failure (Explain)
!-Manual for Preparation of Data 10 Maintenance of Test 2 Manual Scram.
Entry Sheets for Licensee C Refueling 3 Automatic Stram.
Event Report (LER) File (NtlRI G-D-Regulatory Restriction 4-01her (Explahi) 01611 E. Operator Training
- License Examination F Administrative 5
G-Operational Error (Explain)
Exhibit I - Same Source (9/77)
Il-Ot her (Explain)
b BROWNS FERRY NUCLEAR PLANT UNIT 1
CSSC EQUIPMENT
~~
MECllANICAL HAINTEIMNCE
SUMMARY
For the Month of December 19 82 EFFECT ON SAFE AC1105 TAKI:N DATE SYSTEM C+ CdtPONENT 7_ NATURE OF OPERATION OF CAUSE OF RESUl/fS OF it) FRECLUD2 MAINTENANCE "IllE REACTOR MALFUNCTION 5'ALFU';CTION RFCURRENCE 2-13 Radiation
' cam 90-256
-air leak none faulty o' rings &
air leak replaced o' rings &
S_
Monitoring i..
loose handles tightened handles g e 1-
-r -
TR# 216762
- W '.
[;
';= ' -
2a10 Fuel pool pump 1A water leak none worn packing packing leak in shaft installed new packing W-cooling 3
TR# 339337
,9 *-'
r.
IN7 Drywe11 7 Nryvellair._[ yemove 28' none unknown interchange of air removed valve internal Air
.2
~ 7 compressor valve & instal l.
cort. pressor valve to unit IB
'G:
Compreseol Ivalves 2B &~1B ~ca 1B ~~^
TR# 308229
- d~
..._:. iE -
2'-df Radiation? ICAM 90-250 IfketvEleon moisture collect-inlet valve not inverted inlet valve none Monitoring sample inlet suction valve ing in cample funct-loning properly TR# 216726 h
Nalve needs, invert-line 2006 CRD
~~ [.*~:,
+
5'--
L
-ing...
u.
54 l.
4 f-
~
'i'.CRD
- ~
B faulty filter none bad filter unknown replaced with discharg discharge filter
_..~
filter TR# 308253
.-. [s.
g
... ~
~ ;*,
_=c.;; 7,2..
..:.~
7 m. -_:.>.
3, 8
T'
~
Li.
-s g
M J v '{'**-* -
l a
i
?
i e
b e
d
- " V L i
4,
__ 5 _
e BROWNS FERRY NUCLEAR PIANT UNIT _
2_. _
MEQiANICAL FL\\INTE!;A :CE SUliMARY CSSCEOUIPMEhT December 19 82
~
For the Month of 1
ACTION TAKE;;
EFFECT ON SAFE RTE SYS TEM C05tPOSENT NATURE OF OPERATION OF CAUSE OF RESCI.TS OF TO PRECLUDE PtAINTENANCE
' DIE REACTOR MALFUNCTION MALFUNCTIO:I RECUR 3E!!CE unknova unknown replaced valve interna]
L-27 Control HCV-32-307A switch valve none TR# 291708 l-internals Air i L-28 RHR FCV-74-53 packing leak none worn packing valve nonfunctional replaced packing TR# 276141 i
1-29 CRD module 38-07 leakage none faulty valve pressure switch Icaks replac'ed o' ring seal,
through body o' ring,& body isolation valve back-up ring TR# 309985 M
S 4
T h e.
Om
+.9 9
.T=
n f,
' a 0-c..
3 a.
2:c.;
l
~
I l
l f
i i
I..A i
2 4
BROW:S FERRY 1:CCLEAR PIR;T UNIT
~
FE.CllANICAL Malt!TEta!;CE SUltlARY CSSC EQUIPMENT December 19 82 For the Month of ACTIO:; TAKE!J EFFECT 0:1 SAFE ATE SYSTEM COMPONENT NATURE OF OPERATION or CAUSE OF RESUL'Ili 0F M) PRECLUD3 MAINTENANCE T!!E REACTOR MALFUNCTItA3 "M FC' CTIO?!
RECUllRE CE worn packing packing Icak replaced packing TRf 314587 water leak none I
i
,-16 Standby SLC pump A TR# 339077 Liquid Control resweated joint unknown air leak in copper l 1-29 Control Air copper pipe n.e, air Icak none TR# 231389 pipe wall worn packing packing Icak repacked pump TR# 342911 2-15 Standby SLC pump B water leak none Liquid
~
Control cap inoperable test connection drain. replaced existing cap TR# 245108
,2-03 Standby valve 63-529 faulty cap none cap leaking Liquid drain cap Control worn packing valve needed repacked valve TR# 276143 L2-02 RHR FCV-74-67 water leak none repacking-threads on pipe pipe leaking oil at took apart,retapped thread & tightened L1-10 HPCI 3" pipe stop oil leak none pipe thread into bolted-up flanges valve cylinder sump l
TR# 297702 l
to oil sump
'l i
I i
e I
is,'
I
=
~
BRO'.i :S FERRY I:UCLEAR PIN;T UNIT
!!ECilll;ICAL R\\1NTE hNCE SC:Dt* RY CSSC EQUIPMENT December 19 82
~
For the Moi.th of
~~~
AC 1'lO!; TARi;;;
EFFELT 0:1 SAFE JATE SYSTEM COMPONENT NATURE OF OPERATION OF cat:SE OF RESCI.TS OF TO l'RECI.CDE KilNTENANCE iliE REACTOR 2'ALFl3CTIO 1 R\\1.Ft.C;CT IO:1 R!:CURRENCE 5
worn belt broke cam inoperable replaced belt
-13 Radi tion cAta 90-250 faulty cam none TR# 265332
(
Honitoring 1-03 Radiation D.W. cam 90-256 noisey cam none pump worn out sample pump inopera-replaced with spare cam vac pump (rebuilt) ble Monitoring sample pump TR# 275244 installed new white unknown unknown 2-20 Radiation cam 90-250 inleLfaulty cam none hose Monitoring vent line hose TR# 216763 bad o' rings 6 air 1eak replaced o' ring &
repaired handle,
.2-13 Radiation cam 90-256 faulty cam none handle broken Monitoring replaced latch.
coupling inoper-MG set inoperable replaced coupling on
.2-22 LPCI LPCI MG set faulty coupling none generator end abic, needs 3DA TR# 296734 replacing U
4 e
i l
=
I.
l c
i
3 -,-----
EROWI S FERI'Y NUCLEAR P12NT UNIT Common 11ECllANICAL !!AINTENANCE SUSCtARY CSSC EOUIP>!ENT For the !!onth of December 19 82 ACTION TAKL;.
EFFECT ON SAFE DATE SYSTD1 C0d!PONENT NATURE OF OPERATION OF CAUSE OF EESCLT3 OF TO PRECLUDE MAINTENAICE Tile REACTOR
?!ALFUNCTION
"\\LFC:CTIn::
RECURRE::CE 1-15 RHRSW pump 1D Packing needs none worn out packing unknown replaced packing TR# 312597 l
replacing 1-10 RHRSW pump 3D packing needs none worn out packing unknown repacked pump TR# 312596 replacing
.1-10 D/G u-1&2 D/G D bad leak none head gasket worn leak around HP replaced head gasket cylinder head gasket TR# 266983 bank A air compressor
. ---r L1-09 RHRSW pd 3C packing needs none worn out packing unknown repacked pump TR# 312598 replacing L1-19 D/G -'.
D/G-1C air..
faulty start none starter worn out starter inoperable replaced starter, cleaned and inspected a,-
.c.f -
stagg motor motor TR# 245179
- r :t --
+
G p
i
-m I
l I
l ii e*
- n.,
I and Common Page 3 BROWNS FERRY NUCLEAR PLANT UNIT
^
CSSC EQUIPMENT ELECTRICAL MAINTENANCE SQfMARY 9/29/82 December 82 T._w_ _
~ ~ ~
For the Month of 19 bh Effect on Safe Action Taken
- Hature of Operation of Cause of Results of To Preclude Dito System Codponent Maintenance The Reactor Malfunction Malfunction Recurrence 12/1/82 Didsel-.
D/G B. speed While perform-None, start Bad speed sens-D/G B failed to The bad relay was Generators sensing relay ing redundant circuit 2 was ing relay ZSRl.
start by starting replaced, SI 4.9.
- ~.,-
ZSRl.
start test operable.
circuit I during A.1 Supplement A
./ - -
(EMI 3) on the redundant start performed, and u.
D/G B start test.
the diesel gener-
_ F - _,
circuit 1 fail-ator returned to service.-
- ~ _ -
.ed:to function..
4L
- .2 ci.Teke:-
TR #334812
-W "
TR #306702 6r =.. _ _
i - ~ - ~ ~ ~ ~
LER#BFRO-50-259/
[ M...s ~'"-. _ " _
_..R.m I
'?2 8295
-W, - -
-n
.,v m '.
7 c n.;
e.
-e.*..
12/3/83 RER.?-
LPN~ /G'-seth I$tNUutput None Motor generator LPCI M/G set 1EA Adjustments were t~~
IEA voltage -
voltage.
output voltage output voltage was made to the M/G
~
had drifted 470 volts as oppos-set voltage regu-
- 9...
regulator. ;
j,7 down.
ed to 490 volts lator to bring the 5 volts.
voltage level to b.-
output voltage 490 volts. The
[
_-. 73 "
_fi~ 7._ _.
was monitored and i.
,.... L' "4 -; n ;- - [ ~'
found to remain stable.
TR #308244
' ~ ~
T'.3 M.
- q3.-:.
w 7.z-n g-M
._:-_+-
I..
O em 1-
3 BR05"lS FERRY NUCLEAR PLANT U'61T 1 and Common Pa g.c CSSC EQUIPMENT ELECTRICAL MAINTENANCE
SUMMARY
Ap pend 17. B 9/29/82 i
For the Month of December 19 82 r
Effect on Safe Action Taken
' Nature of Operation of Cause of Results of To Preclude Date Svstem Component Maintenance The Reactor Malfunction Malfunction Recurrence 12/7/82 CRD Handswitch 85-HS 85-48 was None Broken stop Required operator to Replaced the brok-!
48 located on not operating plate.
take care not to ro-en stop, the hand i panel 9-5.
properly.
tate the handswitch switch operated past desired setting. properly.
/
TR #341285 12/7/82 CRD Ldvel annun-LA-85-85A was None Bad annunciator LA-85-85A inoperable, Replaced the bad.
ciator LA not operating circuitry card.
circuitry card, 85A (CRD Dis-properly.
annunciator oper-charge Header ated properly.
Water Level TR #339330 High or Equip" ment Failure) located on w"
XA-55-6C of panel 9-6.
12/18/82 High-
"B" fire pump Breaker None Bad coils and Excessive chattering. Replaced the bad Pressure strainer chattering contacts on for-of starters.
starter coils and Fire Pro-breaker.
excessively, ward and re-contacts. The tection versing starters contactors operat-ed properly.
TR #326361 12/21/85 Diesel D/G D annun-Received a None Bad annunciator Received a false Replaced the bad Generators ciator cir-ground fault circuitry card.
ground fault alarm card and the ann-cuitry.
alara on panel on panel 9-23-7.
unciator circuitry 9-23-1.
eperated properly.
TR #244909
.f.
i
I '-
\\
2 Enc 3 BROWNS FERRY NUCLEAP. Pl, ANT UNIT liF EMSIL 30 l
Appendix 3 CSSC EQUIPMENT ELECTRICAL MAINTENANCE SUM!Ar(Y 9/29/82 82
[
For the Month of December 19 Effect on Safe Action Taken
' Nature of Operation of Cause of Results of To Preclude D?ts Svstem Component
!!aintenance The Reactor Malfunction Maltunction Recurrence 11/25/82 Annuncia-821T annunci-Replacement of None Generic problem Resistors were over-Replaced 821T an-tor &
~ator inverter 821T annunci-with the power heating and failing nunciator inverter Sequential control cards, ator inverter rating of a at an excessive control cards with Events control cards resistor in the rate.
watt resistors Recording with h watt inverter con-with repaired resistors with trol card.
cards'having a 1 repaired cards watt resistor.
~,
having a 1 The following an-watt resistor nunciator panel's per manufac-inverter control,
turer sugges-
. cards were replac '
tion.
ed.
Panel 9-3 "I,'
XA-55-3A, 3B, 3C, 3D, 3E and 3F
~
Panel 9-4 XA-55-4A,'4B, and 4C Panel 9-6 XA-55-6A, 6B, and 6C Panel 9-7 XA-55-7A, 7B, and 7C XA-55-1(1st out
'~
printer)
Panel 9-8 XA-55-8B, 8C, 8D, and 8E Panel 9-20 XA-55-20A, 20B, G and 20C 3
~
Panel 9-53 XA-55-53 TR #225220 Ref. Sept.1982-f, monthlyreportfoq<-
m
,,,,4 c, -,,,,
s BROW S FERRY NUCLEAR PLANT UNIT 2
3 gg 3g CSSC EQUIPMENT ELECTRICAL MAINTENANCE SIMIARY
^EE#"
9/29/52
'~
For the Month of December 82 19 Effect on Safe Action Taken Nature of Operation of Cause of Results of To Preclude D*te System Component Maintenance The Reactor Malfunction Malfunction Recurrence 12/10/82 Primary Annunciation Received a None Bad coil on Receive a false Replaced the bad Contain-relay 16A-K39 false closed relay 16A-K39.
closed annunciation relay coil, relay ment on panel 9-42 annunciation.
for valve 16-19-11A.
operated properly.
for torus TR #303527 vacuum relief valve 16 Z 11A inboard
^'
vilve (GE r
Type CR120A) 12/20/82 RBCCW Feeder break-2A-1 drywell None Dirty contacts 2A-1 dryvell blower Cleaned contacts er (chtd. bd.
blower motor on breaker relay inoperable.
and adjusted m; 'f..
2A, compt.
would not
' 52X and breaker latch. Meggered 2C) for 2A-1 start from latch out-of-motor and returned
~
drywell panel 9-25.
adjustment.
blower to service, blower.
TR #339208 a-
- ser om e -=
de
-a$
- .. 7
.]
?
EROUNS FERRY WPCLEAR PLANT L";iT Page 3 BF EMSIL 30 CSSC EQUIPMENT ELFCTRICAL MAINTENANCE
SUMMARY
^EE""
- O 9/29/82 For the Month of December 19 82 Effect on Safe Action Taken Nature of Operation of Cause of Results of To Preclude Date Svstem Component Maintenance The Reactor Malfunction Malfunction P.ecurrence i
11/27/82 CRD Power Supply No power to None, no scram Bad (3A-PS6)
Lost power to the Replaced the bad 3A-PS6.
CRD select functions power supply, rod select push-power supply.
- panel, effected.
button panel and The rod select t
select relay modules panel was func-located in panel tionally checked 9-18.
Operator was and returned to unable to manually service.-
[~
select (move) rods.
TR #275492 12/2/82 Diesel D/G 3D annun-Received a None Bad annunciator Received a false Replaced the bad Generators ciator cir-D/G 3D control circuitry card.
annunciation.
annunciator card, cuitry.
circuit ground trouble alarm annunciation.
cleared.
TR #269571 12/3/82 Air Con-Shutdown Air handling None Air handling Fan locked up which Replaced motor, ditioning boardroom unit 3B1 fan unit fan bear-twisted the fan unit operated (Cooling-air handling motor base ings were bad.
motor base off, properly.
d Heating) unit 3Bl.
twisted.
TR #277447 12/13/82 Contain-Drywell Annunciator None Loose annuncia-Ann. 76-89 inoper-Inserted card ment supply cham-failed.
tor circuitry
- able, full in and the Inerting ber H 0 an-card.
annunciato'r oper-27 alyzer rail-ated properly.
ure annunci-TR #265311 ator circui-try.
i
3 BROWNS FERRY NUCLEAR PLANT UNIT 3
3 MSIL 30 CSSC EQUIPMENT ELECTRICAL MAINTENANCE SUFDIARY EE "
9/29/82 For the Month of_ Decemher 19 82 Effcct on Safe Action Taken l
Nature of Operation of Cause of Results of To Preclude D3tm Svstem Component Maintenance The Reactor Malfunction _
Malfunction Recurrence L2/18/82 Diesel D/G 3C control While D/G 3B D/G 3C was de-Failed coil in This relay's only The NVR relay was Generators power "off" was inoperable clared inoper-relay NVR.
functicn is annunci-replaced SI 4.9.
annunciation for scheduled able, an IP-2 ation, therefore A.1 Supplement A relay NVR.
battery dis-was declared, this relay's failure was performed and charge test, and an orderly in itself did not D/G 3C returned to annunciation shutdown of make the diesel gen-service.l
" Diesel Gener-unit 3 was in-erator inoperable.
TR #314310 ator 3C Control itiated.
However, the diesel LERIBFRO-296/8265 Power OFF" was Diesel Gen. 3B generator was taken received.
was returned out of service for to service corrective mainten-before unit ance.
trip was necessary.
M 12/23/82 Air Con-3B control 3B control bay None Low of freon, Chiller would not Replaced the pilot ditioning bay chiller.
chiller was bad pilot cool properly.
expansion valve, (Cooling-not cooling expansion valve.
charged unit and Heating) properly.
performed EMI 60.
The chiller oper-ated properly.
TR #277484 O
=
I-t i
i
33 FIELD SERVICES SIDO(ARY December 1982 Ma.ior Work Areas I. Work Synopsis The principle work efforts completed during this December report period include torus internal modifications necessary for torus fill, torus ooating, torus fill, the piping portion of Po392 (CRD Scram Discharge Header Modification - Less Hangers and Supports) and CCW Inlet Tunnel Joint Hodification.
Major work still in progress at the close of this report period includes LPCI modification (L1845) tie-in work on Loop I (Loop II tie-in and testing was completed), MSIV reassembly work (all valves have now passed LLRT).
II. Ha.ior Work Areas A.
Refuel area - the primary effort on the refuel floor during the month of December was the installation of 20 jet pump plugs.
The plug installation required to drain down the recirculation risers to allow x-rays to be performed on recirculation riser l
weld indications.
The jet pump plugs have not been removed but will be removed prior to fuel loading.
B.
Turbine - the thermocouple modification on the "B" low-pressure turbine (P0630) was completed this month. This modification installed two thermocouples from the 12th stage.diaphraga turbine end to a junction box on the turbine. This required bringing in a portable milling machine to mill the diaphraga and the horizontal joint.
o
34 FIELD SERVICES SIRetARY i
December 1982 II. Maior Work Areas B.
(Continued)
The number one coupling boring task was also completed.
Eighteen of 18 holes required boring, and fabrication of 18 new bolts was also required.
Currently reassembly of the "B" low-pressure turbine is in progress with installation of the heat shields on the inner cylinder.
The RFPT's governor checks and alignment of controls was also completed on December 1.
C.
Electrical - Work continued this month on the LPCI modification.
LPCI loop II tie-ins were complete along with a successful post-mod test.
Loop II is required for fuel loading. The Loop I tie-in is approximately 98 percent complete and projected to be completed by January 4, 1983 It should be noted that the original plan required Loop I completion prior to Loop II.
The electrical portion of P0392 pas completed and awaits instru-mentation calibration and post-modification testing to see'if any additional adjustments in the last monthly report were resolved by receipt of the original valve design and resolution of level transmitter response time. Other electrical work performed this month includes: LPRM testing, additional conduit hanger work on P0590, and cable-pulling in support of the two new MSRY's that have been installed (L2115).
0
35 i
i FIELD SERVICES
SUMMARY
~~
December 1982 II. Maior Work Areas C.
(Continued)
Emergency lighting (PO479) was continued on a manpower avail-ability routine, and P0624 (new cables to torus vacuum breakers) was started this month. The recirculation MG set brush holder modification (P0600) is still being fabricated at the service shop. Preparation is underway to install the limit switches on the inboard MSIV's in order to support fuel loe. ding. The torus feeders, etc., were removed in support of torus fill.
i D.
Mechanical - The mechanical portion of P0392 was completed this month with the exception of approximately 14 hangers which were added during the month on the vent and drain piping.
A success-ful hydrostatic test was conducted on December 24. Preparations are underway to install water scram discharge header sleuths and
- manometers to support instrument calibration prior to post-modi-fication testing.
b All MSIV's have been modifthd and reassembled to a point where I
the LLRT was performed and all valves passed. Final assembly is in progress with emphasis being placed on the inboard valves in order that limit switches can be completed to give proper indi-cation of the valve position in the control room.
I J
l 36 FIELD SERVICES SIRMARY December 1982 I
II. Ma.ior Work Areas (Continued)
D., (Continued)
Other Mechanical Work:
1.
All probolog has been completed and the final two feedwater heaters are being plugged. All other heaters / coolers / water-boxes have been plugged, if required, and closed up.
The retubed hydrogen cooler "D" was also received and installed.
2.
The MSRV's have been installed on the header and the inlet flanges torqued.
3 The "M" and "N" tailpipe work continued with hangers and supports taking most of the effort. Three x-ray welds remain on "N" line.
4.
Work in the H2/02 modification (P0361M) continued but not on a full-time basis. This work will be complete in time to support ILRT.
5.
The inlet tunnel seal joint repairs P0311/400 were completed with five joints requir[ng repairs. We were unable to pump down the outlet tunnel to conduct inspection.
6.
The 2D RHR heat exchanger modification locking tab acdifica-cation P0366 was completed and returned to service.
7.
P0386 stroke time on containment purge valves is still in work but is approximately 90 percent complete.
37 s.* '
FIELD SERVICES
SUMMARY
December 1982 II. Ma.ior Work Areas (Continued)
D.
(Continued)
Other Mechanical Work: (Continued) 8.
PO428 install 2 debris screens - One screen was installed this month and the other is working as manpower is available.
9 The repairs on the dampers and ventilation ducts on "A" and and "B" drywell coolers is approximately 85 percent complete and will be complete in early January.
10.
Eighty-six trouble reports have been generated by the ISI inspection, and so far 79 have been closed out.
11.
Changeout of hydraulic anubber seals continued during the month of December.
12.
The field work was completed on the Yarway column snubbers.
13 P0580 ILRT flanges to prefilter for drywell control air -
No work was performed on this modification due to material availability. The material was received in late December and only one shif t of work remains.
14.
P0612 - Install 1/2-inch SS flex line from control air to MSRV solenoids; 7 of 13 lines are installed and all pre-fabrication is complete.
- 15. Condenser - ill condenser work was completed this month and the condenser was released to operations.
J
^
38 i
FIELD SERVICES
SUMMARY
December 1982 II. Maior Work Areas (Continued)
E.
Modifications - Reviewed work plans in support of the U2 C4 outage. Expedited the solution of modification-related problems through EN DES via Chattanooga Field Services Hodification Group.
Started preparatory work for unit 1 cycle 5 outage.
Responded to LER's and CCPR's.
F.
Torus During the early part of December, sandblasting and painting efforts continued and setup for heateuring started. Modifica-cation work inside of torus continued in bays 15 and 16 which were released on December 4, 1982 for painting. On December 6, 1982 heateuring of bay 9 was started, but problems with heat con-trollers delayed completion until December 7,1982 and setup started immediately in bay 10.
Heateure was completed on
~
December 12, 1982. By this time strong efforts were being made to move out of the torus and to prepare for fill. SRV test instrumentation inside and outside of the torus was proceeding on schedule. Sandblasting and painting efforts started on November 18, 1982 and painting was completed on December 11, 1982 leaving touchup and washdown prior to torus fill. On December 21, 1982 the torus was mechanically complete for water-fill but closeout of workplans delayed torus fill until December 23/82 at 2400 hours0.0278 days <br />0.667 hours <br />0.00397 weeks <br />9.132e-4 months <br />. After the holidays, work resumed inside the torus with punchlist work such as installation of new hatch, vacuum breaker conduit, grating boltdown, etc. (above waterline work).
4
39 I
..n FIELD SERVICES
SUMMARY
December.1982 2
II. Maior Work Areas (Continued)
F.
(Continued)
Outside the torus, lap-plate work and ECCS header snubber instal-lation continued throughout the month of December. On December 16, 1982 several torus snubbers were found to have leaking seals and installation of snubbers stopped until the vendor's recommen-dations were obtained.
By the end of December the vendor had completed preliminary inspection and made arrangements to start repair of 10 anubbers of 16 total.
G.
Administrative - The evertime percentage for the month of November was 27 percent, with 139,351 straight-time hours and 51,034 overtime hours. As of November 30, 1982, year-to-date overtime percentage -was 24 percent, with 294,216 hours0.0025 days <br />0.06 hours <br />3.571429e-4 weeks <br />8.2188e-5 months <br /> straight time hours and 95,048 overtime hours. The overall overtime goal -
is 17 percent.
The 0 & M budget for Novembep was $2,933,602; expenditures were
$1,593,700, with YTD budget being $5,360,228; and actual YTD i
expenditures were $4,988,700. The capital budget was $3,885,987; expenditures were $2,003.222, with YTD budget being $7,659.773; and actual YTD expenditures were $3,831,982. Overall budget was
$6,819,589 and the overall expenditures were $4.596,922 with YTD budget being $13,020,001. Actual YTD expenditures were
$8,820,681.
The December overall budget is $6,308,834.
b