ML20077A405
| ML20077A405 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 04/01/1983 |
| From: | Thom T TENNESSEE VALLEY AUTHORITY |
| To: | |
| References | |
| NUDOCS 8307220313 | |
| Download: ML20077A405 (45) | |
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TENNESSEE VALLEY AUTHORITY DIVISION OF NUCLEAR POWER BRCWNS FERRY NUCLEAR PLANT MONTHLY OPERATING REPORT March 1, 1983 - March 31, 1983 DOCKET NUMBERS 50-259, 50-260, AND 50-296 l
LICENSE NUMBERS DPR-33, DPR-52, AND DPR-68 Submitted by:
flantSupe/dntendent pss1Guggo c3W m 7 y, p s.
Certified M d
8307320313 830401 h
PDR ADOCK 05000259 R
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TABLE OF CONTENTS 1
Operations Summary............'........
1 Refueling Information..........-...........
3 Significant Operational Instructions.............
5 Average Daily Unit Power Level..........
11 Operating-Data Reports.....
14 Unit Shutdowns and Power Reductions.............
17 Plant Maintenance.
20 Field Services Summary..
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3 Operations Sn==wy March 1983 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 21 reportable occurrences and six revisions. to previous reportable occurrences reported to the NRC during the month of March.
Unit 1 There were no scrams on the unit during the month.
JJnit 2 There was one scram on the unit during the month.
On-March 30, the reactor was' manually scrammed due to time restraints during a controlled shutdown for a
short maintenance outage.
Unit ~4 There was no scrams on the unit during the month.
1 Principally prepared by B. R. McPherson.
a 3
2-Operations nu-- ry (Continued).
March 1983 Fatigue Usaae Evaluation The cumulative usage factors for the-reactor vessel are as follows:
Location Usage Factor Unit 1 Unit 2 Unit 3 Shell at water line 0.00581 0.00458 0.00391 Feedwater nozzle 0.28196 0.19677 0.14871 Closure studs 0.22021 0.16669 0.12705 NOTE:
This accumulated monthly information satisfies Technical Specification Section 6.6. A.17.B(3) reporting requirements.
Common System Approximately 1.10E+06 gallons of waste liquids were discharged containing approximately 1.42E+00 curies of activities.
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3 Operations Su===ry (Continued)
March 1983 Refueline Information Unit 1 Unit 1 is scheduled for its fifth refueling beginning on or about April 15, 1983 with a scheduled restart date of October 7, 1983. This refueling will involve loading 8 X 8 R (retrofit) fuel assemblies into the core; finishing the torus modification; turbine inspection; finishing TMI-2 modifications; post-accident sampling facility tie-ins; core spray changeout; and changeout of jet pump hold-down beams.
There are 764 fuel assemblies in the reactor vessel. The spent fuel storage pool presently contains 216 new fuel assemblies, 260 20C-4 fuel assemblies, 232 E00-3 fuel assemblies, 156 EOC-2 fuel assemblies, and -168 E0C-1 fuel assemblies.
The present capacity is 1,148 locations.
Modification work and testing are in progress to increase the spent fuel pool capacity to 3,471 assemblies.
Unit 2 Unit 2 is scheduled for its fif th refueling beginning on or about June 8,1984 with a scheduled restart date of November 8,1984. This refueling will involve loading 8 I 8 R (retrofit) fuel assemblies into i
i the core,' finishing the torus modification, turbine inspection, finishing TMI-2 modifications, post-accident sampling facility tie-ins, core spray l
l change-out, and feedwater sparger inspection.
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4 Operations sn--arv (Continued)
March 1983 4
Refuelina Information Unit 2 (Continued)
There are 764 fuel assemblies in the reactor vessel.
At the end of the month there were 248 E00-4 fuel assemblies, 353 E00-3 fuel assemblies, 156 E0C-2 fuel assemblies, and 132 E00-1 fuel assemblies in the spent fuel storage pool.
The present available capacity of the spent fuel pool is 861 locations.
Unit 9 Unit 3 is scheduled for its fif th refueling on or about October 11, 1983, with a' scheduled restart date of May 4,1984. 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 E00-4 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.
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5 Significant Operational Event Unit 1 Date Time Event 3/01 0001 Reactor thermal power at 92%, end-of-cycle 5 coastdown.
3/18 1000 Commenced increasing thermal power from 86% by increasing recirculation pump flow.
1335 Recirculation flow increase complete, reactor thermal power at 90%, end-of-cycle 5 coastdown.
3/19 0225 Commenced reducing thereal power from 86% thermal power 7
for recirculation pump MG set brush replacement.
0400 Reactor thermal power at 49% for MG set brush replacement.
0500 Reactor power at 475 for MG set brush replacement.
0600 Reactor power at 46% for MG set brush replacement.
0642 Recirculation pump MG set brush replacement complete, commenced PCIOMR from 46% thermal power.
1300 Reactor thermal power at 90%, end-of-cycle 5 coastdown.
2035 Commenced reducing thermal power for SI 4.7.D.1.b-2.
2100 Reactor thermal power at 70% for SI 4.7.D.1.b-2 (MSIV Closure).
2140-SI 4.7.D.1.b-2 complete, reduced thermal power to 69%
for SI 4.1.A-11 (MSIV Closure).
l 2200 SI 4.1. A-11 complete, commenced power ascension.
3/20 0200 Reactor thermal power at 89%, end-of-cycle 5 coastdown.
3/22 1155 Commenced increasing reactor power from 875 by increasing pressure setpoint to 1000 psi.
1240 Reactor pressure at 1000 pai, reactor power at 88%,
end-of-cycle 5 coastdown.
i 3/31 2400 Reactor power at 85%, end-of-cycle 5 coastdown.
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6 Significant Ooerational Event Unit 2 Date Time Event 3/01 0001 End-of-cycle 4 refuel outage continues 3/18 0635 Commenced rod withdrawal for startup.
0755 Reactor Critical No. 150.
1315 Safety relier valve 1-180 railed to open during testing. Holding up on startup.
(Reactor thermal power at 65.)
2050 Commenced rod withdrawal increasing reactor power.
3/19 2115 Rolled main turbine.
2125
. Tripped main turbine at 100 RPM.
2130 Rolled main turbine to 1800 RPM.
3/20 0140 Main turbine tripped on vibration.
0142 Rolled main turbine.
0145 Synchronized generator, holding at 25% thermal power for startup testing and evaluation of inoperable HPCI, safety relief valve 1-180 and CAD valve 84-8A. (End-of-cycle 4 refuel outage completed).
0455 Tripped main turbine for overspeed trip testing.
0524 Rolled main turbine, overspeed trip testing complete.
0537 Synchronized generator, holding at 25% thermal power for startup testing (Inoperable HPCI, safety relief valve 1-180 and CAD valve 84-8A.)
1818 Manually tripped main turbine from 25% thermal power when a false high temperature alarm was l
received on turbine exhaust hood.
2140 Commenced reducing thermal power from 25%.
l 23D0 Reactor thermal power at 14%. Holding for investigation of turbine exhaust hoed high temperature alarm.
3/21 0030 Continued rod withdrawal for startup.
0310 Rolled main turbine.
l 0314 Synchronized generator at 245 thermal power, holding for startup testing and evaluation of inoperable HPCI, safety relief valve 1-180 and CAD valve 84-8A.
1935 Commenced power ascension from 24% thermal power startup testing in progress.
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7 Significant Ooerational Event Unit 2 Date Time Event 3/22 0030 Reactor thermal power at 38", holding for startup testing. RTI-5 scram timing.
1500 RTI-5 scram timing complete, holding at 38% for startup testing and evaluation of inoperable HPCI, relief valve 1-180, CAD valve 84-8A and IRM problems.
1920 Commenced power ascension from 38% thermal power.
2300 Reactor thermal power at 54%, reducing thermal power for startup testing (inoperable relief valve 1-180, CAD valve 84-8A, "B" RFW pump and IRM's A and B).
3/25 0005 Commenced power ascension from 49% thermal power.
0600 Commenced PCIOMR from 60% thermal power.
2200 Reactor thermal power at 735 holding due to problems with "B" reactor feedwater pump. (Safety relief valve 1-180, CAD valve 84-8A, and IRM's A and B inoperable.)
3/26 0700 Reducing thermal power due to problems with "B" reactor feedwater pump.
2100 Reactor thermal power at 71% holding due to problems with "B" reactor feedwater pump.
3/28 1445 Commenced PCIOMR from 71% thermal power.
1645 Reactor thermal pcwer at 73%, holding due to problems with "B" reactor feedwater pump.
3/29 2138 Commenced reducing thermal power for a controlled shutdown for maintenance outage.
3/30 0151 Turbine tripped from 125 thermal power because of increasing vibration.
0410 Reactor scram no. 140 manual from 25 thermal power for maintenance outage on safety relief valve 1-180, CAD valve 84-8A, 2B reactor feedwater pump and main turbine.
1600 Maintenance complete on safety relief valve 1-180.
3/31 1430 Maintenance and testing complete on CAD valve 84-8A.
2400 Unit remains in maintenance outage. Investigation continues on problem with mnin turbine high vibration bearing d6 temperature spike, and "B" reactor feedwater pump.
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8 Significant Operational Event
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Unit 3 Date Time Event 3/01 0001 Reactor thermal power at 100%, maximum flow.
3 / 06 0005-Commenced reducing thermal power for turbine control valv2 test and SI's.
0020 Reactor thermal power at 915 for turbine control valve tests and SI's.
0035 Increased thermal power to 98% holding for core limit checks.
0055 Commenced power ascension from 985.
0130 Reactor thermal power at iOO%, maximum flow.
3/07 0820 "B" CCW pump tripped reduced thermal power to 935 0845 Commenced power ascension, "B" CCW pump tagged for maintenance.
0900 Reactor thermal power at 100%, maximum flow.
3/11 2110 Commenced reducing thermal power for turbine control valve tests and SI's.
2300 Reactor thermal power at 68% for turbine control valve test and SI's.
2325 Turbine control valve test complete, holding at 68%
power for SI 4.3.B.1.a scram testing control rods.
3/12 0115 SI 4.3.B.1.a complete, control rod 38-31 did not scram test satisfactorily, i
0135 Control rod 38-31 tagged out for maintenance.
Increasing thermal power for SI 4 3. A.2 control rod exercise.
l 0500 control rod exercise complete, holding reactor power at 76% for maintenance on control rod 38-31.
0945 Maintenance and testing' complete on control rod 38-31 commenced power ascension.
1400 Reactor thermal power at 100%, maximum flow.
9 3/16 0650 Commenced reducing thermal power for removal of "C" Reactor Feedwater Pump from service for maintenance.
l 1000 Reactor thermal power at 80%, "C" reactor feedwater pump l
out of service for maintenance, reducing thermal power.
l 1200 Reactor thermal power at 78%, for maintenance on "C" reactor feedwater pump maintenance.
1800 Reactor thermal power at 795, "C" reactor feedwater pump limiting power.
2200 Reactor thermal power at 80%,
"C" reactor feedwater pump limiting power.
2400 Reactor thermal power at 78%,
"C" reactor feedwater pumi s
limiting power.
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9 Significant Operational Event Unit 3 Date Time Event 3/17 0100 Reactor power at 79%,
"C" reactor feedwater pump limiting power.
0810 "C" reactor feedwater pump in service, commenced power ascension.
1010 Commenced PCIOMR from 935 thermal power.
1900 Reactor thermal power at 1005, maximum flow.
3/18 1900 Reactor thermal power at 99%, maximum flow, rod limited.
3/19 1355 Commenced reducing thermal power, reactor zor.c fans will not run in fast speed, causing an increase in main steam tunnel temperature. (Reactor zone fans would not run in fast due to a loose linkage on fan discharge damper FCO-64-14 causing damper to close when fans are placed in fast speed.)
1600 Reactor thermal power at 61% holding due to reactor zone fan isolation.
1635 Reactor zone fans back in fast speed, commenced power ascension.
2315 Commenced reducing thermal power from 95% for recircula-tion pump M.G. set brush replacement.
3/20 0100 Reactor power at 51% for brush replacement on "A" recir-culation pump M.G. set.
0200 "A" recirculation pump back in service, increased thermal power to 59%.
0225 "B" recirculation pump M.G. set out of service for brush replacement, decreasing thermal power.
0300 Reactor thermal power at 49% for "B" recirculation pump M.G. set brush replacement.
0335 "B" recirculation pump back in service, commenced power ascension.
1900 Commenced PCIOMR from 81% thermal power.
l 3/21 1900 Reactor thermal power at 100%, maximum flow.
l 2320 Computer out of service, decreasing thermal power.
l 2400 Reactor thermal power at 985, computer limited.
3/22 0820 Computer back in service, increased thermal power to 100%.
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10 Significant Operational Event
- Unit 3 Date Time Event 3/26 0300 Commenced reducing thermal power for turbine control valve test and SI's.
0315 Reactor thermal power at 925 for turbine control valve test and SI's.
0345 Turbine control valve test and SI's complete, commenced -
power ascension.
0500 Reactor thermal power at 100% maximum flow.
1952 Commenced reducing thermal power due to high back
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pressure.
2010 Reactor thermal power at 935, holding due to high back pressure. (High back pressure due to a cheared pin in intake tunnel drain valve.)
2038 Tunnel drain valve repaired, back pressure =Laillized, commenced power ascension.
2100 Reactor thermal power at 100%; maximum flow.
3/29 2359 Computer out of service, reducing thermal power.
3/30 0200 Reactor thermal power at 995, computer limits.
1345 Computer back in service, increased thermal power to 100%, maximum flow.
3/31 2400 Reactor thermal power at 100%, maximum flow.
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11 AVERAGE DAILY UNIT POWER LEVEL s
50-259 DOCKET NO.
r m s Ferry-1 UNIT DATE 4-1-83 COMPLETED BY Ted Thom-TELEPHO' E 205/729-0834 N
MONTH March 1983 DAY AVERAGli DAILY POWER LEVEL DAY AVERAGE D AILY POWER LEVEL (MWe Neil (M'Sc. Net)
'973 904 g7 2
969 18 936 965
.3 19 824 4
961 20 916 955 921 5
21 950 927 6
7 23 938 921 g
24 9
937' 917 25 940 912 10 933
,g 904 27 925 902 12 23
.927 909 13 29 921 881 g.:
3g 922 892 15 16 t
l' INSTRUCTIONS On this format.hst the eeuge daily unit power lesel in MWe Nel for each da) in the reporting month. Cornpute o the nearest whole negawatt.
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12 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-260 UN!T ' Ercwns Ferry-2 4-I-83 DATE Ted Thom-CO\\fPLETED BY TELEPlf0NE 205/729-0834 MONTil March s
DAY AVERAGE-DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL
~(3fwe.Neg)
\\
(. fWe Net) 1
-6 17
-7 I
2
-6 1S
-18
-7 3
19
-9
-7 117 4
20 170 5
6
-7 380 22
-6 518 7
23 8
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492 24 9
-7 684 25-
-7 763 10 26 II
-8 27 745 I$-
-9 759 23 13
-9 753 29
-9 7-14 30
-10
~9 15 31
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e-INSTRUC Tf 0NS On this f orinat.!ist the aserage dailv i. nit power lesel in 11we Ne li'r each day in the icp..itn~g in. nth. Cuniputt tai the nearest whole megaw.itt.
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13 AVERAGE DAILY UNIT POWER LEVEL 50-296 DOCKET NO.
Browns Ferry-3 g.lT 4/1/83 g,y Ted Thom-COMPLETED BY 205/729-0834-TELEPHONE
.v MONTH March 1983 DAY-AVERAGEDAILY POWER LEVEL DAY AVER AGE DAILY PO\\yER LEVEL (MWe-Net)
(MWe-Net) 1068 948
,7 1068 33 1071 2
1066 993 3
,9 q
1067 758 4
g 1067 987 5
21 10,62 1046 6
1065 1050 7
23 1052 1057 g
24 1061 1054 9
5 1069:
1043 l '
1027.
1051 10 26 3
932 1053
}
1066 1062 113 29
,4
-1064 1038 30 1060 1056 15
.t l 910 16 l~
l INSTRUCTIONS On this forraat, list the aver. ige daily unit power lesel in ilWe-Net for caeli tlay in the reporting in. nih. Coinpute to the nearest whole mepwatt.
(9/77)
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14 OPERATING DATA REPORT DOCKET NO. 50-259 DATE 4-I-83 COMPLETED BY T. Thon TELEPHO.NE 205//a -u834 OPERATING STATUS
- 1. Unit Name:
Browns Ferry - 1 Notes March 1983
- 2. Reporting Period:
- 3. Licensed Thermal Power (MWt):.3293 I152
- 4. Nameplate Rating (Gross MWe):.
1065 S. Design Electrical Rating (Net MWe):
- 6. Maximum Dependable Capacity (Gross MWe): 1098.4 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 N/A
- 9. Power Lesel To which Restricted. If Any (Net MWe)N/A
- 10. Reasons For Restrictions.lf Any:
This Month Yr.-to.Date Cumularise
- 11. Hours In Reporting Period 744 2160 75,962
- 12. Number OfIlours Reactor Was Critical 744 1,998.92 49,388.46
- 13. Reactor Resene Shutdown llours 0
47.71 5,785.02
- 14. liours Generator On.Line 744 1 ~ 956.1 -
48.356.22
- 15. Unit Rewne Shutdown llours 0
0 0
- 16. Cross Thermal Energy Generated (MWil) 2.166.660 5.827.056 137.600.060
- 17. Gross Electrical Energy Generated (MWil) 708.440 1,929,690 45,330,410
- 18. Net Electrical Energy Generated (MWil) 687.321' l.873.352 44.023.131
- 19. Unit Senice Factor 100 90.6 63.8
- 20. Unit Availability Factor 100 90.6 63.8
- 21. Unit Capacity Factor (Usim: MDC Net) 86.7 81.4 54.4
- 22. Unit Capacity Factor (Using DER NeD 86.7 81.4 54.4
- 23. Unit Forced Outage Rate 0
9.4 23.9
- 24. Shutdowns Scheduln) Oser Next 6 Months (T)pe. Date,and Duration of Each t:
REFUEL SCHEDULED 4/15/83
- 25. If Shut Down At End Of 1(eport Period. Estimated Date of Startup:
- 26. Units in Test Statuq Prior to Conunercial Operation):
Forecast Achiesed INITIA L ClllilCA LITY INIII \\ L 1:1.1 C IRICI TY CDM\\1ERCl \\ L OPER AIlON (4/77)
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OPERATING DATA REPORT DOCKET NO. 50-260 DATE 4-1-83 COMPLETED BY Ted Thom TELEPlf0NE 205/729-0834 OPERATING STATUS Bro m h m -2 Notes
- 1. Unit Name:
March 1983
- 2. Reporting Period:
' 3. Licensed Thermal Power (Mht):. 3293 1152
- 4. Nameplate Rating (Gross MWe):
1065
- 5. Design Electrical Rating (Net MWe):
- 6. Maximum Dependable' Capacity (Gross MWe): 1098.4 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 N/A
- 9. Power Lesel To Which Restricted. If Any (Net MWe):
A
- 10. Reasons For Restrictions.If Any:
This Month Yr.-to Date Cumulatise
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l1. Hours In Reporting Period 744 2160 70,903
- 12. Number Of Hours Reactor Was Critical 284.25 284.25 43,577.72 2.0 2.0 13,686.82
- 13. ' Reactar Resene Shutdown liours
- 14. Hou s Generator On-Line 230.47 230.47 -
42,205.92
- 15. Unit Resene Shutdown flours 0
0 0
- 16. Gross Thermal Energy Generated (MWil) 395,518 395,518 120,,875,858
- 17. Gross Electrical Energy Generated (MWil) 133,720__
133,720 40,158.628
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- 18. Net Electrical Energy Generated (MWil) 125,833 125,833 38,998.908 l
19.- Unit Service Factor 31.0' 10.7 59.5' l
- 20. Unit Availability Factor 31.0 10.7 59.5 I.
- 21. Unit Capacity Factor (Using MDC Neti 15.9 5.5 51.6 l
- 22. Unit Capacity Factor (U>ing DER Neti 15.9 5.5 51.6
- 23. Unit Forced Outage Rate 19.3 19.3 27.I
- 24. Shutdowns Scheduled Dict Nest 6 Month <Ilype. Date.and Duration of Eachi:
l
[.
- 25. If Shnt Down At End Of Report Period. Estimated Date of Startup:
- 26. Units In Test Status (Prior to Commercial Operationl-forecast Achiesed INiil \\ L CRITICA LITY INIII A L ELECTRICITY CO\\lMERCI A L OPER A TION l
(9/77)
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"T OPERATIN' G DATA REPORT DOCKET NO. 50-296 DATE 4-1-83 C051PLETED BY Ted Thom TELEffiONE 205/729-0834 OPERATING STATUS Note 5 Browns Ferry - 3
- 1. Unit Name:
March 1983
- 2. Reporting Period:
3293
- 3. Licensed Thermal Power (51% t):
- 4. Nameplate Rating (Gross Nlwe). ' 1152 1065
- 5. Design Electrical Ratihg(Net MWe):
1098.4
- 6. Slaximum Dependable Capacity (Gross alWe):
1065
- 7. hlaximum Dependable Capacity (Net SlWe):
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Gi'e Reasons:
N/A i
- 9. Power Level To which Restricted. If Any (Net MWe):
N/A N/A
- 10. Reasons For Restrictions,If Any:
I This alonth.
Yr..to Date Cumulatise 744 2,160 53,328
- 11. liours In Reporting Period 744 1,716.30 39,328.58
- 12. Number Of Ilours Reactor Was Critical
- 13. Reactor Reserve Shutdown !!ours 0
443.70 3,815.85 l
744 1,690.43 38,464.49
- 14. Hours Generator On-Line j
- 15. Unit Rewrve Shutdown I!ours 0
0 0
- 16. Gross Thermal Energy Generated (51Wil) 2,355.833 5,318.189 114,654,293
- 17. Gross Electrical Energy Generated f 51Wil) 786,390 1,771,390 37,811,180 l
767,136 1,722,105-36,703,009 l
- 18. Net Electrical Energy Generated (atWil)
- 19. Unit Sersice Factor 100 78.3 72.1 f
100 78.3 72.1 l
- 20. Unit Audability Factor 96.8 74.9 64.6
- 21. Unit Capacity Factor (Using NtDC Neti
- 22. Unit Capacity Factor (Using DER Net) 96.8 74.9 64.6 0
21.7 17.6 1
- 23. Unit Forced Out. ige Rate
- 24. Shutdowns Scheduled Oser Nest 6 Slonths (Type. Date yid Duration of Eacht:
s
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
- 26. Units in Test Status IPrior to Commercial Operation):
Forecast Achiesed INillA L CRITICA LI TY INITIA L I:LECTRICITY CO\\1%IERCIA L OPf R ATION l
I (4/77)
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1 UNIT SifUTDOWNS AND POWER REDUCTIONS
. DOCKET NO. 259
.4 UNIT NAME Browns Ferry-1 DATE 4-1-83 i
REPORT MON 11g March 1983 COMPLETED BY -- Ted Thom TELEP!IONE 205/72940834 I
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'F B
Deratdd for recirculation motor-generator. set. brus'.. replacement.
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2 3
4 F: Forced Reason:
Method:
Exhibit G - Instructions S-Scheduled A.Eiguipment Failure (Explain)
!. Manual f.ir Preparation of Data Il-Maintenance or Test 2 Manual Scram.
Entry Sheets for 1.icensee C. Refueling i :
N 3 Autongeic Sce'am.
Even't Repers t Li R) File (NUHl:G-4 D-Regulatory Restriction 4-Other (Explaini m -
0161I t
1 E-Operator Training & License Ebmination F Administrative 5
G-Operattoi>al Eiror (E splain)
Eshibit I Sanne Source p)/77) li Other ( E splain) f*
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s DOCKET NO. 50-260 UNITSilUTDOWNS AND POWER REDNC1)ONS UNIT NAME Browns Ferry-2 DATE. 4-1-83 M##CU COMPLETED BY Ted Thom REPORT MONTil TELEPflONE 205/729-0834
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Licensee
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3 hYh Cause & Currectise No Date i
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Action to jE j di g Report c r$ U H
j' Present Recurrence b
F 243 3/1/83 S
457.75 11 2
EOC-4 refuel outage continues 244 3/20/83 S
0.70 B
Tripped main turbine for overspeed trip test'(no reactor scram) 245 3/20/83 F
8.93 11 Manually tripped turbine on false high temperature alarm on turbine exhaust hood (no reactor scram) g 246 3/20/83 F
11 Derated for turbine exhaust hood high temperature alarm 247 3/30/83 F
2.32 11 Turbine trip on high vibration 248 3/30/83 F
43.83 A
Reactor scram for maintenance on safety relief valve 1-180, CAD valve 84-8A, 2B reactor feedpump and main turbine I
2 3
4 F: Forced Reason:
Metimd:
Exhibit G -Instructions S: Scheduled A Equipment Failure (E3riain) 1 Manual for Preparation of Data ll Maintenance of Test 2-Manual Scrarn.
Entr> Sheets for Licensee C. Refueling 3.Autunutic S6 ram.
. Esent Report (LERI file (NtlRI:G.
D-Regularory Restriction 4 Other (Explain) 0161)
F. Operator Training & License Examination F.AJministratr.c 5
G-Operational Error (Explain)
Eshibit !- Same Source (9/77) li Other ( Explain )
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UNIT SilUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-296 UNIT NAME Brcuns Ferry-3 i
DATE 4-1-83 COMPLETED BY Ted Thom REPORT MON fH March TELLPHONE 20 5 / 729-0M4 g
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3.,
Present Recurrence
.:: E :{
00 m
Q m
125 3/11/83 S
B Derated'for turvine CV tests and_ sis.
126 3/16/83 F
B Derated for maintenance on "C" reac-f
' tor feedpump.
~'
x 12L 3/19/83 F
11 Derated due to reactor zone ventila-tion fan isolation.
N.
128 3/19/83 F
B Derated for "A" and "B" recirculation e
pump motor-generator set brush replacement.
+
~
2 i
I 2
3 4
F: Forced Reason:
Method:
Exhibit G-Instructims S. Schedu!cd A-Equipment Failure (Explain) 1-Manual for Preparation of Data H Maintenance or Test 2-Manual Scram.
Entr> Sheets for Litensee i
C-Refueling 3 Automatic Suam-Esent Report Itt:RI File INURI.G-D-Regulatory Restriction 4-Other (Explain )
0161) j E-Operatur Training & License Examination F-Adrainist rative 5
i G-Opc ational Error (Esplain)
- 1 shibit I - Same Source l
I"/77) 11 Other (Explain) i
~
Y
~
- :_f' BROWNS FERRY NUCLEAR PIANT UNIT 1
~CSSC-EOUIFMENT a
~ " - 5
,{..__
~
~
-___ c. MECHANICAL MAINTENANCE SUNMARY
~~~
For the Month of -March 19 83
-~ _.
EFFECT ON SAFE ACTION TAKEN i
DATE SYSTEM COMPONENT NATURE OF OPERATION OF "CAUSE OF RESULTS OF
'ID PRECLUDE MAINTENANCE
~~' IRE REACTOR MALFUNCTION -
MAI. FUNCTION RECURRENCE fatilty filter faulty filter causing changed filters, 3-12 CRD..
CRD pump A, change.. filter none.- _
high AP installed new one suction filter MR0 62893
_j_
3-13 CRD CRD pump A change filter none faulty filter high AP across filter insts11ed new filter discharge MR# 62267 filter 7
~~
~
3-11 Radwaste FSV-77-15A faulty iso-none valve dirty and valve will not cycle' disassembled, cleaned lation-valve ing in need of clean-to time and reinstalled 3-02 control valve 32-305 valve non-none broken nipple air intake exhaust replaced broken
- - j Air nipple funcitonal connection loose ulpple MR# 74039 w
O 9
m e
i ay l
'J j,
j k
J
. - BROWNS FERRY NUCT "*R PIANT UNIT 2
~
. ~
e-
- MEGIANICAL MA' NANCE
SUMMARY
-CSSC a
' MENT
.+
n'-
For the Month of I!srch 19 83 EFFECT ON SAFE ACTION TAKEN DATE SYSTEM COMPONENT NATURE OF OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE MAINTENANCE illE REACTOR MALFUNCTION MAIFUNCTION RECURRENCE 3-8 HPCI root valve,
valve-not.
Eone.
valve stem broke valve inoperable.
installed new vsive 73-206A fun c tioning __..
off.
sten g
properly.
MR# 61742 3-31 CAD FSV-84-8A CAD not operating'
.none dirty valve needs valve inoperable cleaned, lubricated, valve cleaning and rewelded. body, put
~~
u lubricating back on line
'~. -
MR# 60665 3-31 CRD IICV-85-617 valve blockage none broken lifting valve inoperable installed n.w lif ting; module 10-39 rod will not ears on wedge ears on wedge scram both sides MR# 58999 3-25 HPCI Gland seal assemble
_none unknown nonfunctional asse:nbled exhauster exhauster motor exhauster moton motor asst, elec tricians
'd MR# 60613 3-31 HPCI FCV-73-16 stem packingf none worn packing water leak replaced packing leak MRf 60622 3-28 CRD CRD pump 2A pump inoperable none inboard seal water leak replaced nipple on water line leak-seal water line ing from faulty MR# 129608 nipple
.h30 CRD CRD pump 2A water leak at none nipples and 90's water leak repinced nipples and seal line elbow joint faulty 90's with nev material MR# 129664 J-25 HPCI glend seal worn gasket none faulty top gaske; gasket nonfur.ctional replaced gland seal condenser head needs replacin g condenser gasket gasket MR# 129733.
r
.i Q.
3
.= r: z 2
=-
~
l
_7 BROWS FERRY NUCLEAR PIANT UNIT 3
l,
~..
MECIIANICAL MAINTENANCE
SUMMARY
CSSC EQUIPMEliT, d.
For the Month of March 19 83 EFFECT ON SAFE ACTION TAKEN DATE SYSTEM COMPONENT NATURE OF OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE MAINTENANCE T'IE REACTOR MALFUNCTION M\\LFUNCTION RECURRENCE
~
3-7 Radiation CAM 90-256 check for none faulty restrainin; air leakage fabricated & installed monitoring leakage bracket new restraining bracket' MR# 63265 3-25 LPCI 3EN LPCI MC worn coupling none coupling running coupling not fune-installed new coupling Set without proper tioning properly MR# 28344 lubrication
'~~'
3-4 CO, storagt FCV-39-35 leak none worn cup packing air leak replaced valve cup
& Yire packing protection MR# 59167 3-7 Core Spray IICV-75-539C repair faulty none bad bonnet valves not function-replaced bonnet
~
IICV-75-540C valves ing properly MR# 63974 t
3-26 CRD module 22-03 leak none worn'o' ring nitrogen leak replaced o' ring y
MR# 129235 3-25 Radwaste FCV-77-2A valve not none valve dirty nonfunctional disassembled valve, operating needs cleaning cleaned and replaced MR# 58990 9
m
_ ~..
1 1
k
.-f - --..-.
~_
~ - ~ _
'- BROWNS FERRY NUCL"** PIANT UNIT Common
- ' * - '.,.. yW ]q,
.y.-...,
^"'-
CSSC* E._
MENTA- " a-
.. W_. -M-. MECIANICAL HA '
.iANCE
SUMMARY
~'
M rch 19 83
~
i For the Month of
~
EFFECT ON SAFE ACTION TAFIN DATE
'SYS5EM COMPONENT HATURE OF OPERATION OF CAUSE OF RESUL*IS OF
- IO PRECLUDE.
MAINTENANCE THE REACTOR MALFUNCTION
~ MALFUNCTION RECURRENCE l-2 Diesel A air comprus'so r gasket needs
- none high pressure compressor inopera-replaced gasket on Generator 1-0 D/G replacing -
head gasket tional high pressure head I
blown MR# 63149 l-21 Diesel A air compresso e gasket needs-none high pressure compressor inoperable replaced blown head Generator 1-C D/G replaced head gasket gasket blown MR# 62260
-22 Diesel G 2C #1 air air lejiking none faulty pressure air leak replaced pressure Generator compressor around gasket switch switch
~
j at bottom of
~
switch 3-21 Diesel D/G 2C #1 air relief-valve none faulty high air compressor not replaced high pressure l Generator compressor not seated pressure head functioning properly heac gasket 4
off gasket MR# 129603 y
3-23 Diesel 3D diesel air head gasket none head gasket air leak of air replaced head gasket-Generator compressor B blown blown compressor.
on high pressure side MR# 60637 3-18 Diesel 3D diesel air head gasket none head gasket air leak of air replaced high Generator compressor A blown blown compressor pressure head gasket p
MR# 74018 3-23 Diesel A air compresso c head gaskets none blown head air Icak replaced head gaskets Generator 3D diesel blown gaskets MR# 60638 generator
'9 f
W
- e4m, e
ga u
T 4
l
BROWNS FERRY NUCLEAR PLANT UNIT 1 nnd Common ELIL 30 CSSC EQUIPMENT ELECTRICAL MAINTEMitNCE SUb!ARY Appendix B 9/Z9/82 For the Month of March 19 83 Effect on Safe Action Taken Nature of Operation of Cause of Results of To Preclude Dare System Component Maintenance The Reactor Malfunction Malfunction Recurrence
/28/83 Unit Unit perferred on 1/28/83 None A bad solder joini. Unit I tripped due The capacitor was Perferred MMG set over-Unit pet-ferred on a capacitor on
'to the loss of the replaced on the pilowup:
120 volt voltage relay.
MG set tripped the OVR relay unit perferred MG OVR relay board.
{ectrica ference AC board resulted in set.
The MG set was l
lost field excit-tested and operated 11ntenar -
ation and trip of properly.
the unit preferret MR# A-061507 immary inuary fi3 MG set cutput MR# A-061509 breaker.
'13/83 Air IA control bay Control bay None Bay 12AV7 and Control bay chiller Replaced the bad Condition-chiller temp-chiller tripped 12AX7 temperature inoperable, tubes and the ing.
erature con-controller tubes, chiller was returned (IIca ting-troller.
l to service.
Cooling)
MR# A-063402 t
i i
+
BR0b'NS FERRY
~ EAR PIlliT UNIT 1 and dommon Page 3 BF EMSIL 30 CSS-mQUIPMENT_
ELECTRICAL nAINTENANCE SINIARY
^EE#"
9/29/82 For the Month of March 19 83 Effect on Safe Action Taken Nature of Operation of Cause of Results cf To Preclude Date System Component Maintenance The Reactor Malfunction Malfunction Recurrence
'17/83 Diesel Diesel Genera-During t,he None The ESTD relay The diesel generator The ESTD and FCR Generators tor "C" relay performance of was dropping out did not stop after relays were replaced ESTD EMI-3 D/C "C" in 10 minutes the normal 11.5 and the diesel gen-failed to time (opposed to the-minutes coast down erator successfully out properly, required 15
- period, operated per minutes) which SI 4.9.A,1.D kept ECP, relay MIJ# A-062977 fro.a stopping MR# A-06149 8 the diesel i
f generator.
18/83 CRD l-PCV-85-23 CRD drive water NONE Thermal overload 1-PCV-85-23 Adjusted thermail,
overloadto1157.yl water pressure setting was too (inoperable) control valve
- low, tripping out, valve operated l-PCV-85-23 properly.
tripping on MR# A-063529 l
thermal over-
}
load.
i I
e i
e l
i
+
4
BROWNS FERRY NUCLEAR PLANT UNIT land dommon Pag 3 CSSC EQUIPMEMT ELECTRICAI.MAINTEMANCESUb!ARY Appendix B 9/29/82 For the Month of. March 19 83 Effect on Safe Action Taken Nature of Operation of Cause of Results of To Preclude Date System Component Maintenance The Reactor Malfunction Malfunction Recurrence 3/22/83 Diesel "lD" diesel On 3/22/83, None, engine oil Oil pump motor Lube oil circulating The motor lead Generators generator during d'aily temperature had' leads were short-
" pump inoperable wiring was replaced lube oil inspection, it not dropped ing together due requiring D/G ID and all connections c ircula t ing was discovered below its alarm to the breakdown to be taken out of at the motor were
- pump, that the ID setpoint.
of the insulating service for repairs.
retaped.
D/G lube oil Therefore the tape on the motor LER#BFRO-50-259/831 7 circulating diesel was le d connections MR#A-062949 pump motor had
- operable, flowever, tripped.
the diesM generator was made inoperable for repairs to oil pump, h
Operations None on inspec-Relay coil was Required relay to be The relay coil was The relay personnel tion, the relay
- burned, taken out-of-service replaced and the provides noticed was found to be for coil changcout.
relay returned to automatic discoloration energized but it service.
operation of on glass face appeared the MR# A-129951 FCV-74-7 of relay relay coil was 10A-K108A on the verge of failing. When p-the relay was taken out-of-service, FCV-74-7 could have been manually operated by HS-74-7A ir 78.
i f
i I
4 4
e j
Page 3 BROWNS FERRY *
~ EAR PLA!!T UNIT _.2___ _ -
LF EMSIL 30 C A cQUIPMENT ELECTRICAL c1AINTEI!A!!CE SU$1ARY Appendix B 9/29/82 For the Month of March 19 83 Effect on Safe Action Taken Nature of Operation of Cause of Results of To Preclude
_nate System Cornenent Maintenance The Reactor Malfunction Malfunction kecurrence 2/26/83,CRD CRD drive The valvp was None, valve was Loose break Excessive noise Tightened break pressure ma#ing excessivt operable and assembly.
during valve assembly, performed control valve nosTe during the unit was in operation.
EMI-18.
The valve
^
(2-PVC-85-23) operation.
refueling outagc operated properly.
MR#A-063717 e
f I
B/4/83 HPCI Level Switch IIPCI condensate None LS-73-15B was Condens' ate pump Adjusted the level (2-LS-73-15B) pump would not out of adjust-would riot shut off switch per EMI-57.
shut off on 1
ment.
at low water level.
MR#A-061192 low level.
,w Y
3/5/83 Rh'.SW 2-HCV-23-49 The valve None Limit switch Control room indicat-The NAMCO SAI-2 limit switch position indica-contacts and ing light for this limit switch is ting light was mechanical valve was inoperable obsolete. The limiL inoperable, plunger was switch was replaced corroded from with a CE switch on moisture.
TACF 2-83-02P ratil a NAMCO replacement P
can be obtained.
MR#A-063645 i
i i
i i
BROWKS.FERRhNUCLEARPLANTUNIT
'E' 2
BF EMSIL 30 CSSC EQUIPMENT ELECTRICAL MARITENANCE SUEMARY
^EE*"
9/29/82 For the Month of March 1983 Effect on Safe Action Taken Nature of Operation of-Cause of Results'of To Preclude' Date System Component Maintenance The Reactor Malfunction Malfunction Recurrence j
3/6/83 IRM IRM "D" IRM "D" channe L None Bad coil on rela)
IRM "D" channel Replaced the bad channel drive would not move CR120A.
- would not drive.
relay coil. The logic select IRM channel relay CR120A.
Operated properly.
MRB060298 3/9/83 RHR 2-FCV-74-97
.During the None, the Water in local 2-FCV-74-97 Rebuilt local local control performance valve could control system, local. control control station.
station.
of S1 3.2.10 have been-station inoperable.
MR# 062890 valve fail.ed electrically to operate operated by from the local sw' itching a
control XS-74-97 to
- station, emergency and l
operating the valve with HS-74-97C.
The valve could also have been operated i
- manually, f
1 i
i m
i Page 3 BROWNS FERRY '
EAR PLANT UNIT BF EMSIL 30 CSL c'QUIPMENT ELECTRICALriAINTENANCESU$1ARY App;ndix B 9/29/82 For the Month of - March 19 83 Effect on Safe Action Taken Nature of Operation of Cause of Results of To Preclude Date System Component Maintenance The Reactor Malfunction Malfunction Recurrence
/2/83
- HPCI, Limit switches Indicating None, Unit was.
Normal end of Valve position The limit switch to RHR for the lights for in refueling limit switch life, indicating lights for 2-HCV-73-23
/9/83 and Core following listed valves outage.
water in switch, for the listed valves was adjusted. The Spray valves:
were not adjustment, or were inoperable or limit switches for cooling.
operating operator cable stuck in one position.the remaining valves HPCI properly.
damaged.
wbre replaced.
2-FCV-73-18 I
2-FCV-73-19 MR Numbers 2-HCV-73-23 A-061646 2-HCV-73-25 A-061179 A-061180 RHR A-061598 2-HCV-74-22 A-063746 e
i 2-HCV-74-33 A-061206 5
1 2-HCV-74-90 A-061203 A-061202 CORE SPRAY C:'OLING l
2-HCV-73-17 P
Y g
- E' BROWNS FERRY NUCLEAR PLANT UNIT 2 BF EMSIL 30 CSSC EQUIPMENT ELECTRICAL MAINTEMANCE SU[D!ARY Appendix B 9/29/82 For the Month of March 19 83 Effect on Safe Action Taken Nature of Operation of Cause of Results of To Preclude Date System Component Maintenance The Reactor Malfunction Malfunction Recurrence
- /11/83 Air IA control The chiller None Bad FYZA-115-1 The chiller would Replaced the Condition-by chiller, was not.
control relay.
,not unload properly, bad control relay ing.
unloading and performed (Cooling-properly.
EMI-60.
The Heating) chiller operated properly.
MR# 061647 1/17/83 CRD Scram Received an None, control An inline splice Received an alarm in The level switch accumulator alarm in the rod 38-47 was in the wiring the control room.
was replaced.
level switch control room, at, position f3, to the scram Twelve other for hydraulic This alarm the level switch accumulator switches were d, instrument is common for failed in the switch had inspected for block for low nitrogen safe / alarm shorted to missing sleeves-control rod.
pressure or direction, and ground because with none found.
38-47 water indica-
.the reactor the insulating MR# 074065
- tion, was not in sleeve was Fm# 062639 power operatior missing.
f s
).;
~
i j
t i
BROWNS. FERRY '
EAR PLANT UNIT 2
BF EMSIL 30 CSSc c.QUIPMENT ELECTRICAL MAINTENANCE SU[D!ARY Appendix B 9/29/82~
. For the Month of March 19 83 Effect on Safe Action Taken Nature of Operation of Cause of Results,of To Preclude Date System component Maintenance The Reactor Malfunction Malfunction Recurrence i
i/19/83 CRD Insert sole-The solenoid None Loose plug
..,The insert solenoid Tightened loose noid for CRD would not connection.
would not operate.
plug connection 14-19 operate.
and the solenoid' operated properly.
MR# 060749 i
- s I
l/19/83 HPCI EGM control Problems were IIPCI Inoperable The 'llPCI factory llPCI inoperable.
'The ECM control,
+
(Electronic encountered representative was' replaced 3
governor with the llPCI suggested the during trouble 8 control) speed control, problem was air shooting per Turbine was in the hydraulic mechaincal main-unstable.
system.
tenance request.
This was not-the
. problem.' Any recurrence control will be addressed by mechanical y
maintenance.
MR#'A-060748 P
i 1
i i
i.-
BROWNS. FERRY NUCLEAR PLANT UNIT 2
BF IL 30 CSSC EQUIPMENT ELECTRICAL MAINTEMANCE SU$L\\RY Appendix B 9/29/82 For the Month of.Fbrch 19 83 Effect on Safe Action Taken Nature of Operation of Cause of Results of To Preclude Date Systen Component Maintenance The Reactor Malfunction Malfunction Recurrence 3/20/83 !!PCI IIPCI gland seal Gland soal
- one Bad motor Gland seal condensor Replaced the blower condensor condensor blower inoperable.
motor per EMI-33.
blower motor.
blover motor On 3/25/83 the inoperable.
blower " running" indicating light in the control room failed due to a loose socket. The socket was tightened and the indicating light operated properly.
HR# A-074106 8
MR# A-129704 da i
7 1
I P
I 5
'. - i i
i i
r
- E EROWNS FERRY
- EAR PLANT UllIT 3
BF D!SIL 30
_CS5v r.QUIPMENT ELECTRICAL t:AINTENANCE SU$1ARY Appendix B 9/29/82 For the Month of -March 19 83 Effect on Safe Action Taken Nature of Operation of Cause of Results of To Preclude Date System Component Maintenance The Reactor Malfunction Malfunction Recurrence i
/8/83 IIPCI IIPCI gland A 200 volt d-c None, inopers-The motor windings The pump motor was The notor was seal condensor ground was bility of this were shorted due
-inoperable.
replaced per EMI-condensate detected on the pump does not to water.
33 and the pump pump motor.
- 3,250 volt make the IIPCI returned to service, battery inoperable.
MR# A-064331 a
r I
4 O
N 8
Y i
8
I 8
BROWNS FERRY DUCLEAR PLANT UNIT 3
L 39 CSSC EQUIPMENT ELECTRICAL MAINTEEARCE SUb!ARY PPindix B 9/29/82 For the Month of ' March 19 83 Effect on Safe Action Taken Nature of Operation of Cause of Results of To Preclude Date System Component Maintenance The Reactor Malfunction Malfunction Recurrence c
2/25/83' Fire Battery with During.the None Natural cnd-of-
., Specific gravity The batteries were Protection cells 7 performance life for these readings did not replaced and EMI-through 12 of EMI-4 the batteries.
meet the establishet 4 performed.
in panel listed acceptance criteria, MR# A-061437 3-25-286 batteries were MR# A-061436 and battery found to have with cells low specific 1 through 6 gravity in panel readings.
3-25-287 2/27/83 Diesel Diesel Received a None, control Bad NVR relay.
Received a false The NVR relay EMD Generator Canerator 3EB control power power was not control power "off" part number 8317487 no voltage "Off" alarm lost.
alarm.
is obsolete and nc relay (NVR) in the control longer available, room for the The relay was d, D/G 3EB.
replaced (Tem-j' porary alteration) with the vendor's' recommended replacement EMD P
part number 837075 5 This replacement relay is larger than the original relay. This re-quired a change ir the relay mounting location.
Rep: DCR no.P28: 6 MR# A-063934 f
MR# A-059092 I
i i
INSTTdHDTE l'AT"'ESANCE SUPPAAY
' CSSC EQUI FOR TdE MONill -
March 1983 NA'~JRE EFFECT OS SAFE CA"5E i
ACTICS TAk'E.
'. TE SYSTDi CCP.I G E.7 OF OPEF.AT!CN CF CF PlS'JL!S OF TO PFS '
MA TFlSANC2 T::E KJACTCk PALFC;CT!ON P.A'.FTNCT I ON l
RCCL R F1 i
1/16 90 RM-90-256 Repair None Failed Detector Incorrect output None t-2_
~
,/07 64 PS-64-58D Replace None Unknown Switch leaked None
/16 92 APRM '"E" Repair None Faulty relay Downscale light None would not clear
/30 83 TR-80-1 Repair None Open slidewire Loss of record None
-3
/01 73 TS-73-2[
Replace None*
~
Unknown Switch failed to None i
operate d
f-902 3
LI--3-4 6A -
Replace-None Unknown Erratic indication None 110 90 RM-90-250 Repair None Age No local alarm None O
e
- 8 e
~
9 0
e 4
e
~
q FIRtn SERVICES
SUMMARY
s
~'
March 1983 MaMor Work Areas A.
Refuel area - shipment of old fuel storage racks continued throughout this month.
During the first two weeks of March, 164 fuel bundles were received and unloaded for unit 1.
B.
Turbine - completed crane rail modification on March 10, 1983 and releasedtoplant.
C.
Drywell - with hydrostatic testing of RPV completed on February 28, 1983, major efforts ware made for close-out of drywell. Main steam release valve vacuum breaker modification remained on critical path.
On March 1,1983 testing of prototype was completed at Wyle Lab and manufacture of parts started immediately. Delivery of bolts for assembly and installation became very critical.
On March 8, 1983 machining of parts onsite was completed and pre-assembly continued with partial receipt of bolts.
On March 9, 1983 studs were received and installation was completed March 11, 1983. In parallel, worked last-minute design changes for pipe supports MSS-13 and H-5.
This work was completed on March 10, 1983 with several other punchlist items.
Drywell was closed March 14, 1983 and 50-PSIG test completed.
Estimation of primary containment leakage (TI-50A) was completed at 0500. hours on March 1F,1983 I
I a
_37_-
FIELD SERVICES
SUMMARY
(Continued)
March 1983 Ma ior Work Areas (Continued)
D.
Electrical - during March all unit 2 cycle 4 electrical work was com-pleted in support of the March 20 return-to-service of unit 2.
m Ihe major work performed by the electrical group was completion of all T1P work, including the TIP wattage test, and supported other work such as MSIV closure timing, STEAR 83-07, drywell blower repairs, unit 1 cycle 5 torus preparations and LPRM cable / connector repairs.
A3so, the turbine group repaired steam leak on A2 intercept valve.
In addition to the unit 2 cycle 4 work the electrical group commenced looking ahead to the unit 1 cycle 5 refueling outage by checking material availability and writing werk plans.
E.
Mechanical - completed all mechanical work in support of the March 20 return-to-service of unit 2.
i The major work completed this month is as follows:
1 1.
Completed the modification of the vacuum breakers inside drywell.
l 2.
Completed the platforma and fencing around SDIV tank, 3
Completed the hanger changes to the MSRV control air modification.
4.
Completed all drywell close-out items and closed drywell in sup-port of startup preparations.
'5 5.
Resolved all problems with P0392 hanger discrepancies.
4-*'
I g
-h
38
~
FIELD SERVICES
SUMMARY
(Continued)
March 1983 Major Work Areas (Continued)
E.
Mechanical (Continued) 6.
Started workplans, material checks, and prefabrication in support of unit 1 cycle 5.
F.
Planning and Scheduling 1.
The outage duration was revised on three different occasions during March with the final duration being 232. The reason for the delays was the modification to the drywell vacuum breakers, P0392 hanger deficiencies, heater drain valve repairs, steam packing exhauster motor "A" replacement, and A2 intercept valve steam leak.
2.
During the latter part of March the planning emphasis was placed on looking ahead to the unit 1 cycle 5 outage which is scheduled for shutdown on April 15, 1983 This effort will intensify right up to starting the outage.
G.
Torus 1.
Unit 2 Completed all torus work and released torus to plant March 14,.
i 1983 2.
Unit 1 During March, N, J, and L lapplates were installed with 60-percent completion.
ECC3 gussets were cut and welded out.
Completed installation stands at 70-percent.
Torus snubber wall brackets:
13 have undercut anchors, four brackets have been i
A.
39 FIELD SERVICES SUNNARY (Continued)
March 1983 Maior Work Areas (Continued)
G.
Torus (Continued) 2.
Unit 1 (Continued) drilled and placed on wall, base plate drilling and installation for ECCS ring header snubbers stands at 75-percent complete.
Prefabricated 117 pipe hangers in the shop.
Installed 10 base plates for torus attached piping.
Installed air line from compressor to unit 1 corvice water tunnel.
Additional preparation for unit 1 cycle 5 outage, protective barriers and temporary equipment cables for safety net were installed on unit 1 torus.
H.
Administrative - the overtime percentage for the month of February was 18-percent, with 107,826 straight time hours and 23,935 overtime hours.
As of February 28, 1983 year-to-date overtime percentage was 20-percent, 689,148 straight time hours and 177,503 overtime hours.
The overall goal of the overtime percentage is 17 percent.
The O&M budget for February was $1,825,884 and tha expenditures were
$2,942,144 with year-to-date budget being $14,614,819 and actual year-to-date expenditures being $13,175,488 The capital budget was
$2,034,025 and the expenditures were $1,030,627 with year-to-date budget being $16,096,805 and actual year-to-date expenditures being
$7,812,330.
Overall budget was $3,859,909 and the overall expendi-ss tures were $3,972,771 with year-to-date budget being $32,745,649 and actual year-to-date expenditures being $20,967,818.
W
~
NUCLEAR PLANT OPERATING STAT!STICS
'B y loNa+au Browns Ferry Nuclear Plant m
-g 744 Month March 19 83 period Hours Item i
No.
Unit No.
Unit 1 Unit 2 Unit 3 Plant
_1 Averace Hourly Gross Load. kW 952 204 SRO:206 1,056.976 947.674 2
Maximum Hour Net Generation. MWh 978 790 1072 2,694
- 3 Core Thermal Energy Gen. GWD (t)2 90.2775 16.4799 98.1597 204.9171 4
Steam Gen. Thermal Energy Gen., GWD (t)'-
8 5
Gross Electrical Gen.. MW5 708,440 133,720 786,390 1,628 550 5
6 Station Use, MWh 21_119 7.887' 19.254 48,260 h
7 Net Electrical Gen. MWh 5.&7 '121 125.833 767.136 -
1.580.290 8
Station Use, Percent 2.9R 5.90 2.45 2.96 9
Accum. Core Avg. E xpnsure, MWD / Ton!
1B_734 12.011 14.382 _ 45.127 10 CTCG This Month 106 BTU 7_289_242 1_342.499 8.041.181 16.772.92; 11 SGTEG This Mcr th, ID6 BTU 12 13 Hours Reactor Was Critical 744 284.25 744 1772.25 14 Unit Use. Hours-Min.
744 230r28 744 1718:28 15 Capacity Factor, Percent 86_7 16.4 96.2 66.4 16 Turbine Avail. Factor. Percent 100 37 3 100.
74.4 j
17 Generator Avail. Futor. Percent 1_ nn
'1R ;
100 79.5 g
0 18 Turbonen. Avail. Factor. Percent 100 32.3 100 74.4 19 Reactor Avail. Factor. Percent 100 38.5 100 79.5 2
20 Unit Avail, Factor. Percent 100 31.0 100 77.0 21 Turbine Startuos 0
2 0
2 22 Reactor Cold Startups 0
1 0
1 23 24 Gross Heat Rate, Btu /kWh 10.430 10.040 10,230 10,300 h
y 25 Net Heat Rate. 8tu/kWh 10.750 10.670 10,480 10,620 y
26 E
27 g
28 Throttle Pressure, psig 953 932 936 943 29 Throttle Temperature. *F sqq 536 537 538 d
30 Evhaust Pressure, inHg Abs.
1.27 0.98 2.00 1.55
{
E 31 Intake Water Temp., F 54.0 53.5 54.0 53.9 I
32 33 Main Feedwater, M tb7hr 11.5 7.2 13.0 11.6 i
34 I
35 l
36
~
37 Full Power Capacity, EFPD (1) 412 301 377 38 Accum. Cycle Full Power Days. EFPD(1) 467 5
263 N
39 Oil Fired for Generation, Gallons 30,834 5
40 Oil Heatina Vatue. Btu / Gal.
140,900 46.2 41 Diesel Generation. MWh 4?
Max. Hour Net Gen.
Max. Day Net Gen-Load MWh Time Date MWh Date Fac*or %
3 43 2695 2100 1/29 65.366 3/29 78.8 Remarks: IFor BFNP this value is MWD /STU and for SQNP and WBNP this value is MW9/MTU.
2(t) indicates Thermal Energy.
(1) Information provided by Reactor Analysis Group, Chattanooga I
s, Date Subn :tted March'11, 1983 Date Revised
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