ML20115C808
| ML20115C808 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 02/28/1985 |
| From: | Jones G, Thom T TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| NUDOCS 8504180573 | |
| Download: ML20115C808 (37) | |
Text
-
1ENNESSEE VALLEY AU'INORITY DIVISION OF NUCLEAR POWER
. BROWNS FERRY NUCLEAR PLANT MONTHLY OPERATING REPORT 'ID NRC February 1,1985 - February 28, 1985 DOCKET NUMBERS 50-259, 50-260, AND 50-296 LICENSE NUMBERS DPR-33, DPR-52, AND DPR-68 r'
Submitted by: J
-3
//
Plant Manager
.L E2Y 8504180573 850228 gDR ADOCK 05000259
/f eDR
1 TABLE OF CONTENTS Operations Summary.......................
1 Refueling Information.....................
3 Significant Operational Instructions.........
5 Average Daily U. sit Power Level.................
12 Operating Data Reports.....................
15 Unit Shutdowns and Power Reductions..............
18 Plant Maintenance...................'....
21 Outage Maintenance & Major Modification............
30
~ Addenda.............................
33 (Corrections to. January 1985 Report) 9
1 Onerations~9' rv February 1985 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 five reportable occurrences reported to the NRC during the month of January.
Unit 1
-There were no-scrams on the unit-during the month.
Unit 2 The. unit was in cold shutdown the entire month for the unit's end-of-cycle 5 refueling outage.
Unit "4 There was one scram on the unit during the month.. On February 9,1985, the unit was manually scranmed due to a leak in the drywell on a test line on valve 69-1.
Prepared principally by B. L. Porter.
2-Ooerations 4--rv (Continued)
February 1985 Fatinue Usane Evaluation The cumulative usage factors for the reactor vessel are as follows:
Location Usane Factor Unit 1 Unit 2 Unit 9 Shell at water line 0.00619 0.00492 0.00428 Feedwater nozzle 0.29671 0.21319 0.16022 Closure studs
, 0.23876 0.17629 0.14292 NOTE:
This ' accumulated monthly information satisfies Technical Specification Section 6.6.A.17.B(3) reporting requirements.
Common System Approximately 9.25E+05 gallons of waste liquids were discharged containing approximately 1.84E-01 curies of activities.
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3 Doerations R-r v (Continued)
February 1985 Refbelina Information Unit-1 Unit 1.is scheduled for its sixth refueling approximately June 1,1985 with a scheduled restart date of March 31, 1986. This refueling will involve
. loading 8x8R (retrofit) fuel assemblies into the core, replacing recirculation piping, work on "A" and "B" low-pressure turbine, upgrade hangers and anchors,
- and environmentally qualify instrunentations.
There are 764 fuel assemblies in the reactor vessel. The spent fuel stor-age pool presently contains 252 EOC-5 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 fuel pool capacity is 3,471 locations.
Unit 2 Unit 2 was shut down for its fifth refueling outage on September 15, 1984.
with a scheduled restart date of August 1,1985. This refueling outage will involve loading additional 8X8R (retrofit) fuel assemblies into the core, finishing torus modification, turbine inspection,. piping inspection, 'INI-2
~ modifications; post-accident sampling facility tie-ins, core spray change-out, and feedwater sparger inspection.
There are no fuel assemblies in the reactor vessel. At month end, there were 273 new fuel assemblies, 764 EOC-5 fuel assemblies, 248 EOC-4 fuel assemblies, 352 EOC-3 fuel assemblies,156 EOC-2 fuel assemblies, and 132 EOC-1 fuel assemblies in the speit fuel storage pool. The present available capacity of the spent fuel pool is 77 locations. All old racks have been removed from the pool and new HDR's are being installed, n
. s.
a.
4 Operations Sununarv (Catinued)
February 1985 Unit ~4 Unit 3 is scheduled for its sixth' refueling outage approximately November 30, 1985,-with a scheduled restart date of Novenber 10, 1986. This refueling involves ~ loading 8X8R (retrofit) assemblies into the core, and complete reinspection of stainless steel piping.
There are 764 fuel assemblies presently in the reactor vessel. There are 248 EOC-5 fuel assemblies, 280 EOC-4 fuel assemblies, 124 EOC-3 fuel assemblies,144 EOC-2 fuel assemblies, and 208 EOC-1 fuel assemblies in the spent fuel storage pool. The present available capacity.of the spent fuel pool is'914 locations.
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5 Sianif'icant Ooerational Events -
Date Tima Event Unit 1 2/01/85 0001 Reactor thermal' power at 100-percent (5), maximum flow, rod limited.
1730 Commenced reducing themal power for Control. Rod Drive (CRD) Exercise (Surveillance Instruction (SI) 4.3.A-2).
1800-Reactor thennal power at 975 for CRD Exercise.
1910 CRD Exercise complete, commenced power ascension.
1930 Reactor thennal power at 1005, maximum flow, rod limited.-
2/03/85 0700 Reactor thennal power at 995, maximum flow, rod limited.
2/04/85 2200 Reactor thermal power at 985, maximum flow, md limited.
~
2/06/ 85 2200 Reactor thermal power at 975, maximum flow, rod. limited.
2/09 0745 Commenced reducing thennal power 'for ST-8501 (Single Recirculation Loop Operation).
0950 "B" recirculation pump out-of-service for ST-8501, reactor thennal power at 47%.
1030 Commenced power ascension with "A" recirculation pump for ST-8501.
1200 Reactor thennal power at 59% for ST-8501..
1230 Coimnenced inserting control rods for ST-8501.
1243 Reactor thennal power at 54% for ST-8501.
1329-Commenced' power ascension with rod withdrawal for ST-8501.
1335 Reactor thermal power at 60% for ST-8501.
1337 Coimnenced reducing thermal power with recirculation flow for ST-8501.
1345 Reactor thennal power at 50% for ST-8501.
1354 "B" 4ecirculation pump back in service, commenced power ascension for ST-8501.
~1450 ST-8501 complete, commenced power ascension from 84%
thennal power.
2030 Commenced PCIOMR from 955 thermal power.
2/10 0030 Reactor thennal power at 995, maximum flow, rod limited.
0700 Reactor thermal power at. 985, maximum flow, rod limited.
1200 Reactor thennal power at 975, maximum flow, rod limited.
2400 Reactor thennal power at 965, maximtzn flow, rod limited.
6 Sinnif'icant Ooerational Events Date Tima Event Unit 1 (Continued) 2/11 1500 Reactor thermal power at 955, maximtn flow, rod limited.
2/14 2300 Reactor thermal power at 945, maximum flow, rod limited.
2/16 2200 Commenced reducing themal power for control rod pattern adjustment.
2/17-0100 Reactor thermal power at 63% for control rod pattern adjustment, increasing thermal power.
0215 Control rod pattern adjustment complete, commenced power ascension from 65% thermal power.
0230 Commenced PCIOMR from 69% thennal power.
2/18 0630 Reactor thennal power at 995, maximum flow, rod limited.
0900 Reactor thermal power at 98%, maximum flow, rod ' limited.
1400 Reactor themal power at 975, maximum flow, rod limited.
1900 Reactor thennal power at 965, maximum flow, rod limited.
2/19 0700 Reactor thermal power at 955, maximum flow, rod limited.
2/20 0700 Reactor thennal power at 945, maximum flow, rod limited.
1440 Commenced power ascension from 945 due to increased pressure regulator set point.
1600 Reactor thennal power. at 98%, maximta flow, rod limited.
1614~
Commenced reducing thennal power for SI 4.6.E-1 (Jet Pump Operability).
1700 Reactor thennal power at 93% for SI 4.6.E-1.
1730 SI 4.6.E-1 complete, commenced PCIOMR.
2230 Reactor thermal power at 985, maximum flow, rod limited.
2/ 21 1500 Reactor themal power at 975, maximum flow, rod limited.
2/22 0910 Commenced reducing thermal power to time CR 34-03.
0922 Reactor thermal power at 925, timing CR 34-03.
0945 Completed timing of CR 34-03, commenced power ascension.
1100 Reactor thennal power at 975, maximum flow, rod limited.
2/23 0218 Commenced reducing thennal power for CRD Exercise (SI 4.3.A-2).
t 0226 Reactor thennal power at 94% for SI 4.3.A-2.
0345 SI 4.3.A-2 complete, holding for turbine control valve tests and sis.
l 0415 Turbine control valve tests and sis complete. commenced power ascension.
0600 Reactor thennal power at 975, maximum flow, rod limited.
1900 Reactor thermal power at 96%, maximum flow, rod limited.
7 Sinnificant Ooerational Events Date Tirw Event Unit 1 (Continued)
P/26 1300 Reactor thermal power at 955, maximm flow, rod limited.
2/28 2200 Reactor thermal power at 945, maximm riow, rod limited.
2400 Reactor thermal power at 945, maximum flow, rod limited.
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8 Sinnificant Ooerationni Events Date Tima Event Unit 2
-2/01 0001 End-of-cycle 5 refuel outage continues (controlled shutdown on 9/15/84).
.2/28 2400 End-of-cycle 5 refuel outage continues (controlled shutdown on 9/15/84).
9 Sinnificant Ooerationni Events Date Tima Event Unit 3 2/02 0001 Reactor themal power at 1005, maximun flow, rod limited.
2/03 1100 Corsnenced reducing thermal power for turbine control-valve test and sis.
'1115 Reactor thermal power at 96% for turbine control valve tests and sis.
1135 Turbine control valve tests and sis complete, commenced power ascension.
1140 Commenced PCIOMR from 985 themal power.
1340 Reactor thennal power at 1005, maximum flow, rod limited.
2/09 0315 Commenced reducing thermal power for turbine control valve tests and sis.
0400 Reactor thennal power at 90% for turbine control valve i
tests and sis.
0430 Turbine control valve te'sts and sis complete, commenced PCIOMR.
1130 Reactor thennal power at 100%, maximum flow, rod limited.
2120 Commenced reducing thennal power for shutdown to repair leaks in drywell (test line for valve 69-1).
2315 Reactor manual Scran No.116 from 38% thennal power to repair leak on valve 69-1 test line.
i'/10 1015 Unit in cold shutdown.
2/'2 0600 Maintenance complete on valve 69-1 test line.
Unit remains offline for maintenance on IRMs.
2/13 2000 Maintenance complete on IRMs, commenced rod withdrawal for startup.
2058 Reactor critical No. 133.
2/14 1000 Rolled turbine / generator.
1057 Synchronized generator, commenced power ascension.
2/15 1130 Reactor thennal power at 73% for RTI-23A (Reactor Feed Punp Turbine (RFPT) Test).
1500 "B" RFPT removal from service for maintenance, reducing thennal power to 70%, RTI-23A dogged off.
10
'Sinnificant Ooerational Events Date Tima Event Unit 3 (Continued) 2/16 0600 -
"B" RFPT back in service, reactor power at 70% for RTI-23A.
1036 Commenced power ascension from 70% themal power.
1730 Commenced PCIOMR from 80% themal power.
2/17 1630 Reduced thermal power from 985 to 96% due to vibration alam on "A" and "B" recirculation ptaps.
.2/18 1430 Commenced reducing thermal power for maintenance on CRD 54-35.
1500 Reactor themal power at 87% for maintenance on CRD 54-35.
2335 Comenced reducing themal power for SI 4.3.B.1.a (Control Rod Coupling Integrity).
2345 Reactor' thermal power at 84%, increasing for SI 4.3.B.1.a.
2355 Completed SI 4.3.B.1.a, reactor themal power at 93%,
commenced power ascension.
2/19 0035 Commenced PCIOMR from 94% themal power.
0135 Reactor themal power at 98%, maximum flow, rod limited.
2/21 0410 Cmmenced reducing thermal power for removal of "B" RWP from service for maintenance.
0445 "B" RWP out-of-service, reactor themal power at 84%.
0812 Reducing reactor themal power for RWP maintenance.
0817 9eactor thermal power at 80% for RWP maintenance.
1700 Heactor themal power at 81% for RWP maintenance.
2200 Reactor themal poder at 82% for RWP maintenance.
2/22 0415 "B" RWP in service, holding for RTI-23A (Reactor Feed Pump Turbine Test).
1510 RTI-23A complete, reducing themal power for control rod pattern adjustment.
1600 Reactor themal power at 75% for control rod pattern adjustment, increasing thermal power.
2300 Control rod pattern adjustment complete, reactor themal power at 77%, holding for CRD Exercise (SI 4.3.A-2).
2/23 0100 SI 4.3. A-2 complete, commenced PCIOMR.
1230 Stopped PCIOMR at 86% power due to computer probles.
1840 Computer back in service, commenced PCIOMR.
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jigglificant Operationni Events Date Tima Event Unit 3 (continued) 2/24 1700 Reactor thennal power at 1005, maximum flow, rod limited.-
2/28 2400 Reactor thennal power at 1005, maximun flow,. rod limited.
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_i 12 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-259 UNIT Browns Ferry One 3-1-85 DATE COMPLETED BY T. Thom TELEPHONE (205) 729-2509 MONTH February 9
DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL IMWe-Net)
(MWe-Net)
I 1088 844 37 2
init 18 1027 3
1056 19 1048 4
1101 20 970 5
1011 21 1031 6
1012 22 1029 7
1029 23 1019 8
1019 1024 24 9
891 25 1026 1052 26 1008 10 11 1012 27 1047 12 1011 23 1019 13 1013 29 14 1001 30 15 999 31 16 980 INSTRUCTIONS On thitformat, list the average daily umt power lesel in Nlwe Net for cach day in the reporting month. Compute to the nearest whole megawatt.
(9/77i
13 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-260 UNIT Browns Ferry Two DATE ~3-1-85 COMPLETED BY T. nom TELEPHONE (205) 729-2509 MONTH-hhrnary DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe-Net)
(Mwe. Net) l
-5
-3 37 2
9 is
-1 3
-4 19
-3 4
-5
-3 2O
-4 21
-4
-4 6
22
-3 7
-4 23
-3 24
-4 8
-5 9
-4 25
-3
-4 10 26
-3
-5
~4 27
~4
~3 12 28 T
13
-5 39
~4 14 30
~3 15 3l 16
-3 INSTRUCTIONS On this format. fist the average daily umt power lesel in MWe-Net for each day in the reporting month. Compute to the nearest whole meg:. watt.
(9/77)
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i 14 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-296 UNIT Browns Ferry Three DATE 1-85 COMPLETED BY T. Thom TELEPHONE (205) 729-2509 MONTH Fabriuiry DAY AVERAGE DAILY POWER LEVEL DAY AVER ACE DAILY POWER LEVEL D1We-Net) de Net) 1072 1000 g7 2
1088 18' 991'
~
3 1079 19 1025 4
1098 20 1029 5
1090 21 RA1 6
1070 22 832 7
1068 23 875 3
1074 24 1034 9
1003 25 inns
-14 10 25 1078 ll
-13 27 1074 12
-13 23 1087 13
~14 29 14 259 30 15 761 3
16 751 INSTRUCTIONS On ihnfortnat. list the average daily unit power Icelin MWe Net for each day in the reporting month. Compute to the nearest whole megawatt.
(9/77)
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4 15 OPERATING DATA REPORT-DOCKET NO.
50-259 DATE 3-1-85 COMPLETED BY T. Thom TELEPHONE (205) 729-2509 OPER ATING STATUS
- 1. Unit Name:
Unit 1. Browns' Ferry Notes
- 2. Reporting Period:
February 1985 3293
' 3. Licensed Thermal Power (MWt):
1152
- 4. Nameplate Rating (Gross MWe):
- 5. Design Electrical Rating (Net MWe):
1065
- 6. Maximum Dependable Capacity (Gross MWe):
1098.4
- 7. Maximum Dependable Capacity (Net MWe).
1065
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:
N/A
'. Power Level To Which Restricted. lf Any (Net MWe):
'N/A 9
- 10. Reasons For Restrictions,if Any:
N/A This Month Yr.-to-Date.
Cumulative
- 11. Hours In Reporting Period 672 1416 92.R16
. 12. Number Of Hours Resctor Was Critical 672 1214.33 59,087.93
- 13. Reactor Reserve Shutdown Hours 0
o n
- 14. Hours Generator On.Line -
672
_ i193.22 57.833.J1 _,
. 15. Unit Reserve Shutdown Hours 0
0 0
- 16. Gross Thermal Energy Generated (MWH) 2.115.907 3.711.204 166.872.650 17.- Gross Electrical Energy Generated dlWH) 700,510 1.225.460 54.970.940
- 18. Net Electrical Energy Generated (MWH) 681,968 1,190,629 53,404,450
- 19. Unit Service Factor 100 84.3 62.3 100 84.3 62.3
- 20. Unit Availability Factor 95.3 79.0 54.0
- 21. Unit Capacity Factor tUsing MDC Net)
- 22. Unit Capacity Factor (Using DER Net) 95.3 79.0 54.0
- 23. Unit Forced Outage Rate 0
15.7 22.0
- 24. Shutdowns Scheduled Over Ne.st 6 Months (Type. Date,and Duration of Each):
June 1985
- 25. If Shut 1)own At End of Report Period, Estimated l) ate of Startup:
- 26. Units in Test Status (Prior to Commercial Operationi:
Forceast
.khicW INITIA L CRITICALITY INITIA L ELECTRICITY COMMERCIA L OPER ATION h
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OPERATING DATA REPORT DOCKET NO.90-260 DATE 3-1 COMPLETED BY T.
%n=
TELEPHONE (205) 729-2509 OPERATING STATUS N"I'5
- 1. Unit Name:
fini e ' 2 Browns Ferry
- 2. Reporting Period:
February 1985
- 3. Licensed Thermal Power IMht1: 3293 1152
- 4. Nameplate Rating (Gross MWel:
- 5. Design Electrical Rating (Net MWel:
1065 6 Masimum Dependable Capacity (Gross MWel:
1098.4 1065 7 \\inimum Dependable Capacity (Net MWe):
h if Changes Occur in Capacity Ratings titems Number 3 Through 7) Since Last Report. Give Reasons:
N/A
- v. Power Lesel To which Restricted.lf Any (Net MWe):
N/A 10 Reasons For Restrictions.lf Any:
N/A This Month Yr.-to.Date Cumulative
- 11. Hours in Reporting Period 672 1416 87.703
- 12. Number Of Hours Reactor Was Critical 0
0 55,860.03
- 13. Reactor Reserve Shutdown Hours 0
0 14.200.44
- 14. Hours Generator On-Line 0
'n 9 A q u _16 -
- 15. Unit Reserve Shutdown flours 0
0 0
- 16. Gross Thermal Energy Generated (MWHI n
n 151.245.167
- 17. Gross Electrical Energy Generated (MWH) 0 0-50.771.798 18.~ Net Electrical Energy Generated (MWH)
-2,609
-5,704 49,297,269
- 19. Unit Service Factor 0
0 62.0 0
0 62.0
- 20. Unit Availability Factor
- 21. Unit Capacity Factor (Uning MDC Net 1 0
0 52.8 0
0 52.8 22.' Unit Capacity Factor (Uning DER Net) 0 0
23.0
- 23. Unit Forced Outage Rate
- 24. Shutdowns Scheduled Oser Nest 6 Months tType. Date.and Duration of Each t:
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
August 1. 1985
- 26. Units in ress Status IPrior to Conunercial Operationi:
Forecast Achiesed INITIA L CRITICALITY INITIAL ELECTRICIT COMMERCIAL OPER ATION l
l 08/77)
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OPERATLNG DATA REPORT DOCKET NO.
50-296 DATE 3-1-85 COMPLETED BY T.
Thom TELEPHONE (205) 729-2509
- OPERATING STATUS Notes
- 1. Unit Name:
Unit 3. Browns Ferry
- 2. Reporting Period:
February 3293
- 3. Licensed Thermal Power (MWt):
1152 i
- 4. Nameplate Rating (Gross MWe):
1065
- 5. Design Electrical Rating (Net MWe):
- 6. Maximum Dependable Capacity (Gross MWe):
1098.4 1065 l
- 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.lf An (Net MWel:
N/A
- 10. Reasons For Restrictions,if Any:
/A This Month Yr. to-Date Cumulatise
- 11. Hours In Reporting Period 672 1416 70.128 578.28 1303.95 45,092.38
- 12. Number Of Hours Reactor Was Critical
- 13. Reactor Reserve Shutdown Hours 93.72 112.05 4.753.55
- 14. Hours Generator On-Line 564.30 1285.38 43,983.18 0
0 0
- 15. Unit Reserve Shutdown !!ours
- 16. Gnu Thermal Energy Generated (MWH) 1.688.158 4.001.972 131.220.399
- 17. Gross Electrical Energy Generated (MWH) 576,020 1.345.920 43.246.910
- 18. Net Electrical Energy Generated (MWH) 560,424 1,311,300 41,977.051
- 19. Unit Service Factor 84.0 90.8 62.7
- 20. Unit Availability Factor 84.0 90.8 62.7
- 21. Unit Capacity Factor (Using MDC Net) 78.3 87.0 56.2
- 22. Unit Capacity Factor (Using DER Net) 78.3 87.0 56.2
- 23. Unit Forced Outage Rate 16.0 9.2 17.7
- 24. Shutdowns Scheduled Over Next 6 Months (Type. Date,and Duration of Each t:
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
- 26. Units in Test Status (Prior to Commercial Operationi:
Forecast Achiesed INITIA L C".lTICALITY INITIA L ELECTRICITY COMMERCIAL OPER AT10N t'8/71)
w-UNITSIIUTDOWNS AND POWER REDUCTIONS ~
DOCKET NO. 50-259 UNIT NAME Browns Ferry One-DATE 3-1-8S COMPLETED BY T-Tha=
REPORTMONTil February
- TELEPHONE (205) 729-2509
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j $5 Licensee
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Cause & Currective No.
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Repors=
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310 2-9-85 S
B Derated for ST 8501 (Single Recirculation Loop Operation) 311 2-16-85 S
H Derated for control rod pattern adjustment.
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3 4
F: Forced Reason:
Method:
Exhibit G -Instructions S: Scheduled A-Equipment FailureIEsplain)-
I-Manual for Preparation of Data B-Maintenance oi Test 2 Manual Seram.
Entry Sheets for Licensee C-Refuelmg 3-Automaine Stram.
Eveni Report ILI RI File INL' REG-D-Regulatory Restriction 4-Other I Esplain t 0161)
E. Operator Training & Letense I samination F-Adnunistrative 5
G-Operational E:ror IEsplams Exhibii 1 - Same Source 08/77)
II Other (Esplain t 4
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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKETNO. 50-260 UNIT NAME arouna Ferry ha DATE *t 1 AG REPORT MONTil February COMPLETED BY T-
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TELEPHONE (205) 729-2500 n.=
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Licensee
[v, Cause & Corrective No.
Date g
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Action to
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Preient Recurrence 2
305 2-1-85 5
672 C
4 COC-5 Refuel Outage (Cont)
-(Controlled Shutdown 9-15-84)
I 2
3 4
F: Forced Reason:
MethoJ:-
Exhibit G-Instructions S: Scheduled A Equipment Failure (Esplam) 1412nual fin Preparation of Data B-Maintenance ci Test 2-Manual serain.
En: y Sheets for Licensee.
C-Refueling 3-Automatic Scram.
Esent Report al LR File NL REG-D-Regulatory Restriction 4-Other i Esplain) 0161)
E Operator Training & 1Aense Esanunaison F-Adnunistrair.e 4
G Oper.iiiosul tiror Ilhplaial E shibii I - Same Source 19/77)
II Other IExplain) b__
3 DOCKETNO. 50-296 UNIT SilUTDOWNS AND POWER REDUCI10NS UNIT NAME Browns Ferry Three DATE 3-1-85 COMPLETED SY T. Thom REPORT MONTH February TELEPHONE (205) 720-25n0
.53 3
$k Licensee
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Cause & Corrective h
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4 2s5 Event
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9-3 Action to
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Report :
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Prevent Recurrence e
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C 152 2-9-85 F
54.75 A
2 Reactor scrammed to repair leak on valve 69-1 test line.
153 2-12-85 F
52.95 A
2 Unit remains offline for maintenance on IRM's.
154 2-21-85 S
H Derated for control rod pattern adjustment.
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.
Entsy Sheets for Licensee C-Refueling 3-Automatic Scram.
. Eveni Report (LI:R s File t NL Hl.G-
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D-Regula or) Restnetion 4-Other I Explaud 01611 IX)perator Training & Lisense Examination F-Administrative 5
G-Operational E:ror II.splaial L shibii I - Same Souice 19/77)
Il4hher (Explaini
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M O W S FERRY NUCLEAR F1 ANT UNIT 1
~
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cgSC EQUIFIENT W G ANICAL MAINTENkNCE SIRGILEE For the Month of Februnry?'19 85
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EFFECT ON SAFE ACTIM 11EEN i
-DATE SYSTEN COMPONENT NATURE W OPERATION OF CAUSE QF RESULTS OF
' TO PRECINDE MAINTENANCE THE REACTOR MALFUNCTIM MALFUNCTIM RECURRENCE
' 17-85 64 Drywell A P Repair Cooling corrosion Replaced section of pi l
/
Air compressor water leak on i
line coming off after cooler
- 20-85 74 1D RHR Pump Lincouple pump 0
0 N/A
'N/A from motor so motor could be pulled 85 74 1D RHR Pump Torque Motor N/A N/A N/A Motor repl'acement Motor base bolts to t
Pump I
D k
>e 9
t 9
e e
O u.
--__..__m,.-
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BROWNS FERRY NUCLEAR FIANT UNIT 2
CSSC EOUIPMENT-DECHANICAL HAINTEBULNCE iiUIGIARY For the IIonth.of February 19 85 EFFECT ON SAFE ACTION TAKEN SkTE SYSTEM COMPONENT NATURE OF OPERATION OF CAUSE OF RESULTS OF
-10 PRECLUDE' MAINTENANCE THE REACTOR MALFUNCTION-MALFUNCTION RECURRENCE-9-20-85 74 RHR 2B pump LIncouple pump
' ip motor going to from motor in unit 1 order to pull motor 2-21-85 0
1D & 2B RHR deld configurat ion Possible Replace ID pump motor pump motor as in SEMI 46 6 Outage with 2B pump motor ~
47 D
U b
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3 namnes FERRY NUCLEAR PIANT UNIT -
- * -... i
... y CSSC EOUIPMENT MEGANICAL MAINTENANCE SUlefANY ij F;bruary gg' 85
- + =.
For the Month of i.y
~
EFFECT ON SAFE ACTION TAEEN I
IRTE SYSTEM COMP 001ENT NATURE OF OPERATION OF CAUSE OF RESULTS OF TO PRECIRDE-I h
MAINTENANCE THE REACTOR MALFUNCTION MALFUNCTION RECURRENCE i 85 68 Valve 68-558 Removed valve Material Failure :'aused erratic Replaced valve with.-
i from U-3, replaced temperature and alarms valve.fromunit2g-alth valve 68-an 3B pump seal i
558 from U-2
.-1 0-82 69 FCV 69-1 Repair test line Material failure Reactor shutdown to Replaced section of g;
for FCV 69-1 determine leak and S. S. pipe'approximately, nake repairs.
5 3/4" long
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BRot.'NS FERRY CCt. EAR Pl.AST L'51T -
'O CSSC EOLTIPMENT ELECTRICAL ltAl!TsENANCE.SODGRY-9/29/82; s'
For the M. nth of' February 19 85' Effect on Safe Act loa Tak'eit-l Nature of Operation of :
Cause.of i<esults of I To Precluele
)a tn Svste a f
-Ca=ponent 5!aintenance The Reactor Malfunction
' Malfunction i<ecurrence
.985
/1 Standby CEN-082-000D Troubleshoot None Tachometer Erratic-operation-Replacedtachometerl-diesel diesel genera-tachometer generator brushes generator.
generator tor D tachome-appeared to be ter worn MR 312140 e
i
- /5 Radiation PMP-090-0152A Replace motor None Bad motor-
~lStackgassamplepump Replaced motor monitoring stack gas on stack gas
' inoperable-
.MR 161107 sample. pump B1 sample pump.
Shipped bad motprc to service shop.for repairs.
/11 Diesel FAN-254-000C Troubleshoot None Relay contacts Alarm in on panel; Freed contacts; 125VDC D/G C battery abnormal annunc sticking together will not clear annunciator clearr -
- ys exhaust fan on control room panel MR 179211 4
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I fil:0 C S FElmY f.FC:. EAR Ptx;r U';IT 1
SF E!!SIL 30 m
ELECTRICAL }DINTEL'. ;ct' SL't.'!ARY I
s
' 9/29/82 i
for the.'Lnth af_Jshruary 19 85 Eticct on Safe,
.k t ion laka j
Nature of.
Operation of
_Cause.of I
Haaults of f To Pre'clude
') ate Svste C.v.ponent Miintenance The Reactor
>!.il f unc t ion M.a li_.ine r f an T
R ec a r re n.:.*
1985 I
.1/23 Reactor RLY-099-5AK12F Investigate llalf scran of Burned-up relay Gave a half scram Replaced relay a
protection neutron moni-control room unit 1 coil system toring relay annunciation
,MR 182526 s
t i
N1/30 Control
'PNLA-009-0004 Replace inverter None g ad inverter Power failure on Replaced inverter B
bay panels annunciation on annunciation Ipanel 9-4 panel 9-4 panel MR 175285 i
.I 1/31 Fire XS-039-66YE Performing None lDefectivesmoke Detector inoperable Replaced detector protection zone Y smoke SI 4.11.C.1 & 5 j
el 565 U
l2/8 480V CEN-268-1[A Determine cause None Voltage regulator Generator output Adjusted voltage 8
reactor 1EA LPCI mg of low voltage out of adjustment voltage low
. regulator per MOV bds set on LEA LPCI EMI 96 mg set l
MR 182911 l
t 2/10 Cranes &
Refuel floor Repair cooling None Broken wire on Cooling fan inoperable Replaced motor hoists main hoist fan motor motor i
cooling fan MR 181172 motor i
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BPOW;S FERRY N'JC;f..iR PLANT UNIT 1
BF EllSIL 33
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O CSSC EQUIPl!ENT ELECTRICAL IL\\INTENANCE SU30L\\RY f
9/29/82 For the'>f3 nth nf February 19 85
{
Effect on Safe.
.ktion Taken j
Nature of Operation of Cause.of Results of fo Preclude D*te System Cc. :panen t Pla in t enance The Reactor St.t i f unc t i. n St nl f ul.c t laa i Recurrence 1985
'2/13 Fire XS-039-15A Performing None Defective smoke Detector inoperable Replaced detector protection smoke detector SI 4.11.C.1 & 5 detection aux inst rm HR 175286 l
4 2/20 Residual MTR-074-0039 Troubleshoot 7-day LCO
' Undetermined RIIR loop II inoperable Pulled motor and i
heat ID RiiR motor failure of RIIR shipped to service )
removal pump motor ID shop -
l 1
i 1
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MR 269592.
l Installed motor l
removed from unit 2 MR 269593 w
L /21 Control AllU-031-0110 Repair emergenc3 None Leak in shutoff Cooling unit inoperable Adjusted shutoff 2
bay, heat, shutdown bd air-conditioninL valve valve vent and rm emergency unit E
34 I
a ir-cond i-cooling unit l
l tioning
- 2/23 480V GEN-268-1EA Lower voltage 7-day LCO Blown diode con-IEA LPCI mg set was MR 179555 reactor IEA LPCI mg on LPCI mg set nections in tripped by ASE due to LER 259-85004 1
MOV bds set IEA.
generator caused smoke coming out of exciter failure Repic ced voltage Troubleshoot Q
IEA LPCI mg regulat r and set generator l
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,y BI:0!C;S FERRY *.'JCLi'."J. I'!X.T l*!;IT 2__
gy ggggt 3, FLECTRICAL !!A1!.*TENrICE SC01ARY Appendix B CSSC E0l'IPMENT g
For the >fanth of February 19 85 Effeet on Safe Aa 1*2n Taken __
i Nature of Operation at Cause pf Results of I To Prceluile Dato System Co: pone:nt Sh in t ena:ic e The Reactor Malfunctian l _ ?!alfuncttan Recurrence i
L985
.l/3 '
Fire XS-039-67WL Performing None protection zone W smoke SI 4.11.C.1 &.5
' Defective smoke
! Detector was inoperabl e Replaced detector _ l detector I
i detector, el l
fMR320317-l 565 t
I i
t L/10 RHR service HCV-023-0043 I Troubleshoot None i
Defective positiod Loss of valve positioh Replaced position,
water
'RilR heat exh fpositionswitch I
switch
' indication i indication switch '
B sw-intet viv;.
j l
MR 170164
{
l
- ,/30 Residual HS-74-96B RilR Replace hand-None Corrosion 4
?
lN/A-lReplacedhand-heat pump A switch removal suction cross-a switch i
tie valve
}
MR 171139
+
handswitch
/30' Residual HS-74-97B RHR Replace hand-None Corrosion N/A Replaced hand-heat pump C switch switch removal suction cross-tie valve MR 171140 handswitch 8.
/30 Residual JB-74-2258 Replace termi-None Corrosion Junction box Replaced terminal junction box nal strips in FCV-74-96 improperly sealed strips and sealed FCV-74-97 junction box i
MR 171142
/20 Residual MTR-074-028 Pull motor and 30-day LCO N/A N/A Pulled motor.
(
heat 2B RHR motor install on ID removal RHR pump Install spare motoi l
on 2B when received j
from service shop jMR269593
p i
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!!"OICS Ft.!GY
'.Ui :.i'.AI: 11 A:;r UNIT 2
fiF t.':sIL 33 CSSC EQUll'MF'.T ELECTRICAL !!Al'Tr*:A?Cl! SDDt\\RY
'I 9/29/82 fo r t he
.'!.'n i e February I ')_ 85 1:t iect on Saie j
.ic : 10 3 2,,, e n j
!La t ure o f i
l Operation of Cause of Re.vil t.i o f i To Preclude Dat?
System Cen;,on ca t Sta in t enance The Reactor
~
.talfunctian
'ta l f u:w r f.,a Itecurrence 1/2/84 480V RLY-268-2E/5A Performing DPS0 None
Contact:
close Replaced relay Bad undervoltage reactor 27B undervolt-SMI 3 RMOVDE instantaneously on l
MOV bd age relay loss of voltage;
.MR 320159 should close with
. a time delay l
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CSSC EQUIP > TENT-ELECTRICAL MAINTENA';CE SDetARY:.
9/29/82-For J the.'!anth~ of,_ February 19'85 4
.I' Effect on Safe,
, Aetion Taken
.j Nature of.
.Operatton of Cause,of 1--
Results of' 1 To Preclude
- lat+
Sv s t e:n t
Component
?!a inten mce -
The Reactor
!!al funct ian '
!!a l f unc t lan i Recurrence-t 1985
- l
'J/9 Standby TS-063-0004 Check calibra-None Thermostat: set, liigh temperature on Reset thermostat liquid-SLC pump B-tion of strip too.high (100*F) entire suction pipe to 85*F 5
control suction piping heater thermo-MR 182856 EbefEobIah*#
femp*atl105'F I/12 Control bay CliR-031-1976 Troubleshoot None Leaking unloader 3B-1 chiller would Replaced unloader.
heating,.
' shutdown bd chiller-gaskets not starti gaskets l
vent and rm chiller air-cond 3B-1 MR 177267 l
/10 Reactor HS-70-43A Troubleshoot None
' Stops on hand-Closing contacts Replaced switch
-l j b1dg heat 6 drywell ATM handswitch switch bad.
make-up intermittently y
ventilatior cooling coil MR 182860 B2 fan mer i
/16 Reactor RLY-64-16AK80 Troubleshoot None Burned-up relay Inop FCV-43-14 '
lieplaced. relay.
b1dg closed recirc sample FCV-43-14 coil cooling line isolation MR 179102 water relay outbd-1 6.
,j
'I l
6,
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30 OUTAGE MAINTENANCE & MAJOR MODIFICATION MANAGENENT February 1985 MAJOR 1dORK COMPLETED A.
Refuel Floor 1.
The unit 1 fuel pool was sampled in preparation for equipment decontamination.
2.
Baseplat.es were ses in the unit 2 fuel pool on February 28,1985, for rod consolidation demonstration equipment.
B.'
Turbine Fitting bolts and aligning No. 2 coupling was finished on February 7, 1985.
C.
Drywell Recirculation pump motor "B" was disassembled on February 6,1985 due to high vibration while testing. The pump motor upper guide bearing was replaced (for the second time) and the pump was successfully run on l
February 13, 1985.
D.
Balance-of-Plant Eddy current testing was reported complete on February 12, 1985.
E.
Modifications Sections l
1.
ECN P0126 core drilling was reported complete on February 12, 1985.
2.
ECN P0392 tank prefabrications were reported complete on February 15, 1985 3
.All physical security plant modifications were reported complete and signed off at 1500 on February 24, 1985.
t c
31 4'
OUTAGE MAINTENANCE & MAJOR MODIFICATION MANAGENENT February 1985 MAJOR iiORK COMPLETED'(Continued)
F.
Major Non-Modification Items in Work on February 28, 1985:
1.
IHSI is approximately 85-percent complete. Loop "A" recirculation.
(except two 4" welds), common recirculation, core spray and' reactor
~
water clean up-(except two outside - drywell welds) are complete; 2.
Preparations of the docking facility for receipt of the new low-pressure "C" (old low-pressure'"A") turbine from Muscle Shoals; 3
Main condenser maintenance and repairs;-
'4.-
Condenser cooling water intake tunnel joint repair; 5.
Major valves 54, 74-61, 75-26,-73-16, 84-series, 64-series, main steam relief valve vacuum breakers, main steam isolation valves; 6.
'2 "B" residual heat removal heat exchanger bottom tube plugging and vent valve repairs.
OTHER ITEMS OF INTEREST A.
ECN P0646, Addition of Diesel Air Start Valves, is field complete.
B.
Winter storms accounted for at least three lost days and one lost weekend of work.
- C.
Torus sandblasting started on February 13, 1985.
D..
Physical Security Plan modifications were completed on schedule. Scme backfits will be required.
E.
Weld GR-2-15 was found to-be leaking during post-IHSI penetrant test inspection. Forty-eight additional post-IHSI penetrant tests will be required..
F.
Evaluation of a proposal to add 12 recirculation nozzles to IHSI is in progress.
I
0 32 OUTAGE MAINTENANCE & MAJOR MODIFICATION MANAGEMENT February 1985 MODIFICATIONS IN WORK ON FEBRUARY 28. 1985 P0126 - Analog trip instrunents changeouts P0361 - Torus attached piping hangers
_P0697 - HVAC to control bays P0612/P0613 - Main. steam isolation valve modifications on ~B I/B, C I/B, C O/B
.P0555 - Torus sandblast and coating P0085 - Drywell temperature instrumentation (prefabrications)
P0533 - Torus temperature instrumentation (prefabrications)
P0392 - Scran header tanic and piping (prefabrications)
P0688/P0695/P0690 - Valve modifications; FCV-76 and -84 series
~
- Corrected Copy UNIT Sill'TDOWNS AND POWI.R RI:DllCT10NS DOCKET NO. 50-259 UNIT NAME wns Ferry One DATE 2 1 85 s
R EPORT MON fil January COMPLETED gy T. Thom TELEPilONE (205) 729-3834 i
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3 k $k Licensee 8 -r.,
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Cause & Coreccine DJIe C,,
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Evens
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5-?
Auson to i
6-fE
~ft Repois :
20 E'
Psevens Returrence u
d 306 1-11-85 S
H Derated for control rod pattern i
adjustment.
307 1-16-85 F
- 222.78 A 3
Reacton scram due to low water level which caused loss of steam to the fuel pumps. The unit remained down j
due to IRM problems and to repair a C
leak on bonnet vent line (valve 68-509) on "A" recirc. discharge valve 68-3.
308 1-29-85 F
A Derated for leak on reactor feedwater pump.
309 1-30-85 F
A Derated for feedwater control problemt i
i.
'l 2
1
-4 l: Forced Reason Ales hod.
Esinbii G - Instruco wi>
S Scheduled A-Equipmeni F.niure iL splaini
!-Manual for Prep.itation of Daia l
Il Maintenance or Test 2 Manual Scram.
Entn Sheen for Licen>ee C Refueling
.i-Auiom.itse Scrain.
1 seni Report i1.1 R e life s ' t R1 G-D Hegulaint) Resistenun I-Oihes (l'splaml 0161I l' Opesator Training & I hens I sanun.rtion F-Ad nanist s.su.e 5
O-Opciastuinal I isus ll.spl.iin t I sliibit I - S.nne so o c (9/77I Il-Oihes Il splaint
m CCorr:cted Copy OPERATING DATA REPORT DOCKET NO. 50-259 DATE 2/1/85 COMPLETED BY T. Thor.
TELEPliONE (205) 729-3834 OPERATING STATUS Notes
- 1. Unit Name:
Browns Ferry One
- 2. Reporting Period:
January 1985
- 3. Licensed Thermal Power (MWt):
3293 l
1152
- 4. Nameplate Rating (Gross MWe):
- 5. Design Electrical Rating (Net MWe):
1065
- 6. Maximum Dependable Capacity (Gross MWe):
1098.4 1065 l
- 7. Maximum Dependable Capacity (Net MWe):
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7)Since Last Report Give Rea>ons:
N/A
- 9. Power Level To Which Restricted. lf Any (Net MWe):
N/A
- 10. Re.isons For Restrictions. If Any:
N/A This Month Yr..to.Da te Cumu!.nis e
- 11. Ilours in Reporting Period 744 744
_92.144
- 12. Number Of flours Iteactor Was Critical 542.33 542.33 58.415.93
- 13. Reactor
- Reserve Shut own flours 201.67 201.67 6,686.89 d
- 14. llours Generator On-Line 521.22 521.22 57.16L 81
- 15. Unit Reserve Shutdown !!ours 0
0 0
- 16. Grow Thermal Energy Gcnerated (MWil) 1.595.297 1.595.297 164.756.743 17 Grow Electrical Energy Generated (MWil) 524.930_ _.,.. 524.950 54.270.430 lb. Net Electrical Energy Generated (MWil) 508.661 508.661
_52.722.482
- 19. Unit Service Factor 70.1 70.1 62.0
- 20. Unit Availability Factor 70.1 70.1 62.0
- 21. Unit Capacity Factor IUsing MDC Net) 64.2 64.2 53.7 2.'. Unit Capacity Factor IUsing DER Net) 64.2 64.2 53.7
- 23. Unit Forced Outage Rate
- 29.9
- 22 9
- 22.2
- 24. Shutdowns Scheduled Over Next 6 Months IType. Date.and Duration of Eacht:
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
- 26. Units in Test Status IPrior to Commercial Operationi:
Forecast Achiewd INITIA L CHIIICALITY INITIAL ELECTRICITY CO\\lMERCIAL OPER ATION en n
- 2:A 2- -!:22 2:=--
=
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- };
..,.._.., m TENNESSEE VALLEY AUTHORITY Browns Ferry Nuclear Plant P. O. Box 2000
-Decatur,. Alabama 35602 MAR 111985 Nuclear ~ Regulatory Commission Office of Management Information and Program Control Washington,' DC 20555 Gentlemen:
Enclosed is the February 1985 Monthly Operating Report to NRC for Browns Ferry Nuclear Plant Units 1, 2, and 3.
Very truly yours, TENNESSEE VALLEY AUIBORITY
$. Ox W
/), G. T. Jones F Plant Manager Enclosures cc: - Director, Region II INPO Records Center Nuclear Regulatory-Commission Institute of Nuclear Power
.0ffice of Inspection and Enforcement Suite 1500 101 Marietta Street 1100 Circle 75 Parkway Atlanta, GA 30303 (1 copy)
Atlanta, GA 30389 Director, Office of Inspection and Enforcement Nuclear Regulatory Commission Washington,.D. C.
20555 (10 copies)
Mr. A. Rubio, Director Electric Power Research Institute P. O. Box 10412 Palo Alto, CA 94304 f2-Y An Equal Opportunity Employer ll8
.