ML19323D332
| ML19323D332 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 05/01/1980 |
| From: | Green D TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML19323D327 | List: |
| References | |
| NUDOCS 8005210443 | |
| Download: ML19323D332 (33) | |
Text
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- O TENNESSEE VALLEY AUTHORITY f
DIVISION OF POWER PRODUCTION BROWNS FERRY NUCLEAR PLANT 4
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MONTHLY OPERATING REPORT 4
April 1, 1980 - April 30, 1980 4
I DOCKET NUMBERS 50-259, 50-260, AND 50-296 LICENSE NUMBERS DPR-33, DPR-52, AND DPR-68 4
Submitted By:
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" Plant S6perintendent J
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TABLE OF CONTENTS Operations Summary..............
1 i
Refueling Information 3
i Significant Operational Events...
5 Average Daily Unit Power Level...........'.....
13 i
i Operating Data Reports.
16 l
Unit Shutdowns and Power Reductions.
19 3
Plant Maintenance 22 Outage Summary........................
32 4
1 4
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Operations Summary April 1980 The following summary describes the significant operational activities during the reporting period. In support of this summary, a chronological log of significant events is included in this report.
There were eighteen reportable occurrences (plus three supplemental reports) reported to the NRC during the month of April.
Unit 1 There were three scrams on the unit during the month. On April 20, the reactor was manually scrammed for maintenance on FCV-69-1 which f ailed to close during an SI.
The reactor was manually scrammed on April 23 to re-balance the main turbine generator after balance weights were inadvertently placed 180 degrees out of alignment during the previous shutdown. On April 25, the reactor was manually scrammed for maintenance (bearing low oil level alarm) l on the "B" recirculation pump motor.
'4 Unit 2 There were two scrams on the unit during the month. On April 15, the reactor scrammed from a low water level signal caused when the steam flow signal was accidentally removed from the steam flow /f eedwater flow mismatch circuit (causing RFP runback). The reactor scrammed on April 22 due to turbine stop valve closure from main and RFP turbine trips caused by a reactor high water level signal (personnel error on SI).
Unit 3 There were no scrams on the unit during the month.
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2 Operations Summary (Continued)
April 1980 Fatigue Usage 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 0.00445 0.00333 0.00291 Feedwater nozzle 0.21444 0.14471 0.10717 Closure studs 0.18899 0.11906 0.08728 Note:
This accumulated monthly information satisfies technical specification section 6.6. A.17.b(3) reporting requirements.
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common Systems i
i Approximately 1.02E+06 gallons of waste liquid were discharged containing i
approximately 6.61E-01 curies of activity.
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3 Refueling Information April 1980 i
Unit 1 Unit 1 is scheduled for its fourth refueling beginning on or about April 15, 1981, with a scheduled restart date of July 25, 1981. This re-fueling will involve loading additional 8 x 8 R (retrofit) fuel assemblies into the core and torus modifications if all approvals are received.
There are 764 fuel assemblies in the reactor vessel. The spent fuel storage pool presently contains 550 spent 7 x 7 fuel assemblies, five 8 x 8 fuel assemblies, one 8 x 8 R fuel assemblies, and 20 new P 8 x 8 R assemblies.
Because of modification work to increase spent fuel pool capacity to 3471
]
assemblies, present capacity is limited to 1152 assemblies.
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i Unit 2 Unit 2 is scheduled for its third refueling beginning on or about September 1, 1980, with a scheduled restart date of October 10, 1980.
t Resumption of operation on that date will require a change in technical specifications pertaining to the core thermal limits. Licensing information in support of these changes will be submitted to the NRC before the outage.
This refueling involves replacing some more 7 x 7 fuel assemblies with 8 x 8 R (retrofit) assemblies.
There are 764 fuel assemblies in the reactor vessel. At the end of the month, there were 132 discharged cycle 1 fuel assemblies and 268 discharged j
cycle 2 fuel assemblies in the spent fuel storage pool. The present storage capacity of the spent fuel pool is 1080 assemblies. With present capacity,
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4 Refueling Information (Continued)
April 1980 Unit 2 (Continued) the 1979 refueling would be the last refueling that could be discharged to the spent fuel pool without exceeding that capacity and maintaining full core discharge capability in the pool.
Unit 3 Unit 3 is scheduled for its third refueling beginning on or about October 15, 1980, with a scheduled restart date of November 22, 1980. This EOC-3 refueling involves loading additional 8 x 8 R (retrofit) assemblies into the core.
There are 764 fuel assemblies presently in the reactor vessel. There are 144 discharged cycle 2 fuel assemblies and 208 discharged cycle 1 fuel assemblies in the spent fuel storage pool. The present storage capacity of the spent fuel pool is 1528 assemblies. With present capacity, the 1980 refueling would be the last refueling that could be discharged to the spent fuel pool without exceeding that capacity and maintaining full core discharge capability in the pool.
5 Significant Operational Events Unit 1 Date Time Event 4/01/80 0001 Reactor at cold shutdown for "B" recirculation pump main 62 nance 0935 "B" recirculation maintenance comple.te, commenced rod withdrawal, sequence "A" 1100 Reactor critical No. 140 1
2220 Rolled T/G 2256 Synchronized generator commenced power ascension 4/02/80 0350 Reactor thermal power at 40% and holding for scram testing control rods 1818 Scram testing completed commenced power ascension 4/03/80 1420 Reduced reactor thermal power from 53% to 40% for scram ratesting control rods (pressure 15 psi low during previous scram tests) 4/04/80 1628 Scram retesting complete commenced power ascension from 40% thermal power 4/05/80 0125 Reduced reactor thermal power from 55% to 49% for control rod pattern adjustment l
0155 Commenced power ascension from 49% thermal power 0400 Commenced PCIOMR from 65% thermal power (sequence "A")
4/06/80 0800 Reactor thermal power 80%, holding for 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> fuel soak 2000 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> fuel soak completed, holding for SI's 4/07/80 0945 Reduced reactor thermal power from 80% to 55% for RTI-23A (Feedwater controls) 1705 Commenced power ascension from 55% thermal power
(
1835 Commenced PCIOMR from 80% thermal power 4/08/80 1210 Reduced thermal power from 84% to 56% for RTI-23A 1700 Commenced power ascension from 56% thermal power 2100 Commenced PCIOMR from 78% thermal power 4/09/80 0630 Reduced reactor thermal power from 83% to 63%
thermal power for RTI-23A 1105 Increased reactor thermal power to 69% for RTI-23A (Feedwater control) 1630 RTI-23A complete holding for RTI-32A (Recirculation pump controls) 1722 Reduced thermal power from 69% to 52% for RTI-32A t
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6 Significant Operational Events Unit 1 Date Time Event 4/09/80 2315 RTI-32A complete holding at 52% thermal due to problems with process computer 4/10/80 1100 Process computer problems resolved commenced PCIOMR from 52% thermal power 4/12/80 0700 Reactor thermal power at 93% maximum flow 4/13/80 0320 Reduced thermal power from 93% to 56% for control l
rod pattern adjustment 0540 Control rod pattern adjustment completed commenced power ascension 0930 Commenced PCIOMR from 65% thermal power 4/14/80 1345 Reactor thermal power at 93% holding due to pro-cess computer being out of service 1720 Process computer placed in service resumed PCIOMR 4/15/80 0400 Reactor thermal power at >99% steady state 0715 Reduced thermal power from >99% to 50% due to loss of "B" recirculation pump when unit 2 scrammed 0800 "B" recirculation placed in service commenced power ascension 0930 Commenced PCIOMR from 80% thermal power 1245 Reactor thermal power at 88% holding for backwash and precoat of "H" condensate demineralizer 1500 Reactor thermal power at 88% holding due to "C" and "H" condensate demineralizers being out of service 4/16/80 2040 "H" condensate demineralizer maintenance completed and placed in service 2100 Commenced PCIOMR from 88% the mal power 4/17/80 1300 Reactor thermal power at >99% commenced 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> fuel soak 4/18/80 0100 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> fuel soak completed reactor thermal power at >99% steady state 2320 Reduced thermal power from 99% to 85% for turbine C.V. and SI's 4/19/80 0330 Turbine C.V. tests and SI's completed commenced PCIOMR from 85% thermal power 1030 Reactor thermal power at 99% steady state i
7 Significant Operational Events Unit 1 Date Time Event 4/20/80 1600 Commenced reducing thermal power for shutdown repairs to reactor water clean up system FCV-69-1 valve l
1722 Reactor scram No. 121 (manual) from 35% thermal t
power to accommodate maintenance to FCV 69-1 valve i
4/21/80 2020 Commenced rod withdrawal for startup 2300 Reactor critical No.141 (Sequence "A")
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4/22/80 0529 Rolled T/G 0550 Synchronized generator commenced power ascension 1500 Reactor thermal power at 43% holding due to high vibration on main turbine 4/23/80 0805 Reduced thermal power from 43% to 35% due to high turbine vibration 0817 Reactor scram No. 122 (manual) from 35% thermal power for turbine balancing 1650 Turbine balancing completed commenced rod with-drawal 1750 Reactor critical No. 142 (Sequence "A")
2100 Rolled T/G 2205 Tripped main turbine due to high vibration 2252 Rolled T/G 2314 Synchronized generator commenced power ascension l
4/24/80 1355 Reduced thermal power from 73% to 64% due to "B"
,i recirculation pump motor upper bearing oil level low 1440 Reduced thermal power from 64% to 50% to trip "B" recirculation pump 2116 "B" recirculation pump restored to service 2122 "B" re.dtculation pump removed from service due to low oil level alarm
)
2140 Commenced reducing thermal power for shutdown due to "B" recirculation pump problems 2200 Reactor scram No. 123 (manual) from 36% thermal power to accommodate maintenance to "B" recir-culation pump motor 4/25/80 1435 Commenced rod withdrawal 2107 Reactor critical No. 143 (Sequence "A")
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Significant Operational Events Unit 1 4
Date Time Event l
4/26/80' 0500 Rolled T/G 0530 Synchronized generator commenced power ascension 1800 Commenced PCIOMR from 77% thermal power I
4/27/80 1100 Reactor thermal power at 88%' rod limited 1610 Reduced thermal power from 88% to 64% for control rod pattern cdjustment 1645 Control rod pattern adjustment completed commenced power ascension 1830 Commenced PCIOMR from 80% thermal power 4/28/80 1500 Reactor thermal power at 99% maximum flow (rod limited) 4/30/80 2400 Reactor thermal power at 99% maximum flow (rod limited 4
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9 Significant Ooerational Events Unit 2 Date Time Event 4/01/80 0001 Reactor thermal power at 97% sequence "B" Maximum flow (rods /Xe limited) 4/04/80 2315 Reduced thermal power from 97% to 85% for turbine control valve tests and SI's 4/05/80 0140 Turbine control valve tests and SI's completed commenced power ascension 0330 Commenced PCIOMR from 91% thermal power (rod sequence "B")
1340 Reactor thermal power at 98% maximum flow (rods /
Xe limited) 4/10/80 1500 Reactor thermal power at 97% maximum flow (rods /
c Xe limited) 4/12/80 2330 Reduced thermal power from 97% to 80% for turbine C.V. tests and SI's 4/13/80 0030 Turbine C. V. tests and SI's completed commenced powar ascension 0200 Commenced PCIOMR from 90% thermal power 1500 Reactor thermal power at 97% maximum flow (rods /
Xe limited) 4/15/80 0715 Reactor scram No. 96(1)from 97% thermal power on i
low water level due to inadvertent opening of main steam flow control circuit 0914 Commenced rod withdrawal 1152 Reactor critical No. 107 (Sequence "A")
1445 Rolled T/G 1515 Synchronized generator commenced power ascension 1610 Reactor thermal power at 25% holding due to the process computer being out of service 4/16/80 0030 The process computer placed in service commenced power ascension 1500 Commenced PCIOMR from 724 thermal power (Sequence "A")
4/18/80 1500 Reactor thermal power at 94% flow limited I
10 Significant Operational Events Unit 2 Date Time Event 4/19/80 2100 Reduced thermal power from 94% to 65% for removal of "C" string high pressure heaters from service for a valve torque test 2240 "C" string high pressure heaters placed in service commenced power ascension 4/20/80 0015 Commenced PCIOMR from 70% thermal power 1123 Reduced thermal power from 75% to 70% for removal "B" high pressure heaters from service for main-tenance 1430 "B" string high pressure heaters placed in service commenced PCIOMR from 70% thermal power 4/21/80 1605 Reactor thermal power at 99% maximum flow (rods /
Xe limited) 4/22/80 0230 Reduced thermal power from 99% to 93% for condensate flow control problemgy) from 93% thermal power while 1056 Reactor scram No. 97 performing SI's 1242 Commenced rod withdrawal 1340 Commenced bring reactor to cold shutdown 2028 Reactor at cold shutdown 4/24/80 0740 Commenced rod withdrawal 4/25/80 0504 Reactor critical No. 108 (Sequence "A")
1316 Rolled T/G 1355 Synchronized generator commenced power ascension 4/26/80 0505 Commenced PCIOMR from 73% thermal power 4/27/80 1105 Reduced thermal power from 99% to 70% for removal of "C" string low pressure heaters from service for maintenance 1232 Commenced power ascension 1430 Commenced PCIOMR from 75% thermal power 4/28/80 2020 Reactor thermal power at 95% holding for TIP run 2340 TIP run completed resumed PCIOMR 4/29/80 0700 Reactor thermal power at 98% CPR limited 4/30/80 2400 Reactor thermal power at 98% CPR limited
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11 Significant Operational Events Unit 3 Date Time Event 4/01/80 0001 Reactor thermal power at 99% maximum flow (rod limited) 4/05/80 0145 Reduced thermal power from 99% to 76% for turbine control valve tests and SI's I
0240 Turbine control valve tests and SI's completed commenced power ascension 0430 Coumenced PCIOMR from 95% thermal power (Sequence "B")
0730 Reactor thermal power at 99% maximum flow (rod limited) 4/09/80 0935 Reduced thermal power from 99% to 72% due to false high river temperature (see below) 1011 River temperature sensor malfunction commenced power ascension 1715 Reactor thermal power at 99% maximum flow (rod limited) 4/11/80 2030 Reduced thermal power from 99% to 48% for control rod sequence exchange from "B" to "A" 4/12/80 0145 Control rod sequence exchange from "B" to "A" com-pleted commenced power ascension 0345 Peactor thermal power at 75% holding for turbine C. V.
test and SI's 0445 Turbine C. V. tests and SI's completed commenced i 's PCIOMR from 75% thermal power 1900 Reactor thermal power at 99% maximum flow (Rod limited) 4/17/80 1500 Reactor thermal power at 97% maximum flow (roa limited) 4/19/80 0040 Reduced thermal power from 97% to 85% for. turbine C. V. tests and SI's 0135 Turbine C. 7. tests and SI's completed and core flow indicator was re-calibrated allowing the unit to reach 99% thermal power 0301 Commenced PCIOMR from 95% thermal power 0700 Reactor thermal power at 99% maximum flow (rod limited) 4/26/80 2355 Reduced thermal power from 99% to 85% for turbine C. V. tests and SI's c
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i 12 Significant Operational Events Unit 3 Date Time Event 4/27/80 0120 Turbine C. V. tests and SI's completed commenced power ascension 0330 Commenced PCIOMR from 95% thermal power 1500 Reactor thermal power at 99% maximum flow (rod limited) 4/30/80 2400 Reactor thermal power at 99% maximum flow (rod limited)
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e 13 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-259 UNIT Browns Ferry 1 DATE 5-1-80 CONIPLETED BY Don Green TELEPHONE 205/729-6846 310 NTH Acril 1980 DAY AVER AGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (51We-Net)
(stwe. Net) 1
-3 g7 1039 2
353 is 1056 455 19 1041 3,
401 4
20 735 13 5
21
-8 6
22 260 760' 23 137 7
787 8
24 540 745 25
-8 9
586 26 490 10 t
II 889 27 892 (CST to CDST) 12 954
- s 1015 790 1067 13 29 955 14 30 1071 15 955 3;
16 942 INSTRUCTIONS On this format list the average daily unit power leselin N1We. Net for each day in the reporting month. Compute to the nearest whole megawatt.
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(9/77) f i
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14 AVERAGE DAILY UNIT POWER LEVEL i
DOCKET NO.
50-260 UNIT Browns Ferry 2 DATE 5-1-80 f
CONIPLETED BY Don Green TELEPHONE 205/729-6846 1
a SiONTH Ahril 19R0 l
DAY AVER AG'E DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL l (SIWE-Net)
(Slwe-Net) 1062 17 gA1 I
2 1056 18 963 1071 3,,
19 934 4
1060 20 816 5
1045 21 1030 6
1056 22 451 7
1057 3
_9 8
1047 24
-10 9
1045 25 169 10 1047 26 794 i
11 1062 27 875 -(CST to cnsT) 12 1022 23 947 13
' 1018 29 1060 1030 14 30 1072 l
15 141 31 16 595 4
INS'IRUCTIONS 1
On this funnat,!ist the average daily unit power leselin SIWE Net for each day in the reporting inonth. Compute to the nearest whole megawatt.
l (9./77 )
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15 AVERAGE DAILY UNIT POWER LEVEL i
DOCKET NO.
50-296 UNIT Browns Ferry 3 DATE 5-1-80 Don Green COM/LETED BY 205/729-6846 TELEPHONE MONTH April I
DAY AVERAG'E DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe-Net t l (MWe-Net) i 1079 17 in6a l'083 is 1067 2
1082 19 1067 3,,
1074 4
1080 20 1063 21 1079 5
1079 6
22 1075 1077 1082 23 7
8 1077 2.g 1078 1069 25 1080 9
1074 10 26 1072 1016 27 1070 (CST to CDST)
- I II 863 28 1078 12 13 1066 29 1079 1074 14 30 in?1 15 1067 3
16 1066 i
INSTRUCTIONS On th;s format, list the average daily unit power lesel in MWe Net for cach day in the reporting month. Compute to the nearest whole megawatt.
(9/77)
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OPERATING DATA REPORT DOCKET NO. 50-259 DATE 5-1-80 COhlPLETED BY Den Green TELEPHONE 205/729-6846 OPERATING STATUS
- 1. Unit Name:
Browns Ferry 1 Notes
- 2. Reporting Period: April 1980
- 3. Licensed Thermal Power (S!Wt):
3293
- 4. Nameplate Rating (Gross 51We):
1152 1065
- 5. Design Electrical Rating (Net 51We):
- 6. 51aximum Dependable Capacity (Gross StWe):
1098.4 1065
- 7. 51aximum Dependable Capacity (Net SlWe):
- 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 31We):
N/A
- 10. Reasons For Restrictions,if Any:
N/A This Month Yr..to.Date Cumulative i
I
- 11. Hours In Reporting Period 719 2.903 50.401
- 12. Number Of Hours Reactor Was Critical 645.70 823:60 29,100,88
- 13. Reactor Reserve Shutdown Hours 73.30 247.93 4,937.54
.,14 Hours Generator On.Line 614.15 727.37 28.340.10
- 15. Unit Reserve Shutdown Hours 0
0 0
- 16. Gross Thermal Energy Generated (MWH) 1,535,026 1,741,532 75,878,025
- 17. Gross Electrical Energy Generated (MWH) 502,970 _,
572,960 25,091,420
- 18. Net Electrical Energy Generated (MWH) 490,352 549,605 24,351,573
- 19. Unit Service Factor 85.4 25.1 56.2
{
- 20. Unit Availability Factor 85.4 25.1
'i 6. ?
- 21. Unit Capacity Factor IUsing MDC Net) -
64.0 17.8 45.4-
- 22. Unit Capacity FactoriUsing DER Net) 64.0 17.8 45.4
- 23. Unit Forced Outage Rate 14.6 28.3 32.9
- 24. Shutdowns Scheduled Over Next 6 Months (Type.Date.and huration of Eacht:
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
- 26. Units in Test Status IPrior to Commercial Operation):
' Forecast
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". Achieved INITIA L CRITICALITY cjNITIAL ELECTRICITY COS1M ERCIAL OPER ATION l
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OPERATING DATA REPORT DOCKET NO. 50-260 DATE 5-1-80 COMPLETED BY Don Green TELEPHONE m/ / 49-6546 j
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OPERATING STITUS
- l. Unit Name:
Browns Ferrv 2 Notes
- j
- 2. Reporting Period:' April 1980
- 3. Licensed Thermal Power (MWt):
3293
'4. Nameplate Rating '(Gross MWe):
1152
- 5. Design Electrical Rating (Net MWe):1065
- 6. Maximum Dependable Capacity (Gross MWe):
1098.4
- 7. Maximum Dependhble Capacity (Net MWe):
1065
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:
N/A
- 9. Power Level To Which Restricted. If A (Net MWe):
N/A
,10. Reasons For Restrictions,If Any:
5 i
This Month Yr to.Date Cumulative II. Hours In Reporting Period 719 2,903 45.312
[
- 12. Number Of Hours Reactor Was Critical 648.25 2,431.08 26,915.56
- 13. Reactor Reserve Shutdown Hours 70.75 471.92 17.96A RA
,14. Hours Generator On.Line 636.02 2.367.44 26.031.7s
,i
- 15. Unit Reserve Shutdown Hours 0
0 n
- 16. Gross Thermal Energy Generated (MWH) 1.888,675 6.660.849 72.s's sao
- 17. Gross Electrical Energy Generated (MWH) 630,280 _
2.224.880 24.174.94s
- 18. Net Electrical Energy Generated (MWH) 614,015_
2,163,956 23.495.4~25
- 19. Unit Service Factor 88.5 81.6 57.5
- 20. Unit Availability Factor 88.5 81.6 57.5 80.2 70.0 48.7
- 21. Unit Capacity Factor (Using MDC Net)
- 22. Unit Capacity Factor (Using DER Net) 80.2 70.0 AA 7
- 21. Unit Forced Outage Rate 11.5 18.4 35.5
- 24. Shutdowns Scheduled Over Next 6 Months (Type. Date.and buration of Each t:
Refuel outane' Sect. 1980
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- 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
- 26. Units In Test Status IPrior to Commercial Operation):
Forecast Achieved INITIA L CRITICA LITY fjNITIA L ELECTRICITY COMMERCIA L OPERATION I
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l OPERATING DATA REPORT
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DOCKET NO.
50-296 DATE 5-1-80 i
C051PLETED BY Don Green TELEPHONE 90s/779-6846 l
i OPERATING STITUS
- 1. Unit Name:
Browns Ferry 3 b
5 g
- 2. Reporting Period:l Anril 1980
- 3. Licensed Thermal Power (N1Wtp:
3293
- 4. Nameplate Rating (Gross 51We):
1152 i
- 5. Design Electrical Rating (Net SIWE):
1065 1098.4
- 6. Slaximum Dependable Capacity (Gross htWe):
- 7. Staximum Dependhble Capacity (Net 51We):
1065
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:
N/A
_9. Power Level To which Restricted,If Any (Net AlWe):
M/A
- 10. Reasons For Restrictions. !f Any:
N/A t
t This Sicath Yr. to Date Cumulative i1. Ifours In Reporting Period 719 2.901 27,767 f
- 12. Number Of Hours Reactor Was Critical 719 2,491.43 21,398.98
- 13. Reactor Reserve Shutdown Hours 0
0 1.658.31
- 14. Hours Generator On Line 719 2,467.93 20,905.74 i
- 15. Unit Reserve Shutdown Hours 0
0 0
4
- 16. Gross Thermal Energy Generated (51WH) 2.319.562 7,807,443 60,915,309
- 17. Gross Electrical Energy Generated (51WH) 783,420 _
2,638,210 20,040,790
- 18. Net Electrical Energy Generated (htWH) 765.935 2.572.441 19,460,214
- 19. Unit Service Factor 100 85.0 75.3
- 20. Unit Availability Factor 100 85.0 75.3
- 21. Unit Capacity Factor (Using SIDC Net) 100 83.2 65.8
- 22. Unit Capacity Factor (Using DER Net) 100 83.2 65.8 1
- 23. Unit Forced Outage Rate 0
15.0 9.8
- 24. ShutdownsScheduled Over Next 6 Months (Type.Date.and buration of Eacht:
Refuel outage October 1980 j
- 25. If Shur Down At End Of Report Period. Estimated Date of Startup:
- 26. Units in Test Status IPrior t9 Commercial Operation):
Forecast Achieved INITIA L CRITICALITY I
.JNITFAL ELECTRICITY j
COh31ERCIAL OPER ATION l
lI E (of77) i m
DOCKET N0' 50-259 UNif SilUTDOWNS AND POWER REDUCTIONS UNIT N AME B rntm q Forrv 1 DATE 5-1-80 COMPLETED BY Don Green TELEPilONE 205/729-6846 REPORT MONTil Anril i
n.
E c
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$ $3 Licensee
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$"3 1,
Cause & Cor&ctive 9
Action to j No.
Date g
3g g
.2 s s Event gg y=
y 3 ;g c Repori n mO EO Prevent Recurrence H
l i
111 800401 F
22.93 A
2 liigh traperature on "B" recire. pump cont.
thrust bearing.
i 112 800407 S
B Derated for RTI 23A (Feedwater Contro. )
113 800408 S
B Derated for RTI 23A (Feedwater Contro1) 114 800409 S
B Derated for RTI 32A (Recirc. pump
_f controls) 115 800413 S
11 Derated for control rod adjustment.
116 800415 F
A "B" recirc. pump trip.
G 117 800420 F
36.47 A
2 Maintenance to FCV-69-1, 118 800423 F
14.95 B
2 Main turbine balancing (lligh vibration) 119 800424 F
A Derated.idue to "B" recirc. pump low oil leveli. signal.
120 800424 F
30.50 A
2 Maintenance to "B" recire. pump (low oil level signal) (loose wires in conduit) 121 800427 S
11 Derated for control rod pattern adj tis tmen t.
l 2
3 4
F: Forced Reason:
Method:
Exhibit G-Instructions S: Scheduled
. A.Lyuipment Failure (Explain) 1-Manual for Preparation of Data j
H-Maintenance of Test
- 2. Manual Scram.
Entry Sheets for Licensee C-Refueling 3-Automatic Scram.
Event Report (LER) File (NUREG-D.Itegulatory Restriction 4.Other (Explain t 0161)
I'-Operator Training & License Examination F-Administrative 5
G-Operational Eiror (Explain)
Exhibit I - Same Source (9/77) 11-01her (Explain) s s
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s UNIISilUTDOWNS AND POWER R'EI)UCTIONS DOCKET NO.
50-260 UNIT NAME Browns Ferry 2 DATE 5-1-80 COMPLETED BY Don Green REPORT MONTil Anril TELEPHONE 205/729-6846
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$Yh Licensee
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je, Cause & Corrective No.
Date g,
3g jj jj$
Event g?
9-3 Action to Report #
mO EV Prevent Recurrence jE 3 ;f3 6
c g
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O 132 800415 F
8.0 G
3 Low Rx water level signal due to inadvertant opening of main steam flow control circuit.
133 800419 F
B Derated to take "C", llP string 15 eaters out'of service for testine.
134 800422 F
74.98 G
3 III Rx water level signal due to personnel error during S.I.
nO 135 800427 F
B Derated to take "C" string L. P.
heaters out of service for maintenance i
3 4
F: Forced Reason:
Method:
Exhibit G-Instructions S: Scheduled A-Equipment Failure (Explain) l Manual for Preparation of Data It-Maintenance of Test 2 Manual Scram.
Entry Sheets for Licensee C Refueling 3 Automatic Scram.
Event Report (LER) File (NUREG-D-Regulatory Restriction 4-Other (Explain) 0161)
IDOpciator Tiaining & License Examination F-Administialive 5
G-Operational Es tor (Explain)
Exhibit I - Same Source (9/77)
Il-Other ( Explain) t f
1 i
UNif SIIUTDOWNS AND POWER REDUCTIONS DOCKET NO.
50-296 UNIT N AME Browns Ferry 3 DATE 5-1-80 COMPLETED BY Don Green REPORT MONTil Anri1 TELEPIIONE 205/729-6846 w.
E E
.5 ?
3 j Ei Licensee
,Ev, je, Cause & Correceive No.
Date 3
3g s
jg5 Event gy 93 Action to j=
5 3 ig g ReporI a mo gu prevent Recurrence H
e v
Q 120 800405 S
B Derated to perform turbine control valve tests and SI's.
121 800409 F
A Derated due to river temperature sensor malfunction (false high indication).
p 122 800411 S
H Derated for control rod sequence exchange from "B" to "A."
d l
.3 4-F: Forced Reason:
Mettuxt:
Exhibit G-Instructions S: Scheduleil A Equipment Failure (Explain) 1-Manual for Preparation of Data It-Maintenance of Test 2-Manual Scram.
Entry Sheets for Licensee C Refueling 3 Automatic Scram.
Eveni Report (LER) File (NUREG-D Regulatory Restriction 4-Other (Explain) 0161)
E-Operator Training & Ucense Examination F-Administrative 5
G Operational Enror (Explain)
Exhibii I - Same Source (9/77)
Il-Ot her ( Explain) e er
BROWNS FERRY NUCLEAR PLANT UNIT 1
!!ECllAliICAL HAINTE!MNCE SUt@!ARY
]
CSSC EQUIPl!ENT For the Month of - April 19 80 EFFECT ON SAFE ACTION TAKEN DATE SYSTD1 COMPONENT NATURE OF OPERATION OF CAUSE OF RESULTS OF 10 PRECLUDE MAINTENANCE THE REACTO' HALFUNCTION MALFUNCTION RECURRENCE 4/2/80 CRD CRD 26-19 scram will not scram Solenoid valve CRD would not scram Instdlled new solenois pilot valve for scram test None core assembly valve repair kit was stuck TR 147833 4/3 RCIC Inner rupture ruptured disc None ruptured disc RCIC inoperable Installed new rupture disc on RCIC disc TR 153165 4/7 Fuel Fool Panel 25-16 Temp. isolatioi Cooling valve instal)et None None None.
N/A TR 138208 4/7 HPCI Exhaust Line Rupture disc Rupture disc Steam leaks Removed and replaced blown None blown inner rupture disc TR 153166 4/21 RilRSW Panel 1-25-338 Packing leak None Packing leak Water line leaking Tightened packing TR 162190 4/21 RBCCW Pump B seal water line Pump seal leak and Tightened union y
water line leaking None Union leak loss of suction TR 162191 N
's i
l l
A*MuMg4 EROWNS FERRY NUCLEAR PIANT UNIT
_9 IECllANICAL MAIi1TENANCE SUtefARY CSSC EQUIPitENT
'For the Month of Anril 19 80 ACTION TAKEN EFFECT ON SAFE DATF.
SYSIDI C011 POTENT NATURE OF OPERATION OF CAUSE OF RESULTS OF ID PRECLUDE MAINTENANCE Tile REACTOR MALFUNCTION MALFUNCTION RECURRENCE 4/2 Fuel pool Panel 25-16 Temp. Isolatioa None None None N/A TR 138209 cooling valve insta11eil 4/18 Fuel pool Pump A Packing leak None Packing leak Leaking packing Adjusted packing TR 166514 cooling 4/23 Drywell Drywell blower loose damper None Loose damper Inoperable damper Readjusted damper and reinstalled on rod ventilation TR 159594 4/23 Main steam MSIV's A, B, C, Hanger clamps Loose hanger MSIV's inoperable Replaced hanger clamp.
TR 153174 and D were missing None 4/23 Main steam Valves 1-533 &
Drain valves Cracked stationer y Leaking valves Replaced bonnet stem 1-532 leaking None seat and upper seat TR 166533 E$
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BROWNS FERRY WUCLEAR PIANT UNIT
'Cou, mon.
MECilANICAL MAINTENiLNCE SUNIARY CSSC EQUIPi1ENT
~For the Month of April 19 80 ACTION TAKEN EFFECT ON SAFE DATE SYS1EM COMPONENT NATURE OF OPERATION OF CAUSE OF RESULTS OF 10 PRECLUDE MAINTENA!!CE Tile REACTOR MALFUNCTION MALFUNCTION RECURRENCE 4/15 RilRSW D3 Pump Packing leak None Loose packing vibrating pump adjusted packing TR 159473 4/21 RilRSW B1 Pump Pump vibration Nones Loose coupling pump vibration tightened coupling TR 155377 4/12 RilRSW Al Pump Excessive None' Pump worn out pump vibration removed and rebuilt pump. MMI 29 Vibration TR 137205 4/22 RilRSW A3 Pump
- Vibration limit s Worn impe11ers, 0-- pump vibration replaced Impe11ers, too high None rings and bottom o-rings and bushings bushings TR 159332 U
e 4
i t
- ~_.
1*
ERO'.GS FERRY IlUCLEAD PLA?iT UllIT ELECTRICAL HAINTENANCE sum!ARY CSSC EQUIPt!ENT For the Month of ' April 19 80
~
's Action Taken Effect on Safe Nature of Operation of Cause of Results of To Preclude Date System Component Haintenance The Reactor Halfunction Malfunction Recurrence 4/17/81 480V shut-Normal feeder Bus failed at Loss of recirc-Bad bus. Failure Loss of IB 480 Volt Replaced damaged b,uss down board bus buss way joint ulation pump 1B of bus at buss shutdown ' board for a sections and tested 18 231 above the and loss of IB way joint.
short period of time in accordance with EMI 77.1.
board.
SLC pump motor.
LER 259-8031 I
Board was re-TRf 148319, 146724, energized on.
alternate feed.
146727, 166907, 16690.
I 143521, 166918 i
4/17/80 RHR SYS lE RX Hov lE Rx HOV Lost loop II Feeder wires Caused board to trip Replaced wire and Board spare board spare LPCI valves for mashed behind out. Board was de-breaker checked ok.
I compartment compartment automatic
- breaker, energized for about TRf 136931 breaker breaker in operation. RHR four minutes.
LER # 259/8033 operation pump 1A out of e
service for heat exchange l
repairs.
a I
4/21/80 Reactor FCV 69-1 Valve would NONE Rire 16EC1 Motor in operation Changed setting water not close with partially broken on closed torque clean-up a close signal at lug switch from 1 to 2.
Reluged wire.
Checked ok.
TRf 162183 LERf 259/8034 4/20/80 CRD CRD pump 1A Check bearing NONE
' Unknown Oli level low.
Put in 35 pint of oil TRI 162174 oil level j
l.
i l
liRO'GS FERl;Y NUCLEAll PLANT UllIT _ i CLECTRICAL MAINTENANCE SUIR!ARY CSSC EQUIPt!ENT
' For the Month of April 19 80 Action Taken Effect on Safe Nature of Operation of Cause of Results;of To Preclude D.te Sys ten:
Component liaintenance The Reactor Malfunction Malfunction R.acurrence l
4/21/80 RilR Check valve Red and green NONE Reed switched Bad switched.
Adjusted reed switched.
- 74-68 light on RIIR out of adjust-TR# 159387 ment.
system II check valve.
l 4/28/80 Primary FC0 64-5
- FCO-64-5 NONE Position switch Improper indication. Adjusted position switch.
containment
.shows in mid out of adjust-TR# 162050 ment.
position.
f
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BRO'.lNS FERRY NUCLEAll PLANT UNIT 2
ELECTRICAL MAINTENANCE SUta!ARY CSSC EQUIPf1ENT For the Month of April 19 80 Action Taken Effect on Safe Nature of Operation of Cause of Results of To Preclude D..t e Sys tere Component Maintenance The Reactor Malfunction Malfunction Recurrence 4/19/83 IIPCI Valve 73-5 Valve 73-5 NONE Level switch Level switch not Cleaned, lubricated will not close 73-5 stuck working broperly, and freed Icvel closed.
switch.
TRf 166598 l
4/23/80 Main steam MSIV 1-37 Limit switch
.NONE Arm on limit Bad limit switch.
Replaced arm on on MSIV l-37 l
switch was bad.
operator and set for green light limit switch, has malfunc-
- R# 159391 tioned_ keeping, green light on
/e/23/80 Reactor FCV 68-1 FCV 68-1 NONE Torque switch on Bad torque switch.
Cleaned torque switcl water inoperable.
valve was dirty TRf 166292 recircula-and not making l
- tion, contact.,
I I
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=
i
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3 IIRO',s'NS FERRY NUCLEAR PLMIT UllIT ELECTRICAL f!AINTENANCE SUt!!!ARY CSSC EQUTPf1ENT
- For the Month of April 19_HQ Action Taken Effect on Safe llature of Operation of Cause of Results of To Preclude D-te System Component
!!aintenance The Reactor Halfunction Malfunction Recurrence i
d'
'4/12/80 Drywell Isolation Alarm drywell NONE Ead coil on Bad relay.
Replaced coil floor valve.
floor drain relay 16AK20.
cleared annunciation.
TRf 145982
- drain, isolation I
valves closed and will not clear.
4/16/80 Shutdown Spare 4kV Spare 4kV ACB NONE Racking release Spare breaker would Straightened racking Board ACB at 3EB 4kV level bent on not operate properly level. Checked ok, shutdown board breaker.
TRf 136927 I
would not close when racked into I
compartment.
he-luggedwire.
8 Reactor FCV-69-2 FCV-69-2 will NONE
[
S 1 wire going Bad motor.
l4/17/80 not close with to motor, lug Checked ok.
water l
clean-up, the motor, broken off.
TRf 166756 LER f 296/8011 i
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9
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BROWNS FERRY NUCLEAR PLANT UNIT 1 2,3 0
INSTRUMENT MAINTENANCE
SUMMARY
CSSC EQUIPMENT FOR Tile MONTl! OF April 19 80 NATURE EFFECT ON SAFE CAUSE ACTION TAKEN DATE SYSTDI COMPONENT OF OPERATION OF OF RESULTS OF TO PRECLUDE MAINTENANCE THE REACTOR MALFUNCTION MALFUNCTION RECURRENCE Unit 1 4-2-80 Radiation FA-90-165 Mairtenance Nenc Moisture in Sens-Flow Abnormal Alarm None Monitoring ing Line e
4-6-80 Neutron APRM "B" Flow Calibrate None Instrument Drift Spurious Rod Blocks None Monitoring Converter 4-7-80 RCIC TS-71-2G Repair None Broken lleater Wire Could Not Function-None ally Test 4-14-8CNeutron APRM "A" and Calibrate None Instrument Drift Rod Blocks None Monitoring "B"
4-14-80 Primary Con-LT-64-54 Repair None Faulty Amplifier Indicated Low Water None 8
Level in Torus tainant 4-15-80 Standby LI-63-1B Calibrate None Instrument Drift Reading Did Not Agree None With Rod Measurement
, Liquid Con-crol 4-23-8C Radiation TS-90-144A & B Calibrate None Instrument Drift False Alarm On Temp-None erature Monitoring Unit 2 f
,4 80 Standby LI-64-1B Calibrate None Instrument Drift Did Not Agree With None Rod Measurement Liquid Con-trol 4-24-80 Neutron APRM "C" Replace None Faulty Switch Unreliable Selec' tion None of LPRM Input Konitoring 6
l ll1 11l ll1\\
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32 OUTACE
SUMMARY
April 1980 The major outage efforts during this month have focused on security modifications and the completion of necessary cooling tower work to make the cooling towers available for the summer season.
A major effort is being mounted to complete the committed sec-urity modifications by the June 30th deadline. The E field parameter detection system has been completed and three of the eleven multi-plexers for the card reader system are ready to be tied in, with security arrangements being made with public safety to maintain door security during the tie ins.
The work on the two of three trip logic on the cooling towers as well as the cooling tower bypass switch mod was essentially completed; lacking only the post modifications I
testing. Several other cooling tower mods are in various stages of completion on towers four and five with an expected completion date, of May 9 on tower five and May 16 on tower four, thus making the towers available for summer cperation.
Several other jobs were started with major emphasis being placed on timely completion of the unit 3 condenser pullout area as a low level radwaste storage area, and the completion of refuel floor overhead maintenance for the high density storage rack mods. Work was also started on an outage shop facility to accommodate necessary equipment to perform f
e 33 OUTAGE
SUMMARY
(Continued)
- April 1980 outage associated work and thus clear the turbine breezeway; con-struction of an ambulance storage facility; and RHRSW check valve modification. Several safety related modifications were started.
Structual steel was installed for the hypochloride' building; and temporary construction facilities are being erected for the perma-nent LLRW storage modules. Preliminary work for the installation of recirculation pumps, high and low level oil alarms, and duct work prefabrication for a steam tunnel duct modification was completed in preparation for a short unit 2 outage.
I l
.