ML19309E796

Monthly Operating Repts for Mar 1980

ML19309E796
Person / Time
Site:	Browns Ferry
Issue date:	04/02/1980
From:	Thom T TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML18025A817	List: ML18025A816 ML19309E796
References
NUDOCS 8004240415
Download: ML19309E796 (32)

Text

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TENNESSEE VALLEY AUTHORITY DIVISION OF POWER PRODUCTION BROWNS FERRY NUCLEAR PLANT MONTHLY OPERATING REPORT A

March 1, 1980 - March 31, 1980 0

DOCKET NUMBERS 50-259, 50-260, AND 50-296 LICENSE ND!BERS DPR-33, DPR-52, AND DPR-68

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Submitted By: f/ /*/ ////ner

/ Plant Supe'rintendent 8 0 0 4 24 0 y /5 i

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I TABLE OF CONTENTS t

1 Operations Sunnaary . . . . . . . . . . . . . . . . . . . . . . 1 L Refueling Information . . ..... ... . . . . . . . . . . 3 Significant Operational Events . ...... . . . . . . . . . 5 Average Daily Unit Power Level . . . . . . . . . . . . . . . . 12 ,

Operating Data Reports . . . . .. .. ... . . . . . . . . . 15 Unit Shutdowns and Power Reductions. . . . . . . . . . . . . . 18 Plant Maintenance . . . . .. ...... . . . . . . . . . . 21 Outage Sununary . . . . . . .. .. ........ . . . . . . 30 l I r

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s Operations Summary ,

March 1980 The following summary describes the significant operational activities '

l during the reporting period. In support of this summary, a chronological log of significant events is included in this report.

There were fif teen reportable occurrences (plus two supplemental reports) reported to the NRC during the month of March.

i Unit 1 There were three scrams on the unit during the month. On March 22, and 29, the reactor was manually scrammed for maintenance (bearing high ,

temperature alarm and bearing low oil alarm) on the "B" recirculation pump motor. The reactor scrammed on March 27 because of generator neutral overvoltage. On March 22, the unit returned to service (BOC 4) af ter its refueling outage.

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Unit 2 l

There was one scram on the unit during the month. On March 9, the reactor scrammed when "B" channel, 2 and 3 groups, scram valve solenoids de-energized from an undetermined cause followed closely by a reactor-low water activated auto scram. The unit returned to service March 3 after an outage to repair the HPCI turbine bearing pedestals. l I

Unit 3 There were no scrams on the unit during the month.

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2 Operations Summary (Continued)

March 1980 ,

4 Fatigue Usage Evaluation f

l-The cumulative usage factors for the reactor vessel are as follows: ,

Location Usage Factor Unit 1 Unit 2 Unit 3 Shell at water line 0.00443 0.00328 0.00291 ;

i Feedwater nozzle 0.20862 0.14224 0.10716 ,

closure studs 0.18532 0.11771 0.08728 Note: This accumulated monthly information satisfies technical specification section 6.6. A.17.b(3) reporting requirements.

Common Systems  :

Approximately 1.43E+06 gallons of, waste liquid were discharged containing approximately 1.11E+00 curies of activity, i

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3 Refueling nformation March 1980 Unit 1 Unit 1 is schedul ' for its fourth refueling beginning on April 1, 1981, with a scheduled restart date of June 21, 1981. This refueling will involve loading additional 8 x 8 R (retrofit) fuel assemblies ,

into the core. ,

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.

Unit 2 Unit 2 is scheduled for its third refueling beginning on September 1, 1980, with a scheduled restart date of October 7, 1980. 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 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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Refueling Information (Continued)

March 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 October 1,  ;

I'980, with a scheduled restart date of November 22, 1980. This EOC-3 refuel- '

ing 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 po'ol. 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 I

fuel pool without exceeding that capacity and maintaining full core discharge capability in the pool.

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Significant Operational Events Unitl Date Time Event 3/01/80 0001 Unit in refueling outage (EOC-3) 3/19/80 1100 Commenced rod withdrawal 1309 Reactor critical no. 134 (Sequence "A")

1750 Commenced inserting control rods for shutdown for main-tenance to relief valve no. 1-18 (Popped open) 2300 Reactor at cold shutdown 3/20/80 1400 Commenced rod withdrawal, maintenance to relief valve completed 1525 Reactor critical no. 135 (Sequence "A")

3/21/80 0446 Commenced inserting control rods for shutdown to repair leaks in relief valve 1-18 0755 Reactor at cold shutdown 1450 Commenced rod withdrawal, relief valve maintenance completed 1605 Reactor critical no. 136 (Sequence "A")

3/22/80 1400 Rolled T/G 1547 Synchronized generator, commenced power ascension 1720 Commenced shutdown from 21% thermal power 1955 Reactor scram no. 118 manual from 10% thermal power for recirculation pump maintenance (blown inner seal) 3/23/80 0303 Reactor at cold shutdown 3/25/80 1130 "B" recirculation pump seal replaced and all startup requirement met, commenced rod withdrawal 1311 Reactor critical no. 137 (Sequence "A") i 2350 Rolled T/G i 3/26/80 0022 Synchronized generator, commenced power ascension 3/27/80 0559 Rx scram no. 119 5 ) from 26% thermal power (generator neutral overvoltage) 1310 Reactor at cold shutdown 3/29/80 0215 Commenced rod withdrawal 0510 Reactor critical no. 138 (Sequence "A")

1215 Rolled T/G 1246 Synchronized generator, commenced power ascension 2032 Reactor scram no. 120 manual from 30% thermal power due to high temperature on "B" recirculation pump thrust bearing i l

3/30/80 0455' Reactor at cold shutdown 1

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Significant Operational Events Unit 1 Dat? Time Event .

3/31/80 0200 Commenced rod withdrawal 0315 Reactor critical no. 139 (Sequence "B")

0725 Commenced shutdown due to abnormal upper bearing oil level (low) on "B" recirculation pump 2400 Reactor at cold shutdown for "B" recirculation pump _

maintenance i

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Significant Operational Events Unit 2 Date Time Event 3/01/80 0001 Reactor in cold shutdown - primary containment leakage problems 3/02/80 2031 Commenced rod withdrawal (Sequence "A")

2130 Reactor critical no. 105 3/03/80 0837 Rolled T/G 0928 Synchronized generator, commenced power ascension 2346 Reactor thermal power at 65%, holding for SI's and control rod pattern adjustment 3/04/80 2330 Control rod pattern adjustment and SI's completed, commenced power ascension 3/05/80 1200 Commenced PCIOMR from 70% thermal power  !

t 3/07/80 0500 Reactor thermal power at 95%, maxiumum flow 2224 Reduced thermal power from 95% to 63% for removal of "B" recirculation pump from service for M/G set brush replacement 3/08/80 0130 Reduced thermal', power from 63% to 55% for control rod pattern adjustment, control rod pattern adjustment completed, commenced power asension 1500 Co=menced PCIOMR from 68% thermal power 3/09/80 0059 Reactor scram no. 95(1) from 73% thermal power on reactor i low water level while performing SI 4.2.C-1 (APRM functional) '

1530 Commenced rod withdrawal for startup (Sequence "A")

1842 Reactor critical no. 106 2112 Rolled T/G 2133 Synchronized generator, commenced power ascension 3/10/80 2325 Commenced PCIOMR from 65% thermal power 3/13/80 0900 Reactor thermal power at 91% maximum flow 3/14/80 2243 Reduced thermal power from 91% to 50% for control rod. j sequence exchange from "A" to "B' j 3/15/80 0115 Control sequence exchange from "A" to "B" completed, commenced power ascension 0150 Commenced PCIOMR from 567. thermal power 3/17/80 0030 Reactor thermal power at 98%, maximum flow 3/18/80 1325 Reduced thermal power from 98% to'92% from removal of  ;

"C" string high pressure heaters from service for i maintenance '

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8 Significant Operational Events Unit 2 Date Time Event 3/19/80 1710 Maintenance to "C" string high pressure heaters completed, commenced power ascension 1830 Commenced PCIOMR from 95% thermal power 3/20/80 0700 Reactor thermal power at 98%, maximum flow 3/21/80 0230 Reduced thermal power from 98% to 60% due to "A" recircu-lation pump trip (malfunction of the high temperature field relay) 1115 "A" recirculation pump.placed in service, holding at 60%

thermal power for control rod pattern adjustment 1350 Reduced thermal power from 60% to 56% for control rod pattern adjustment .

2350 control rod pattern adjustment completed, com=enced power ascension 3/22/80 0700 Commenced PCIOMR from 68% thermal power 3/23/S0 2030 Reactor thermal power at 99%, =aximum flow 3/26/80 0250 Reduced thermal / power from 99% to 93% for removal of "A" string HP-FW heaters from service for maintenance (leaks) 3/27/30 1245 Reduced thermal power from 93% to 68% thermal power for <

removal of reactor FW pump "A" from service for maintenance  !

1340 Increased load to 73% thermal power and holding for "A" reactor FW pump maintenance 3/28/80 0620 "A" reactor feedpump maintenance completed and pump placed in service, increased thermal power from 73% to 86%, holding for "A" string high pressure heaters maintenance 0955 "A" string high pressure heaters maintenance completed,  !

holding for "B" high pressure heaters maintenance 1050 "B" string high pressure heaters out of service for mainte- 1 nance, reactor thermal power at 86% I l

3/29/80 1140 Reduced thermal power from 86% to 46% for removal of "C"  !

string high pressure heaters for maintenance 2122 "B" string high pressure her.ters maintenance completed and heaters placed in service, holding at 46% thermal power  ;

for "C" high pressure heaters maintenance i 2140 "C" string high pressure heaters maintenance completed and l heaters placed in service, commenced power ascension 3/30/80 0700 Commenced PCIOMR from 70% thermal power

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Significant Operational Events -

Unit 2 Date Time Event 3/31/80 1010 Reduced thermal power from 97% to 80% for removal of "C" condensate booster pump from service 1049 "C" condensate booster pump placed in service, commenced power ascension 1300 Commenced PCIOMR from 93% tharmal power 1700 Reactor thermal power at 97%, maximum flow 2400 Reactor thermal power at 97%, maximum flow l

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-O s 10 Significant Operational Events Unit 3 Date Time Event 3/01/80 0001 Reactor thermal power at 99%, at maximum flow (rod limited) 1028 Reduced thermal power from 99% to 90% due to loss of both 161 volt lines, plant preferred power, control and station air compressors, control bay chillers, and bus tie board 1040 Both 161 volt lines back in service 1045 Control bay chillers in service 1135 Bus tie board back to normal 1315 Commenced power ascension 1400 Loss plant preferred power at 95% thermal power 1450 Plant preferred power restored, commenced power ascension 1500 Reactor thermal power at 99%, maximum flow (rod limited) 3/03/80 0105 Reduced thermal power frca 99% to 85% for turbine CV tests and SI's 0205 Turbine CV tests and SI's completed, commenced power ascension 0300 Commenced PCIOMR from 95% thermal power, sequence "B" 3/04/80 0330 Reactor thermal power at 99%, maximum flow (rod 11aited) 3/08/80 2140 Reduced thermal power from 99% to 70% for turbine CV tests and SI's ,

3/09/80 C225 Turbine CV test and SI's completed, commenced power ascension 0340 Commenced PCIOMR from 90% thermal power 1500 Reactor thermal powcr at 99%, maximum flow (rod limited) 3/ 15/80 0125 Reduced thermal power from 99% to 85% for turbine CV tests and SI's 0300 Turbine CV tests and SI's completed, commenced power ascension 1500 Reactor thermal power at 99%, maximum flow (rod limited) 3/22/80 2002 Reduced thermal power from 99% to 47% for both recirculation pump MG sets (brush replacement) and control red pattern adjustment 3/23/80 0218 Brush replacement on both recirculation pumps and control rod pattern adjustment completed, commenced power ascension 0400 Commenced PCICMR from 65% thermal power 3/25/80 2330 Reactor thermal power at 99%, maximum load (rod limited) 3/29/80 0100 Reduced thermal power from 99% tc 85% for turbine CV tests and SI's 0335 Turbine CV tests and SI's completed, commenced power ascension 0600 Commenced PCIOMR from 95% thermal power

-0805 Reactor thermal power at 99%, maximum load (rod limited)

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Significant Operational Events ,

Unit 3  ;

5 Date Time Event

3/31/80 2400 Reactor thermal power at 99%, maximum load (rod limited) l t

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(1) Personnel error (2) Maintenance error *

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12 AVER AGE DAILY UNIT POhER LEVEL DOCKET NO. 50-259 B'IT Br" owns Ferry 1 DATE 4/ /80 COMPLETED BY Ted Thott TELEPl!ONE ?n a; / 7 79-6 R4 6 MONT11 Starch 1980 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL

, (MWe-Net) (Mwe. Net I -1n 37 -7 2 -8 3g -9 ,

3 -8 -9 l 9

4 -9 ~9 20 3 -5 23 -10 6 -7 15

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-9 -8 23 8 -10 .- -7 l 24 9 -7 -8 25 10 -in 26 151 II -5 2; 60 12

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-7 13 -4 29 68  !

1 14 -6 30 -8

,15 -8 -8 3

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-7 INSTRUCTIONS On this torm.t.hst the avers:;c Jaily unit power feschn MWe Net for each day in the reporting month. Compute to the nearest whole megawatt.

(9/77 )

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AVERAGE D AILY UNIT POWER LEVEL DOCKET NO. 50-260 WIT B ewns Ferry 2 DATE 4/ /80 COMPLETED BY Tad Thon TELEPHONE 205/729-6846

.i MONTH March 1980

.s DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net) (Mwe. Net)

I -6 37 1063 2 -5 gg 1035

.3 287 gg 1001 4 643 20 1063 5 741 620 21 6 966 787 7 22 7 976 967 23 g 683 . 34 1064

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9 55 25 1061 10 545 1011 26 744 -

883 g g 12 885 882 33 13 973 681 39 34 954 . 809 39

,15 695 3g 1036 16 c59

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INSTRUCTIONS On this format. list the netage daily unir power focian \lwe Net for each day in :he reporting snonth. Compute to the nearest whole me;pw.stt.

1 (9/77) e

s 14 4 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-296 UNIT Br* owns Ferry 3 DATE A/9/nn COMPLETED BY Tod Thom TELEPHONE 205/729-6846 l'.

MONTil llarch 1980 a

DAY AVER AGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (51We-Net) (SIWE. Net) 1 1076 17 1080 2 1063 gg 1080

.3 1061 1074 39 4 In77 20 1075 5 1084 ;g 1073 6 1077 952 7 22 7 1079 753

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23 3 ID49

• 962 24 9 1067 ' I- 1070 10 1075 1084 26 11 1082 -

1077 27 12 1083 1084 28 13 1088 1055 29

,4 1074 , 1079 39

,15 1067 31 1087 16 1079 INSTRUCTIONS On ilus torrnat.!ist the avera s e da:!y unit power inehn MWe Net for each day in the reporting inonen. Compute to the nearest whole rnepwatt, e

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OPERATING DATA REPORT ,

5 DOCKET NO. 504259 DATE 4/'2/80 -

COMPLETED BY Dort Green TELEPHONE ?ns/7?o4 846 OPERATING STATUS Browns Ferry 1 Notes -

1. Unit Name: ,

2. Reporting Period. March 1980 ,

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3. Licensed Thermal Power (MWt):  ;

4. Nameplate Rating (Gross MWe): 1152 '

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5. Design Electrical Rating (Net MWe): '

6. Maximum Dependable Capacity (Gross MWe): looR a i

7. Maximum Dependable Capacity (Net MWe): ins

8. If Changes Occur in Capacity Ratings (Items ilumber 3 Through 7) Since Last Report. Give Reasons: l 9/A i

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9. Power Level To Which Restricted.lf Any (Net SIWE): M/A  ;

10. Reasons For Restrictions. If Any: N/A l

This Month Yr to.Date Cumulative

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11. Hours in Reporting Period 6. ' ' r. 7 ,1 y. 401682

12. Number Of Hours Reactor Was Critical ~ 106.20 177.90 28.455.18

13. Reactor Reserve Shutdown llours 174.63 174.63 4,864.24

14. Hours Generaint On.Line 41.52 113.22 27,725.9,5 i

15. Unit Reserve Shutdown flours 0 0- 0 i

16. Cross Thermal Energy Generated (MWH) 22,354 206.506 74.342,999 .

17. Gross Electrical Energy Generated (MWH) 8.030 ,,,

69.990 24,563,450 4

18. Net Electrical Energy Generated (MWII) 2,089 59,253 23,361.221 ..

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19. Unit Service Factor 5.6 5.2 55.8 .', l

! 20. Unit Availa"bility Factor .5.6 5.2 55.6  : '

21. , Unit Capacity Factor (Using MDC Net) . 0.3 2.5 45.1

22. Unit Capacity Factor (Using DER Net) 0.J 2.5 45.1

23. Unit Forced Outa;;e Rate 81.5 61.7 33.2

24. Shutdowns Scheduled Over Next 6 Months (Type.Date.and Duration of Eacht:

25. If Shut Down At End Of Report Period. Estimaied Date of Startup:

26. Units in Test StatudPrior to Commercial Operationt Forecast Ac:.iesed I INITIA L CRIT!CA LITY INITIAL ELECTRICITY

, COM%IERCIA L OPER A TION

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OPERATING DATA REPORT .

DOCKET NO. SD-260 DATE 4'/ ? / 80 i COMPLETED BY nh neaan TELEPHONE ons/790-6846 OPER ATING STATUS

't. Unit Name: Browns Ferry 2 N8 *

2. Reporting Period. March 1980 ,

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3. Licensed Thermal Power (MWt): 3293

4. Nameplate Rating (Gross MWe): 1152 ,;

S. 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 i

9. Power Level To Which Restricted,If Any(Net MWe): N/A

10. Reasons For Restrictions. lf Any: N/A i

. . This Month Yr..to.Date Cumulatise

11. Hours In Reporting Period '.

e 744 680.78 2184 1,782.83 44,593 26,267.31 l

12. Number OfIlours Reactor was Critical

13. Reactor Reserve Shutdown Hours 63.22 401.17 12,176.11 -

14. Hours Generator On.Line 665.97 1731.42 25,395.13 j

15. Unit Reserve Shutdown llours 0 0- 0 .

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16. Cross Thermal Energy Generated (MWH) 1,772,736 4,772,174 70,927,174 . I

17. Gross Electrical Energy Generated (MWH) 593.150 , _ , , 1.594.600 23.544.668  ;

18. Net Electrical Energy Generated (MWH) 577.104 1,549,941 22,881,410 , j

19. Unit Service Factor 89.5 79.3 57.0 -j i

20. Unit Availa'bility Factor 89.5 79.3 57.0 -

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21. , Unit Capacity Factor (Using MDC Net) 72.8 66.6 48.2 l

22. Unit Capacity Factor (Using DER Net) 72.8 66.6 48.2 '

23. Unit Forced Outa;;e Rate 10.5 20,7 35.9

24. Shutdowns Scheduled Over Next 6 Months (Type. Date,and Duration of Each1:

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25. If Shur Down At End Of Re:mrt Period. Estinated Date of Startup: '

26. Units in Test StatuuPrior to Commercial Operationi: Forecast Achieved

! Nill A L CRITICA LITY ,

INITIA L ELECTRICITY

, COMMERCIAL OPER ATION

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DOC KET NO. 501296 DATE A/?/9n COSIPLETED BY 94 r ~-,

TELEPHONE ?ns/739_K846 OPERATING STATUS Browns Ferry 3 Notes

1. Unit Name:

2. Reporting Period: March 1980

3. Licensed Thermal Power 131Wti: 3293

4. Nameplate Rating (Gross alWe): 1152 ,

5. Design Electrical Rating (Net SlWe): 1065

6. Sf aximum Dependable Capacity (Gross hlWe): 1008.4

7. Alaximum Dependable Capacity (Net SIWE): 1065

3. 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 SIWE): N/A

10. Reasons For Restrictions. If Any: N/A

. . This alonth Yr. to Date Cumulative ,

11. Ilours In Reporting Period ~#- 744 2 184 27 048 i

12. Number Of ifours Reactor Was Critial 744 1,772.43 20,679.98

13. Reactor Reserve Shutdown !!ours 0 0 1.658.31 l

14. Ilours Cenerator 0n.Line 744 1,748.93 20,186.74

15. Unit Reserve Shutdown flours 0 0 0

16. Gross Thermal Energy Generated (SIWil) 2.375.681 5.487.381 58_595 747 -

17 Gross Electrical Ens rgy Generated (SlWH) 804.87.0 _ . , 1.854.790 19.257.370 IS. Net Electrical Energy Generated (alwii) 786,318 1,306,506 18,694.279 80.1

19. Unit Service Factor 100 74.6 _

20. Unit Availa'bility Factor 100 80.1 74.6

21. , Unit Capacity Factor (Using SIDC Net) "*' ##

• l 99.2 77.7 64.9

22. Unit Capacity Factor (Uning DER Net)  !

23. Umt Forced Outage Rate O 19.9 10.1 j

24. Shutdowns Scheduled Oser Nest 6 Alonths(Type. Date.and Duration of Eacht: l l

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25. If Shur Down At End Of Report Period. Esnmated Date of St.:rtup:

6. Units in Test Status # Prior to Commerci.it Operatunii: Forecast Achieved .

INITIA L CRI TICA LI TY  !

l INITIAL ELECTRICITY i C0\lilERCI \L OPER ATION

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DOCKET NO. 50-259 UNIT SIIUIDOWNS AND POWER REDUCTIONS Browns Ferry 1 UNIT NAME DATE 4/2/80 COMPLETED BY nan cronn REPORT MONTil March 205/729-6846

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-, .$ ? 3 h Yk Licensee [v, hg 'Cause A Corrective Na - Dne i 3? $ .5 s 5 Event gy ET Attion so

• j5 5 3@g Report : mV v

E' Prevent Recurrence .

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.n 108 800301 S 519.78 C 2 Refueling 109 800322 F 76.45 A 2 '*i P Blown seal on "B" rectre pump 110 800327 F 54.78 A 3 Cenerator neutral over voltage due to problems with main transformer 1B 111 800329 F 51.47 A 2 High temperature on "B" recirc pump thrust bearing I 2 3 4 F: Forced Reason: Method: Exhibit G - Instructions S: Scheduled A Equipment Failure (Explain) I Manual for Pseparation of Data loMaintenance of Test 2 Manual Seram. Enin Sheets for I.icensee C.Reiocling 3 Automatic Stram. Event Repost (l.f R) File,1NURI:G-D-Regulatosy Restriction , 4 Othes (Explain) O t til l E Opciator Training & License Examination F Administsative 5 G. Operational Es tor (Explain) Exhibit I - Same Source (9/77) Il-Olher (E splain) ,

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DOCKET NO. 50-260 UNITSilUTDOWNS AND POWER REDUCTIONS

. UNIT NAM E Browns Ferry 2 DATE 4/?/Rn .

REPORT MONTil March ~

U"I 1 TE! LI'llONE ons/790 AAAA I

. *k No. Date c-5? 3j k Ek Licensee g r, h S7, 'Cause & Corrective 3g ji5 Event :s 7 3 Action to

$E 5 5 e- ;5 g Repori3 (E U E' v

Preveni Recurrence .'

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125 800301 F 57.46 A 4 Priraary containment Icakage. Rx was

.- previously down for ilPCI maintenance.

126 800307 S B Derated for recire M.G. set brush replacement.

0; 127 800309 20.57 B 3 --

Rx low water level signal while performing S.I. (APIO! functional) 128 800314 S H Derated for control rod sequence exchange.

129 800321 F 11 Derated due to recirc pump trip 130 800327 F 11 .

Derated for maintenance to !!P htra and.Rx FW pumps i, . . . i '

131 800329 F 11 Derated for lip W heater maintebance 1 2 3 4 F: Forced Reason: hiethod: Exnibit C instructions S: Scheduled A-Equipment Failure (Explain) l-Manual for Pieparation of Data D-Maintenance of Test 2 Manual Scram. Entry Sheets for I.ieensee C Refueling 3 Automatic Scram. Event ReporI(LER) File tNUREG-D-ReEulatosy Restriction , 4-Oiher (Explain) 0161)

F Opciator Training & l.icense Examination F AJnunist ative 5-G-Operational Error (Explain) Exhibit I - Same Source p>f77) Il-Olher (E xplain)

f UNITSilUTDOWNS AND POWER REs)UCTIONS DOCKET NO. 50-296

. UNIT NAME B roem vorrv' 3 DATE A/? fen ,

COMPLETED BY nna r'ronn REPORT MONTil March TELEPilONE 205 / 7 29-68 t.6 *

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~L 53 E g.gf Licensec ,E r, f',E Cause & Corrective f,-

e? 4 .2 ; oc Event s? E Action to 35 c2 y is, RePur8 8 'N 0 y' Prevent Recurrence ,'

O 118 800308 S B Derated for turbine control valve

.. tests and SI's.

- :- 9 119 800322: S B Derated for recirc pumps M.C. set srush replacement and control rod adjustments.

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...t i 2 3 4 F: Forced Reason: Method: Exhibit G - Instructions S: Scheduled A Equipment Failure (Explain) I Manual for Pseparation of Data Italaintenance of Test 2-Manual Scram. Entsy Sheets for I.icensee C Refueling 3 Automatic Scram. Event Repuo (1.E!Ol'ilclNUREG-D Regulatory Restriction , 4-Oth r (Explain) 0161)

E-Operator Daining & IJcense Examination F AJnunistrative 5 G Operational Error (Explain) Exhibit 1 Same Source (9p7) 11 Other (Explain) i

BROWS FERRY NUCLEAR PIANT UNIT 1 -

CSSC EQUIP!ENT MECilANICAL HAINTENANCE SU12tARY For the Month of March 1980 EFFECT ON SAFE ACTION TAKEN DjTE SYSTEM COMPONENT NATURE OF OPERATION OF CAUSE OF RESULIS OF IV PRECLUDE MAINTENANCE Tile REACTOR MAT. FUNCTION MALFUNCTION RECURRENCE 3/14/80 RilR FCV 74-66 Packing leak None Water leak None Repacked valve TR 145397 3/12/80 Diesel ID D/G No. 1 Nipple broken None Vibration None Welded line and Generator air compressor- on line causin.r returned air compress.

air leak to service TR 151383 3/13/80 llPCI Solenoid' valves Valves stickin; ; Could 1 .9ave !!PCI Operator of valve Valves not working Installed new valves73-17A and inope r'a' Ole TR 143071 73-17B 3/17/8( RilR Angle valve Hand wheel None Operation of Could not manually Replaced hand wheely 74-52 missing , valve operate TR 151495 3/17/8f RilR FCV 74-66 Crack in weld None Repaired weld leakoff line going to packi ig TR 137644 gland 3/20/81 . Radwaste Valve 77-14B Valve not None Valve would not None Tighten spring tension opening ful1y open TR 153153 3/26/80 SLC SLC shutoff Sodium buildup Nane Packing gland Leaking valve Tightened packing valve 63-11 around valve leaking TR 143979 3/23/80 Reactor "II" Recircula- Replace seal None' Normal wear Degraded seal Replaced seal with Water tion pump seal performance new one Recirculati in TR 137646 3/27/8 ) IIPCI IICV 73-587 Packing leak None Leak at packing Inoperable valve Tightened packing glai gland TR 159324

-3/12/8 ) IIPCI PT 73-4 Drain leaking Disassembled and Isolation valve excessively None Valve leaking Inoperable valve cleaned plug and seal and replaced valve TR 151473

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UROUNS FERRY NUCLEAR FIAtlT UtilT 3 CSSC EQUIPMENT ,

MEC11ANICAL MAINTENANCE SUl21ARY For clic Montli of March 19 80 EFFECT ON SAFE ACTI0li TAKEN DATE SYSTD1 COIIFONEllT NA' LURE OF OPERATION OF CAUSE OF RESULIS OF W PRECLUDE MAItrl'EllANCE T!!E REACTOR MALFIRICTION MAT. FUNCTION RECURRENCE 1/24 EECW FCV 67-50, Filters were None Dirty filters Clogged valves hanged filters per 67-51 and 67-53 dirty schedule maintenance TR 130218 U$

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4 EROWNS FERRY NUCLEAR PIANT UNIT Common s CSSC EOffIPMENT MECl!ANICAL MAINTENANCE SU t!ARY Fer the Month of Ma rch 19 80 EFFECT ON SAFE ACTION LEEN Il\TE SYSTEli CO)!PONENT NATURE OF OPElbiTION OF CAUSE OF RESULTS OF 'lU PiiECLUDC 11AINTENAMCE TiiE REACTOR MALFUNCTION R\LFl%CTION RECIIRRENCE 3/4/80 EECW Sensing line to Pipe leak None Rusted pipe Transmitter sending Installed new valves FI-67-9A false signal and pipe on flow element, FE-67-9A TR 152383 3/6/80 RilRSW D-2 pump Vent valve not None Vent valve Icak All.ows water flow thr i Tightened vent valve seating correc .ly small pipe nipple on TR 137393 '

top 3/10/80 RilRSW A-3 RilRSW pump Sensing line Loose llangers Vibration of discharg ? Put hangers in suppo:

loose from Norid} piping '.'R 137 388 hangers 3/21/80 CAD Tank B 1.cak oa weld o f None Vent valve leaking Valve will frost up Seated valve g of inner vesse -

TR 151367

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P i ping 3/21/8t CAD llCV 84-511 Vent valve wil  ! .None Valve not seating Inoperable valve Reseated valve and (Tank A) not close stopped leak properly TR 151308 3/21/80 CAD llCV 84-551 F11ange leak- None Bonnet Icak Bonnet will frost up Tightened packing stopped leak TR 151374

w ERO'GS FERRY NUCLEAR PLA'IT UNIT 1 s CSSC FQUTPMENT ELECTRICAL liiTNTENANCE

SUMMARY

For the Month of Ma rch 19 80 I

, f~~ Effect on Safe Action Taken Dctc Systcc Ccaponent Nature of Operation of Cause of Results of To Preclude Maintenance The Reactor Malfunction Malfunction Recurrence 3-1-80 SLC 1A SLC punp 1A SLC pump NONE Bad Transformer Transformer burned motor Replaced transfor'er, m

motor heater out in compartment. put system back into keeps tripping operation, checked

} out.

t ok, TR#151920 i

l3-3-80 RiiR llCV 74-22 IC RilR heat NONE Switch out of Position switch out Adjusted position i exchanger ,

adjustment, of adjustment. switch for red light outlet valve "P 5 checked ok TR #151952  ;

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l3-3-80 RBCCU Drywell cool Drywell cool NONE Limit switch is Limit switch out of Adjusted limits to I air inlet air inlet bad, adjustment, operate properly.

l valve 70-65 valve 70-65 Lights presently l and 70-56 and 70-66 does working properly.

not show TR #151953 closed positior 8

lights when llS is in closed position 3-4-80 RllR Testable Lhecl Testable check NONE Limit switch out Red light switch was Adjusted red light valve 74-68 valve 74-68 of adjustment. out of adjustment. limit switch. Red red light for -

light now working disc position properly. TR#143442 will not work.

i 3-4-80 RilR liCV-74-22 "C" Outlet limit NONE BAD switch Position switch out Adjusted valve switch needs af adjustment. Position switch. Check-to be fixed. ad ok. TR #151267

w ERO'.?NS FERRY NUCLEAR PLANT UNIT 1 s CSSC EOUIINENT ELECTRICAL lii1NTEind1CE SUM 1ARY For the Month of March 19 80 Effect on Sate Action Taken Nature of Operation of Cause of Results of To Preclude

Dale System Ccaponent Malfunction Recurrence i Maintenance The Reactor Malfunction RWCU FCU 69-12 Repair unit 1 NONE Bad limit Limits out of Reset limit per Epil-l3-12-80 18. Checked ok.

I valve 69-12 adj us tment .

.i TR #161462 3-17-80 Fire Fire pump B 4kV ACB trips NONE Bad breaker Breaker tripping Adjusted trip latch j protection free in normal free, also breaker mechanism so breaker

and emergency would not close would not trip free.

I ,,, electrically Replace limit switcher l '# ? in closed circuit.

Breaker operated ok.

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BRO'.!NS FERRY NUCLEAR PIRIT UNIT 2 s CSSC E0llIP1 TENT ELECTRICAL MAINTCIW1CE Sb72fARY For the Month of March 19 1 l Effect on Saic Action Taken

! ' 11.-4 c Syste: Component Nature of Operation of Cause of Results of To Preclude Maintenance The Reactor Malfunction Malfunction Recurrence 3-19-80 RBCCW 2A RBCCW- 2A RBCCW pump NONE Bad motor 2A RBCCW pump motor Checked vibration and noisy had some noise, temperature. Both oka Greased bearing and

.l noise cleared up.

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e ERO'.C4S FERRY NUCLEAR PLANT UNIT # 3'  %

CSSC H)!!f MU:t!T ELECTRICAL ILAINTENANCE

SUMMARY

For the Month of  !!a rch 1 910 FItfect on Sate Action Taken Ude Systes Ccaponent flature of Operation of Cause of Results of To Preclude Maintenance The Reactor Malfunction Malfunction R.2currence i

3-20-80j RWCU FCV-69-2 Replace NONE Bad terminal Terminal block Replaced T.B. and terminal strip block needed replacement lug performed. EMI-block and run 18 A checked ok DtI-18 on TR # 145771 -

valve.

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.s BROWNS FERRY NUCLEAR PLANT UNIT 1,2&3 i A

INSTRUI1ENT MAINTENANCE

SUMMARY

CSSC Ef)lIIPMENT FOIL Tile MONTil OF Marci 19 80 NATURE EFFECT ON SAFE CAUSE ACTION TAKEN DNIE SYSTEM COMPONENT OF OPERATION OF OF RESULTS OF TO PRECLUDE '

MATNTEl&JICE THE REACTOR MALFUNCTION MALFUNCTION RECURRENCE Unit 1 3-4 Control Rod RPIS Probes Drive 42-39 Replace Mone Faulty reed switcl No "00" indication None 34-59 Replace None Faulty reed switcl "o "00" indication hone '

34-31 Replace None Faulty reed switcl No Full-in indication None 3-10 Stand-by TS-63 Calibrate None Setpoint Drift liigh Temp. Alarm Would None Liquid Not Clear Control l 3-23 Control Rod RPIS Probe Replace None Faulty reed switcl Superimposed Positions None Drive 46-55 Jnit 2 - O l-24 Radiation RM-90-265 Repair None Faulty Pre-Regul- None -

Monitoring ator RegdLowon10 and  !

10 position snit 3 Radwaste FQ-77-16 Calibrate None Instrument Drift Indicated Flow with None -

Pump Off 3-10 Emergency IT-67-9A,B Calibrate None Instrurent Drift Showed Flow Too Low None Equipment '%

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30 OUTAGE

SUMMARY

March 1980 During this reporting period, the Unit 1 generator bearing grounding problem was identified and repaired. This problem did not contribute to the outage extention. MSRV 1-13 was leaking during startup. This valve was changed out and sent to Wyle Labs for retesting. The valve did pass the stean test and will be used as a standby spare.

, The Unit 1 RPCI turbine work was critical path work during the month.

Frame straightening and pedestal replacement extended the outage by 8-10 days. The feedwater check valve 3-568 was discovered leaking. A new seal plate was placed in the valve and a hydro was conducted. Other Unit 1 items included oil level annunciator problemy on the recirc pamp and neutral bus fault problems. ModificationI started or continued during th'e month in-cluded security, low level radwaste storage (cable shed), Unit 3 condenser pullout radwaste storage area and the area outage office. The inspection of hangers and anchors associated with NRC Bulletins 79-14 and 79-02 continued with configuration inspection on NRC Bulletin 79-14 and plate and anchor grouting on NRC 79-02.

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