ML20108B075

Monthly Operating Repts for Sept 1984

ML20108B075
Person / Time
Site:	Browns Ferry
Issue date:	09/30/1984
From:	Jones G, Pittman J, Thom T TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8411150296
Download: ML20108B075 (29)

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TENNESSEE VALLEY AUTHORITY DIVISION OF NUCLEAR POWER BROWNS FERRY NUCLEAR PLANT MON 111LY OPERATING REPORT 10 NRC September 1, 1984 - September 30, 1984 DOCKET NUMBERS 50-259, 50-260, AND 50-296 LICENSE NUMBERS DPR-33, DPR-52, AND DPR-68 r

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Plant Manager 8411150296 840930 DR ADOCK 05000 xe m L..

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f TABLE OF CONTENTS Operations Summary......................

1 Refueling Infonnation..............,,.....

3 Significant Operational Instructions........._....

5 Average Daily Unit Power Level................

11 5

Operating Data Reports....................

14 Unit Shutdowns and Power Reductions.............

17 Plant Maintenance'......................

20 Outage Maintenance & Major Modification...........

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1 Ooerations Sumary September 1984 The following stamary describes the significant operation activities during l

the reporting period.

In support of this stamary, a chronological log of ~

significant events is included in this report.

There were three reportable occurrences and one revision to previous reportable occurrences reported to the NRC auring the month of September.

Unit 1 There were no scrams on the unit during the month.

Unit 2 There were no scrams on the unit during the month; however, on September 15, the unit was shut down by a controlled shutdown to start its' fifth refueling outage.

Unit 3 The unit was in cold shutdown the entire month for the unit's end-of-cycle 5 refueling outage.

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Prepared principally by B. L. Porter.

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g Ooerations Simnary (Continued)

September 1984-Fatigue Usage Evaluation The cumulative usage factors for the reactor vessel are as follows:

Location Usage Factor

' Unit 1 Unit 2 Unit '4 Shell at water line 0.00611 0.00492

~ 0.00406 Feedwater nozzle 0.29402 0.21319-0.15444 Closure studs 0.23744 0.17335 0.13566 NOTE:

This accumulated monthly information satisfies Tec!Jiical Specification Section 6.6.A.17.B(3) reporting requirements.

i Common System Approximately 1.07E+06 gallons of waste liquids were discharged containing approximately 5.19E-01 curies of activities.

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-Operations m===ry (Continued)

September 1984 Refueling Information Unit 1 Unit 1 is scheduled for its sixth refueling beginning on or about March 22, 1985 with a scheduled restart date of October 8, 1985. 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 instrumentations.

There are 764 fuel assemblies in the reactor vessel. The spent fuel stor-l age pool presently contains 252 EOC-5 fuel assemblies, 260 EOC-4 fuel assemblies; 232 E0C-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 January 31, 1985. This refueling outage will involve loading additional 8X8R (retrofit) fuel assemblies into the core,

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finishing the torus modification, turbine inspection, finishing piping inspection, finishing TMI-2 modifications; post-accident sampling facility tie-ins, core spray change-out, and feedwater sparger inspection.,

i There are 764 fuel assemblies in the reactor vessel. At the end of the

-month there were 248 EOC-4 fuel assemblies, 352 EOC-3 fuel assemblies,156 EOC-2 fuel assemblies, and 132 EOC-1 fuel assemblies in the spent fuel storage

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pool. The present available capacity of the spent fuel pool is 1170 l

locations. All old racks have been removed from the pool and new HDR's are being installed.

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g Ooerations Si===ry (Continued)

September 1984 Unit 1 Unit 3 shutdown for its fifth refueling outage on September 7, 1983, with a scheduled restart date of October 15, 1984. This refueling involves loading 8X8R (retrofit) assemblies into the core, finishing the torus modifications, postaccident sampling facility tie-in, core spray change-out, finishing THI-2 modifications, turbine inspection, piping inspections for cracks, and changeout of jet pump hold-down beams.

There are 764 fbel assemblies presently in the reactor vessel. There are 248 EOC-5 fuel assemblies, 280 E00-4 fuel assemblies, 124 E0C-3 fuel assemblies,144 EOC-2 fbel 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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Sinnificant Ooerational Events Date Time Event Unit 1 9/01 0001 startup in progress.

0916 Rolled turbine / generator-(T/G).

0940 Synchronized generator, comenced power ascension.

9/02 0010 Holding up on startup, at 57-percent (5) power, to rm a TIP set.

0015 TIP set in progress, "B" TIP machine inoperable, holding up startup for repair of "B" TIP machine.

1500 Reactor power at 55%, holding for repair of "B" TIP machine.

2300 Reactor power at 54%, holding for repair of "B" TIP machine.

9/03 1555 "B" TIP machine repairen, started running a set of TIPS.

1902 TIP run complete, commenced power ascension from 545.

9/04 0400 Comenced PCIOMR from 80% thermal power.

9/05 0630 Reactor thermal power at 96%, maximum flow, rod limited.

1100 Comenced PCIOMR from 96% thermal power.

1230 Reactor thermal power at 98%, maximum flow, rod limited.

1900 Reactor thermal power at 97%, maximum flow, rod limited.

9/06 0200 Reactor thermal power at 965, maximum flow, rod limited.

9/07 2200 Comenced reducing thermal power for control rod pattern adjustment.

2300 Reactor thermal power at 75% for control rod pattern adjustment, increasing power.

9/08 0230 Control rod pattern adjustment complete, comenced PCIOMR from 81% thermal power.

9/09 0220 Reducing thermal power from 95% due to core limits ("R" factor).

0330 Reactor power at 93%, holding due to core limits.

1030 Comenced PCIOMR from 93% themal power.

1325 Reactor thermal power at 975, comenced reducing power to remove "A" Condenser Cooling Water (CCW) pump from l

service for backflush (Milfoil) l 1330 "A" CCW pump out-of-service for backflush, reactor power at 91%.

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l Significant Operational Events Date Time Event Unit 1 (Continued) i

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9/09 1400 Reduced reactor power to 795 due to'high backpressure.

(Cont).

1405

'"A" CCW pump back in service.

F 1415 "B" CCW pump out-of-service for backflush (Milfoil)..

1445 "B" CCW pump back in service and "A" CCW pump out-of--

service for backflush (Milfoil).

1615

". A" CCW pump in service and "C" CCW pump out-ct-service for backflush,. reactor power at 785, high backpressure.

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1700 Reactor thermal power at 775, high backpressure.

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-1730 Comenced reducing thermal power due to high back-pressure.

4 1900 Reactor thermal power at 725, "C" CCW pump back in service and "B" CCW pump out-of-service for backflush (Milfoil).

L 1955 Commenced power ascension from 725 themal power.

g-2030 "B" CCW pump in service and "A" CCW pump out'for back-flush, power ascension in progress.

2100 Comenced PCIOMR from 795 thermal power.

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9/10 0700 Reactor themal power at 875, holding, "R" factor out of limits.

2150 Comenced PCIOMR from 875 themal power.

9/11 1400 Reactor thermal power at 1005, maximum flow, rod J

limited.

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1800 Reducing thermal power to backflush "A" CCW pump (Milfoil).

2115 "A" CCW pump out-of-service for backflush, reactor power at 995.

l 2215 "A" CCW pump in service, increasing thermal power.

2300 Reactor themal power at 1005, maximum flow, rod limited.

9/12 0200 "A" CCW ptanp out-of-service for backflush (Milfoil),

reducing thermal power.

0230 "A" CCW pump in service and "B" CCW pump out-of-servica i

for backflush (Milfoil), reactor power at 995.

0255 "B" CCW pump back in service, commenced power ascension.

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0400 Reactor thermal power at 1005, maximum flow, rod limited.

1100 Reactor themal power at 995, maximum flow, rod limited.

1930 Increasing themal power from 995.

2000 Reactor thermal power at 1005, maximum flow, rod

-limited.

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' Sinnificant Operational Events Date Tine-Event Unit 1 (Continued) 9/15-2400' Commenced. reducing thermal power for turbine control valve. test and sis.

'9/16

.0300

- Reactor-thermal power at 66% for turbine control valve.

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l-test and sis.

.0405 Turbine control valve test and sis complete, conmenced power l ascension.

0500-Conmenced PCIOMR from 955 thennal power.

i 0800 Reactor thermal power at 1005, maximun flow, rod limited.-

9/17 1325 Conmenced reducing thennal power to repair. flange leaks on demineralizer valves.

i-1700~

Reactor power at 69% to repair flange leaks on demineralizer valves.

2155 Conmenced power ascension from 695 thermal power.

2205' Conmenced PCIOMR from 935 thennal power.

9/18 0200 Reactor thermal power at 985, holding, due to demineralizer problans.

0930 Conmenced reducing thennal power for removal of "A" CCW pump from service for backflush (Milfoil).

0950 "A" CCW pump out-of-service for backflush, reactor _ power at 925.

1215 "A" CCW pump back in service and "B" CCW pump out-of-service for backflush, reactor power at 925.

1320 "B" CCW pump back in service and "C" CCW pump out-of-service for backflush, reactor power at 915.

i 1400 "C" CCW pump back in service and "A" CCW pump out-of I

service for backflush, reactor power.at 915.

i 1440 "A" CCW pump back in service, comenced power ascension from 915.

1600 Comnenced PCIOMR from 965 thermal power.

2042 Conmenced reducing thermal power from.985 for removal of "C" CCW pump from-service for backflush (Milfoil c

problens).

2100 "C" CCW pump out-of-service for backflush, reactor power at 935.

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2215 "C" CCW pump back in service and "A" CCW pump out-of-i service for backflush.

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2245 "A" CCW pump back in service, conmenced power ascension j

from 935.

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8 Sinnificant Ooerational Events Date Time Event Unit 1 (Continued) 9/19 0400 Reactor thermal power at 100%, maximum flow, rod limited.

0958 Comenced reducing thermal power to remove CCW pumps from service for backflush (Milfoil problems).

1012 Reactor themal power. at 935 for removal of CCW pump from service for backflush (Milfoil problems).

1445 Comenced power accension from 935 themal power.

1530 Comenced PCIOMR from 975 themal power.

1900 Reactor thencal power at 1005, maximum, rod limited.

l 9/22 0300 Comenced reducing thermal power for CRD exercise.

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0500 Reactor thermal power at 94% for CRD exercise.(SI j

4.3.A.2).

l 0600 CRD exercise complete, comenced power ascension.

0730 Comenced PCIOMR from 96% themal power.

1030 Reactor thermal power at 100%, maximum flow, rod limited.

9/25 2300 Reactor thermal power at 995, maximum flow, rod limited.

9/28 2230 Comenced reducing themal power for control rod pattern adjustment.

9/29 0300 Reactor power at 70% for control rod pattern adjustment, increasing thermal power.

0450 Control rod pattern adjustment complete, comenced power i

ascension from 75% thermal power.

0600 Comenced PCIOMR from 77% thermal power.

l 2100 Stopped PCIOMR at 91% due to APRM rod blocks.

2123 Commenced reducing thermal power due to APRM rod blocks.

2200 Reactor power at 90%, rod block limited.

9/30 0300 Comenced PCIOMR from 90% themal power.

2100 Reactor themal power at 100%, maximum flow, rod limited.

2400 Reactor thermal power at 100%, maximum flow, rod limited.

9 Significant Operational Events Date Time Event Unit 2 9/ 01 0001-Reactor thermal power at 62%, maximm now, rod limited.

9/02 2300 Reactor thermal power at 61%, maximm now, rod limited.

9/07 1500 Reactor thermal power.at 60%, maximum n ow, rod limited.

9/12 2300 Reactor themal power at 595, maximm now, rod limited.

9/14 2220 Comenced reducing thermal power for a con ~ rolled c

shutdown for end-of-cycle 5 refuel outage.

9/15 0456 Tripped main turbine from 11% thennal power, end-of-cycle 5 refuel outage begins.

1708 All rods inserted, controlled shutdown complete.

9/16 0424 Reactor in cold shutdown 9/30 2400 End-of-cycle 5 refuel outage continues.

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- Significant Operational Events Date Time Event-Unit 3 9/01 0001 End-of-cycle 5 refuel outage continues.

9/30-2400 End-of-cycle 5 refuel outage continues.

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11-AVERAGE DAILY UNIT POWER LEVEL DOCKEY NO. 50-259 Bro'wns Ferry 1

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UNIT DATE ~10-1-84 COMPLETED BY T. Thom TELEPHONE -(205) 729-0834 MONTil September 1984 DAY AVER AGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe. Net) 292 948 g7 2

501 995 "'

gg 3

527 39 1032 q,-

3 4

868 20 1046 5

_1015 21 1069 6

1044 1016 22 7

954 23 1062 8

885 24 1058 9

939 25 1033 884 10 26 1041 Il 1008 27 1057-12 1044 28 1034

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13 1046 888 29 14 1043 30 988 l

15 1046 3g i

16 977

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l INSTRUCTIONS On this forrnat. list the average daily unit giower lesel in Mwe. Net for each day in the reporting month. Compute to the nearest whole megawatt.

(9/771 O

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'12 AVERAGE DAILY UNIT POWER LEVEL 50-260 DOCKET NO.

UNIT Browns Ferry 2 DATE '10-1-84 COMPLETED BY T. Thom TELEPHONE -(205) 729-0834 MONTil September 1984 DAY AVERAGE D. II.

'ER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe-Net) 601

-12 2

605 gg

_11 3

601 39

_g 4

605

-10 20 5

596 21

-10 600 6

22

-9 7

596

-10 23 8

589 24

-9 588 9

25

-8 583 10 26

-10 il 578

_9 12 572

-9 28 13 567 29

-9 14 554

-8 30 15 28 3t 16

-11 INSTRUCTIONS On this fortnat. list the average daily umt power resel in Mwe. Net for each day in the reporting month. Compute to

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the nearest whole megawatt.

(9/771 i--

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=.2 13 AVERAGE DAILY UNIT POWER LEVEL 50-296 DOCKET NO.

UNIT Browns Ferry 3 DATE 10-1-84 COMPLETED BY T. Thom TELEPHONE (205) 729-0834 MONTil September 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL

- (MWe-Net)

(MWe-Net) 1

-6 g7

-11 2

-7 gg

.-9 3

-7 g9

_9 4

-5 20

-9 5

-5

-10 21

-4 6

g

_9 7

-7 23-

-10 8

-10 24

-10 9

-10 25

-9

-10

-10 10 26 II

-10 37

-9 12

-12

-10 23 13

-10 79

-11 i

14

_ -10

-11 30 15

-11 3

I 16

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INSIRUCTIONS

-On this format, list the average daily unit power leselin MWe Net for each day in the reporting month. Compute to I

the nearest whole megawatt.

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OPERATING DATA REPORT.

DOCKET NO. 50-259 DATE 10-1-84 T. Thom CO.\\lPLETED lty T205T 729-0834 TELEPilONE -

OPERATING STATUS

1. Unit Name: Browns Ferrv One b"I'5

2. iteporting Period: September 1984-

3. Licensed Thennal Power (5tht): 3293 1152

4. Nameplate Itating (Gross 5tWe):

1065

5. Design Electrical Rating (Nc alWe):

6. Stasimum !)cpendable Capacitv (Gross $1We): 1098.4 1065

' 7..\\laximum Dependable Capacity (Net A!We):

M. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:

N/A

9. Power Lesel To Which Restricted. lf Any (Net 31We):

N/A

10. Reasons For Restrictions.lf Any:

N/A This atonth Yr..to.Date Cumulatise

11. Ilours In Reporting Period 720 6.575 89,191

12. Number OfIlours Reactor Was Critical 720 5,858.48 55,664.6

13. Reactor !!esene Shutdown flours 0

700.20 6.485.22

14. Iloun Generator On.Line 710.33 5.713.95 54,431.59

15. Unit Rewne Shntdown llours 0

0 0

16. Grow Thermal Energy Generated 151Wil) 2,150,282 17,556,940 156,114,619 17 Grow Electrical Energy Generated (.\\1Wil) 698,310 5.781.530 51,427,150

18. Net Electrical Energy Generated (alWil) 680,140 5,628,148 49.953,475

19. Unit Senice Factor 98.7 86.9 61.1

20. Unit Availability Factor 98.7 86.9

-61.1

21. Unit Capacity Factor (Using SIDC Net) 88.7 80.4 52.6 22 l' nit Capacity Factor (Using DER Net) 88.7 80.4 52.6

23. Unit Forced Outage Rre 1.3 12.7 22.8

24. Shutdowns Scheduled Gier Nest 6 31onths(Type.Date,and Duration of Eacht:

25. If Shur Down At End Of Report Period. Estimated Date of Startup:

2o. Units la rest StatuuPrior to Commercial Operation):

Forecast Achiesed INITIA L ClllTICA LITY INITIAL ELECTRICITY CO\\1\\1ERCIA L OFFR ATION i9/77:

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p i-9 15 OPERATING DATA REPORT DOCKET NO.

50-260 DATE 10-T~BT_

CO.\\lPLETED By T. Thom TELEPIIONE 7M5T729-0834 ~

OPERATING STATUS I. Unit Name:

Browns Ferry Two N"'"'

2. Reporting Period:

September 1984-l p

3. Licensed ThermalPower(51Wt): 3293 l

4. Nameplate Rating (Gross 51We):

1152 I

S. Design Electrical Rating (Net SIWE): 1065

6. 5!aximum Dependable Capacity (Gross 51We): 1098.4

7. 5faximum Dependable Capacity (Net 51We):

M.~ If Changes Occur in Capacity Ratings (items Number 3 Through 7) Since Last Report. Gi e Reasons:

N/A-

9. Power Level To which R. icted.If Anv(Net 51We):

N/A

10. Reasons For Restrictions.It Any:

N/A This alonth Yr.-to Date Cumulaeise

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720 6,575 84,078

11. !!ours In Reporting Pen. d o

12. Number OfIlours Rentor Was Critical 340.93 5.895.85 55,860.03 y

13. Reactor Reserve Shutdown llours 0

300.08 14,200.44

14. Ilours Generator On-Line 340.93 5,845.52 54,338.36

15. Unit Reserve Shutdown !!ours 0

0 0

16. Gr m Thermal Energy Generated (N!Wil) 665.357 13,100,122 153,245,167

17. Grow Electrical Energy Generated (SIWil) 206.930 4,174,510 50,771,798

18. Net Electrical Energy Generated (31Wil)

.194.862 4.044,370 49,302,973

19. Unit Service Factor 47.4 88.9 64.6

20. Unit Availability Factor 47.4 88.9 64.6

21. Unit Capacity Factor (Using 51DC Net) 25.4 57.8 55.1

22. Unit Capacity Factor (Using DER Net) 25.4 57.8 55.1

23. Unit Forced Outage Rate 0

4.I 23.0

24. Shutdowns Scheduled Oser Next 6 hionths (Type. Date.and Duration of rathi.

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

26. Units in Test Status (Prior to Commercial Operationi:

Fm ecast At hiesed INITIA L CRITICA LITY INIIIA L ELECTRICITY CO.\\lilERCIAL OPER ATION J

('>l1 l 5 7

.-c.

16 OPERATING DATA REPORT DOCKET NO. 50-296 DATE 10-1-84 CONIPLETED 13Y T. Thorn TELEPil0NE DOU m-0834 OPERATING STATUS

1. Unit Name: Brows Ferry Three

• No t"

2. Reporting Period:

Septernber 1984 3 Licemed Thennal Power (S!Wt): 3293'-

4. Nameplate Rating (Gross 31We):

1152

5. Design Electrical Rating (Net 51We): -1065

6. 31asinmm Dependable Capacity (Gross StWe): 1098.4

7. Stasimum Dependable Capacity (Net atWe):

1065 N. If ( hanges Occur in Capacity Ratings (Items Number 31hrough 7) Since Last Report. Gi e Reawne N/A

9. Power Lesel To which Restricted.If Any (Net 31Wel:

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

N/A This Atonth Yr..to.Da te Cumulative

11. Ilours In Reporting Period 720 6,PS 66.503

12. Number Of Ilours Reietor Was Critical 0

0 43,087.80 y

13. Reactor Resene Shutdown Ifours 0

0 3,878.13

14. Ilours Generator On Line 0

0 42.193.71

15. Unit Rewne Shutdown llours 0

0 0

16. Grow Thermal Energy Generated (31Wil) 0 0

126.307.711-17 Grow Electrical Energy Generated (.\\lWil) 0 0

41,597,620 IM. Net Electrical Energy Generated (51Wil) 0 0

40,375,256

19. Unit Senice Factor 0

0 63.4

20. L' nit Asai!ahility Factor 0

0 63.4 21 Unit Capacity Factor (Using.\\lDC Net) 0 0

57.0 2.'

Unit Capacity Factor (Using DER Net) 0 0

57.0

23. Umt l'orted Outage Rate 0

0 16.4

24. Shutdowns Scheduled Oser Nc6 6.\\1onths IType. Date.and Duratiun of Eacht:

25. If Shut Dusn Tt Enti Of Report Period. Estimated Date of Startup:

October 15, 1984 26.1: nit,in l'est Status (Prior to Commercial Operation):

Forecast Achiesed INITIA L CRITICAL.ITY INi flT I. El.FCI RICI TY CO%1\\ lei!Cl4L OPER$1 ION l

19/77) m-

50-259 UNIT SilUTDOWNS AND POWER REDUCTIONS DOCKET NO. _

UNIT NAME Browns Ferry 1 DATE 10-1-84 REPORT MONT11 September 1984 COMPLETED BY T. Thom TELEPHONE (205) 729-0834' n.

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Present Recurrense 6

289 9/1/84 F

9.67 B

Reactor manually Scrammed to. test check valve FCV-75-26 for proper sealing 290 9/7/84 S

11 Derated for control rod pattern adjustment 291 9/9/84 F

F Derated due to high back pressure

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292 9/15/84 S

H Derated for Turbine CV Tests and sis 293 9/17/84 F

B Derated'to repair flange leaks on demineralizer valves 294 9/28/84 S

H Derated for control rod pattern adjustment i

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F: Forced Reason:

Method:

Exhibit G -Ins: ructions S: Scheduled A Equipment Failure (Explain) 1 Manual.

for Preparation of Data B-Maintenance of Test 2-Manual Sciam-Enir,s Sheets for txensee C Refueling 3-Automatic Saam.

Esent Report (t.l:RI Fde t NUREG-D Regulatory Restriction 4 Other (Explaint Olbil i

E-Operator Training & Licenw Examination F-Administrati.e j

5 G-Operational Eeror (Explain)

INinbit I - Same Source 19/77)

II4)ther (Explaini j

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q DOCKET NO. 50-260 UNIT SilUTDOWNS AND POWER REDUCTIONS UNITNAME Iirowns Ferry 2 10-1-84 DATE RLpORT MONTil Septeraber 1984 COMPLETED BY T-Thom TELEPHONE (205) 729-0834 i

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,E -t, Cause & Correctise No.

Date y,

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Action to jE E

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Report :

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Prevent Recurrence e

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305 9/15/84 S

379.07 C

4 EOC-5 Refuel Outege (Controlled ~ Shutdown 9/15/84)

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F: Forced Reason:

Method:

Exhibit G - Instiuetions S. Scheduled A Equipment Failure (Explain) l-Manual for Preparation of Data B. Maintenance of Test 2 Manual Scram.

Entry Sheets for Liecusee C. Refueling 3 Automatic Scram.

Event Report ILERi File INURI:G-D Regulatory Restriction 44ther (Explaini 0161)

E-Operator Training & License Examination F. Administrative 5

G-Operational Error (Explain)

Exhibit I - Same Source 19/77)

Il-Other (Explain!

50-296 UNIT SHUTDOWNS AND POWER REDUCT10NS DOCKET NO.

UNITNAME Browns Ferry 3 DATE' 10-1-84 REPORT MON 1y September 1984 COMPLETED BY.

T. Thom TELEPHONE (205) 729-0834 9

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f.s X Licensee g4 Cause A Corrective

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$ 2.,

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Repost =

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Prevent Recurrence e

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140 9/1/84 S

720 C

4 EOC-5 Refuel Outage Continues (Controlled Shutdown 9/7/83)

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1 F: Forced Reason:

Method:

Exhibit G-Instructions S: Scheduled A-Equipment Failure (Explain) 1-mnual for Preparatiim of Data B-Maintenance of Test 2 mnul Scram.

C-Refueling 3-Autometic Scram.

Entry Sheets for L+censee Event Repor: 1Ll!RI Fde iNURI G-D Regulatory Restriction 4-Other (Explain) 016II i

E-Operator Training & Utense Examination F Adninistrative 5

1 Goperational Error (Explain)

Exhioit I-Same Somcc i

(9/77)

IIDther (Explain)

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CSSC EQt'IPS!F'T ELECTR ICAL.'Lil :TF';.i: CC '5D2tARY

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For the ibath of Septchber 19 ~ 84 a -

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Effect ca Saie, Ae ; 10:. Take:-

i Nature of Operatica of JCause.of Re.mits ef

' To Prc,lude-t*

Svsten Component Maintenance The Reactor Malfunc. tion

'alfunctie

! d ecorrence 84 7

480V Reactc r 2-MG-268-2DA Repair motor None Defectivemateriall-Loosecoilclnmp Repaired motor j

MOV Bds generator.

material found.

on MR 314906;

- 4 Rer.oved from service repaired generator to be repaired by on MR 322605

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Power Service Shop

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I 17 Crancs &

Refuel Bridge Replace brake None Burnt coil Bridge will not drive Replaced burnt coil'-

Hoists coil MR 252095

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22 Cranes &

Refu d Bridge Replace brake Ncac Burnt coil

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Bridge pill not drive Replaced burnt coil' Hoists coil MR 271101-

'l 23 Cranes &

Refuel Bridge Replace brake None Burnt coil Bridge will not drive Replaced burnt coil Hoists c'il o

MR 320776 26 Radiation 2-PNL-90-229 Replace con-None Bent ring Connector will not Replaced bent Monitoring nector plug "into receptacle connector IIR 318784 I-

/4 Crancs &

Refuel Bridge Replace brake None Burnt coil Bridge will not drive Replaced burnt colh

• Holsts coil MR 064126

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For the l' 'a t - of ' September

t. 84 ^

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Effect on Safe, fu.. h,n 7,ge.,

j-Sature of OperationLof,

Malfunction

' *:a l f u nc e : a n '

Recidrence Ca':se.of K e y: *. t';; c f.

LTe ~Prd'e lude -

-Date Systen Cc-ponent Maintenance The Reactor' 1983

'I

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12/21 480V Shut-1-BRK-231-1B Replace Coil None Burnt-out closing. Breaker blows fuses Replaced burnt. coil; down Bds coil when= closing?

}MR'214257J i

1984 9/7 CO2 Storagt 1-PNL-39 Replaced None-Nat, ural endLof Batteries failed Replaced bad,

~

Fire Pro-286 batteries life routine testing _

batteries'.

tection MR'271062' 9/12 Reactor 1-FSV-64-44 Replaced relay None Burnt-out relay Damper will~not open. Replaced' bad relay Building automatically w

Ventila-MR.321609' tion

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For the ?* n:5 of September li; 84 I

j Effcct ca Safe, 73 3,.

da t e*

s[aintenance.

the Reactor Malfunctian Ma l f un.' t io n R.currence Cause.cf Re 3.d t,; cf Te i'rc.:lu !e M : e --

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1984 6/17 Air Con-3-CHR-31-943 &

Replace expan-None Bad expansion Chillers will not start Replaced bad valve ditioning 951 sion valve valv MR 253110 System 9/6 Unit Pre-3-MG-252-003 Replaced bear-None Bad bearings Vibration of motor Replaced bad bear-ferred ings ings on MR 209504 120VAC 9/7 Sequential 3-XA-55-1-30 Replace card None Bad card Alarm will not clear i Replaced bad card '

Events Recorder MR 321935 9/8 Core Spray 3-MV0P-75-22 Replace spare None Broken terminal None Replaced broken Cooling terminal block block terminal block I

w MR 271076 9/10 Fire Pro-3-BAT-39-25-305 Replace battery None Bad battery Would not pass routine Replaced bad batter;.

tection &

testing MR '322822 CO2 St rage 9/10 Unit 3-MG-57-1 Replace bad None Bad diodes MG set'will not trans-Replaced bad diodes Preferred diodes fer to DC MR 305655 9/14 Standby 3-MTR-82-3C Replaced bad None Bad bearings Lube oil pump motor Replaced bad bear Diesel bearings making loud noise ings l

Generator MR 322070 9/15 Air Con-3-AHU-31-110 Replaced timer None Bad timer Will not start Replaced bad timer i tioning System MR 320209 9/18 Standby 3-RLY-82-TDD0 Replaced relay None Bad relay Diesel exhaust fans Replaced bad relay Diesel 3A 6 3B will not start TACF3-84-193-82l MR 322158 C""*#

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• r BROWNS FERRY NUCLEAR PLANT UNIT CSSC EQUIPMENT MECHANICAL MAINTENANCE

SUMMARY

For the Month of Sept.

84 39 i

EFFECT-ON SAFE ACTION TAKEN DATE SYSTEM COMPONENT NATURE OF OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE MAINTENANCE THE REACTOR MALFUNCTION MALFUNCTION RECURRENCE 8/30/82 85 Valve 3-85-516A Replace None Valve would not Could not Replaced valve seal isolate CRD with a substitut pump with thiobecause the oris' valve nal valve is obsolete

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24 OUTAGE MAINTENANCE & MAJOR N0DIFICATION MANAGDiENT SEPTERBER.1984

'I.

~ Work Synoosis During the September report period, the unit 3 outage progressed through day number 390 of what is currently projected to be a' 412-day outage. Unit 2 was brought offline on September 14,-1984,.for refueling outage. Major schedule milestones accomplished this month include:

U-3 Core Reload Completed 9/3/84-Core Verification Completed 9/4/84 Closed Fuel Fool Gates 9/4/84 RPV Reassembly Complete 9/10/84

.RPV Hydro Complete 9/14/84 U-2 Controlled Shutdown 9/15/84 4

HDFS Racks Set 9/16/ 84 RPV Disassembly Complete 9/30/84 4

Critical path work on unit 3 involved core reload and vessel disassembly.

On September 17,1984, valve 74-68 failed Local Leak Rate Test (LLRT) and -

required repair. This work became the new critical path. Valve 74-54 was also identified as needing repair. This work will delay the return to service approximately two weeks.

Critical path activities for unit 2 involved the vessel disassembly, prepa-ration for core unload, and turbine maintenance work in preparation for rotor shipment to the Service Shop. Lc.'-pressure "A" and "C" turbine covers and inner cylinders have been removed, with the high-pressure turbine bolting removal being 90-percent complete.

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25 OUTAGE MAINTENANCE & MAJOR MODIFICATION MANAGEMENT

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SEPTEMBER 1984_

II. Mechanical %

rv - Modifications 'Section Listed below are some highlights of major. mechanical work performed on unit 3:

-A.

64-series and 84-series valves - This work continued with LLRT being performed on all valves. Valves that failed were reworked and retested.

B.

The steam dryer was inspected with no indications being found.

C.

The 79-02 inspections were completed on September 10, 1984.

D.

. STEAR 83 LLRT Instrtment After Hydro - This work was completed i

September 25, 1984.

E.

P0392 - Scram Discharge System Modification - Work was conducted on the platform installation and re-installation of heater drain lines.

Listed below are some highlights of major mechanical work performed on unit 2:

A.

Blade guides were transferred from unit 3 to unit 2.

B.

Control rod drive hydrolazing was completed on both system headers.

III. Electrical Si=marv - Modifications Section The majority of the efforts by the Modifications Section were directed a

toward unit 3, and its' completion. The following is a list of major electrical work performed.

A.

TIP tubing installation was completed. The TIP indexer maintenance, however, continues.

B.

P0621 - Work was conducted on the main steam -isolation valve limit switch installation.

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j 26 OUTAGE MAINTENANCE & MAJOR MODIFICATION MANAGEMENT SEPTEMBER 1984 III. Electrical Si===r v - Modifications Section (Continued)

C.

P3139 - Fan motor installation on core' spray Loop II was completed

' September 7, 1984.

D.

The storing of rings on the recirculation motor-generator sets was completed on September 24, 1984.

E.

Faulty limit switches were completed en the torus vacuum breakers.

F.

P0126 - ECCS ATU Inverters - This work continues along with P0533, Torus Temperature Monitor modifications.

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. TENNESSEE VALLEY ' AUTHORITY Browns Ferry Nuclear Plant-P. O. Box 2000.

Decatur, Alabama 35602..

OCT 111984 Nuclear. Regulatory Consnission Office of Management Infonnation and Program Control Washington, DC 20555 Gentlemen:

Enclosed'is the September 1984 Monthly Operating Report to NRC for Browns Ferry Nuclear Plant Units 1, 2, and 3 Very truly yours, TENNESSEE VALLEY AU1HORITY

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G. T. Jones Plant Manager Enclosures cc: Director, Region II INPO Records Center Nuclear Regulatory Commission Institute of Nuclear Power Office 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 Ccamission Washington, D. C.

20555 (10 copies)

Mr. A. Rubio, Director Electric Power Research Institute P. O. Box 10412 Palo Alto, CA 94304 9

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An Equal C sportunity Employer

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