ML20031F210

Monthly Operating Repts for Sept 1981

ML20031F210
Person / Time
Site:	Browns Ferry
Issue date:	10/09/1981
From:	Jones G TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20031F206	List: ML20031F205 ML20031F210
References
NUDOCS 8110190357
Download: ML20031F210 (38)

Text

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TENNESSEE VALLEY AUTHORITY DIVISION OF POWER PRODUCTION BROWNS FERRY NUCLEAR PLANT MONTHLY OPERATING REPORT September 1, 1981 - September 30, 1981 DOCRET NUMBERS 50-259, 50-260, AND 50-296 LICENSE NUMBERS DPR-33, DPR-52, AND DPR-68

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Submitted By:

V Plant perintendent 8110190357 811009 PDR ADOCK 05000259

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TABLE OF CONTENTS

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Operations Sumary...

1 I

Refueling Information 3

Significant Operational Events.

5 srin.es.

Average Daily Unit Power Level.

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l Operating Data Reports.

16 Unit Shutdowns and Power Reductions.

19 Plant Maintenance 23 Field Services Sumary..

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1 Operations Summary September 1981 The following summary describes the significant operations activities during the reporting period.

In support of this summary, a chronological log of significant events is included in this report.

There were 17 reportable occurrences and five revisions to previous reportable occurrences reported to the NRC during the month of September.

Unit 1 Unit 1 was in its EOC-4 refueling outage the entire month.

Unit 2 There were two scrams on the unit during the month.

On September 7, the reactor scrammed after receiving a turbine control valve fast closure signal when a generator breaker underwent a spurious opening giving an indication of a power load unbalance. The reactor scrammed on September 16 after a turbine trip occurred due to the loss of stator cooling when a faulty overload relay on the feeder breaker tripped the "A" stator cooling pump while the "B" pump was tagged out for seal maintenance.

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

9 2

Operations Summary (Continued)

September 1981 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 0.00507 0.00422 0.00359 Feedwater nozzle 0.24422 0.18079 0.13937 Closure studs 0.20226 0.14260 0.10649 NOTE:

This accumulated monthly information satisfies technical specification section 6.6. A.17.B(3) reporting requirements Common System Approximately 1.06E+06-gallors of waste liquid were discharged containing approximately 6.51E-01 curies of activities.

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I Operations Summary (Continued)

September 1981 Refueling Information Unit 1 Unit 1 began its EOC-4 tefueling outage on April ll, with a scheduled restart date of October 1, 1981. This refueling will involve loading additional 8 X 8 R (retrofit) fuel assemblies into the core, the final fix on the sparger modification, power supply of LPCI modification, generator breaker and unit 1

station transformer tie-in (requires Unit 2 to be shutdown) and torus modifica-l tions.

There are 764 fuel assemblies in the reactor vessel. The spent fuel storage pool presently contains 260 EOC-4 fuel assemblies, 232 EOC-3 fuel assemblies, 156 EOC-2 fuel assemblies, and 168 EOC-1 fuel assemblies. Because of modification work to increase spent fuel pool capacity to 3471 assemblies, present available capacity is limited to 1200 locations.

Unit 2 Unit 2 is scheduled for its fourth refueling beginning~on or about August 1, 1982, with a scheduled restart date of Detember 30, 1982. This refueling outage will involve completing relief valve modifications, torus modifications, "A" low pressure turbine inspection, liG set installation for LPCI modification, and loading additional 8 X 8 fuel assemblies into the core.

There are 764 fuel assemblics in the reactor vessel. At the end of the month, there were 352 EOC-3 fuel assemblies, 156 EOC-2 fuel assemblies, and 132 EOC-1 fuel assemblies in the spent storage pool.

The present available storage capacity of the spent fuel pool is 160 locations. With present capacity, the 1979 refueling was the last refueling that could be discharged to the spent fuel pool without exceeding that capacity and maintaining full core discharge

0 4

Operations Summary (Continued)

September 1981 Refueling Information Unit 2 (Continued) capability in t'c pool.

I' owe.'er, 949 new. ugh density storage locations have been installed.

Unit 3 Unit 3 is scheduled for its fourth refueling beginning on or about October 30, 1981, with a scheduled restart date of March 7, 1982. This refueling involves loading additional 8 X 8 R (retrofit) assemblics into the core, relief valve modification, turbine inspections, generator breaker and unit station transformer tie-in, and torus modifications.

There are 764 fuel assemblies presently in the reactor vessel. There are 124 EOC-3 fuel assemblics, 144 EvC-2 fuel assemblics, 208 EOC-1 fuel assemblies, and 252 new fuel assemblies in the s.ent fuel storage pool. The present avail-able capacity of the spent fuel pool is 800 locations.

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e Significant Operational Events Unit 1 Date Time Event 9/31/81 0001 End of cycle 4 refuel outage continues.

9/30/81 0005 Commenced rod withdrawal for startup.

0115 Reactor Critical No. 162.

1900 Reactor thermal power at 14%, holding for inspection and startup tests.

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2033 Rolled T/G.

2050 Tripped turbine due to indicated high vibration on recorder.

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Significant Operational Events Unit 2 Date Time Event 9/01/81 0001 Reactor thermal power at 96%, maximum flow, rod limited.

9/02/81 1617 Commenced control rod pattern adjustment, reactor power at 96%.

1730 Control rod pattern adjustment complete, commenced power ascension from 96% thermal power.

2100 Reactor thermal power at 98%, maximum flow, rod limited.

9/03/21 2300 Reactor thermal power at 97%, maximum flow, rod limited.

9/05/81 0020 Commenced reducing thermal power for turbine con-trol valve tests and SI's.

0400 Reactor thermal power at 62%, holding for turbine control valve tests and SI's.

0445 Turbine control valve tests and SI's complete, commenced power ascension.

0630 Commenced PCIOMR from 88% thermal power (Sequence "B").

1300 Reactor thermal power at 98%, maximum flow, rod limited.

9/07/81 0050 Commenced reducing thermal power for control rod pattern adjustment.

0130 Reactor thermal power at 73%, control rod pattern adjustment complete, commenced power ascension.

0430 Commenced PCIOMR from 87% thermal power (Sequence "B")

1202 Reactor Scram No. 126(1) from 94% thermal power from control valve fost closure due to power load unbalance when BKN 224 opened.

2110 Commenced rod withdrawal for start-up.

9/08/81 0100 Reactor Critical No. 139.

0317 Rolled T/G.

0353 Synchronized generator, commenced power ascension.

2230 Commenced PCICMR from 81% thermal power (Sequence "B").

C/09/81 0020 Stopped PCIOMR at 83% thermal power, computer out out of service.

0130 Commenced PCIOMR f rom 83% thermal power (Sequence "B").

1630 Reactor thermal power at 90% holding, computer out of service.

0 7

Significant Operational Events Unit 2 Date Time Event 9/10/81 1420 Commenced power ascension, computer remains out of service.

1500 Reactor thermal power at 93% holding, computer out of service.

2130 Computer back in service, commenced power ascension.

2300 Reactor thermal power at 97%, holding due to erroneous high reading on MWE meter.

9/12/81 0110 Commenced rcducing thermal power for turbine control valve tests and SI's.

0136

' Reactor thermal power at 86%, holding for turbine control valve tests and Sl's.

0150 Turbine control valve tests and S'.'s complete, commenced power ascension.

0205 Reactor thermal power at 96%, holding due to erroneous reading on MWE meter.

2215 Commenced reducing thermal power for control rod pattern adjustment.

2300

- Reactor thermal power at 65%, holding for control rod pattern adjustment.

9/13/81 0106 Control rod pattern adjustment complete, commenced power ascension.

0200 Commenced PCIOMR from 75% thermal power (Sequence "B").

9/14/81 0701 Reactor thermal power at 97%, holding due to erroneous reading on MWE meter.

9/16/81 0230 Commenced power ascension from 97% thermal power.-

0330 Reactor thermal power at 99%, maximum flow, rod limited.

0845 Reactor Scram No. 127 1) from 99% thermal power due to loss of stator cooling when "A" stator cooling pump tripped.

("B" pump was tagged for maintenance).

1905 Commenced rod withdrawal for startup.

2125 Reactor Critical No. 140.

2330 Rolled T/C.

2345 Synchronized generator, commenced power ascension.

9/17/81 0830 Commenced PCIOMR from 78% thermal power (Sequence

" B" ).

2050 Reactor thermal power at 82% holding, control rod pattern adjustment in progress.

2300 Control rod pattern adjustment complete, commenced PCIOMR (Sequence "B").

9/18/81 '0500 Reactor thermal power at 99%, maximum flow, rod limited.

1500 Reactor thermal power at 98%, maximum flow, rod limited.

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8 Significant Operational Events Unit 2 Date Time Event 9/19/81 0001 Reactor thermal power at 97%, maximum flow, rod limited.

0700 Reactor thermal power at 95%, maximum flow, rod l

limited.

1500 Reactor thermal power at 94%, maximum flow, rod a

l limited.

2030 Commenced reducing thermal power for control rod pattern adjustment.

2300 Reactor thermal power at 66%, control rod pattern

, adjustment in progress.

9/20/81 0055 Control rod pattern adjustment complete, commenced 4

power ascension.

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0430 Commenced PCIOMR from 87% thermal power (Sequence ugn),

0600 Commenced reducing thermal power from 90% to 85% for 4

turbine control valve tests and SI's.

1 0625 Turbine control valve tests and SI's complete,

..- commenced power ascension.

0730 Commenced PCIOMR from 89% thermal power (Sequence

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"B").

1600 Reactor thermal power at 99%, maximum flow, rod limited.

9/21/81 2350 Received an alarm on "APRM flow bias of f normal".

9/22/81 0015 Manual one-half scram (RPS "A" trip system). Began reducing thermal power for shutdown.

0055 "APRM flow off normal" reset.

0105 Stopped load reduction at 96% thermal powerf reset -

I one-half scram.

0516 Commenced power ascension from 96% thermal power.

0525 Reactor thermal power at 99%, maximum flow, rod limited.

9/24/81 1500 Reactor thermal power at 99%, limited by EHC vibration.

9/25/81 0700 Reactor thermal power at 99%, maximum flow, rod limited.

2011 Lost unit preferred power during transfer of 4KV SD board from normal to alternate feed which isolated the SJAE and reduced thermal power to 50%.

2015 SJAE back in service, commenced power ascension.

Commenced PCIOMR from 93% thermal power (Sequenc'e 9/26/81 0001 "B").

~0420 Reactor thermal power at 99%, maximum flow, rod limited.

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9 Significant Operational Events Unit 2 Date Time Event 9/28/81 1500 Reactor thermal power at >99%, maximum flow, rod limited.

9/30/81 2400 Reactor thermal power at >99%, maximum flow, rod limited.

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10 Significant Operational Events Unit 3 Event Date Time 9/01/81 0001 Reactor thermal power at 93%, PCIOMR in progress (control ec11 core).

0430 Reactor thermal power at 97%, maximt., flow, rod limited.

Commenced reducing thermal power for control rod 1055 pattern adjustment.

Reactor thermal power at 84%, control rod pattern 1200

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adjustment complete in progress.

Control rod pattern adjustment complete, commenced 1430 PCIOMR (control cell co.a).

1455 Reactor thermal power at 88%, holding for control rod pattern adjustment.

1530 Control rod pattern cdjustment complete, commenced PCIOMR (control cell core).

1845 Stopped PCIOMR at 92% thermal power, computer out of service.

2025 Computer back in service, commenced PCIOMR.

Reduced thermal power from 98% to 69% when "A" 9/02/81 0220 RFWP tripped due to an apparent ground in the RFWP govecnor motor.

"A" RFWP back in service (manual control), commenced 0330 power ascension.

Commenced PCIOMR from 94% thermal pcver (control 0400 cell core).

Reactor thermal power at 99%, maximum flow, rod 0700 limited.

Commenced reducing thermal power for tsIV SI's.

9/05/81 2200 Reactor thermal power at 70%, holding for MSIV SI's.

9/06/81 0020 0201 MSIV SI's complete, comuenced power ascension.

Commenced PCIOMR from 80% thermal power (control 0330 cell core).

Reactor thermal power at 99%, maximum flow, rod 2300 limited.

Commenced reducing thermal power due to Loop 2 RHR 9/07/81 2015 system bein7, inoperable, FCV-74-75 failed partially open (failure of limitorque operator).

2100 Reactor thermal power at 95%, he ding due to Loop l

2 RllR system being inoperable.

9/08/81 0520 Commenced power ascension f rom 95% thermal power.

0700 Reactor thermal power at 99%, maximum flow, rod limited.

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0 11 Significant Operational Events Unit 3 Date Time Event 9/08/81 1740 RHR Loop 2 operable.

9/10/81 2207 Reactor thermal power at 99%, maximum flow, rod limited.

9/12/81 0010 Reduced thermal power to 89% for turbine control valve tests and SI's.

0025 Turbine control valve tests and SI's complete, commenced power ascension.

0200 Reactor thermal power at 99%, maximum flow, rod limited.

1500 7eactor thermal power at 98%, maximum flow, rod limited.

9/13/81 1340 Commenced reducing thermal power for shutdown due to "3C" diesel generator being inoperable at the same time the Trinity line was out of service.

1423 The Trinity line w'as returned to service, power reduction was discontinued at 88% and holding due to high river AT.

1616 Commenced power ascension from 88% thermal power.

1637 Reactor thermal power at 98%, maximum flow, rod limited.

9/14/81 1500 Reactor thermal power at 97%, maximum flow, rod limited.

9/16/81 0842 Plant preferred and non-preferred power transferred' when U-2 tripped, which caused both recirculution pumps to runback reducing thermal poer to 92%.

0900 Recirculation pumps back to normal, commenced power ascension.

0930 Recctor thermal power at 96%, maximum flow, rod limited.

9/18/81 2200 Commenced reducing thermal power for control rod pattern adjustment.

2300 Reactor thermal power at 66%, control rod pattern adjustment in progress.

9/19/81 0001 Control rod pattern adjustment complete, commenced power ascension.

0030 Commenced PCIOMR from 85% thermal power (control j

cell core).

1900 Reactor thermal power at 99%, maximum flow, rod limited.

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i 12 Significant Operational Events Unit 3 Date Time Event 9/21/81 2300 Reactor thermal power at 98%, maximum flow, EOC-4 i

CoaStdown.

9/25/81 0700 Reactor thermal power at 97%, maximum flow, EOC-4 Coastdown.

9/26/81 0329 Commenced reducing themal power for trubine control valve tests and SI's.

0336-

, Reactor thermal power at 91%, holding for turbine control valve tests and SI's.

0522 Turbine control valve tests and SI's complete, l

commenced power ascension.

0535 Reactor thermal power at 97%, maximum flow, EOC-4 coastdown.

9/27/81 2300 Reactor thermal power at 96%, maximum flow, EOC-4 j

coastdown.

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9/30/81 1500.

Reactor thermal power at 95%, maximum flow, EOC-4 coastdown.

j 2400 Reactor thermal power at 95%, maximum flow, EOC-4 i

coastdown.

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(1) Equipment Malfunction

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13 AVERAGE DAILY UNIT POhER LEVEL i-h DOCKET NO. 259 l

UNIT Browns Ferry - 1 1

D\\TE 10-1-81 i

CO\\lPLETED fly Ted Thom 205-729-6M6 TELEPHONE MONTij September 1981 i

DAY AVERAGE DAILY PO%ER LEVEL DAY AVER AGE DAILY POWER LEVEL 01We-Net)

I Mwe-Net )

-12 10 l

37 2

11 18 o

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-10 3

39

-9 i

4

-10 20

-q S

-11 21

-4 6

-11 22

-9

-12 7

23

-11 g

-11 i

24

-11

-12 25

-10 9

-10

-6 10 26 l

-10

-10 27 l2

-11 23

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-12

-10 i

33 79

-12

-12 l4 30

~13 15 31

-14 I ci INSTRUC110NS

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AVER AGE DAILY UNIT P0hER LEVfL i

i DOCKET NO.

50-260 UNIT Br wns Ferry - 2 i'

DATE 10-1-81 CO\\1PLETED 11Y Ted Thom 205-729-6846 TELEPilONE i

j MONTil ScPtember 1981 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL IMhe NetI (Mwe Nei 4

1020 758 j

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1028 1042 y

3 1044 19 966 3

1035 993 4

20 953 1066 I

5 21 1025 1063 i

6 g

453 1070 563 1068 3

923 1045 9

25 977 IOM i

10 26 1031 1058 j

997 1059 g

3 912 1064

,3 3

l 1043 1074 14 30 l

L o3' is 3i i t, 377 f

INSTRUCTIONS On this thrnut. !nt the average dails uma p.mes lesel in MWe Nei l'os each Jn in the sep.. tmp ntniiih. (..inpute i.-

the nearnt win.le n>.*gaw. sis.

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15 AVER.\\GE D All.Y l'.NII POk ER I.EVEl.

1-DOCKET NO. 296 l' Nil Br wns Ferry - 3 DATE 10-1-8J 3

i CO\\lPLElED ilY -Ted Thom 205-729-6846 i

T ELEPflONE i

September 1981

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DAY AVERAGE D.\\lLY POWER LEVEL DAY AVER ACE DAILY POWER LEVEL j

(M We* Net i I\\lWe Net) i 973 i7 1021

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3 g3 1032 1000 1051 1009 3

39 1047 1061 4

,o 1015 1054 3

1052 6

1038 1051 7

,3 1044 1045 3

24 i

1054 1032 9

,..y 10 1060 26 10_2.3 i

1050 1024

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,7 1041 1017

,3 1025 1016

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,9 2035 1029 4,

,4 yn 1022 15 1027 i s, INSTRL'CTIONS On tiiis I.irtitat. hst alie' net.sge J.cl> i. nit,. wre im1 ve \\M e '.et i.it e.e i:.:.n n, i!.e. :..itter.; n:...

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OPEP.? TING DATA REPORT 50-259 DOCKET NO.

DATE 16-1-81 CO31PLETED 11Y Ted Thom TELEPilONE 205-729-6846 OPERATING STATUS Browns' Ferry - 1 Notes

1. Unit Name:

2. Reporting Period:

September 1981 3293

3. Licensed Thermal Power (athtl:

1

4. Nameplate Rating IGross MWe):

4 1065 i

5. Desig.n Electrical Rating (Net AlWe):

1098.4

6. Niasimum Dependable Capacity (Gross alwe):

1065

7. Stasimum Dependable Capacity INet SlWe):

8. If Changes Occur in Capacity Ratings (1: ems Number 3 Through 7) Since Last Report.Giie Reasons.

NA

9. Power Lesel To which Restricted.lf Any(Net alwe):

NA NA

10. Reasons For Restrictions. If Any:

This Stonth Yr. to.Date Cunw.atise 720 6,551 62,833 ll, llours in Reporting Period

12. Number Of Ilour. Reactor was Critical 22.75 2,407.15 37.213.72 1.17 17.59 5,116.46

13. Reactor Reserve Standown flours

14. Ilours Generator On.Line 0

2,380.77 36,373.59

15. Unit Resene Shutdown llours 0

0 0

0 7,425,495 100,717,856,

16. Grow Thermal Energy Generated (SIWil) i

17. Gron Electrical Energy Generated (MWil) 2,474,200 33,237,490 0

0 2,407,849 32,271,666

18. Net Electrical Energy Generated IMwill 0

36.3 57.9

19. Unit Senice Factor 0

36.3 57.9

26. Unit Asailability factor

21. Unit C.spacity Factor IUsing MDC Net, 34.5 48.2 0

0 34.5

_ 48.2 2.'

Unit Cagutity Factor IUsing DER Neti

23. Unit Forced Outage tate

_. 0 0.8 28.0 s

24. Shutdowns Scheduled ther Nest ti MonthsIType. Date.and Duration of Each t:

25. If Shut linwn \\t I nd Of Repori Period. Estimated Date of Startup:.

2tt l' nits in l'est Status aPrior to Commercial Operationi:

Forecast Achies ed INill \\ L CRillCA LII Y INill \\ L El.EC TRICilY

" CO\\l\\ll'RCI A L Ol'I.R A TION (W 73

i 17 OPERATING DATA REPORT 50-260 DOCKETNO.

Isa TE Ef 81 '-

COMPLE1ED BY Ted_T_hopt TELEPilONE.201 729-6846 OPERATING STATUS N"tes Browns Ferry - 2

1. Unit Name:

September 1981

2. Reporting Period:

3293

3. Licensed Thermal Power (Mht):

1152

4. Nameplate Rating IGross MWe):

_ Tu65

5. Design E etrical Rating (Net MWe):

1098.4

6. Masimum Dependable Capacity (Gron MWe):

1065

7. Masimum Dependable Capacity (Net MWe):

8. If Chan;es Occur in Capacity Ratings (Items Nuuber 3 Through 7i Since Last Report.Giie Reawns:

1 NA NA

9. Power Lesel To which Restricted.If AngANet MWe):

i

10. Reawns For Restrictions.!f Any:

l This Month YrAo.Date Cumulath e 720 6,551 57,774 i1. Ilours In Reporting Period 694.37 5,557.05 36,300.66

12. Number Of Ilours Re ector Was Critical 25.63 965.58 13,419.06

13. Reactor Reserse Shuidown Hours 689.15 5,309.83 35,050.79 l

14. Iluurs Generator On l.ine

15. Unit Resene Shntdown llours 0

_0

_Q _

16. Gross Thermal Energy Generated IMWill 2,151,859 16,270,_612-99.841,265 4

17 Grow Electiical Energ) Geneta:cd (MWill 709.24Q__..

5,M2A60

.,_3.3,1.4 9,38,_,

18? Net Electrical Energy Generated iMWili 691,010 5_,.M9a503 32,J.9J,810 95.7 81.1 60.7

19. Unit Senice Factor 95.7 81.1 60.7

20. Unit Asailabihty Factor

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21.- Unit Capacity f actor IUsing MDC Neil

__10_.1

___Z5 2..

._51.4 a

90.1 75.2 52.4 f

2L Us.it Capacity Factor (Using lil R NetI 4.3 12.2

__30.3

23. Unit Forced Ontage Rate

24. Simidowns Scheduled Oscr Next 6 Months i1 ype.Date..and Duration of Tacht.

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

26, Units la iest Status (Prior to Commercial Op< r.ition);

Forecast

\\chiesed '

INIl l \\ 1. CRITICT l.1 FY INI II \\1. I'l.I.C 1ItICI1 Y COM\\lrltCI \\L UPl.R A llON....

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OPERATING DATA REPORT i

DOCKET NO. 50-296 l

DATE 10-1-81 COilPLETED llY Tod Thom._

T El.EPilON E 205-729-6846 OPERATING STATL!S N"I**

1. Unit Name.

Browns Ferry -3

2. Reporting Period: September 1981 3293

3. Licensed Thermal Power (5tht): 1152 J

4. Nameplate Rating (Gross Slwe):

5. Design Electrical Rating (Net SlWe):

1065 1098.4

6. Stasimum Dependable Capacity (Gross 31We):

1065

7. 31asimum Dependable Capacity (Net 31We):

8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report.Gi e Reasone NA NA

9. Power L etel To which Restr.';ted. lf Any (Net Nlwe):

A

10. Reamns For Restrictions 1. y:

This alonth Yr. to Date Cumulatise 720 6,551 40,199 i1. flours In Reporting Period

12. Number Of flours Reactor W.w Critical 720 5,774.96 31,746.23 0

320.14 2,131.03

13. Reactor Reserve Shutdown flours

14. Iluurs Generator On-Line

_ 720 5.640.03 31.030.03

15. Unit Resene Shutdown ilours 0

0 0

16. Gross Thermal Energy Generated (SIWil) 2.303.971 17,387.210 91.752e238

17. Gross Electrical Energy Gener,ted (NIWill 761 S_40 5.757,840 30,296,870 u

lb.. Net E!cetrical Energy Generated 151Wil) 741,483 5,584,552 29,408,875

19. Unit Senice Factor 100 86.1 77.2 20 Unit Asailability Factor 86.1 77.2 100 96.7 80.0 68.7 _

21. Unit Capacity factor IUsing 31DC Neti 96.7 80.0 68.7

22. Unit Capacity Fattor IUsing DI:R Net)

_ _ _ 0 8.0 9.4

23. Unit l'orced Ontage Rate

24. Shuidowes Scheduled Oser Nest 6 %Innths IType. Date.and Duration of fach t.

25. If Shut Down At 1:nd Of Report Period. Estimated Date of Startup:

2 ti. L; nits in Test Status (Prior to Commercial Operation :

Iorecast bluesed

Nill \\l. CRillC Al t l Y INill \\1 LLt.CIRICllY

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50-259

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DOCKET NO, UNIT SilUTDOWNS AND POWER REDUCTIONS UNIT N AME Browns Ferry - 1 DATE 10 1-R1 l.

, COMPLETED BY tea h-f

'8 REPORT MONTil Septemb(.3-TELEPIIONE 205-729-6846 I

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Cause & Currective i

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Prevent Recurrence P

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i'01/81 S

720 C

2 EOC-4 Refuel Outage 172 (Continued)

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F: Forced Reason:

Method:

Eshibit G Instructions S: Ssheduled A Equipment Failure (Explain) 1-Manual for Prepar.ition of Data 4

B. Maintenance of Test 2 Manual Scram.

Entry Sheets for l_icensee A

C Refueling 3-Automatic Scram.

Event Report (LERI File (Nt> REG.

D Regulatory Restriction 4-Other (Explain) 0161)

E. Operator Training & License Examination F Adminigrati.'c 5

Exhibit I-Same Source j

a G-Operatical Error (Explain)

(9/77)

II-Otl.:< (E < plain)

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DOCKET NO. 50-260 UNIT SIIUTDOWNS AND POWER REDUCTIONS UNIT NAME R rm m e F o r r,-

- 2 DATE 10-1-81 COMPLETED BY Ted Thon REPORT MONTH September TELEPilONE 205-729-6846

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=.a.:

Cause & Corrective

.5 ?

E f.E X Licensee

[ r,

$*?

g-Action to No.

Date 5=

R 255 Event u?

$E E

j5g Report #

(E 0 j'

Prevent Recurrence 6

Derated for turbine control valve 205 9/05/81 S

B test and SI's.

Derated for control. rod pattern 206 9/07/81 S

H adjur.tment Reactor scram due to control valve y

207 9/07/81 F

15.85 A

3 o

fast closure when generator breaker 224 hac" a spurious open signal and indicated a load unbalance Derated fcir control rod pattern 208 9/12/81 S

H adjustment Reactor scram when "A" stator cooling 209 9/16/81 F

15.00 A

3 pump tripped; "B" pump was tagged for' maintenance

)

I f 2

3 4

F: Forced Reason:

Method:

Exhibit G - Instructions 5: Sched utett A-Equipment Failure (Explain) 1 Manual for Preparation of Data B Maintenance of Test 2-Manual Scram.

Entry Sheets for Licensee A

C-Refueling 3 Artomatic Scram.

Event Report (LER) Fde (NLIREG-D Regulatorj Restriction 4-Other (Explain) 0161)

F Operator Tra'ning & License Examination F Administrative 5

Exhibit I - Same Source C Operational Enor (Explain) 4 19/77)

Il-Other (Explain) -

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50-260 DOCKET NO.

UNIT SilUTDOWNS AND POWER REDUCTIONS Browns Ferry - 2 UNIT NAME DATE 10-1-81 f

COMPLETED BY Tod Thom REPORT MONTil September TELEPHONE ons_7?o Apf,A i

i "i-l f

.3 -a =

z" Cause & Corrective i

=

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p.s X Licensee g".

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35 5

.555 Eventj s9

[-3 Action to

$5 5

j [5 g Report #

rN 0 jO Prevent Recurrence

~C Derated for control rod pattern f,

220 9/19/81 S

H adjustment Derated for lost unit preferred power 211 9/25/81 F

H during transfer of 4Kv SD Bd from i

normal to alternate feed which l

n~

isolated the SJAE and reduced thermal i

power i

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5 3

4 I'

2 II: Forced Reason:

3 Method:

Exhibit G -Instructions 1-Manual for Preparation of Data S-Scheduled A. Equipment Failure (Explain) r 4

B Maintenance of Test 2 Manual Scram.

Entry Sheets for Licerisce A

C Refueling 3-Automatic Scram.

Event Report (LERI File (NUREG.

D Regulatory Restriction 4 Other (Explain) 0161)

' E-Operator Training & License Examination 5

F-Administrative Exhibit I-Sarne Source G.Operationa! Error (Explain) 4 (9/77) 11 Other (Explain) -

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50-296 DOCKET NO.

UNIT SilUTDOWNS AND POWER REDUCTIONS lirouns Ferry - 3 UNIT NAME DATE 10-1-81 COMPLETED BY Tod Thnm REPORT MONTli ScPtember TELEPilONE

?ns_790_AotA l

'=.e 5 E

'e 55 5

553 Licensee 3 s;,

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Cause & Corrective

=

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Action to

's,, '

g )3,'.

33 5

j5g Repurt =.

40

$0 Prevent Recurrence d

Derated for "A" RFW pump trip -

89 9/02/81 F

11 (governor motor ground)

Derated for MSIV Si's 90-9/05/81 S

B l

Derated for control rod pattern 91 9/18/81 S

H adjustment

}

.I I f 2

3 4

0 Forced Reason:

Meth'od:

Exhibit C - Instructioas S Sshedufeil A Equipment Failure (Explain) 1-Manual for Preparation of Data 4

B-Mairanance of Test 2 Manual Scram Entry Sheets for Liecusee

/

C-Refueling.

' 3 Automatic Scram.

Event Report (LE R) Fde (NUREG.

D Regulatory Restriction 4-Other (Explain) 0161)

E-Operator Training & License Examination F-Admmistrative 5

Exhibit I - Sarae Souree 4

G-Operational Eirur (Expbm)

(9/77)

Il-Other (Explain) -

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BR0ZIS FERRY NUCLEAR Pl.A:IT UNIT 1 & Common

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ELECTRICAL MAINTENANCE

SUMMARY

g,,

CSSC EQUIPMENT k

FOR THE MONTil 0F eptember 19 81 S

t, t.t i cc t on Salc Action Isken 4"

!:ature of Operation of Cause of Results of To Preclude fi,

ff' c

S ys t c:-

Cenponent Itaintenance The Reactor Malfunction

!!al f unc t io n Recurrence l[: '

2/81 Diesel Relay 14A-K17A During the per-None Relay 14A-K17A Core spray pump was Performed EMI-15,

' Generators formance of SI was out of cali-s'ightly slow to calibrated relay to y{

4.9.A.l.b on bration.

start.

proper timing

'J la*.

D/G A the core sequence.

TR #235967 ll spray pump was b,

slightly slow D;-

to start.

1 Q

7/81 RilR LPCI MG set MO set voltage None The voltage reg-A fluctuation of 1 Replaced and cali-h L

LEA voltage regulator ulator has been 10tvolts about twice brated the voltage regulator.

voltage un-sent to the man-per second.

regulator. The 1

stable, ufacturer for voltage regulator j

l f

evaluation.

was adjusted again j

l 9/22/81 due to high L

voltage reading.

'q'd TR #215235 o.'

TR #235969 5

t

]

I i

7/81 Fire Smoke detec-Received a None Bad smoke detec-Ecceived false Replaced detector, Protectior tor XA-39-27C false alarm tor.

alarm.

the detecter oper-gj ated properly per 4

periodically, S1 4.11.C.1 & 5.

i i TR #182860 b

t taef r

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BR0'.CS FERRY NUCLEAR PLANT UNIT 1 & Common ELECTRICAL MAINTENANCE SD! MARY s

CSSC EQUIPMENT i

FOR TliE MONTil 0F eptember 1981 S

I !

r.i t c e t on Sate Action Taken

~

!!ature of Operation of Cause of-Results of-To P:cclude h D.:c Syste.-

Cenponent

alf unction Recurrence

aintenance The Reactor Malfunction i

fl! 9/3/81 Secondary Emergency by-A monentary None Unidentified The damaged emer-The push button 2!

,Contain-pass switch breach of personnel using gency bypass push switch was replaced ment on the U-1 secondary con-the emergency button prevented and the electrical

,l' personnel tainment bypass switch.

operation of the interlock was access airlock occurred.

for door 235 solenoid, which successfully tested l'

doors.

damaged the allowed a monentary and returned to emergency bypass breach of secondary service. Emergency push button.

contaimrnnt.

bypass push buttons 4

,l' were disabled to i.

prevent. recurrence.

i; TR #203748 LER #BFRO-50-259/8150 i

t i

j i

s Drywell blow-Motor leads None Loose connec-Overheating burned Replaced and tested f

9/6/81'l' RBCCWer 1B-5 motor found burned.

tion cable insulation on portions of damaged conductors T1 and cables.

i leads Tl & T2 T2.

TR #203743 Z

fI at feeder l breaker (480

• i

'I volt R.e!0V Bda ll 1C pnl. llA.

l J.'

t

9/8/81 RHR FCV-74-66 During refuel None Contacts on FCV-74-66 did not The relay contacts were cleaned and

!,f control outage, while relay 10A-K35B open.

circuitry performing SI did not make up.

adjusted and FCV-74-66 was satisfac-

}

4.5.B.l.a, FCV-74-66 did I

torily tested.

3'

+

l jj not open.

LER #BFRO-50-259/8153!

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BROWNS FERRY SUCLEAR PL'diT UNIT 1 & Common ELECTRICAL MAINTENANCE SLM!ARY CSSC EQUIPMENT, FOR THE MONTH OF SCPtember 19 81

~2iicet on balc Action iaken Mature of Operation of Cause of Results of To Prcelude Date S ys t c.-

Cceponent taintenance The Reactor Malfunction

al f unc tion K?currence I

I j 9/19/81 Air con-Control bay The unit would None Burned 16AK53 Unable to shut con-Replaced the burned

' ditioning emergency not shutdown relay coil.

trol bay emergency relay coil in pnl.

(cooling-pressuriza-from the con-pressurization 9-42.

The' control heating) tion unit A.

trol switch.

unit A down from circuitry operated control room.

properly.

control TR #182913 circuitry.

J t

9/27/81 Diesel D/G-C degrad-Degraded None Timer contacts Degraded voltage The timer was re-Generatore ed voltage voltage timer fail to make up.

timer inoperabic.

placed and success-fully tested.

timer inoperable.

TR #219532 I

2-211-C2.

LER#BFRO-50-259/8155.

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' BROWNS FERRY NUCLEAR PLANT UNIT 2

i ELECTRICAL MAINTENANCE

SUMMARY

[

CSSC EQUIPMENT FOR THE MONTH OF September 19 81 i

h.~

7t i cc c on ba t e Action Taken.

i

!!sture of Operation of Cause of Results of To Preclude Dr.:e S ys c c:-

Ceeponent O

Maintenance The licactor Malfunction Malfunction R.tcurrence Contain-H0 analyz r During normal East side H 0 Pump motor wind-The sample return The motor was re-

[

l;9/13/81 22 27

. ment operation the ings were ground <- pump was inoperable.

paired, installed J

B sample re-

!f Inserting 110 analyzer ed and burned, and the sainple re-1 turn pump.

22 drywell inoper-turn pump success-i B sample re-able.

fully tested.

turn pump was TR #236228 l

4 discovered t LER#BFRO-50-260/8144.

t,-

1 be inoperable.

1 l

9/14/81 RBCCW RBCCW surge Could not re-None Low level switch The low level alarm Flushed out the i

was inoperable.

circuitry for the level switch. The it tank low ceive a low i

RBCCW surge tank switch operated I!

level switch.

level annunci-ation in the was inoperable.

properly.

l control room.

TR #236311

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u os (e

9/15/81 RHR RHR IC cooler During the None The overload RHR pump IC cooler The overloads Nare i!

}.

fan circuitry, performance relays on CR106-was inoperable.

reset and the SI

+

i I

of SI.4.2.B-57 C0 full' voltage was successfully l!

the cooler for non-revering completed. The l

l i

RHR pump 1C magnetic starter current pulled by i;

was found to had tripped out.

the pump cooler was i

be inoperable, checked and found to be acceptable.

I Cooler overloads for RHR pumps lA, 1B and

[

1D vere checked for l}

}

le i

proper settings, i

i TR #235978

't 1

TR #235976 jl IldR#BFRO-50-260/8146.. !

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BROWNS FERRY N'.' CLEAR PLANT UNIT 2 ELECTRICAL MAINTENANCE SLY. MARY CSSC EQUIPMENT 81 FOR THE MONT!! 0FSeptember 19 ftsect on Salc Action taken

!!ature of Operation of Cattse of Results of To Preclude f l D.:c Syste-Ccoponent liaintenance The Reactor Malfunction Malfunction R.currence 1

• 9/15/81 Core Spray Core spray While perform-None The overload Core spray NW and NE The overloads were

' Cooling northwest ing SI 4.2.B-relays on CR106-room cooler fans, reset and the SI and northeast 60 core spray C0 full voltage were inoperable.

successfully com-room cooler, room coolers non-reversing ple ted.' The current fan circuitry. were found to magnetic starters for the NE and NW l

be inoperable.

had tripped, core spray room coolers were checked and found to be acceptable on e

TR #235977.

TR's 196456, 196457, and 196458 was I

initiated 10/2/81 i

for U-1, U-2 and U-3 to check and/or set overloads tou l

proper settings."

LER#BFRO-50-260/8147.

l l

t 9/18/81 HPC1 FSV2-73-8 A grounded None FSV2-73-8 coil FSV2-73-8 was I Replaced the coil, lead was broken inoperable.

the ground cleared.

i circuit was and grounded.

FSV-2-73-8 operated indicated on properly.

the 250V TR's #236172, 279905, battery bd.

279901, 279902, and I

t 279903.

t

^

t

9/24/81 Reactor RPS MG set 2A MG set fail to None Time delay relay The motor generator Replaced the bad.

1. protectior, trip circui-trip. '

l K4 failed to did not trip.

relay, timed the l

e I

time out due to relay per EMI 15 and n

^

l system try.

a bad time delay tested operability per EMI 13.

The MG 3

set time delay relay operated properly.

TR #250727

,i 1

SROR S FERRY NUCLEAR PI.x;I UNIT 3 4

ELECTRICAL MAINTENx;CE

SUMMARY

CSSC EQUIPMENT FOR THE MONTl! 0F ScPtember 19 81

'Ettect on Saic Action Iaken

!!ature of Operation of Cause of Results of To Pteclude f L'. :e Syster Cenpenent

aintenance lhe Reactor Malfunction b1 function Recurrence 9/13/81 Diesel D/G 3C redun-While perform-The diesel gen-Redundant start The time delay The time delay relay 8

' Generators dant start ing redundant crator was tak-time delay relay relay was slightly was calibrated, I

circuitry, start test en out of ser-was out of cal-slow to operate.

successfully tested.

(EMI 3) the vice to calibr-

ibration, and the diesel gen-crator returned to redundant ate the time service.

start relay delay relay.

PFD1 was Load reduction TR #183842 TR #241452 slightly slow was begun due LER#BERO-50-296/8149.

to operate.

to the Trinity l

161kV line be-ing out of ser-vice, however, I

the diesel gen-l crator would l

have started.

u

+

The Trinity line was return-ed to service.

l I

t l

lReplacedthebad 9/13/81 Diesel D/G 3A Received a None, control Bad coil on NVR Received a false i

Generatory annunciator

" control power power was not relay.

" control powe r of f,'

relay coil, the circuitry.

off," annunci-Icst.

annunciaticn.

annunciator was successfully tested.

ation in the TR #203620 control room.

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I

BRO'4NS FERRY NUCLEAR PLANT UNIT 3 ELECTRICAL FL\\lNTENANCE SLMCRY CSSC EQUIPMENT FOR TliE MONTli 0F September 19 81 lifcct ca balc Action !aken

~

l

!!ature of Operation of Cause of Results of To Freclude f 'J.;:e S ys t er-Cceponent

!!aintcannte The Re.ic to r Malfunction

!!al f unc t ion Eecurrence t

t i 9/27/81 RilR 3EA LPCI MG Unstable out It was required Bad voltage regue A fluctuation of 1 Replaced the voltage 6

set, put voltage.

to remove the lator. The LPCI 15 volts.

regulator, the out MG set from MG set voltage put voltagd was service to re-regulator has stable. Future place the been sent to the recurrence control voltage regula-manufacture for will be dependent

tor, evaluation.

on the failure

,anlaysis.

'TR #203742 TR #241699 LER#BFRO-50-296/8152.

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BROICIS FERRY EUCLEAR FI.UIT GIT 1

MECIIANICAL MAINTE!%MCE SUFCIARY CSSC EOUIPMENT For the Month of September 19 81

/sCTIO:I TAKEN EFFECT 0:; SAFE Tale SYSTEM COMPONENT NATURE OF OPERATION OF CAUSE OF RESU1.TG CF TO PRECLUDE R\\INTENANCE TdE REACTOR R\\LFU;CTION MALFU::CTIO:!

RECURRE! CE s-13-81 CRD CRD 14-15 serar Valve Leak None Valve stem too Leakage Lengthened valve stem short 1/2 c';rn

(

jinlet valve TR# 223316 3-10-81 RHR FCV-74-61 Valve Leak None Bonnet leaking Valve Leak Torqued bolts 100 f t.lb:

TR# 189709 3-14-81 HPCI FCV-73-35 Faulty Stem None Stem Bent Unknown Fab. new stem, replaced stem & press. seal ring 5 repacked.

TR# 233373 wo W

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5 BRO'JES FERRY ' NUCLEAR FIldIT UNIT 2

MECIIANICAL MAINTE 3NCE SUMGRY CSSC EOUIPP/MT For the Month of September 19_81

(

ACTIO:I TAKEN EFFECT ON SAFE DATE SYSTEM

. COMPONEI;T NATURE OF OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE MAINTENANCE THE REACTOR

}L\\LFU!!CTION MALFUNCTION RECURRE! CE 3-27-81 Secondary Equip. Air Doors not None Weather stripping Door would not func. Replaced lock &

l Containmnt Lock Door 238 working off track &

correctly adjusted stripping l

(

faulty lock

& hinges TR# 203761

(~

l l 1-16-81 HPCI Gland Seal 31own gasket None Upper gasket Leak Changed gasket l

Condenser blown IR# 236236

' ater Leak None 0-ring out of Water leak Replaced O' Ring J

7-19-81 CRD:

CRD 50-27 groove & pinched TRf 236225 l

l l

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ER0kMS FERRY NUCLEAR PLANT UNIT

-3 MECIIANICAL MAINTEfGNCE

SUMMARY

CSSC EQUIP 1ENT For the Month of September 19 81 ACTION 'lAKEN EFFECT ON SAFE i

DATE SYSTEM COMPONENT NATURE OF OPERATION OF CAUSE OF

• RESULTS OF TO PRECLUDE MAINTENANCE Tile REACTOR MALFUNCTION MALFUNCTION RECURRENCE 7-8-81 Fire HCV-26-587 Valve None Broken Stem Valve would not oper. Installed new valve Protection Non-functional (Stuck Open)

& was blanked off, stem TR# 227210 l

i)-2-81 D/G 3EB D/G Air Leak on High None Blown Head Gasket Air Leak Installed new head Compressor #1 Pressure cyl.

spacer & gasket TR#241952 j-2-81 D/G.

3EA D/G Air Leak on High None Blown Head Gasket Air Leak Replaced head gasket TR# 241953 Compressor #2 Pressure cyl.

)-15-81 RBCCW Valve 3-70-612 Leakage None Valve bad Valve leaking Replaced with new valve. TR# 224855 i

1)-24-81 Rx Bld.

3FCO-64-10 Blown diaphrage None Bad air damper Diaphragm ruptured Replaced air damper Vent operator operator u"

TR# 241620 I

J

\\

4 t

I

_ BROWNS FERRY HUCLEAR PLANT UNIT. Common MECliANICAL MAINTENANCE SUE!ARY CSSC EOUIPMENT-For the Month of September 19 81 ACTION TAKEN EFFECT ON SAFE

'DATE

-SYSTEM COMPONENT NATURE OF OPERATION OF CAUSE OF RESULTS OF

'ID PRECLUDE MAINTENANCE TIIE REACTOR MALFUNCTION

._ MALFUNCTION RECURRENCE I

9-1-81 RilR Serv.

4" Air Release Faulty Valve None Guides broken off se would not Installed new air

& float marked up manction properly release valve Water' Valve on B3 Pmp.

TR# 233356 l

9-1-81 RilR Serv.

Air Release Faulty Valve None Damaged '.loat on Valve would not Installed new air Water Valve on C1.Pmp.

release valve function properly release valve TR# 233358

~

Installed new seat &

9-3-81 RilR Serv.

4" Air Release.

Bad seat on 40 None l Bad seat & valve Faulty valve & bad Water Valve seat on bad & valve or seat valve TR# 233370 C3 pump &

1"~

1" valve on dischg.

9-16-81 CO Storage FCV-39-ll Valve Leak None Bad seat & cup Valve leaking Replaced sent & cup

& hire i

seal seal TR# 233153 w

]

Proteciton u

9-24-81 EECW PS 67-54 & 55 Broken nipple None Unknown Bent nipple & PS Replaced nipples &

sticking out reserved P.S.

TR# 151400 t

4 4

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t i

1 t

sa I

I l

EROWNS FERR'l NUCLEAR PLANT IFJIT 1

INSTRUMENT IfAINTENANCE SUMMidtY CSSC EQUIPMENT FOR Tile MONTH OF September 19 81 NATURE EFFECT ON SAFE CAUSE ACTION TAKEN

'.'. fE SYSTDI C0tiPONENT

~

OF OPERATION OF OF RESULTS OF TO PhiCLUDE RECURRENCE MAINTENANCE THE REACTOR MALFUNCTION liALFUNCTION 9-3 Rod Position RPIS. Probes Repair None Sw Failure.

Loss of Indication None Information 42-23 50-35 i

42-59 9-5 F2edwater LI-3-46A Repair None Bad Solder Joint Loss of Indication None 9-5 Neutron "U" SRM Repair None Dirty Connector Downscale None Monitoring h

None None Dirty Connector Downscale 9-10 Neutron "A" SRM Repair Monitoring 9-11 Feedwater FI-3-13 Calibration None Instrument Shift Indicating High None c~

9-27 Neutron "B" SRM Repair None Drive Cable No Retract None Broken Monitoring 9-27 Neutron -

'"C"" IliM Repair None Bad Connector Indicating Ifigh None Monitoring Indicating High None 9-29 EECW FT-67-6A

' Replace None Fai, led Transmitter 9-30 Feedwater FI-46-3 Calibr ation None Instrument Drift Indicating Low None e

• a l

t BROWNS FERitY TEUCLEAR FIRT UEf1T 2&3 INSTRUMEPIT MAINTE14ANCE

SUMMARY

CSSC EQUIPMENT FOR TiiE MONIll OF September 19 81 NAIVRE EFFECT ON SAFE CAUSE ACTION TAKEN

'3 TE SYSTDI C0tlPONENT OF OPERATION OF OF RESULTS OF TO PRECLUDC RECURFENCE MAINTEMA!!CE Tile REACTOR MALFUNCTION PALFUNCTTO'i 4

7-5.

Neutron "D" SRM Repair None Faulty Connector Indicating Upscale None Monitoring i

9-9 Feeduater LR-3-62 Beplace None Failed Transmitter Indicating Downscale None 9-15 Control Rod PI-85-1 Calibration None Instrument. Drift Indicating Downscale None Drive Unit 3

9-4 EECW PDS-67-1 Replace None Natural End of Ground on 48 VDC None

~

s Life

9-11 Neutron

" B" AP RM Calibration None Instrument Drift Indicating Low None O

Monitoring 9-17 Core Spray FT-75-21 Calibration None Instrument Drift Indicating Low None.

G S

O e

9 e

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4

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36 FIELD SERVICES

SUMMARY

September 1981 Major field services efforts were expended on completing maintenance and modification activities on the unit 1 cycle 4 refueling / torus outage.

Emphasis was placed on the following activities in order to complete the l

refueling outage as soon as possible.

.l.

Torus Modifications - Additional torus work was identified which included the installation of two gussets on each side of the 16 cradles, four gussets and 2 support plates on five external ring head to the external ring girders. Torus closeout September 29, 1981.

2.

LPCI modification continued - Completed Loop II portion of this modification and testing. The two motor generator sets associated with Loop II have been released to Operations.

3.

H /0 Analyzer - Hanger installation has been completed as 2 2 I

well as all RCW and EECW piping modifications. All work plans were reviewed and apprrved for startup on September 29, l

1981.

4.

Turbine Floor - General cleanup completed.

i 5.

Generator Breaker Modification P0214 - Completed all post-mod testing during backfeed September 25, 1981.

6.

Unit Station Service Transformer P0275 - Completed all post-mod testing during backfeed on September 27, 1981.

7.

Drywell - All drywell work completed and closcout accomplished on September 25, 1981.

8.

Reactor Status - Rod pulls commenced September 30, 1981.

9 m

e me 4

_ _...