ML20042A391

Monthly Operating Repts for Nov 1981

ML20042A391
Person / Time
Site:	Browns Ferry
Issue date:	12/01/1981
From:	Thom T TENNESSEE VALLEY AUTHORITY
To:
References
NUDOCS 8203230383
Download: ML20042A391 (33)

Text

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TENNESSEE VALLEY AUTHORITY DIVISION OF POWER PRODUCTION BROWNS FERRY NUCLEAR PLANT MONTHLY OPERATING REPORT November 1, 1981 - November 30, 1981 DOCKET NUMBERS 50-259, 50- 260, AND 50-296 l

LICENSE NUMBERS DPR-33, DPR-52, AND DPR-68 I

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f,/ cm+<7 Submitted By: '

Plan't userintendent

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$!S382RoS$$$$;

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t TABLE OF CONTENTS 1

Operations Summary.

r Refueling Information 3

Significant Operational Evente.

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

12 15 Operating Data Reports..

Unit Shutdowns and Power Reductions..-.

18 Plant Maintenance 21 Field Services Summary..

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1 Operations Summary November 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 25 reportable occurrences and two revisions to previous reportable occurrences reportid to the NRC during the month of November.

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

Unit 2 There were no scrams on the unit during the month.

Unit _3 The unit was in its EOC-4 refueling outage the entire month.

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

Location Usage Factor j

Unit 1 Unit 2 Unit 3 Shell at water line 0.00521 0.00422 0.00361 Feedwater nozzle 0.24937 0.18081 0.14108 Closure studs 0.20492 0.14260 0.10977 NOTE:

This accumulated monthly information satisfies technical I

specification section 6.6.A.17.B (3) reporting requirements.

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Operations Summary (Continued)

November 1981 Common System Approximately 4.42E+05 gallons of waste liquid.were-discharged containing

-approximately 2.31E-01 curies of activities.

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jfL Operations Summary (Continued) j (uss)g/l OAg)

November 1981 Refueling Information J

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1 Unit 1

%* f Unit 1 is scheduled for its'fifth refueling beginning o oraNui$ arch 4, 1983, with a scheduled restart date of June 3, 1983. This refueling will involve loading 8 X 8 R (retrofit) fuel assemblies into the core, finishing the torus modifications, turbine inspection,,and finishing TMI-2 modifications.

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Unit 1 ended its EOC-4 r3 fueling outage then' it was synchronized to the system October 1, 1981.

There are 764 fuel assemblies in the reactor vessel. The spent fuel storage pool presently contains 260 EOC-4 fuel assemblies, 232 E0C-3 fuel assemblies,156 EOC-2 fuel assemblies, and 168 EOC-1 fuel assemblies. The pre-sent capacity is 2655 locations.

Unit 2, Unit 2 is scheduled for its fourth refueling beginning on or about July 30, 1982, with a scheduled restart date of January 1, 1983. This refueling outage will involve completing relief valve modifications, torus modifications, "A" low pressure turbine inspection, MG set installation for LPCI modification, and loading additional 8 X 8 fuel assemblies into the core.

There are 764 fuel assemblies in the reactor vessel. At the end of the month there were 352 EOC-3 fuel assemblies, 156 E0C-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 capability in the pool. However, 949 new high density storage locations have b'een installed and can be used after they are qualified.

4-Operations Summary (Continued)

November 1981 Refueling Information (Continued)

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Unit 3'.

l UnIb.3beganitsfourthrefuelingonOctober30,withascheduledrestart date of March 7, 1982.' This refueling involves loading additional P X 8 R

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(retrofit) as,semblies int'o the core, relief' valve. modification, turbine in-sp'ection, generator breaker and unit station transformer tie-in, and torus modifications.

There are 0 fuel assemblies presently in the reactor vessel. There are 764 EOC-4 fuel assemblies, 124 EOC-3 fuel assemblies, 144-EOC-2 fuel assemblies,

- 208 EOC-1 fuel assemblies, and 288 new fuel assemblies in the spent fuel storage pool. The present available capacity of the spent fuel pool is 221 locations.

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5 Significant Operational Events Unit 1 Date Time Event 11/01/81 0001 Reactor thermal power at 85%, PCIOMR in progress (sequence "A").

11/02/81 0515 Reactor thermal power at 99%, maximum flow, rod limited.

11/03/81 0805

. Commenced reducing thermal power when "A" recir-culation pump tripped dur,ing SI 4.2.B-69.

(Instrumentation ini.tiates or controls CSCS reactor

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high pressure).-

0825 Reactor charsal power at 70%, SI 4.6.A.6 and 7 com-plete for re-start of "A" recirculation pump.

0835 "A" recirculation pump in service, commenced power ascension from 70% thermal power.

1030 Reactor thermal power at 95% thermal power, commenced PCIOMR (sequence "A").

1300 Reactor thermal power at 99%, maximum flow, rod limited.

11/06/81 1527 Received 1/2 scram and loss of RPS MG set "B" while transferring 480V' shutdown board "lB",

reactor thermal

. power at 99%. Reset all PCIS isolations and recircu-lation pump "B" scoop tube lock.

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

l 11/07/81 2302 Commenced reducing thermal power for turbine control valve tests and SI's.

j 2330 Reactor thermal power at 87%, holding for turbine l

control valve tests and SI's.

t 11/08/81 0110 Turbine control valve tests and SI's complete, commenced power ascension.

j 2000 Reactor thermal power at 99%, maximum flow, rod i

limited.

l 11/09/81 0105 Reduced thermal power to 94% for SI 4.3.A.2 control rod exercise.

0145 Commenced power ascension from 94% thermal power.

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

11/13/81 0908 Commenced reducing thermal power to reduce "R"

factor, 1132 Inserted. rods, reactor thermal power at 93%, commenced power ascension.

1138.

Reactor thermal power increased to 96%, holding for SI 4.1.B.15 APRM flow bias adjustment and SI 4.1.B.2 APRM gain.

6 Significant Operational Events Unit 1 Date Time Event 11/13/81 1300 S1 4.1.B.15 and SI 4.1.B.2 complete, reactor power at 96%, holding for S1 4.6.E.1 jet pump operability.

1600 SI 4.6.E.1 complete, reactor power at 96%, holding for MSIV exercise.

1820 MSIV exercise complete, reducing thermal power from 96% for control rod pattern adjustment.

1909 Reactor thermal power at 75% for control rod pattern adjustment.

1920 Control rod pattern adjustment complete, commenced power ascension.

2000 Commenced PCIOMR from 84% thermal power (sequence "A").

11/14/81 0030 Reactor thermal power at 92%, holding for turbine control valve tests and SI's.

0100 Turbine control valve tests and SI's complete, commenced power PCIOMR (sequence "A").

0500 Reactor thermal power at 96%, maximum flow, rod limited.

1240 Commenced power ascension from 96% thermal power.

1300 Reactor thermal power at 99%, maximum flow, rod limited.

11/15/51 0735 Commenced reducing thermal power for RTI-22.

1000 Reactor thermal power at 92%, holding for RTI-22.

1314 RTI-22 complete, reactor thermal power at 92%, holding for control rod pattern adjustment.

1905 Commenced reducing thermal power for control rod pattern adjustment.

1955 Stopped reducing thermal power at request of load dispatcher, reactor power at 77%.

2025 Commenced reducing thermal power for control rod pattern adjustment.

2200 Reactor thermal power at 64%, holding for control rod pattern adjustment.

11/16/81 0001 Control rod pattern adjustment complete, commenced power ascension.

0045 Commenced PCIOMR from 70% thermal power (sequence "A").

11/17/81 0500 Reactor thermal power at 99%, maximum flow, rod limited.

11/2'l/81 0230 Commenced reducing thermal power.for turbine control valve tests and SI's.

0300 Reactor thermal power at 87%, holding for turbine con-trol valve tests and SI's.

0630 "

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

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7 Significant Operational Events i

Unit 1 Date Time Event 11/28/81 2323 Commenced reducing thermal power for turbine control valve tests and SI's.

2400

' Reactor thermal power at 87%, holding for turbine control valve tests and SI's.

11/29/81 0028 Turbine control valve tests and SI's complete,

-commenced power ascension.

0400

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

t 11/30/81 2400 Reactor thermal power at 99%, maximum flow, rod limited.

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Significant Operational Events Unit 2 Date Time Evert 11/01/81 0001 Reactor thermal power at 67%, holding for control rod pattern adjustment.

0330 Control rod pattern adjustment complete, commenced PCIOMR (sequence "A").

1717 Commenced reducing thermal power from 85% to place "C" string high and low pressure heaters in service.

Reactor thermal power at 75%, "C" string heaters in 2210 service, commsnced PCIOMR (sequence "A").

Reactor thermal' power at 99%, maximum flow, rod 11/02/81 2300 limited.

11/06/81 0225 Commenced reducing thermal power when FCV 66-28 went closed when a fuse blev in panel 9-10.

0230 Reactor thermal power at 96%, holding due to problems with FCV 66-28.

0525 Commenced power ascension from 96% thermal p~ower.

0600 Reactor thermal power at 99%, maximum flow, rod limited.

11/07/81 0042 Commenced reducing thermal power for turbine control valve tests and SI's.

0130 Reactor thermal power at 82%, holding for turbine con-trol valve tests and Sl's.

0208 Turbine control valve tests and SI's complete, commenced power ascension.

0500 Reactor thermal power at 99%, maximum flow, rod limited.

11/09/81 2200 Commenced reducing thermal power for removal of "2C" conden. ite booster pump for service for maintenance.

2300 Reacto-thermal power at 64%, holding for maintenance to "20 condensate booster pump seal.

11/10/81 0120 Reactor thermal power at 64%, holding for maint' nance e

to "2C" condensate booster pump and for control rod pattern adjustment.

0150 "2C" condensate booster pump in service and control rod pattern adjustment complete, commenced power ascension.

0400 Commenced PCIOMR from 70% thermal power (sequence "A").

0805 Commenced reducing thermal power from 75C due to rod blo'cks of APRM's.

0900 Commenced PCIOMR from 69% thermal power (sequence "A").

,11/11/81 1300 Reactor thermal power at 99%, maximum flow,' rod limited.

9 Significant Operational Events Unit 2 Date Time Event 11/13/81 2043 Commenced reducing thermal power for "2A" recircu-lation pump MG set brush replacement.

2245 "2A" recirculation pump out of service for brush replacement, reactor power at 50%.

11/14/81 0105 "2A" recirculation pump MG set brush replacement

. completed, holding at 50% power for "2B" recircu-lation pump MG set brush replacement.

0120 "2B" recirculation, pump MG set out of service for brush replacement' reactor power at 50%.

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0325 "2B" recirculation pump MG set brush replacement complete, both recirculation pumps back in service, commenced power ascension.

0700 Commenced PCIOMR from 91% thermal power (sequence "A").

1500 Reactor thermal power at 99%, maximum flow, rod limited.

11/21/81 0010 Commenced reducing thermal power for turbine control valve tests and SI's.

0100 Reactor thermal power at 88%, holding for turbire.

control valve tests and SI's.

I 0256 Turbine control valve tests and SI's complete,-

commenced power ascension.

0400 Reactor thermal power at 99%, maximum flow, rod limited.

11/24/81 0931 Reduced thermal power to 82% when "2A" and "2B" recirculation pumps ranback due to a momentary interruption of I and C bus.

0945 Commenced power ascension from 82% thermal power.

1100 Reactor thermal power at 99%, maximum flow, rod limited.

11/27/81 2200 Commenced reducing thermal power for control rod I

sequence exchange from "A" to "B".

2400 Reactor thermal power at 50%, control rod sequence exchange in progress.

11/28/81 0130 Control rod sequence exchange complete, commenced power ascension (sequence "B").

0400 Reactor thermal power at 69%, holding for turbine control valve tests and SI's.

0435 Turbine control valve tests and SI's complete, l

commenced PCIOMR (sequence "B").

0835 Reactor thermal power at 78%, holding due Xenon transient.

1030 Commenced PCIOMR from 78% thermal power (sequence "B").

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i Significant Operational Events Unit 2 Date Time Event 1

11/29/81 1600 Reactor thermal power at 99%, maximum flow, rod limited.

11/30/81 2400 Reactor thermal power at 99%, maximum flow, rod limited.

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11 Significant Operational Events Unit 3 Date Time Event-11/01/81 0001 End of cycle 4 refu'el outage continues.

11/05/81-2236 Commenced fuel unloading.

11/16/81 1425-Core unloaded.

11/30/81 2400

.End of cycle 4 refuel outage continued.

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12 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-259 UNIT Browns Ferry - 1

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DATE COMPLETED BY Ted Thom s

s TELEP110NE 205 729 6846 NOVEMBER gg DAY AVER AGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL

. (MWe Net)

(MWe Net)

I 1013 g7 1058

.s, 1055 1055 2

g3 3

in??

39 1052 4

1060 20 1065 5

1064 21 1051 1061 1056 6

g 1071 1056 7

23 8

1053 24 1065 9

1046 1063 25 1068 1060 10 26 1065 1070 12 1055 1065 28 1055 13 29 l4 1023

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30 1069 947 15 31 s-16 893 INSTRUCTIONS On this format. list the average daily unit power levelin MWe Net for each day in the reportinF month.Cuenpute to i

the nearest whole megawatt.

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AVERAGE DAILY l' NIT POWER LEVEL 4

a DOCKET NO.

50-260 UNIT Browns Ferry - 2 e_

DATE 12-1-81 Ted Thom COMPLETED BY a*

TELEPHONE 205 729-6846 I-NOVEMBER l'

MONTH 1

- DAY' AVERAGE DAILY POWER LEVEL DAY AVERAGN DAILY POWER LEVEL

, (M We-Net)

(MWe-Net) 798 1076 g

37 952 1059 2

33 3

1056 39 1063 1064 20 1083 4

1069' 1058

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5 21 1067~

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1065 1063 7

23 1063 1064 1076 8.

24 1032 1071 9

25 785 l

10 1071 i

1021 1042

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12 1061 28' 818 i

1024 1031 13 29 14 924

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30 1075 f

1071 15 3,

1071 16

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INSTRUCTIONS On this format,hst the hverage daily unit power levelin MWe Net for each day in the reporting month. Compute to i

l the cearest whole inegawatt.

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AVER AGE DAILY UNIT POWER LEVEL

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DOCKET NO.

50-296 L

UNIT Browns Ferry - 3 DATE 12-1-81 COMPLETED BY, Ted Thom TELEPHONE 205 729 6846 1

I NOVEMBER

. l MONTH i

DAY AVER ACE DAILY POWER LEVEL ~

DAY AVER AGE' DAILY POWER LEVEL (MWe NeO (MWe Net)

-10

-8 37 I

-12

-10 2

,3

-10

-10 3

-11

-9 4

20 I

-10

-8 g

21

-9

-8 6

,2

[

-10

-8 23

-10

-8 8

24 9

-8 25

-8

-8

-7 10 26 11

-9 27

-8

-8

-6 12 23

-8

-6 13 29

-8

-6 14 30

-8 15 3,

-8 16 t.

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INSTRUCTIONS On this format.bst the avera;c daily unit powei leselin MWe. Net for each day in the reportmg m.inth. Ciempute tii the nearest whole megawatt.

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15 OPERATING DATA REPORT

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DOCKET NO. 50-259 DATE 12-1-81 COMPLETED BY Ted Thom TELEP110NE 9fM 770 6846 OPERATING STATUS Browns Ferry - 1 Notes

1. Unit Name:

1

2. Reporting Period: November 1981 3293

3. Licensed Thermal Power (MWt):

1152

4. Nameplate Rating (Gross MWe):

10M

5. Desigt: Electrical Rating (Net MWe):

1098.4

6. Maximum Dependable Capacity (Gross MWe):

1065

7. Masimum Dependable Capacity (Net MWe):

,s

8. If Changes Occur in Capacity Ratir.gs (Items Number 3 Through 7) Since Last Report.Give Reasons:

NA

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9. Power LeselTo which Restricted,lf Any(Net MWe):

NA l

10. Reasons For Restrictions,If Any:

4 This Month Yr. to Date Cumulatise 720 8,016 64,298 II. liours I, Reporting Period

12. Number Of }{ours Reactor Was Critical 720.0 3,764.23 38,570.8.

0 116.33 5,215.20

13. Reactor Reserve Shutdown !!ours 720.0 3,693.35 37,686.17

14. Ilours Generator On Line y'

15. Unit Rewne Shutdown llours 0

0 0

16. Gross Thermal Energy Generated (MWil) 2,325,646 11.178.327 104.470.688

17. Gross Electrical Energy Generated (MWil) 774,890 3,727,160 34,490,450

18. Net Electrical Energy Generated (MWil) 752,352

_3,622,873 33.486.690

19. Udit Senice Factor 100 46.1 58.6 i-

20. Unit Asailability Factor 100 46.1 58.6 98.1 42.4 48.9

21. Unit Capacity Factor IU>ing MDC Net) 98.1 42.4 48.9

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22. Unit Capacity Factor (Using DER Net) 0 4.4 27.5

23. Unit Forced Outage Rate

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

9

25. If Shut Down At End Of Report Period, E timated Date of Startup:

26. Units in Test Status aPrior to Commercial Operationi:

Forecast Achiesed INITI A L CRITICA LITY INITIA L* ELECTRICIT Y COMMERCl AL OPERATION 28/77)

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16 OPERATING DATA REPORT 50-260 DOCKET NO.

DATE 12-1-81 COMPLETED BY Ted Thom TELEPilONE 20s 729 6846 OPERATING STATUS Browns Ferry - 2 Notes

1. Unit Name:

November 1981

2. Reporting Period:

3293

3. Licensed Thermal Power (MWI):

1102

4. Nameplate Rating (Gr9ss MWe):

5. Design Electrical Rat!'ng (Net MWe):

1065_

6. Masimum Dependable Capacity (Gross MWe): 1098.4 1065

7. Maxipium Dependable Capacity (Net MWe):

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

NA NA

9. Power Lesel To Which Restricted.lf Any Net MWe):

A

10. Reasons For Restrictions. lf Any; This Month Yr. to Date Cumulatise 1

720 8,016 59,239

11. Ilours In Reporting Period

12. Number Of flours Reactor Was Critical 720 7,022.05 37,7.65 46 0

965.58 13,419.06

13. Reactor Resene Shutdown llours 720 6,774.83

_36,515.79 I4. Ilours Generator On Line

15. Unit Rcsene Shutdown llour, 0

0 0

16. Gross Thermal Energy Generated (MWil) 2,255,743 20,900,821 104,471,464

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17. Gross Electrical Energy Generated (MWill 759,970 _,,,

6,960,380 34,697,568 738,451 6,755,754 33,706,061

18. Net Electrical Energy Generated (MWil) 100 84.5 61.6

19. Unit Senice Factor 100 84.5 61.6

20. Unit Availability Factor 96.3 79.1 53.4

21. Unit Capacity Factor IUsing MDC Net) 96.3 79.1 53.4

22. Unit Capacity FactorIUsing DER Net) 0 9.8 2.9

23. Unit Forced Outage Rate

24. Shutdowns Scheduled over Nest 6 Months (Type. Date.and Duration of Facht:

25. If Shut Dumn \\t End Of Report Period. Estimated Date of Startup:

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

Futecast Achiesed INITI A L CRITICALITY INITI AL ELECTRICITY COMMERCI A L 0l'ER ATION t

(9/77 )

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OPERATING DATA REPORT DOCKET NO.

50-296 DATE 12-1-81 CO\\lPLETED BY _Ieddhoq o

l TELEPllONE ons 729-6846 l

OPERATING STATUS m Feny - 3 Noto

l. Unit Name:

2. Reporting Period:

3293

3. Licensed Thermal Power (51Wt):

4. Nameplate Rating (Gross h!We):

1152 1065 l

5. Design Electrical Rating (Net htWe):

1098.4

6. Staximum Dependable Capacity (Gross MWe):

1065 l

7. hiaxipium Dependable Capacity (Net StWe):

l

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

l' NA 9

9. Power Lesel To Which Restricted. If Any (Net MWe):

NA NA

10. Reason > For Restrictions.lf Any:

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This 31onth Yr.-to Date Cumulatise f

720 8,01'6 41,664 I1. Ilours In Reporting Period

12. Number OfIlours Reactor Was Critical 0

6.495.71 32.466.98 l

13. Reactor Reserve Shutdown Hours 0

6.360.78

__31.750.78 330.64 2.141.53 0

14. Ifours Generator On Line

_ 0 0

15. Unit Resene Shutdown liours

,0

16. Gross Thermal Energy Generated (51Wil) 0 19,493 592 91;R58,62n_

17. Gross Electrical Energy Generated (SIWH) 0 6.459.160 30.998.190.

0 6,264,623 30.088.946

13. Net Electrical Energy Generated (StWH) 0 79.4 76.2

19. Unit Senice Factor 0

79.4 76.2

20. Unit Asailability Factor

21. Unit Capacity Factor IUsing StDC Net, 0

73.4 67.8 0

73.4 67.8 22 Unit Capacity Factor (U>ing DER Net)

23. Unit Forced Ontage Rate 0

7.1 9.2

24. Shutdowns Scheduled Oser Nest 6 Stonths(Type. Date.and Duration of Each t:

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

26. Units In Test Status (l'rior to Commercial Operationi:

Forecast Achiesed INITI A L CRITICALITY INITIA L ELECTRICITY CO%1 MERCI AL OPER ATION v.c 2,

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UNIT S!!UTDOWNS AND POWER REDUCTIONS' DOCKET N3.

50-259 UNIT NAME - Browns Ferry - 1 DATE 17-1-R1 November COMPLETED BY -TaA mm REPORT MONTil TELEPilONE 205 729 6846 s.

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Cause A Corrective 2 ~5 Event

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93 Action to 4,4 N...

Date y,

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Report e mO EO Prevent Recurrence j5 H

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c5 190 11-03-81 F

H Derated due to "A" recirculation pump trip during SI'due to inadvertently shorting PS with test instrument 191 11-13-81 S

11 Oerated for control rod pattern adjustment N

192 11-15-81 S

B Derated for RTI-22 pressure regulator test and control rod pattern adjust-ment I

2 3

4 F: Forced Reason:

Method:

Exhibit C - Instructions S: Scheduled A. Equipment Failure (Explain)

I Manual for Preparation of Data B. Maintenance of Test 2-Manual Scram.

- Entry Sheets for Licensee 3

C Refueling 3 Automatic Scram.

Event Report (LER) File (NUREG-D Regulatory Restriction 4-Other (Explain) 0161)

E-Operator Training & License Examination g

i F-Administrative 5

G-Operational Error (Explain)

Exhibit I-Same Sourec (9/77)

Il-Other (E xplain) l e

D

DOCKET NO.

50-260 UNIT SilUTDOWNS AND POWI.R REDUCTIONS UNIT NA!!E Browns Ferry - 2 DATE 12-1-81 November COMPl.ET El) ItY J ed Thnm REPORT atONT!!

TELEPilONE

__205 729-6 Mh._

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3 4 $3 Licensee j-r, h,

Cause A Corrective No.

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Action io f

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Report :

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Prevent Recurrence H

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213 11-09-81 F

B Derated to remove "2C" condensate booster puriip from service for maintenance 214 11-13-81 F

B Derated for "2A" and "2B" recircula-tion pump MG set brush replacement 215 11-27-81 S

H Derated for control rod sequence G

exchange from "A" to "B" I

I 2

3 4

F: Forced Reason:

Method:

Exhibit G -Insienctions -

S: Scheduled A Equipment Failure (Explain) 141anual for Pieparation of Data B41aintenance of Test 2-Manual Scram-Ent y St. cess l'or Licensee C-Refueling 3-Automatic Scram.

Esen Report ILERI FileINUREG-D-Regulatory Restriction 4-Other (Explain) 01611 li-Operator Training & License Examin..* ion F Administrative 5

G-Operational Error Ilixplain t Eshibit I - Same Source 19/77)

Il Other (Explain) j

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50-296 DOCKET NO.

UNIT SilU! DOWNS AND "OWER REI)UCTIONS UNn NAME Bro. ins Ferry -3

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DATE _12-1-R1 COMPLE TED ltY _ Icd _,Jhem l

November REPORT SlONiil

• f IELLPilONE _205 729 6846_

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2, 5 i Licensee

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Cause & Currectise l

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EE5 Event s?

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Present Recurrence e

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93 11-01-81 S

720 C

2 Reactor scram to accomodate EOC-4 refuel outage (Cont) w O

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4 F: Forced Reason:

Method:

Exhibii G - Instructions S: Scheduled A-Equipment Failure (Explain) 1 Manual for Preparation of Data ll Maintenance of Test 2 Manual Scram.

Entry Sheets fur Licensee C Refueling 3 Automatie Scram.

Eveni Report iLI:R) File (NUREG-D Regulatory Restriction 4-Ot her ( E xplain) 01611 S

L-Operator Training & License Examination F Admims:rative 5

G Operational Eirus (Explain)

Exlubis 1 - Same Source (9/77) 11-01her ( E xplam) 9

.- a -

BROUNS FERRY UUCLEAR PLAST UNIT 1 & Common ELECTRICAL MAINTENANCE

SUMMARY

CSSC EQUIPMENT M vember 81

.o FOR Tile MONTil OF gg tutect on Salc Action Takca flDate

' ' S ys t cr-Cceponent

!!a ture of Operation of Cause of Results of To Preclude

.taintenance The Reactor

!;alfunction Malfunction Recurrence f

11/2/81 Diesel IC D/G cen-Communication None Bab inverter Annunciator circui-Replaced bad inver-Generator tral commun-alarm panel ry inoperable ter, annunciator a

circuitry. operated ication alarm annunciator properly.

panel circuitry TR #203791 inoperable.

l i

Air con-1A control Chiller trip-None Bad vane motor Chiller inoperable Replaced motor, l11/4/81 vacuum tubes, and ditioning bay chiller ped on low micro relay.

(cooling-suction Calibrated controls l

heating) pressure chiller operated I

properly.

i TR #250626 l

U a

11/5/81 liigh-Fire pump A Received a None Bad annunciator Received a false Replaced circuitry I

pressure annunciator false circuitry card

" fire pump running" card, annunciator j

alarm operated properly.

! circuitry annunciation

{

l fire-TR #226569

! protec-card TR #236056 tion q

i shut,- While trans-

'1B' 480 volt During previous

'IB' shutdown board The shutdown board 11/6/81 480 volt l 480 volt l

shutdown down board 1B ferring 'IB' shutdown board maintenance the wa's de-energized was transferred boards normal feeder 480 volt shutA was de-energized safety pin was for approximately back to alternate l

breaker down board for appro'ximate-left in place 3 minutes feed. The breaker from alter-ly three minutes in the push rod was replaced with i

I nate to nor-preventing rap-unit 3 shutdown mal feed the id closure cap-board alternate j

i normal feeder ability of the feeder breaker.

breaker fail-breaker Removed the safety pin, and reinstalled l

ed to close on unit 3 shutdown

)

board, the breaker j

operated properly.

e TR #203784 LER#BFRO-50-259/8168 I

I

BROb'NS FERRY NUCLEAR PLANT Ul3IT 1 & Common ELECTRICAL MAINTENANCE sum 1ARY CSSC EQUIPMD3T FOR Tile MONTl! 0F November 19 81 fifect on bafc Action Taken

!!ature of Operation of Cause of Results of To l'reclude D.;ec

~ Systce Ccaponent

taintcaance The R e.nc to r

al func tica

!!al f unc t io n Recurrence 11/6/81 Contain-CAD system FCV-1-84-19 None Bad coil on FCV-1-84-19 Replaced the bad

' ment vent valve was blowing relay 84-K3A inoperable coil, valve oper-atmoshere (FCV-1-84-19) fuses l

ated prop'rly e

dilution control TR #203783 circuitry i

f j

A

~

ELECTRICAL MAINTENANCE SUFDIARY CSSC EQUIPMENT FOR Tile MONTH OF November 19 81

=

Ettect on Sa[c Action Taken 0

g

( Unte.

Systce Ccaponent Itature of Operation of Cause of Results of To Preclude b

Maintcaance The Reactor Malfunction Malfunction 7e?currence g__

11/2/81 IIPCI FCV-73-16B A ground was None Moisture in A ground was indi-Cleaned and dried push button indicated on push button cated on 250 volt push button control control

1. 2 250 volt control battery board station, ground station battery board cleared.

j TR #203790

^

D 911/17/81 Core Northwest During the-None The overload Core spray NW room The overload (s) spray core spray performance relay on CR106CO cooler fans were were reset and I

cooling room cooler of SI4.2.B.60 full voltage inoperable the SI successfully I

fan circuitry the N/W core non-reversing completed. This I

spray room magnetic starter is presently under cooler was had tripped investigation.

found to be LERfBFRO-50-260/

{

inoperable 8163 Ul.

I I

l 1

1 I

I i

l i

t l

I I

l

BROWNS FERRY NUCLEAR PLANT Ul!ZT M'

ELECTRICAL MAINTENANCE SUID!ARY CSSC EQUIPMENT November 81 FOR Tile MONTil 0F gg iftect on dalc Action Taken D.e c ~ ~ ~ Systce Ccmponent

!!sture of Operation of Cause of Results of To Preclude

tsintenance T't e Reactor Malfunction

-falf unc t ion Recurrence 10/31/81 RCIC FCV 3-71-3 During shut-3-FCV-71-3 Valve motor Valve inoperable The limitorque down for re-inoperable failed due to valve motor will fueling out-an open field be replaced during age RCIC

~

winding this refueling steam supply outage..

TR #279773 and valve 3-FCV-TR #276729 are I

71-3 could not be closed outstanding pend-electrically ing completion of repairs.

LER#BFRO-50-296/

8165 11/3/81 Fuel pool 3A fuel pool Pump vibrat-None Bad motor Excessive vibra-Replaced the pump y cooling cooling pump ing bearing tion, worn end bell motor. Pump oper-bearing housing ated properly.

motor TR #235020 t

t 11/12/81 Contain-11 sample In order to None, unit 3 was Bad relay 11 sample return Replaced the bad 2

2 ment return pump stop the re-in cold shutdown pump ran continu-relay, control turn pump it ally circuitry operated inerting control l was required

~

properly circuitry (Relay R3 in to trip the TR #237228 panel 25-341) panel 25-341 power supply breaker #309 on panel 9-9 e

I I

I l

BROWNS FERRY NUCLEAR PLANT UNIT 3 ELECTRICAL HAINTENMCE SUIDIARY CSSC EQUIPl!ENT FOR Tl!E ?!ONTil OF November 19 81 f.t t cc t on Salc Action Taken D..S c -

Systce Ccoponent flature of Operation of Cause of Results of To Preclude ltaintenance The Reactor Malfunction

lalfunction Recurrence I

' 11/14/81 Neutron IRl! bypass The bypass None, unit 3 in Switch contact The IRM channel Tightened screws, monitor-switch on switch was refueling block screw bypass switch was the switch oper-ing panel 9-5 stuck on

'H' outage loose indperable ated properly on channel all positions.

I bypassed TR #182622 i

I I

i i

i 1

5 i

f l

1 I

i l

I e

I I

e i

l l

k

BROW 11S FERRY IPJCLEAR PLANT UBIT COMMON CSSC EQUIP.' TENT IIECIIANICAL FL\\INTENANCE SUlru\\RY For the 11onth of November 19 81

~

1 EFFECT ON SAFE ACTION TAKEN DA1E SYS TEIl CO:!PONENT NATURE OF OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE IL\\T NTENANCE Tile REACTOR MALFITNCTION ItALFUNCTION RI:CURRENCE l-2-81 Sec. Cont.

RilR D'oor C&D Doors out of None Worn bushings &

Doors are latched, Installed bushing on C

~

Adjustment out of adjustmnt, but too loose Adjusted D TR0 232549 l

0-22-8 L D/G l-11 D/G Increased None None Dirty Starters Replaced both right-sid Rebuilt freq.

Starters of Starters TR# 233098 l-24-8 L RilRSW Vac Relief Vlv Valve Leaking None Valve Inoperable Valve Leaking Replaced whole valve on disch. of C2 TRS 280487 RilRSW Pump i

Ch

• i O

e

BROWNS FERRY NUCLEAR PL\\MT UNIT 1

CSSC EQUIP!!ENT MECllANICAL !!AINTENANCE SUFCIARY For the Month of November 19 81 EFFECT ON SAFE ACTIO!i TAKEN DATE SYSTD1 CO)!PONENT NATURE OF OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE

!!AINTENANCE

'IllE REACTOR MALFUNCTION MALFUNCTION RECURRE?:CE T 26-81 CRD CRD Module 14-llValve Leaking None Valve Non-funct.

Valve leaking at sole - Replaced with new f

Dir. Contr. Viv noid housing subassem valve 1-85-40B TR# 280337 I

@-19-8 1 Fuel Pool 1B FPC Pump Pump broken None Broken Impeller Shaft housing busted Repaired impeller, Cooling installed new shaft, sleeves, packing, bearing retainer housing TRf 226943

.1-23-81 RllR Serv.

FCV-23-52 llandwheel out None Unknown Wheel off valve Replaced Wheel Water of place TR# 282067 1-13-81 RllR LPCI lEN Gen. Coupl.

Bad coupling None Worn Seals Grease leaking Replaced Coupling U seaks TR# 280360 e

9 e

BROUNS FERRY l'UCLEAR PLINT Ui4IT 2

CSSC EOUIP:IE::T MECilANICAL MAINTE!LiNCE SUFCIARY For the 11onth of November 19 81 EFFECT ON SAFE ACTION TAKEN IliTE SYS TE!!

COMPONENT NATURE OF OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE MAINTD:ANCE Tile REACTOR R\\LFUNCTION MALFUNCTION RECURRENCE

=21-83 RilR Line in B6D RilR Leaking Nonc Seal Bad Union leaking Replaced seal & repiped IIcat Exch. Rm.

union TR# 206578 l 81 Standby Accura. on 2A Faulty bladder None Jnknown Broken valve stem Replaced bladder Liquid SLC pump (blad)

TR# 237805 Contr.

1 D

sg l

i

BROU?!S FERRY NUCLEAR PIANT UNIT 3

MECllANICAL MAI!!TENANCE

SUMMARY

CSSC EOUTP:i:NT For the Month of Novenber.19 81 EFFECT ON SAiA ACTION TAl:LN DATE SYS TEM COIIFO: EI;T NATURE OF OPERATION OF CAUSE OF RESULTS OF TO PRECLUDC

!!AINTENANCE Tile REACTOR R\\LFUUCTION MALFUtCTION RECURREt:CE I

0.-ll-8l CRD CRD Module 22-Leak None Faulty Valve Valve leaking at nut Replaced valve 23 Dir contr.

TR# 182627 Valve l

0-31-81 RilR 3A RilR Pump Rm.

Cooler Leaking None Vent valve nipple Cooler Leaking Silver soldered new Cooler broken nipple & rept. valve TR# 227829 D-28-81 Containmt A Analyzer 76-Broken nipple None Unknown Nipple broken off Welded nipple &

Inerting 93 analy cr analyzer TR# 280008 1-3-81 RilR 3B RilR Pump Leak None Worn Seal Seal Leaking Repl. seal & realigned pump TR# 205575 M

l-18-E l LPCI 3EN LPCI MG Set Out of Alignmt.None Bad Coupling Extrem vibration Changed coupling on

& Vibrating motor end TR# 318692 1-17-01 LPCI 3EN LPCI MG Set Noisey pillow None Bad Bearing Unknown Installed new bearings, block bearing Aligned, greased. made MC Set coupling & dialed O

o 8

EROWNS PERRY !;JCLEAR PLAllT UNIT 0, 1,2&3 INSTRU11LNT MAINTENANCE

SUMMARY

CSSC EQUIPMEttr FOR DIE MONDI OF November 19 81 NATURE EFFECT ON SAFE CAUSE ACTIOt; MKEN MTE SYSTEM CCtiPCNENT OF OPERATION OF OF RESULTS OF TO PRECLUDE MAINTENANCE

' TiiE REACTOR _

GLFUNCTION MALFUNCTION RECURRENCE nit 0 1129 64 PDIS-64-61B/D Replace None Nomal End of Lif.

Incorrect Switch None Action 11-19 84 LT-84-2A Calibrate None Instrument Drift Indicating Low None nit 1 R1-24 71 FT-71-36 Replace None Normal End of Lif Indicating Low Nonc e

11-25 76 0 R-76-43 Repair N one Dirty Slide Wire Erratic Indication Nonc 2

nit '2 11-3 92 RBM Replace

. None Faulty Relay, Rod' Block None Rl-17 71 PDIS-71-1A Replace None Instrument Drift

~ Incorrect.Setpoint Nene - -

11-17 71 PDIS-71-1B Replace None Instrument Drift Incorrect Setpoint Noae nit 3 11-11 90 RM-90-143 Replace None Faulty Relay Reactor Zone None Isolation 11-19 ;

78 LS-78-51 Calibrate None Instrument Drift False Alarm None O

+

-~

f 31 a

FIELD SERVICES SUE!ARY November 1981 The principal field services effort during this reporting period has been support of the unit 3 cycle 4 outage which is currently in progress.

Major activities accomplished thus far include:

Reactor vessel disassembly Completed fuci removal from reactor vessel Torus drain down, sandblasting and decon,tamination Removed six main steam relief valves and'tdo safety valves Performed LP "A" and HP turbine disassembly Completed LPRM changeout 4

Completed control blade replacement (17 each)

Completed bus duct cutting for generator breaker' installation

~

Started MSIV disassembly for repairs Started installation of new MSRV vacuum breakers (P0093)

Completed approximately 80% of sandblasting required on turbine components-Started torus internal modifications The major activities accomplished to date are on schedule based on the 127 day master schedule.

Other major work ef forts, independent of unit 3 outage work, have been centered around security modifications. These include:

l P0286 - Illuminate the exterior of the protected area P0487 - Provide the Wells Fargo System with tamper indication PO457 - Batteries for Wells Fargo backup l

PO423 - Intake structure infrared system P0463 - Wells Fargo Alarm System to RHRSW tunnels PO409 - Infrared detection at main gate PO406 - Provide permalert with redundancy in SAS P0'455 - Provide Rusco System with tamper indication Y

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