ML20079M713

Monthly Operating Repts for Dec 1983

ML20079M713
Person / Time
Site:	Browns Ferry
Issue date:	12/31/1983
From:	Swindell J, Thom T TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8401270398
Download: ML20079M713 (34)

Text

r-i TENNESSEE VALLEY AUTHORITY DIVISION OF NUCLEAR POWER BROWNS FERRY NUCLEAR PLANT HONTHLY OPERATING REPORT TO NRC December 1,1983 - December 31, 1983 DOCKET HUMBERS 50-259, 50-260, AND 296 l

LICENSE NUMBERS DPR-33, DPR-52, AND DPR-68 l~

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Submitted by:

plant Superintendent

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'8401270398 831231 DR ADOCK 05000 l

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4 TABLE OF CONTENTS 1

Operations Summary...

Refueling Information....................

3 Significant Operational Instructions..

5 i

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

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

13 Unit Shutdowns and Power Reductions.

16 Plant Maintenance.

19 28 Field Services Summary...............

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1 Ooerations Su===ry December 1983 The following summary describes the significant operation activities during the reporting period.

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

There were 10 reportable occurrences and three revisions to previous report-able occurrences reported to the NRC during the month of December.

Unit 1 The unit was in cold shutdown the entire month for the units' end-of-cycle 5 refueling outage.

Unit 2 i

There were two scrams on the unit during the month. On December 10, during i

maintenance on an offgas temperature switch, the SJAE isolated, and the reactor scrammed on loss of condenser vacuum.

On December 21, the reactor scrammed when the A2 and B2 reactor trip actuators deenergized from an undetermined cause. The main turbine was manually tripped.

Unit ~4 The unit was in cold shutdown the entire month for the unit's end-of-cycle

/

5 refueling outage.

Principally prepared by B. L. Porter.

2 Ooerations Summarv (Continued)

December 1'983 Fatinue Usane Evaluation The cumulative usage factors for the reactor vessel are as follows:

Location Usane Factor Unit 1 Unit 2 Unit 1 Shell at water line 0.00592 0.00479 0.00403 Feedwater nozzle 0.28331 0.20828 0.15429 Closure studs 0.23343 0.17103 0.13233 NOTE:

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

Common System Approximately 1.40E+06 gallons of waste liquids were discharged containing approximately 7 36E-01 curies of activities.

l i

3 Ocerations Sn===r.Y (Continued)

Decamber 1'983 Refuelina Information Unit 1 Unit 1 began its fif th refueling outage on April 16, 1983 The sched-uled restart date is December 19, 1983 This refueling will involve loading 8X8R (retrofit) fuel assemblies into the core, finishing the torus modifica-

tion, turbine inspection, finishing THI-2 modifications, post-accident sampling facility tie-ins, core spray changeout, and changeout of jet pump hold-down beams.

There are 764 fuel assemblies in the reactor vessel. The spent fuel stor-age pool presently contains 252 EOC-5 fuel assemblies, 260 EOC-4 fuel assemblies; 232 EOC-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 is scheduled for its fifth refueling beginning on or about June 8, 1984 with a scheduled restart date of November 8, 1984. This refueling outage will involve loading additional 8X8R (retrofit) fuel assemblies into the core, finishing the torus modification, turbine inspection, finishing piping inspection, finishing TMI-2 modifications; post-accide.nt sampling facility tie-

ins, core spray change-out, and feedwater sparger inspection.

There are 764 fuel assemblies in the reactor vessel.

At the end of the month there were 248 EOC-4 fuel assemblies, 353 EOC-3 -fuel assemblies, 156 E00-2 fuel assemblies, and 132 EOC-1 fuel assemblies in the spent fuel storage pool. The present available capacity of the spent fuel pool is 861 locations.

4 Ooerations Sum==ry (Continued)

December 1983 Unit i Unit 3 shutdown for its fifth refueling outage on September 7, 1983, with n scheduled restart date of May 4, 1984. This refueling involves loading 8X8B (retrofit) assemblies into the core, finishing the torus modifications, post-accident sampling facility tie-in, core spray change-out, finishing THI-2 modificat. ions, turbine inspection, piping inspections for cracks, and change-cut of jet pump hold-down beams.

There are O fuel assemblies presently in the reactor vessel.

There are 764 EOC-5 fuel assemblies, 280 EOC-4 fuel assemblies, 124 EOC-3 fuel assemblies, 144 - EOC-2 fuel assemblies, and 208 EOC-1 fuel assemblies in the spent fuel storage pool.

The present available capacity of the spent fuel pool is 398 locations.

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o-5 Significant ODerational Events Date Time Event Unit 1 12/ 01 0001 End-of-cycle 5 refuel outage continues.

12/29 1712 Commenced rod withdrawal for startup.

'1840 Reactor Critical No.189 L

12/31 0200 Increasing thermal power.

1220 Reactor water quality out-of-limits, going to cold shut down froc 11-percent thermal power.

1420 Discontinued reactor shutdown and holding reactor power at 9-percent.

2000 Reactor thermal power at 8-percent and holding for startup (water quality out-of-limits).

2400 Reactor thermal power at 7-percent and holding for starttp (water quality out-of-limits).

End-of-cycle 5 refuel outage continues.

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6 Sienificant Ocerational Events Date Time Event Unit 2 12/ 01 0001 Reactor thermal power at 100-percent, maximum flow, rod limited.

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12/02 2205 Commenced reducing thermal power for turbine control valve tests, SI's, and control rod drive (CRD) exercise.

12/03 0100 Reactor thermal power at 61-percent for turbine control valve test and SI's.

0145 Turbine control valve test and SI's complete, reducing power for CRD exercise.

0300 Reactor power at 58-percent CRD exercise in progress.

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.CRD exercise _ complete, commenced power ascension.

065c Commenced PCIOMR from 97-percent thermal power.

0800 Reactor thermal power at 100-percent, maximum flow, rod limited.

1800 Reactor thermal power at 99-percent, maximum flow, rod limited.

12/04 1500 Reactor thermal power at 100-percent, maximum flow, rod limited.

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12/10 0035 Commenced reducing thermal power for turbine control valve test, SI's, and CRD exercise.

0100 Reactor thermal power at 90-percent for turbine control valve tests, SI's and CRD exercise.

0113 Turbine control valve test and SI's complete, holding at 90-percent for CRD exercise.

0310 CRD exercise complete, commenced power ascension.

0330 Commenced PCIOMR from 95-percent thermal power.

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0825 Stopped PCIOMR at 99-percent due to problems with computer.

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0840 Reduced thermal power to 96-percent, computer problems.

1015 Commenced PCIOMR from 96-percent thermal power.

l 1600 Reactor thermal power at 100-percent, maximum flow, rod limited.

2325 Commenced reducing thermal power due. to offgas isolation.

2335 Reactor Scram No.147 frca 66-percent thermal power on l

TIS-66-22A transmitted spurious "0FF Gas Hold Up Volume Temp High" alarm and one-half SJ AE isolation signal (temperature was verified to be less than set point).

l An IM began maintenance on TIS-66-22B, which was functioning properly, causing it to transmit a false high-temperature signal, resulting in full SJAE isola-tion. Attempts to reset the switches were unsuccessful.

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The reactor scrammed on loss of condenser vacuum.

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L Sinnificant Operational Events

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Date Time Event t

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' Unit,2 (Continued) 1 12/11 0605 Commenced rod withdrawal for startup.

0900 Reactor Critical No. 158.

1410 Rolled turbine / generator.

1442 Synchronized generator, commenced power ascension.

12/12' 0145 Commenced PCIOMR from 86-percent thermal power.

0710 Stopped PCIOMR at 87-percent thermal power for GI 4 3.B.1.a (Control Rod _ Coupling Check).

0922 Completed SI 4 3.B.1.a, commenced power ascension.

0935 Commenced PCIOMR from 91-percent thermal power.

12/13 0230 Reactor thermalspower at 99-percent, maximum flow, rod

.1 limited..

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~0800 Reactor thermal power at 98-percent, maximum flow, rod limited.

1100 Reactor thermal power at 97-percent, maximum flow, rod limited.

1500 Reactor thermal power at 96-percent, maximum flow, rod limited.

4 2300-Reactor thermal power at 95-percent, maximum flow, rod limited.

1

-12/17 2340

' Commenced reducing thermal power for_ turbine control SI's,'and icontrol rod pattern adjustment.

valve test,

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Reactor tdermal po' erf at 73-percent for turbine control 12/18 0100 u

valve test,1SI's, and l control rod pattern adjustment, increasing thermal power.

0330 Reactor powe'r at 63-pe& cent, turbine control valve test and SI's complete, control rod pattern adje tment continues.

0530 Control rod pattern adjustment complete, commenced PC10MR from 83-percent thermal power.

1140 Commenced reducing thermal power from 87-percent for SI 4 3.B.1.a=(Control Rod Coupling Integrity).

1200 Reactor p0wer at 81-percent for SI 4 3.B.1.a.

1230 Completed SI 4 3.B.1.a, commenced PCIOMR, 1

12/19 1100 Reactor thermal power at 100-percent, maximum flow, rod limited.

1400

_ Reacter thermal power'at 99-percett, maximum flow, rod limited.

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8 Stanif'icant Ogrational Events Date Time Event Unit 2 (Continued) 12/20 0830 Commenced PCIOMR from 99-percent power.

1300 Reactor thermal power at 100-percent, maximun flow, rod limited.

12/21 0949 Reactor Scram No.148 from 100-percent thermal power when the A2 and B2 reactor trip actuators deenergized fr:n an undetermined cause. The main turbine was manually tripped.

1855 Commenced rod withdrawal for startup.

2130 Reactor Critical'No. 159 12/22 0412 Rolled turbine / generator.

0437 Synchronized generator, commenced power ascension.

1900 Commenced PCIOMR from 82-percent thermal power.

12/23 1335 Recirculation pump "A" tripped from 93-percent power, reducing thermal power.

2000 Reactor power at 60-percent, "A" recirculation pump out-of-service.

2300 Reactor power at 61-percent, "A" recirculation pump out-of-service, increasing power.

12/24 1100 Reactor power at 76-percent, "A" recirculation pump out-of-service for maintenance.

1140 "A" recirculation pump in service, commenced power ascension from 76-percent rower.

1430 Commenced PCIOMR from 87-percent thermal power.

12/25 0600 Reactor thermal power at 100-percent, maximum ficw, rod limited.

12/30 0700 Reactor thermal power at '99-percent, maximum flow, rod limited (100-percent electrical).

12/31 2340 Commenced reducing thermal power for turbine control valve test and SI's.

2400 Reactor thermal power at 96-percent for turbino control valve test and SI's.

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Sienifican't Oforationni Events s

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Date

- Time Event Unit 3 i

12/01 0001.

,End-of-cycle 5 refuel outage continues.

12/31-2400 End-of-cycle 5 refuel outage continues.

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10 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-259 1

UNIT DATE COMPLE1ED llY Ted Thom

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TELEPHONE December 1983 MONTH DAY AVER AGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe Neti IMWe-Net)

-10

-10 g7

-10

-9 3

,3

~

3 19 4

-11 20

-9

-12

-8 5

3:

-0

~0 6

22 7

-8 23

-8

-7 8

-10 34

-8

-11 3

10

~

~

26

-9

-8 II 27 12

-10 23

-5

~9

~1I 13 29

-8 g4 30

-10

-11 15 31 16

-9 INSTRUCTIONS On this forinat. fist the average daily unit powc leselin \\lWe Net for e.neh day in the repiniing in.inth. Coinpute to the nearest whole megawatt.

l'a '77 i i

I1 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-260 UNIT DATE _1/1/84 COMPLETED BY Ted Thom TELEPHONE 205/729-0834 MONTy December 1983 DAY AVERAGE DAILY POWER LEVEL D.\\Y AVER AGE ilAILY POWER LEVEL (MWe-NetI g y g,.3,,,

i 1085 g7 1019 2

1054 905

gg 961 1061 3

39 4

1065 20 1097 5

1088 419 6

1080 508 22 7

11n?

33 ggg 8

1058 24 822 9

1085 1115 25 to 1029 1041 3

189 g,

1077 963 1057 12 23 13 1044 1063 9

1023

,4 1075 0

1022 1074 IS 3

16 1021 I

INSTRUCTIONS On this format,hst the average dail> unit power leselin MWe. Net for each das m the reporting month. Compute t the nearest whole rnegawatt.

(9/776

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12,

AVER AGE DAILY UNIT POhER LEVEL 50-296 DOCKET NO.

UNIT DATE _1/1/84 COMPLETED BY Ted Thom 205/729-0834 TELEPflONE MONTH December 1983 DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE D.\\lLY POWER LEVEL OfWe NetI (MWe-Neil 1

-7

-6 17

-7

-6 is 3

-6 gg 4

-7 20

-6 5

-7

-6 23

-3

-6 6

~0 23

-5 8

-5

_7

-6

~

_4 9

10

-6 26

-3 ll

-8

_3 27 12

-6

~3 28

-6 13

_7 29 l

14

-6

-6 30 l

15

~6

-6 31 l

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-6 I

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l INSTRUCTIONS I

On this forinat. list the aserage dad > unis powei icsel in uwe.Nei :os eash d.i> '" 'I'# '"P""'"F 'nonth Loinpute to l

the nearest whole nwgawaii, i

19177) 1 r

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14 OPERATING DATA REPORT DOCKET NO. 50-260 DATE 1/1/E4 COMPLETED BY Ted Thom TELEPilONE 205/729-0834 OPERATING STATUS

l. Unit Name:

Bro m Fcrq - 2 Notes

2. Reporting Period:

December 1983

3. Licensed Thermal Power (MWt):

3293

4. Nameplate Rating (Gross MWe):

1152 1065

5. Design Electrical Rating (Net MWe):

6. Masimum Dependable Capacity (Gross MWe):

1098.4

7. Masimum Dependable Capacity (Net MWe):

1065

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

N/A

9. Power Lesel To Which Restricted.lf Any(Net MWe): N/A

10. Reasons For Restrictions,if Any:

N/A This Month Yr..to.Da t e Cumulatise

11. Ifours in Reporting Period 744 8,760 77,503

12. Number Of Hours Reactor Was Critical 722.9

__6,670.71

_49,964.18

13. Reactor Reserve Shutdown Hours 21.1 215.54 13,900.36

14. Hours Generator On-Line 710.08 6,517.39 48,492.84

15. Unis Rewne Shutdown flours 0

0 0

16. Gross Thermal Energy Generated (MWH) l

17. Gross Electrical Energy Generated (MWH) 741 540 6.572.380 46.597.288 2

18. Net Elcctrical Energy Generated (MWil) 721,370 6,385,528 45,258,603

19. Unit Service Factor 95.4 74.4 62.6 l

20. Unit Availability Factor 95.4 74.4 62.6

21. Unit Capacity Factor (Using MDC Net) 91.0 68.4 54.8 91.0 68.4 54.8

22. Unit Capacity Factor (Using DER Net) 4.6 5.3 24.6

23. Unit Forced Outage Rate

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

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

26. Units in Test Status (Prior to Commercial Operat:on):

Furecast Achiesed INITI A L CRillCALITY INITIAL ELECTRICITY COMMERCI AL OPER ATION (9/77J l

.. -. ~. -..

~ - - - -, -. _ -,, - -. - _ - -

15 OPERATING DATA REPORT DOCKET NO.

%0-296 DATE 1/1/84 COMPLETED BY Tod Thom TELEI'l!ONE 205/720-0834 OPERATING STATUS

1. Unit Name:

Browns Ferry -3 Notes

2. iteporting Period:

December 1983

3. Licensed Thermal Power (MWI):

3293

4. Nameplate Rating (Gross MWe):

1152

5. Design Electrical Rating (Net MWe):

1065

6. Maximum Dependable Capacity (Gross MWe): 1098.4

7. Ma.simum Dependable Capacity (Net MWe):

1065

8. If Changes Occur in Capacity Ratings tirems Number 3 Through 7 p Since I.ast Report. Give Reasons:

N/A

9. Power Lesel To Which Restricted,if Any (Net MWel: N/A

10. Reasons For Restrictions,if Any:

N/A This Month Yr..to Date Cumulative

11. Hours in Reporting Period 744 8,760

_59,928

12. Number Of Hours Reactor Was Critical 0

5,475.52 43,087.80

13. Reactor Reserve Shutdown Hours 0

505.98 3,878.13 u

3, 4 W. t> >

u,m.n

14. Hours Generator On Line

15. Unit Reserse Shardown flours 0

0 0

16. Gran Thermal Energy Generated (MWii) 0 16.971,607 126.307,711

17. Gross Electrical Energy Generated (MWH) 0 5,557,830 41,597,620 l.

18. Net Electrical Energy Generated (MWH) 0 5.394.352 J,375,256

19. Unit Service Factor 0

61.9 70.4

20. Unit Asailability Factor 0

61.9 70.4 0

57.8 63.3

21. Unit Capacity Factor (Using MDC Net)

22. Unit Capuity Factor (Using DER Net) 0 57.8 63.3

23. Unit Forced Outage Rate 0

9.3

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

16.4 i

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

26. Units in Test Status IPrior to Commercial Operationi:

Forecast Achiesed s lNITIAL CRITICALIT Y INITIAL ELECTRICITY l-COMMERCIAL OPER ATION l-1 (9/77)

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13 1

OPERATING DATA REPORT DOCKET NO. 50-259 DATE l-1-84 COSIPLETED BY Ted Thom TELEPl!ONE on5/7?o_ng54 OPERATING STATUS

1. Unit Name:

Browns Ferrv - 1 N"'"

December 1983

2. Heporting Period:

3293

3. Licenwd Thennal Power (MWtp:

1152

4. Nameplate Rating (Gross MWe):

1065

5. Design Electrical Rating (Net MWe):

6. Masimum Dependable Capacity (Gross MWel:

1098.4

7. Masimum Dependable Capacity (Net MW'):

1065 e

8.' If Changes Occur in Capacity Ratings titems Number 3 Through 7) Since Last Report. Gi'e Reasons:

N/A

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

N/A

10. Reasons For Restrictions.If Any:

N/A This Manth Yr. to-Date Cumulative

11. Hours in Reporting Period 744 8,760 82,562 l

12. Number Of Hours Reactor Was Critical 53.33 2,416.58 49,806.12 0

47.71 5,785.02

13. Reactor Reserve Shutdown Hours

- 14. Hours Generator On-Line 0

_2,317.52 48.717.64

15. Unit Reserve Shutdown flours 0

L 0

16. Grow Thermal Energy Generated (MWH)

17. Gross Electrical Energy Generated (MWHI O

2,244,900 45,645,620

18. Net Electrical Energy Generated (MWH) 0 2,175,548 44,325,327 f

19. Unit Senice Factor 0

26.5 59.0

20. Unit Availability Factor 0

26.5 59.0

21. Unit Capacity Factor (Using MDC Net) 0 23.3 50.4 0

23.3 50.4

22. Unit Capacity Factor (Using DER Net)

23. Unit Forced Outage Rate r0 8.I 23.8

24. Shutdowns Scheduled Over Nest 6 MonthsIT.spe.Date,and Duration of Each1:

i

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

26. Units in Test Status IPrior o Commercial Operationi:

Forecast Achiesed i

INITIA L CR111CA LITY f

INITIAL ELECTRICITY COMMI RCIAL OPER ATiON l

(9/77)

UNITS 11UTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-259 UNIT NAME Browns Ferrv-l DATE 1/1/84 REPORT MONTil December 1983 COMPLETED BY Ted Thom TELEPilONE 205/729-0834 l

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3 j YIi Licensee jg jw'l, Cause & Corrective e

No.

Date i

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Event

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Action to F

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Report :

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Present Recurrence O

6 264 12/1/83 S

744 C

4 End-of-cycle 5, refuel outage continues.

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4 F: Forced Reason:

Method:

Exhibit G. Instructions i

S: Scheduled A Equipment Failure (Explain) 1-Manual for Preparation of Data B. Maintenance of Test 2-Manual Saam.

Er.try Sheets for 1.ieen>ee C-Refueling 3 Automatic Scram.

Event ReparI (LERI Fife t NtiREG-D-Regulatory Restriction 4 01her (Explain) 0161i E-Operator Training & License Examination F Administrative 5

G. Operational Error (Explain t 19/77)

Il-Other (Explaird Exhibit I - Same Source j

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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKETNO. 50-265 UNITNAME Browns Ferry-2 DATE 1/1/84 REPORT MONTH December 1983 COMPLETED BY Ted Thnm TELEPHONE 205/729-0834

.! E 3

.E Licensee h

- Cat.se & Corrective No.

Date g

3?

.355 Event 77 e.8 Action to E

j@g Repors =

. iS C H

j' Prevent Recurrence d

279 12/2/83 S

B Derated for turbine CV test, SI's and CRD exercise.

280 12/10/83 F

15.12 H

3 Reactor scram on sp'rious "offgas u

holdup volume temp high" alarm and one/ half SJAE isola *. ion signal.

281 12/17/83 S

B Derated for turbine CV test, SI's and control rod pattern adjustment.

282 12/21/83 F

18.80 11 3

Reactor scram when the A2 and B2 react or trip actuators de-energized from an undetermined cause.

1 283 12/23/83 F

B Derated for "A" recirculatinn pump main _t_e_ nance.

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2 3

4 F: Forced Reason:

Method:

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

B. Maintenance of Test 2 Manual Scrarn.

Entry Sheets for Licensee C Refueling 3 Automatic Scram.

Event Report (LERIFdeiNURI:G.

i D. Regulator) Restriction 4-Other ( Expt:.in) 01611 E Operator Training & License Examination F Adndnistrative 5

G-Operational Error (Explain t Exhibit i. Same Source 19/77) llother (Explain) i

I 50-296 DOCKET NO.

UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME Browns Ferry-3 DATE' I/1/84 REPORT MONTH December 1983 COMPLETED BY Ted Thom TELEPHONE 205/729-0834 E

E 5g "h

jM Licensee

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Cause & Corrective No.

Date 5g T;

j ~$

Event g?

93 Action to f:

5

<. 5 g Report e mV E'

Prevent Recurrence H

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140 12/1/83 S

744 C

4 End-of-cycle 5, refuel outage continues.

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l 2

3 4

F: Forced Reason:

Method:

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

Entry Sheets for Licensee C-Refueling 3-Automatic Scram.

Event Report iLERI Fde (NUREG-D-Regulatory Restriction 1-Other ( Explain) ul611 E-Operator Training & License Examination F Administrative 5

G. Operational Error (Explain)

Exhibit I Same Source (9/77) 11-O her(Explain) s

__- - _. - _.~ - - - -

BROWNS. FERRY NUCLEAR PLANT UNIT-1i MECilANICAI. MAINTEMANCE

SUMMARY

CSSC EQUIPMENT For the Month of December 19 83 ACTION TAKENi EFFECT ON SAFE DATE SYSTEli-COMPONENT NATURE OF

' OPERATION OF

,-CAUSE OF RESULTS OF.

.TO PRECLUDE '

MAINTENANCE Tile REACTOR MALFUNCTION MALFUNCTION RECURED;CE 12-22 26 Fire protection Replace elbow None Normal age and Leak Cut out and-replaced 3", 90 elbow on' fir.

header-for. Diesel $

piping leaking down-use stream of U1 Generator Building D/G fire header isolation valve 12 85 Star valve Valve is broke t None Mechanical Abuse Valve in-operable-Installed new valve.

1-85-229-A on from valve stent i

ACC 22-07

$ 12 68 Valve 1-68-558 Bench test None Unknown R.V. would not seat R.V. set 1250 a

! 12-14 68 Valve 1-68-553 Bench test RsV. set 1250 None Unknown R.V. would not' seat q

12-11 74 1C RilR pump Uncouple 1C None Motor required N/A N/A'-

'D RilR pump to replacement and allow for.moto other craft b

removal. Aft,e :

support motor mainte-

r nance, recoupl

[

pump 12-18 74 1C RilR pump replace pump I n-op -1 loop of seal fail to seal Icaking excess-Replaced seal per.'

seal

. seal on 1"C" RilR respond to adjust-ively

}D!I 16-A

{

ment required by RilR pump.

Leaks badly new motor t,

when pump is running 4

I 4

6

3 BROWNS FERRY.UUCLEAR PLWT UMIT MEQlANICAL MAINTE2'ANCE

SUMMARY

CSSC EQUIPME;;T For.the Month of December 19 R1 ACTIO:3 TAKEN EFFECT 0! SAFE DAIE SYSTD1 COMPO!.~ENT MATURE OF OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE l'.AINTENANr Tile REACTOR MALFUNCTION MALFUNCTION RECURRE!:CE 12-3 82 Diesel Generat'oc Clean Coolet. In-Op Diesel Normal age and In-op diesel genera-N/A I

3C Cenerator use.

tor i

12-3 82 3D Diesel Clean Cooler In-op Diesel Normal age and In-op Diesel Genera-N/A Cenerator Generator use tor 12-3 82 3A Diesel Clean Cooler In-op Diesel Normal age and In-op Diesel Genera-N/A Cenerator Generator use tor 12-18 260 Equipment Air Repair door; None Normal age and N/A N/A Lock Door Door will not use close a

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EFFECT uN SAFE ACTION T.WhN DATE

, SYSTEM COMPONENT NATURE OF OPERATION OF CAUSE OF RESULTS OF

'IO PRECLUl:E

?!AIITENANCE TILE REACTOR MALFUNCITO.'

MALFU:!CTION REC 1:RRENCr:

12-5 67 D3 EECW Pump Adjust pump None Abnormal Flow Pump would not pump N/A-impeller clear-4500 gpm g

ance on D3 EECW Pump 12-20 23 Air Release B3 RilRSW pump None Unknown I. caking into the room N/A valve 23-590 discharge air release valve 23-590 Icaking thru O

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BROWNS FERRY NUCLEAR PLAhT t* SIT 0

ag 3 CSSC EQUIPMEST ELECTRICAL MAINTE!?ANCE SD: MARY 9/29/82 For the Month of December 19 83 Effect on Safe Action raken Nature of Operation of Cause of Results of To Preclude

&c Systen Component Maintenance The Reactor Malfunction

!!al f unc t ion Recurrence 1983 7/16 Air Condi-Emerg. Cooling Replaced motor None Burned up a motor Motor failure Replaced motor.

tioning Unit for Shut-for condenser Performed EMI 33 System (31) down Board Room MR 154200 1A

~

12/20 RilR Service RHRSW pump Change oil in None RHRSW Room Maintenance pcrformed Performed EMI64 Water motor B3 Intake lower bearing flooded as a precautionary on botton bearing !

System (23) of motor measur MR 215864 l2/30 RIIR Service C3 RHRSW Replace test None Contacts Test switch Replaced test water pump breaker switch inoperable switch (23) test switch 4KV shutdown MR216851 g

board - 3EB compartment 10 l

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BF EMSIL 20 CSSC EQUIPMENT ELECTRICAL. MAINTENANCE Sl*mtARY 9/29/82 For the Month of December 19 83 Effect on Safe Action Taken Nature of Operation of Cause of Results of To Preclude alrL Systen Connonent Maintenance The Reactor Malfunction Ma l fu: e t ien Recurrence 1983 11/30 Residual 1 FCV-74-48 Replace FCV None Bad motor bearing Motor failure Replaced motor; lleat Re-DW El. 563 motor burned motor performed EMI 18.1 moval winding

& 188.

System (74:

MR 205195 12/1 Residual 1 FCV-74-48 Replace breaker None A6E Operating toggle Replaced main Heat Re-480 RMOV Bd broke off breaker; breaker & tightened!'

moval 2A - Feeder I

breaker inoperable wiring.

System (74) breaker MR 216251 12/2 Standby ES Relay "B" Replaced ES re-None Unknown Relay failed Replaced ES relay diesel gen-diesel gen-lay on SSP 1 and on SSP 1 & SSP 2,.

crator crator SSP 2 control and performed panel EMI72.

3 MR 216252 10/27 Air con-Shutdown Board Replaced fan Mone Burne3 up motor Motor failure Replaced fan motor ditioning room supply motor and verified system (31) fan lA correct rotation.

MR 138623 11/29 Reactor 1-HCV-71-32 Replace limit None Switch damaged Valve is open but Replaced. switch, core vacuum pump switch from modifica-limit switch fails i

isolation discharge valve tions in progress to indicate open MR 208717 cooling to torus.

in area on panci 9-3 system (71) El 519 Bay 9 12/11 Residual IC RHR motor Remove and None Burned motor Motor inoperable Replaced with Heat Re-EL 519 replace motor windings rebuilt motor.

moval Col. RlU System (74)

MR 21626L l

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. 1 BROWNS FERRY NUCLEAR PLANT 1 NIT II

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.CSSC EOUIPMENT ELECTRICAL HAINTENANCE SL'MMARY 9/29/82 For the Month of Decetaber 19 83 Effect on: Safe Action Taken Nature of Operation of Cause of Results off To Preclude

j t.c Systen Component Maintenance

'The Reactor

' Malfunction

'Halfunction Recurrene.-

~

1983 12/17 CO2 Stor-Smoke detector Replaced de--

None Water. causing Continuous alarm Replaced s'moke.

I age Fire XS-39;.66 WB' tector

'short/ ground detector.~

Protection 7

and Purg-MR'208907 4

ing System (39) i 12/17 Fain Steam MSRV l-34 panel Replace SBM None.

Cycle fatigue Valve will not.indi-Replaced SBM switch' System (l) 9-3, 25-32 switch cate emergency position per EM123. Ran j

on panel'25-32 T1-73 steps 5-11.

1 MR 208910'

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i 12/19 Associated Fuse failure Replaced relay None Unknown Indication of-blown Replaced relay $

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andt verified propcE Elect.

circuit - ~~

fuse in panel 9-28 System (57) Control Bay but unable to locate-operation.

i MR 214254 12/20 Contain-Vent to SB6T Reterminate None Wire not Valve not operating MAI!13 - Reterminate ment Atmos-Valve FCV-84-20 wire from landed properly from wire.

phere Rx b1dg.El 593 16AK 34 (BD)

HS-64-35. If torus MR 216160 Dilution terminal 6 to bypass switch is used, System (84) 16 AK35(BZ) valve operates; l

terminal:6 in however, valve should panel 9-43 operate without using the bypass switch

!12/23 480V Shut-Shutdown Bd.

Replace closing None Bad coil Shutdown board 1B Closing coil ordered I

down Bds.

feeder breaker-coil inoperable and being expedited.

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MR 214257 l

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Page 3 BRO *.i:IS FERRY NUCLEAR PLANT t: NIT

-2 BF EMSIL 30 A;>pendtx S CSSC EQt'!PMENT.

ELECTRICAL mal:ITENANCE SM'MAPJ g729jg2 For the Month'of December 19 83 Effcet en Safe Action T n.en.

Nature of Operation of Cause of Results-of To Preclude.

Lt c S v.s t e n Co :ondnt Maintenance The Reactor Malfunction Malfunction Recurrence L983 3/30 Unit pre-Unit preferred Replace meter None Switch volt meter Abnormal alarm will Replaced' meter ferred' MG set-lCEL.

relay on MG set control not' clear - no reason relay.

120V AC cabinet for alarm MR 129789)'

lCO2.Storag None High sens. readiny, De'tector'does not Replaced smoke 12/1. Fire Pro g Smoke detector Replace

[XS-39-67ZN detector alarm detector.

E EI "

MR'216446 Purging System (39) l-t 12/1 CO2 Storage Smoke detector Replace detector None liigh sen. reading Detector does not Replaced smoke Fire Pro-XA 39-67YQ alarm

detector, tection &

CPD1201 MR'216447 j

Purging System (39) 12/3 Residual HCV 74-89 Replace missing,,None Someone had None Straps replaced.

j.

Heat Re-Rx bldg.EL519 straps on con-removed straps moval duit going to MR 062179 l System (74) limit switch 12/3 Residual HCV 74-90 Replace missing None Someone had None Straps replaced.

Ileat Re-Rx bldg.EL519 straps on con-removed straps FIR 062180 moval duit going to System (74) limit switch

,L2/8 CO St rage Fire Prot. Panel Replace K1 re-None Bad card Fails to reset Replaced plug in 2

Fire Pro-2-25-3 33 lay in panel type card in panel tection &

Flex Alarm 25-333.

furging Rx.bidg.E1621 MR 216439 System (39) l j

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2 BROWNS FERRY NUCLEAR PLANT CitT CSSC EQUIPMENT ELECTRICAL MAINTENANCE SC MARY 9/29/82 For the Month of December 19 83 Etfect on Safe Ae t ion T.G en

_ Nature of Operation'of Cause of Restilts of Ta Preclude in t e Systen Component Maintenance The Reactor Malfunction Malfunction Recurrence 1983 12/13 Sequential Sequential Even : Repair or None Bad cord Points 133 & 134 did Installed card.

Event Recorder replace cord not print when 1/2 g

Recorder scram was given on MR 204421 g

scram volume discharge i

S1 12/23 Reactor Recire pump 2A Splice cable None Bad cable Unit placed in 24 hr.

Spliced cabic.

Water Re-LCO MR 215595 circulatior System (68)

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12/26 RB IIcating Z1-64-124.

Replace relay None Material defect Not a valid Changed R3B relay.

& Ventila-Refuel zone is lation present g

R3B tion isolation MR 215611 os System (64) g c.

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U-1 12/9 3

LT-3-53 Replace None Age Loss of Indication None

'12/9i3 LT-3-60 Replace None Age Loss'of Indication None 12/18 71 FT-71-1A Replace None Age Loss of Indication None 11/20 23 FT-23-36 Replace None Age g

Loss of Indication None e

11/28.90 RE-90-266 Replace None Age Loss of Indication None 12/21 3 LI-3-58B Replace None Age Loss of Indication None 1

U-2.

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12/16 23 FT-23-42 Repair

None Zero Shift on.

Faulty Indication None l

w Transmitter l,

i12/1$1 TR-p-l. -

Repair None jAge Loss of Record None I12/2$77

, LIS-77-14A/B Repair None jAge Alarm iNone i

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12/20 90

[ RM-90-250 Repair None

! Dirty Connector l Loss of Record

'None

!!2/221

, PDIS-1-13B Repair None Age Faulty Indication None i

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12/19 90 RR-90-249 Repair lNone Age Loss of Record None 1

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s 28 FIELD SERVICES SUle!ARY December 1983 Work Synoosis The unit 1 cycle 5 outage ended January 1,1984, for an actual outage duration of 262 days.

The principle work performed during the December rcport period involved completion of reactor pressure vessel (RPV) assembly and hydro plus necessary completion of work items to support startup. Unit 3 work continued on torus modification, turbine floor effort, and control rod drive changeout.

Maior Work Areas A.

Refuel Floor - Tensioning of RPV head began on December 2,1983 at 0820 hours0.00949 days <br />0.228 hours <br />0.00136 weeks <br />3.1201e-4 months <br /> and was completed on December 3 at 1330 hours0.0154 days <br />0.369 hours <br />0.0022 weeks <br />5.06065e-4 months <br /> in preparation for completion of unit 1 refueling outage.

Preparations for RPV hydro were completed at 0915 hours0.0106 days <br />0.254 hours <br />0.00151 weeks <br />3.481575e-4 months <br /> on December 4, 1983 B.

Turbine - The unit 3 "c" low-pressure turbine inspection and repair con-tinued during December. The work on the dovetail pin replacement was The rotor completed along with the installation of the 13th stage blades.

was reset and the lower diaphragms were installed. The tightening of the joint bolts on the inner cylinder and the installation of the heat shields were completed.

The unit 3 feed pump turbine "A" rotor was sandblasted.

Some of the blades were changed out and sent to the Service Shop for balancing. They are currently still in the shop.

29 i

FIELD SERVI.CES

SUMMARY

4 December 1983 Maior Work Areas (Continued)

C.

Other Mechanical Work -

The month of December was spent completing work required for the startup of unit 1.

Some of this work is summarized below:

1.

Bilux weld inspection work in the drywell was completed by ISI on December 4.

2.

L1970 emergency equipment cooling water (EECW) piping replacement (affecting Loop I) work was completed on December 18.

3 Work on the air surge backwash modification was completed during December.

4.

P0650 redundant air system was worked through the month and completed on December 27 5

PO462 local leak rate test (LLRT) completed on the personnel airlock (strongback installed).

6.

Repair work was completed on December 28 for the 1C2 waterbox expansion joint.

7 LLRT was performed on 64-series and 76-series valves during the month.

Some repairs were required and were completed by the end of the month.

i 8.

Repair of valve 74-48 was completed on December 1.

This had impaired shutdown cooling and RPV heatup control.

9 Drywell-to-torus leak rate testing was completed on December 26 at 1000. TI SOA test was run and completed on December 27 at 2345 hours0.0271 days <br />0.651 hours <br />0.00388 weeks <br />8.922725e-4 months <br />.

30 1

FIELD SERVICES

SUMMARY

December, 1983 Maior Work Areas (Continued)

C.

Other Mechanical work (Continued) 10.

A gasket was replaced on the "B" residual heat removal heat exchanger bottom bowl on December 23 11.

On December 29, unit 1 went critical at 1840 hours0.0213 days <br />0.511 hours <br />0.00304 weeks <br />7.0012e-4 months <br />.

12.

Breaker was closed on unit 1 on January 2,1984 at 0745 hours0.00862 days <br />0.207 hours <br />0.00123 weeks <br />2.834725e-4 months <br />.

Other Mechanical work for unit 3 -

1.

Ultrasonic testing (UT) of the pipe welds in the drywell continued during December.

175 were inspected with one being rejected.

Presently waiting on the nozzle flush to complete the UT.

Work is continuing.

2.

The condensers were opened on December 5 3

Control rod drive (CRD) uncoupling was begun on December 9 By December 30, 57 of the 63 CRD's had been changed out.

4.

Reactor water cleanup (RWCU) supports were sandblasted.

L Electrical / Instrumentation - The majority of time was spent resolving l

D.

i problems for the startup of unit 1.

The work performed is as follows:

1.

P0323 - Work was completed on December 20.

2.

P0324 - Supplement existing containment radiation monitors. Completed on December 20.

3 The problems with handcranking on the TIPS was resolved on December 12 l

and the limits were set.

The wattage testing was then completed on 1

December 19 l

l

31 FIELD SERVICES

SUMMARY

December 1983 D.

Electrical / Instrumentation (Continued) 4.

The 1C RHR pump motor was set in place on December 15 with all conduit and wiring completed.

5.

The SI was run and completed on the instrument for P0126. This modification was completed on December 22, 6.

The diesel generator load acceptance test was completed on December 22.

7 Valve 74-66 was released to operations af ter EMI-18 was completed on December 10.

Tag-out of this valve put unit 2 in a 10-day Limiting Condition of Operation which had started on December 6.

8.

Cable tray seismic restraint problems (CAR 83-70) was completed on December 20.

The resolution by EN DES of CAR 83-70 had made this a requirement for startup of unit 1.

Other Electrical / Instrumentation:

1.

Unit 3 motor-generator set maintenance was delayed due to the lack-of machinist manpower as a result of emphasis to complete i

unit 1 cycle 5 refueling outage.

E.

ALARA: Provided continuous health physics (HP) coverage for unit 1 RPV j

hydro.

Supported the deconning on unit 1 A and C feedwater heater rooms and unit 3 RWCU pump room.

Provided HP coverage for the CRD changeout for

[

unit 3 and rebuild room.

Supported shielding of unit 3 CRD headers and j

unit 3 RHR lines.

Supported the work of removal of core spray spargers (not part of unit 1 cycle 5 or unit 3 cycle 5 work).

I

32 FIELD SERVICES

SUMMARY

December 1983 F.

Planning and Scheduling: Emphasis continued to be placed on monitoring unit 1 activities that were required to be completed for startup.

.The ' engineering and planning efforts that have been put forth on unit 1 in recent weeks have negated any meaningful preparation of work plans and scheduling information for the unit 3 cycle 5 outage. This will impact-

- start of work on several modifications (not torus).

G.

Torus: Work on -unit 3 continued in December and was as follows:

1.

Torus vent header - Main steam relier valve 70 ells and supports were completed on December 6.

2.

Attached piping and prefabrication work continued _ in December. Four of the nine ECCS reinforcing collars have been completed. This work t

is to continue.

3 Internal' torus modifications continued during the month. Tie bars are I

complete in five bays. The X-Y-Z gussets are 50-percent complete.

The high pressure coolant injection (HPCI) modification is 45-percent complete. The 18" RHR modification in bay 13 is 70-percent complete.

l.

No manpower is.available for outside torus modifications until internal modifications are completed in eight bays.

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33-FIELD SERVICES

SUMMARY

December 1983 H.

Administrative: The overtime percentage for the month of November was 19-percent with 141,258 straight-time hours and 33,618 overtime hours. As of November 31, 1983, year-to-date overtime percentage 23-percent with 293,863 straight time hours and 87,909 5 overtime hours. The overall goal of the overtime percentage is 19-percent.

The O&M budget for November was $2,580,940 and the expenditures were

$2,216,046 with year-to-date budget being $4,967,010 and actual year-to-date expenditures being $6,109,926. The capital budget was $2,584,600 and the expenditures were $2,128,321 with year-to-date budget being $5,113,100 and actual year-to-date expenditures being $4,191,877 Overall budget was

$5,165,540 and the overall expenditures were $4,344,367 with year-to-date budget being $10,080,110 and actual year-to-date expenditures being

$10,301,803

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TENNESSEE VALLEY AUTHORITY Browns Ferry Nuclear Plant P. O. Box 2000 Decatur, Alabama 35602 JAN 101984 Nuclear Regulatory Commission Office of Management Information and Program Control Washington, DC 20555 Gentlemen:

Enclosed is the December 1983 Honthly Operating Report to NRC for Browns Ferry Nuclear Plant Units 1, 2, and 3 Very truly yours, TENNESSEE VALLEY AUTHORITY 4Mt E

[G. T. Jones Power Plant Superintendent 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 Commission Washington, D. C.

20555 (10 copies)

Mr. A. Rubio, Director Electric Powe.r Research Institute P. O. Box 10412 Palo Alto, CA 94304 d

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