ML20081M417

Monthly Operating Repts for Sept 1983

ML20081M417
Person / Time
Site:	Browns Ferry
Issue date:	09/30/1983
From:	Jones G, Thom T TENNESSEE VALLEY AUTHORITY
To:	NRC
References
NUDOCS 8311170250
Download: ML20081M417 (42)

Text

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L5'2 331G11 S74 TENNESSEE VALLEY AUTHORITY DIVISION OF NUCLEAR POWER BROWNS FERRY NUCLEAR PLANT HONTHLY OPERATING RFFORT TO NRC September 1,1983 - September 30, 1983 i

DOCKET NUMBERS 50-259, 50-260, AND 50-296 1

LICENSE NUMBERS DPR-33, DPR-52, AND DPR-68 Submitted by:

')

/

Plant perintendent 8311170250 830930 ~

PDR ADOCK 05000259 R

PDR

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

3 Refueling Information....................

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

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

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

13 Unit Shutdowns and Power Reductions.

16 Plant Maintena'nce'.....

19 Field Services Summary.-............

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1 Ooerations Summary September 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 12 reportable occurrences and one revision to previous report-able occurrances reported to the hRC during the month of September.

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

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

On September 16, the r*:actcr 3ceamme'd on reactor high water level during testing of the No. 2 curb' r.e control valve.

On September 18, the reactor scrammed on turbine load reject when a relay was inadvertently bumped.

Unit t t

There were no scrams on the unit during the month.

Power was reduced to cold shutdown to investigate possible cracking in the recirculation piping.

The unit was placed in end-of-cycle 5 refueling outage using a i

controlled shutdown September 7,1983 I

f Principally prepared by B. L. Porter.

2 Ocerations Su===rv (Continued)

September 1983 Fatinue Usage Evaluation The cumulative usage ~ factors for the reactor vessel are as follows:

Location Haag,e Factor

. Unit 1 Unit 2 Unit 1 Shell at water line 0.00583 0.00473 0.00403 Feedwater nozzle 0.28294 0.20130 0.15429 Closure studs 0.22349 0.16969 0.13233 NOTE:

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

. Common System Approximately 4.89E+05 gallons of waste liquids were discharged containing approximately 1 54E-01 curies of activities.

e 3

Ooerations Sn==any (Continued)

September 1983

- Refueling Information Unit 1 Unit 1 began its fifth refueling outage on April 16, 1983 The sched-uled restart date is October 7, 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 O fuel assemblies in the reactor vessel.

The spent fuel stor-

- age pool presently contains 252 new fuel assemblies, 764 E0C-5 fuel assem-blies, 260 EOC-4 fuel assemblies; 232 E00-3 fuel assemblies; 156 E0C-2 fuel assemblies; and 168 EOC-1 fuel assemblies.

The present capacity is 3,471 locations.

ED1.t Z Unit 2 is scheduled for its fif th refueling beginning on or about June 8, j

1984 with a' scheduled restart date of November 8, 1984. This refueling outage i

will involve loading additional 8X8R (retrofit) fuel assemblies into the core, finishing the torus modification, turbine inspection, finishing inspection, l

finishing THI-2 modifications; post-accident sampling facility tie-ins, core i

spray change-out, and feedwater sparger inspection.

l.

l There are 764 fuel assemblies in the reactor vessel.

At the end of the l

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

4

.Qpgfations Su===ry (Continued)

September 1983 Unit ~4

-Unit 3 began shutdown for its fif th refueling outage on September 6, 1983, with a scheduled restart date of May 4,1984.

This refueling involves loading 8X8R (retrofit) assemblies into the core, finishing the torus modifications, post-ac,cident sampling facility tie-in, core spray change-out, finishing TMI-2 modifications, turbine inspection, and change-out of jet pump hold-down beams.

There are 699 fuel assemblies presently in the reactor vessel. There are 65 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 1097 locations.

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Sinnificant Ooerational Events Date Tima Event Unit 1 9/01 0001 End-ct-cycle 5 refuel outage continues.

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

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6 Sinnificant Ooerational Events Date Time Ever.t Unit 2 l'

9/01 0001 Reactor thermal power at 97-percent CHFLPD limited.

1140 Commenced reducing thermal power for removal of "C"

string high-pressure heating from service for maintenance ("C2" H-P heater inlet valve.)

1405 Reactor power at 95-percent for maintenance on "C2" i

l high-pressure heater inlet valve.

2157 Commenced reducing thermal power for maintanance on "C"

l control valve EHC leak.

2212 Reactor power at 85-percent for EHC leak repair on "C" control valve.

9/2 0010 EHC leak repaired on "C" control valve holding at 85-percent power for maintenance on "A" control valve EHC leak.

0142 EHC leak repaired on "A" control valve reducing for "C2*'

high-pressure heater inlet valve maintenance.

0700 Reactor power at 82-percent for "C2" high-pressure heater inlet valve maintenance.

0845 Commenced power ascension from 82-percent power.

1500 Reactor power at 94-percent limited by "C" string high-pressure heater maintenance.

2305 Commenced reducing thermal power for turbine control valve test and SI's.

9/3 0300 Reactor power at 73-percent for turbine control valve test and SI's.

l 0335 Turbine control valve test and SI's complete, commenced power ascension.

i l

1400 Reactor thermal power at 97-percent "C" string high-pressure heater maintenance limited, i

1630 Commenced reducing thermal power to place "C" string high-pressure heater in service.

1 1800 Reactor thermal power at 89-percent for placing "C"

string high-pressure heaters in service.

1840 "C" string high-pressure heater in service, commenced power ascension.

1910 Commenced PCIOMR from 93-percent thermal power.

2300 Reactor thermal power at 97-percent, CMFLPD limited.

9/4 0700 Reactor thermal power at 96-percent, CMFLPD limited.

1500 Reactor thermal power at 95-percent, CMFLPD limited.

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Sinnificant Operational Events Date Time Event Unit 2 (Continued) 9/5 0900 Commenced power ascension from 95-percent thermal power.

1500 Reactor thermal power at 97-percent, CMFLPD limited.

2300 Reactor thermal power at 96-percent, CMFLPD limited.

9/11 0115 Commenced reducing thermal power for control valve test and SI's.

0300 Reactor thermal power at 93-percont for turbine control valve test and SI's.

0410 Turbine control valve test and SI's complete, commenced power ascension.

0700 Reactor thermal power at 96-percent, CHFLPD limited.

9/16 0908 Commenced reducing thermal power for maintenance on No.

2 control valve.

0928 Reactor thermal power at 87-percent for maintenance on ~

No. 2 control valve.

0937 Reactor Scram No.142 from 87-percent thermal power while testing No. 2 control valve af ter maintenance.

~9/17 1715 Commenced rod withdrawal for startup.

1928 Reactor Critical No. 153 9/18 0005 Rolled turbine / generator.

0028 Synchronized generator, commenced power ascension.

0730 Commenced reducing thermal power from 69-percent for control rod pattern adjustment.

1200 Reactor thermal power at 65-percent for control rod pattern adjustment.

1215 Control rod pattern adjustment complete, commenced power :

ascension.

1409 Reactor Scram No.143 from 77-percent thermal power on generator load reject.

9/19 0034 Commenced rod withdrawal for startup.

0235 Reactor Critical No. 154.

0432 Rolled turbine /ganerator.

0451 Synchronized generator, commenced power ascension.

1200 Commenced PCIOMR from 77-percent thermal power. No power increase due to xenon transient.

9/20 0900 Reactor thermal power at 77-percent, rod limited.

2400 Reactor thermal power at 76-percent, rod limited.

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8 Significant Operational Events Date Time Event Unit 2 (Continued) 9/21 1500 Commenced reducing thermal power for control rod patterr.

adjustment.

1900 Reactor power at 72-percent for control rod pattern adjustment, increasing thermal power.

2230 Control rod pattern adjustment complete, commenced PCIOMR from 79-percent thermal power.

9/23 1500 Reactor thermal power at 99-percent maximum flow, rod limited.

9/24 0108 Commenced reducing thermal power for SI 4 3. A.2 (control rod exercise.)

0200 Reactor thermal power at 97-percent for SI 4.3. A.2.

0230 SI 4.3.A.2 complete, commenced ascension.

0300 Reactor thermal power at 99-percent maximum flow, rod limited.

0900 Reactor thermal power at 98-percent, maximum flow, rod limited.

2325 Commenced reducing thermal power for turbine control valve test and SI's.

2350 Reactor thermal power at 91-percent for turbine control valve test and SI's.

9/25 0020 Turbine control valve test and SI's complete, commenced power ascension.

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

9/28 1044 Reduced thermal power when "C" reactor feedwater pump tripped on loss of feedwater inverter (high reactor water level "C".)

1100 Reactor power at 61-percent due to loss of "C" RFWP.

1156 Feedwater inverter fuses replaced, high water level tril reset, "C" RFPT rolled, commenced power ascension.

1700 Reactor thermal power at 99-percent, maximum flow, rod limited.

9/29 1500 Reactor thermal power at 98-percent, maximum flow, rod limited.

9/30 2200 Commenced reducing thermal power to remove "C" reactor feedwater pump from service for maintenance, and contro:

rod pattern adjustment.

2400 Reactor thermal power at 64-percent, "C" RFWP out-of-service for maintenance, and control rod pattern adjustment.

9 l-Sinnificant Operational Events Date Time Event Unit 3 9/1 0001 Reactor thermal power at 88-percent, maximum flow, end-of-cycle 5 coastdown.

9/2 0700.

Reactor thermal power at 87-percent, maximum flow, end-of-cycle 5 coastdown.

9/5 2300 Reactor thermal power at 86-percent, maximum flow, end-of-cycle 5 coastdown.

9/6 2200 commenced reducing thermal power for a controlled shutdown to investigate for cracks in recirculation piping and end-of-cycle 5 refuel outage.

9/7 0237 Turbine off-line, reactor thermal power at 14-percent.

0630 All rods in at "00".

2130 Reactor in cold shutdown.

-9/30 2400 Inspection of recirculation piping and end-of-cycle 5 l

refuel outage continues.

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10 AVERAGE D ALLY UNIT POWER LEVEL DOCKET NO.

50-259 UNIT Browns Ferry-1 DATE 10-1-83 T. Rom COMPLETED BY TELEPHONE 205/729-0834 MONTH September DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL

. (MWe-Net I (MWe Neti I

-2 I7

-2 2

-2 I3

-3

-2 3

-2 4

-3 20

-2 3

-2

,I -2 6

-2 22 7

-2 23

-2 8

-2 24

-2

-2

-2 9

25 10

-2 26

-2 II

-3 n

-2

-2 12 -

-2

,3 13

-2'

,9

-2 14

-2 30

-2

-2 15 3

16

-2 INSTRUCTIDNS O!! this tormat.!ist the average daily unit powei lael m \\lWe Net for each day in the reportinc month. Compute to the nearest whole megawatt.

19177)

11 AVER AGE DAILY UNIT POWER LEVEL DOCKET NO. _50-260 UNIT Browns Ferry-2 DATE 30-1-81 COMPLETED BY T. Thom TELEPHONE 205/729-0834' 510 NTH-September DAY AVER AGE DAILY POWER LEVEL DAY WER AGE DAILY POWER LEVEL

.(MWe Net)

(31we. Net) l 999

-17 g7 912 316 y

33 930 m

3 t9 4

1003 800 20 1013 808 5

21 002 6

932 22 7

1007 1075 23 1005 1047 3

,4 1022 1087 9

10 993 1054 26 i

991 1064

,7 1011 1042

.l3 28 13 994 1065 29 1019 1031 g4 30 15 3

396 16 INSTRUCTIONS On this forrnat. list the average daily umt power lesel m N!We-Net for cash day in the reportine month. Compute to -

the nearest wb.le megawatt.

(9/77 )

12

^

AVER AGE DAILY UNIT POWER LEVEL DOCKET NO. 50-296 UNIT Browns Ferry-3 DATE 10-1-83 T. Thom COMPLETED BY TELEPitONE 205/729-0834 MONDi Scotember DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL

-(MWe-Net)

IMwe-Net)

I, 896-17

-9 892 2

18,

-9 892

-9 3

19 4

887 20

-10 5

899 21 848

-8 6

22 15

~9 y

23 8

-10

-8 24

-10 9

-9 25

-12

-8 10 26 II 27

-9

-10

-9 12 2S

~9' 13

_g 14

-9

-9 30

-10 I5 31

-9

. I t, INSTRUCTIONS On this fortnat. hst the average daily unit p.m er jewl in giwe yet for each da> in the reporting anonth. Compute to the nearest whole agaw.3,,,

(9/77i

13 OPERATING DATA REPORT DOCKET NO. 50-259 DATE 10-1-83 COMPLETED BY T. Thom TELEPilONE 105/729-0834 OPERATING STATUS

1. Unit Name:

Browns Ferry - 1 Notes

2. Reporting Period:

September 1983 3293

3. Licensed Thermal Power (MWt):

1152

4. Nameplate Rating (Gross MWe):

-5. Design Electrical Rating (Net MWe):

1065 6.- Maximum Dependable Capacity (Gross MWe): 1098.4

7. Maximum Dependable Capacity (Net MWe):

1065

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

N/A

9. Power Level To which Restricted If Any(Net MWe):

N/A

10. Reasons For Restrictions. If Any:

N/A This Month Yr..to-Date Cumulative

-11. Ilours in Reporting Period

.720 6,551 80,353

12. Number Of flours Reactor Was Critical 0

2,363.25 49,752.79

13. Reactor Reserve Shutdown flours 0

47.71 5,785.02 0

2,317.52

_ 48,717.64

14. Ilours Generator On-Line

15. Unit Reserve Shutdown ll'ours 0

0 0

16. Gross Thermal Energy Generated (MWH) 0 6,784,675 138,557,679

17. Gross Electrical Energy Generated (MWil) 0 2,244,900 45.645,620

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

19. Unit Service Factor 0

35.4 60.8

20. Unit Availability Factor 0

35.4 60.8

21. Unit Capacity Factor (Using MDC Net) 0 31.2 51.8

22. Unit Capacity Factor (Using DER Net) 0 31.2 51.8

23. Unit Forced Outage Rate 0

8.1 23.8

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

I

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

November 1983 l

26. Units In Test Status IPrior to Commercial Operation):

Forecast Achieved INITIA L CRITICA LITY INITIAL ELECTRICITY COMMERCIA L OPER ATION j

N/77)

L.

14 OPERATING DATA REPORT DOCKET NO. 50-260 DATE 10-1-83 COMPLETED BY T.

Thom TELEPHONE E/72'3-0834 OPERATING STATUS

1. Unit Name: Br wns Ferry - 2 Notes

2. Reporting Period:

Sentember 1983

3. Licenwd Thermal Power (MWt):

3293 1152

4. Nameplate Rating (Gross MWe):

1065

5. Design Electrical Rating (Net MWe):

6. Maximum Dependable Capacity (Gross MWe):

1098.4 1065

7. Maximum Dependable Capacity (Net MWe):

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

N/A

9. Power Level To Which Restricted,if Any (Net MWe):

N/A

10. Reasons For Restrictions,If Any:

N/A This Month Yr.-to Date Cumulative i1. Hours in Reporting Period 720 6,551 75,294

12. Number Of Hours Reactor Was Critical 673.72 4,528.29 47,821.76

'13. Reactor Reserve Shutdown Hours 46.28 148.96 13,833.78

' 14. Hours Generator On-Line _

666.45 4,403.23 46,378.68

15. Unit Reserve Shutdown Hours 0

0 0

16. Gross Thermal Energy Generated (MWH) 2.044.121 13.111.210

.133,521,057

17. Gross Electrical Energy Generated (MWH) 671.130

. 4.354.770 44.379.678

18. Net Electrical Energy Generated (MWH) 652,306 4,227,018 43,100,093

19. Unit Sersice Factor-92.6 67.3 61.6

20. Unit Asailability Factor 92.6 67.3 61.6 85.1 60.6 53./

21. Unit Capacity Factor (Using MDC Net)

22. Unit Capacity Factor (Using DER Net) 85.1 60.6 53.7

23. Unit Forced Outage Rate 7.4 5.8 25.5

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

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

26. Units In Test Status (Prior to Commercial Operation):

Forecast Achiesed INITIA L CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPER ATION (9/77)

15 OPERATING DATA REPORT DOCKET NO. 50-296 DATE 10/1/83 COMPLETED BY T. Thom TELEPHONE 205/729-0834 OPERATING STATUS

1. Unit Name:

Browns Ferry Nuclear Plant - 3 Notes

2. Reporti: 3 eriod:

September 1983 P

3. Licensed Thermal Power (MWt):

3293

4. Nameplate Rating (Gross MWe):

1152

5. Design Electrical Rating (Net MWe):

1065

6. Maimum Dependable Capacity (Gross MWe):

1098.4

7. Maximum Dependable Capacity (Net MWe):

1065

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

N/A

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

N/A

10. Reasons For Restrictions.lf Any:

N/A This Month Yr to-Date Cumulative

11. Hours in Reporting Period 720 6.551 57.719

12. Number Of Hours Reactor Was Critical 150.5 5,475.52 43,087.80

13. Reactor Reserve Shutdown Hours 0

505.98 3,878.13

14. Hours Generator On-Line 146.62 5.419.65 42.193.71

15. Unit Reserve Shutdown llours 0

0 0

16. Gross Thermal Energy Generated (MWH) 406.817 16.971.607 126,307.711

17. Gross Electrical Energy Generated (MWH) 131,320 5,557,830 41,597,620

18. Net Electrical Energy Generated (MWH) 122,014 5,394,352 40,375,256

19. Unit Service Factor 20.4 82.7 73.1

20. Unit Asailability Factor 20.4 82.7 73.1

21. Unit Capacity Factor (Using MDC Net) 15.9 77.3 65.7

22. Unit Capacity Factor IUsing DER Net) 15.9 77.3 65.7 0

9.3 16.4

23. Unit Forced Outage Rate

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

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

26. Units in Test Status lPrior to Commercial Operationi:

Fore < ast Achiesed INITIA L CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPER ATION (9/77)

UNIT SffUTIK)WNS AND POWER REDUCTIONS DOCKET NO.

50-259 UNIT NAME Browns Ferry-1 DATE 10-1-83 i

REPORT MONTH September COMPLETED BY.

T. Thom TELEPHONE 205/729-0834 "E

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s-264 9/1/83 S

720 C

4 EOC-5 Refueling outage continues i

5 1

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1 2

3 4

F: Forced Reason:

Method:

Exhibit G Instrnetions S. Scheduled A Equipment Failure (Explain)

!-Manual for Preparation of Data j

[Mlaintenance of Test 24tanual Scram.

Entry Sheets for Licensee

{

C Refueling 3 Automatic Scram.

Event Report (LER) File tNUREG-i D-Regulatory Restriction 4-Other (ikplain) 01611 L-Operator Training & License Examination

~

F-Admir istrative 5

j i

G-Operational Error iExplain)

Exhibit I Same Source (9/77)

Il-Other ( Explain )

M 4

UNIT Sl!UTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-260 UNIT NAME Browns Ferry-2 DATE ' 10-1-83 l

REPORT MONTil September COMPLETED BY T. Thom TELEPHONE 205 / 729-OR'44 f3

.5 ?

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Licensee s

L Cause & Corrective No.

Date i

3

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255 Event u7 9

Action to

$~

35:

Report :

EU 5'

Prevent Recurrence H

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269 9/16/83 F

38.85 A

3 Scrammed while testing No. 2 control valve 270 9/18/83 F

14.70 A

3 Scrammed on generat'or load reject.

271 9/28/83 F

A Derated for loss of "C" RFWP 272 9/30/83 F

A Derated for "C" RFWFout-of-service, control rod pattern adiustment i

2 3

4 F: Forced Reason:

Met %od:

Exhibit G - Inst.oetions S. Scheduled A Equipment Failure (Explain) 1 Manual for Preparation ol Data

[14taintenance of Test 24fanual Scram.

Entt3 Sheets for 1.ieensee C Refueling 3 Automatic Scram.

Event Report II.l:R) File (NilRI:G-D Regulatory Restriction 4-Other ( Explain) 0161) 1: Operator Training & License Examination F-Administrative 5

t G-Operational E ror (Explain)

Exhibit I - Same Source (9/77)

Il-Other ( Explain)

UNIT SilUTDOWNS AND POWER REDUCTIONS DOCKET NO. _50-296 UNIT NAME _ Browns Ferry-3

.DATE 10-1-83 REPORT MONTil September COMPLETED BY T. Thom TELEPHONE 3'5/729-0834 l

i-n.

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2.3 d Licensee 5"o

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Cause & Corrective

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Action to

$E j di g Report e rN 0 0

Prevent Recurrence 6

I 140 9/6/83 S

573.38 C

4 Controlled shutdown for EOC-5 refuelin g

outage E'

I 2

3 4

F: Forced Reason:

Method:

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

Entry Sheets for Licensee C-Refueling 3 Automatic Scram.

Event Repori t LER) File (NUREG-D-Regulatory Restriction 4-Ot her ( Explain )

0161) 1:-Operator Tr.iining & License Examination F-Administ rative 5

G-Operational 1:i ros i Explaia i Exhibit I - Same Source s

(9/77)

Il-Other (Expbin)

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BF EMSlt 30 CSSC EQUIPMENT ELECTRICAL MAINTENANCE SD MARY A Pendix B P

9/29/82 For the Month of September 19 83 Effect on Safe Action Taken Nature of Operation of Cause of Results of To Preclude.

~

7tc System Comnonent Maintenance The Reactor Malfunction Malfunction Recurrence

!8/7/83 Diesel No voltage Repair or re-None j

Burned coil Coil would not pick up Replaced no voltage Generator relay diesel place no voltago

,g relay.

relay.

geaerator "D" relay that would

' F-Annunciation not pick up.

MR #A-143033 Panel.

/

8/10/8 Air con-Control bqy Chiller tripping None Compressor vpnes Chiller tripping on Adjusted compressor ditioning chiller "B" on low gas, out of calibration low gas.

vanes and worked O.

(cooling 6 trouble shoot &

heating) repair MR #A-147591 i

S/11/8: Neutron Short range Penetration None.

Part missing Caused penetration Replaced penetration i

Monitoring monitor inside shows high re-causing connector to show high resistance connector, drywell perie-sistance which to be loose, and which degrades short 5

tration degrades short not allowing pin range monitor opera-MR #A-202735 range monitor to make contact.

tion.

operation.

I 2

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.n..u puuuuun BF EMSIL 30 CSSC EQUIPMENT ELECTRICAL MAINTENANCE

SUMMARY

Appendix.B k

9/29/82 For the Month of September 19 83 Effect on Safe Action Taken i

Nature of Operation of Cause of Results of To Prcclude j

tre System Component Maintenance The Reactor Malfunction Malfunction Recurrence

/20/83 liigh Fire strainer Fire strainer None Bad limit Fire strainer "B" Replaced bad l

pressure "B"

intake "B" revolves-switch on fire revolves 360' and limit switch on fire pro-structure completely strainer "B".

does not alternate.

fire strainer "B".

tection around & does not alternate.

MR #A-138352 i

/29/83 Unit Unit preferred Replace bearing None Bad bearings.

M.G. was inoperable Change bearings, preferred M.G. set on D.C. motor brushes, and motor 120 v.A.C. control bay IC on unit pre-drive belt, ferred M.G. set MR #A-212076

'29/8 3 Unit Unit preferred Replace bearing None Bad bearings.

M.G. was inoperable.

Replaced bearings, preferred M.G. set on A.C. motor 120 v.D.C' control bay'IC n unit pre-u i

ferred M.G. set MR #A-212074 o

t l

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............n a h uct.t.ax t't.aa 4 vo..-

br r.riS1L 30 Appendix B 6

CSSC EQUIPMENT ELECTRICAL MAINTENANCE

SUMMARY

9/29/82 For the Month of September 19 83 Effect on Safe Action Taken Nature of Operation of Cause of Results of To Preclude

!Drte System Component Maintenance The Reactor Malfunction Malfunction Recurrence

8/31/83 Unit pre-480 v shutdown Investigate None Defective Lockout relay Trip coil replaced ferred BD 1A.

lockout relay material caused inoperable.

and back switch 120 v.D.C.

Lockout relay, inoperability by old age.

mechanism repaired.

i emergency breaker MR #A-212180 MR'#A-212067 i

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4 i

5 3'

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nav o. rum......

..mo common BF EMSIL 30 Ppendix B CSSC EQUIPMENT ELECTRICAL MAINTENANCE SQ! MARY 9/29/82-For the Month of September 19 83 Effect on Safe Action Taken Nature of Operation of-Cause of Results of-To Preclude bte System Component Maintenance The Reactor Malfunction Malfunction Recurrence 9/2/83 Radiation 0-CAM-90-128 Cam inoperable.

None.

Broken fan belt.

Cam inoperable.

Replaced broken belt monitoring anc! CAM put back in service.

MR #A-137412 9/1/83 480v 480 v reactor Test trip None.

Lack of lubri-Test trip switch on Lubricated switch reactor MOV board switch on feeder cation.

breaker did not with LPS-1. Switch MOV board IE.

breaker to MG operate properly operated freely.

set LEA was MR #A-138733 ri f unctienin;;_

9/7/83 Primary Refuel zone Damper would' Nons.

Weak return spring Damper was inoperable. Replaced damper contain-supply fan not close and and cyclic motor.

w

ment, damper IB 6.lA spring return fatigue.

MR #A-212072 air intake would not work.

MR #A-212168 structure.

t a

1

BR0p*NS FERRY NUCLEAR PLANT UNIT 1 and common Page 3

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-CSSC EQUIPMENT ELECTRICAL MAINTENANCE

SUMMARY

9/29/82 For L the Month "of September 19 83 Effect on Safe Action Taken Nature of Operation of Cause of; Results'of "To Preclude Drte System Component Maintenance-The Reactor Malfunction Malfunction Recurrence 3/22/83 Radiation Intermediate Intermediate None Missing parts of.

Intermediate range Replaced connector.

monitorins. range monitor range monitor connector.

monitor D inoperable. MR #A-202774

~

D.

D has open con-nector at de-

~

tector.

3/26/8:l Radiation HEA relay Replace HEA None HEA relay burned HEA relay 5A-K12C Replaced HFA relay monitoring, 5A-K12C relay 5A-K12C.

up.

inoperable.

5A-K12C.

auxiliary MR #A-205067 instrument room panel 9-15.

GE model

[j

1. 12HFA51A49F

)/23/83 Reactor Relay 5A-K14D During perfor-None Auxiliary con-5A-K14D inoperable.

Replaced auxiliary protector panci 9-17 mance of EMI-44 tacts found contacts on relay auxiliary relay 5A-K14D broken.

5A-K14D._ Relay instrument contacts were operated properly.

i room.

found broken.

MR #A-212183 I

s t

i

BhobNS Fkam t s wwum ruol UNIT 1 and ' common BFbMkIL30 f.,

CSSC EQUIPMENT ELECTRICAL MAINTENANCE SU!DtARY Appendix B 9/29/82 For the Month of September 19 83 I

l.

Effect on Safe t

Action Taken Nature of Operation of Cause of Results of To Preclude to System Component Maintenance The Reactor Malfunction Malfunction Recurrence

.j;

'16/8 3 Residual RHRSW Pump D3 Replace amp None Defective pen.

Meter inoperable.

Replaced pen.

!I b

heat re-meter indicatin g moval MR #A-137345 h

pen.

sarvice

{

water.

21/8 3 Residual FCV-74-61 No position None Loose connection No position indica-Loose connection l

I heat indication on found in lamp tion on FCV-74-61 tightened in removal FCV-74-61 circuit.

located on panel 9-3.

lamp circuit.

I g

located on

}R #A-137393 panel 9-3.

22/8 3 Neutron Intermediate Check to see None.

Unclean con-Monitor malfunctioned, Disassembled con-monitoring range moni. tor if IRM C has nector.

open inside nector and cleaned.

penetration.

Intermediate range monitorCoperated{

properly.

l MR #A-202775 Z

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.._......an rLAaA LaAA be r.ets AL JO Apptndix B-CSSC EOUIPMENT ELECTRICAL HAINTENANCE

SUMMARY

9/29/82 For the Month of September 19 83 Effect on Safe Action Taken Nature of Operation of Cause of Results of To Preclude ate System Component Maintenance The Reactor Malfunction Malfunction Recurrence

'/5/83 control SCRAM reset Reset switch None Broken spring in Reset switch does not Defective switch rod drive switch panel will not spring return to normal re, set when released.

operator mechanism 9-5 back to mid-position.

replaced.

position when MR #A-154395 released.

'/1/83 Radiation 2-RM-90-251 Check for pos-None Shorted power Cam was inoperable.

Replaced power monitoring sible blown cord due to heat cord.

fuse, and age.

MR #A-137678 U

i

'/12/8 5 Fire Smoke / heat de-During perfor-None. A fire An inoperable The relay would have The relay was re-Protection tector panel mance of watch was es-Potter-Brumfield prevented automatic placed. SI4.ll.C.3&L l-25-311 S.I.4.ll.C.3&4 tablished while relay.

initiation of fixed was successfully on reactor bldg,the zone was spray zone 1E.

completed on 8/13/83 el. 593 fixed out of service.

and further test was c

spray zone lE, completed 9/12/83.

an inoperable SI revision and heat detector additional training' i

relay was dis-will be completed

covered, by 11/1/83.

LER #

BFRO-50-259/83052 MR #A-212108 MR #A-141037 t

l 1

BROWNS FERRY NUCLEAR PLANT UNIT 2

BF EMSIL 30 Appendix B CSSC EQUIPMENT ELECTRICAL MAINTENANCE S120!ARY 9/29/82 For the Month of September 19 83 Effect on Safe Action Taken Nature of Operation of Cause of Results of To Preclude sto System Component Maintenance The Reactor Malfunction Malfunction Recurrence 9/21/ 33 Residual RHR pump 2C During normal None. The re-The overload rela) RHR pump 2C cooler Far. was removed heat room cooler operation, while dundant residual GE model was inoperable for frcim service and removal fan. 480v performing heat removal CR 124CO28 14.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.

overload heaters reactor MOV SI 4.2.B-57 system loop and tripped.

GE model board ?A it was fodnd room cooler were CR 123C7.78A and compartment that the RHR

operable, overload relays 14A pump 2C cooler were replaced.

fan would not Motor current was operate.

verified to be ac-ceptabic. This is considered a random failure and no re-

^

currence control required.~

y LER #260/83056 *

'1 MR #A-212116 A-142900 A-130651 0

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CSSC EQUIPMENT ELECTRICAL MAINTENANCE

SUMMARY

App;ndix B

.'. l' 9/29/82 For the Month of September 19 83

,.k I

Effcct on Safe Action Taken Nature of Operation of Cause of Results of To Preclude ice Systen C c.nonent Ma in tenance The Reactor Malfunction Malfunction Recurrence d

j.

./15/83 Radiation 2-RM-90-251 Cam air pump None Bad fuse Cam inoperable Installed fuse -

[

monitoring inoperable."

measured current

~

at 7.5A and with

n 1

belt off motor current measured d

at 7.5A.

MR #A-141151 to mechanical & A-141133 to IM to functional 1

test.

jj.

MR #A-142856 h

.' 1 d

t/26/8 3 RB Heatine, Relay 16A-K6B Replace burned Non~e Relay 16A-K6B Relay 16A-K6B Replaced r.elay. N

[^

& ventila- (raw isolat. ion up. relay burned up, inoperable.

f, tion logic). Panel 16A-K6B.

,1 9-17 auxiliary

_g instrument room l

j h.

GE model

1. 12HFA51A49F lli-c J

l'27/8 3 Diesel "B" diesel While checking None.

Bad transformer.

Diesel not operating Replaced transforme r.

generator oil on diesel properly.

MR #A-142983 "B" bad control MR #A-142984 transformer discovered.

': 28/83 CO2 stor-Panel 9-25 Investigate None Defective Invalid smoke de-Replaced smoke de-age fire smoke detector smoke alarm smoke detector, tector alarm, detector. There is protection

detector, and purg-only 1 detector on this alarm and no i

ing system other alarms are affected.

MR #A-142971 i

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BRGk'NS. FERRY NUCLt.AR PLANT UNIT 3

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BF EMSIL 30 Appendix B CSSC EQUIPMENT ELECTRICAL MAIhTENANCE S12! MARY 9/29/82 For the Month of September 19 83 Effect on Safe Action Taken Nature of Operation of Cause of Results of To Preclude.

frte System Component Maintenance The Reactor Malfunction Malfunction Recurrence

9/1/8 1 CO2 Stor-Penel 3-25-305 Replace batter)

None Battery post on Battery inoperable.

Replaced battery.

age fire diesel genera-on cell 1 loose.

MR #A-141495 protectior tor unit 3

& purging system.

9/9/8 1 Residual FCV 3-74-4 7 Find reason for None Opened coil on Valve was in isolatio1. Replaced coil on 4

valve isolatior relay 16AK30.

relay 16AK30. Opera a

tions tested relay to be in good con-dition.

MR #A-137511 1

^

~9/10/H3 Radiatiori 3-RM-90-251*

Belt on pump Nora Stretched belt on Motor was not running Tighten belt as monitoring motor slipping pump motor.

smoothly.

instructed per system BF 6.1.

MR #A-130465

9/19/83 Residual Panel 9-3 Repair amp None Unit 1 meter out Current meter out on Repaired current heat control room.

Indication on of service.

unit 2 and 3.

Unit 1 meter on unite 1, 2 removal units 2 & 3, out of service

63. Unit I repaired service gauging one on completely.

on MR #A-137345.

water unit 1.

bht #A-146890 k

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I.NSTR. UME.N..T. M.A.I.N.T.E.N.A.NC,_ E.. SUM. MA..RY.

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trFECT 0:; SAFE Cr*.

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9-11 85 TR-85-7C Repair None Print Wheel Worn Loss of Reocrd None 9-28 85 Relay 3A-K55A Replace None End of Life Rod Block None out U.

9-6 92 IRME-Recorder Repair None Age Loss of Record None 9-7 18 LS-18-45A Repair None Age Alarm None 3-22 85

.RPIS-85-(26-19)

Replace None Age Loss of Indication None Display Unit-7-22 92 LPRM 32-09B Repair None Age Loss of Indication None Power Supply 1-26 90 RR-90-249 Repair None End of Life Loss of Record None e

m

.I-3,

-31 77 LIS-77-1A Replace None End of Life Loss'of Indication None.

'-14 85 PS-85-35Al Replace None Switch drift None 118 23 FI-23-42 Replace None Age None Loss of Indication,

None

-23 67 PI 67-80A Replace None Age Loss of Indication None e

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BROWNS FERRY UUCLEAR PIAWT UNIT All

}IECIIAEICAL MAINTEXANCE SU5!ARY psc EOUIPMENT For the Month of September 19 83 EFFECT ON SAFE ACTION TAKEN DATE SYSTEM COMPONENT NATURE OF OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE MAINTENANCE Tile REACTOR MALFUNCTION MALFUNCTION RECURRENCE 8-19 075 PSC Pump 3B adjusted no unknown pump was tripping on adjusted impeller impeller over current i

3-31 001 PDIS-1-36A replace or' no unknown valve leaking thru replaced plug repair block i

valve 7-28 260 Door 248 door is hangint no normal operation latch would not work repair per MMI-ll6 up 6-05 082 D/G engine clean cooler no normal operation unknown mleaned cooler cooler "D" mud in cooling water 9-09 067 Solenoid valve adjusting valvc no normal operation valve stayed opened adjusted. valve on supply (N.

8 header) to RBCCL heat exchanger 9-09 068 Relief valve on install valves no normal operation unknown installed relief recire. seal valves 1-68-555, 558 H2O 9-05 064 1B reactor zone adjusted no unknown damper stayed open electrical problem supply fan and needed adjustment 1

.-l

31 FIELD SERVICES

SUMMARY

September 1983 Maior Work Areas A.

Refuel Floor - Unit 1 fuel shuffle started on September 9 nd was com-pleted on September 25.

Several breakdowns of hoist prolonged completion.

of fuel shuffle. Other activities on the refuel floor included: shimming of HDFS racks, maintenance work, replacement of monorail section and rebuild of tools.

B.

Turbine - During September the blade installation and machining was complete on the low-ptessure (LP) "B" turbine. The LP "B" turbine was then reassembled.

During the blade repair and reassembly of the LP "B" turbine, the #1 coupling bolt hole was being bored out and new coupling bolts were fabricated.

Upon completion of the coupling bolt hole boring, the coupling process commenced.

As of this writing the #1 coupling has been made up and j

eccentricity check complete.

No. 2 and 3 coupling work is still in j

progress.

l l

The bull gear and oil pump gear that was received last month was installed I

and the assembly of the front standard was completed.

l l

l I

l l

l 32 FIELD SERVICES

SUMMARY

S6ptember 1983 B.

Turbine (Continued)

-The current projection for completion of couplings, associated covers and starting turbine oil flush is October 10.

In addition, the current schedule date for starting the crane rail modification on unit 1 is October 20.

C.

Drywell - During September, NUTECH/Gapco completed weld-out of all contracted welds; Welding Services completed six out of 10 assigned welds.

Completion of remaining welds is dependent on delivery of welding equipment.

D.

Electrical / Instrumentation - During September, work continued toward meet-ing commitments / requirements to support the unit I core reload.

The major work performed to support unit I core reload was as follows:

1.

Electrical engineering and craft supported the unit 3 preparation for the core unload, as requirement for unit 1 reload.

2.

Supported efforts to complete ECN P0126 analog trip and the electrical portion of ECN P0274 air surge backwash.

3 Started reroute of conduit 1R1674 and associated cables to panel 25-59 (RHR system PO673.)

4.

Supported the overlay weld repair work by removing and re-installing

~

constraints to welding equipment set up.

5 Completed P0590 standby control room emergency lighting modification.

/

,, _ _ _.. ~,

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33 FIELD SERVICES

SUMMARY

September 1983 D.

Electrical / Instrumentation (Continued) 6.

Concentrated on working the control room portion of PO479 emergency lighting modification.

Other Electrical / Instrumentation:

1.

P0324 Containment Wide-Range Radiation Monitors: Completed fabrica-tion of the two junction boxes that will be mounted in the d,rywell.

Completed all cable pulls outside drywell. Termination work outside drywell is in progress.

EN DES is looking at alternate methods to penetrate the drywell wall.

2.

P0322 Drywell Wide-Range Pressure Monitors, and P0323 Torus Wide-Range Level Transmitters: Completed conduit natallation and started cable pulls. The torus level transmitters were installed and a new panel installed to support installation of the drywell pressure transmitter.

The drywell pressure transmitter installation work plan was approved this month. Termination in panel 9-3 was started this month.

3 P0533 Torus Temperature Monitoring System: All conduit over the torus was installed this month and cable pulling started.

Some conduit between the 16 junction boxes around torus remains to be installed before that portion of the cable can be pulled.

s 34 FIELD SERVICES

SUMMARY

September 1983 D.

Electrical / Instrumentation (Continued) 4.

The recirculation motor-generator set holder modification was not completed this month as was projected. Material problems with Macado board delayed the modification completion. The current projectad com-pletion date 'is October 4.

E.

ALARA: The primary ALARA concerns dering September were as follows:

continuation of shielding to support the overlay weld repair, deconning on elevator 519, RHR heat exchanger room deconning, unit 3 recirculation system mirror insulation deconning, support on the unit 1 and 3_ refuel floor and general housekeeping on units 1 and 3 F.-

Planning and Scheduling: Emphasis continued to be placed on monitoring the work required to be completed prior to fuel loading on unit 1.

Some addi-tional work items were identified as prerequisites to fuel load on unit.1.

The most significant of these being the offload of fuel on unit 3 t

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35 FIELD SERVICES

SUMMARY

September 1983 i

' F.

Planning and Scheduling (Continued)

Emphasis was also placed on developing an' integrated plan to allow for an F

orderly transfer of resources from the unit 1 outage to the unit 3 outage.

without impacting the startup of unit 1.

G.

Torus: During the entire month, Williams Paint Contractor was painting the inside of ventheaders which was completed on September 28. By the middle of the month, the torus was ready for fill and af ter paperwork was cleared, filling started on September 18. External modifications continued and progress.as follows:

1.

Completed installation of torus snubbers, 2.

Replaced ECCS header shims, 3

Weld-out of.(HKII) torus tiedowns (955),

4.

Catwalk grating and bolting (60%),

i 5.

Monornil removal (50%),

l 6.

Torus vacuum breakers (20%).

Attached Piping: A total of 43 supports was completed during September, leaving one to complete of 407 Additional design information was received to rework nine main steam line supports in drywell. The H 0 system sup-22 ports were completed and 50-percent of the 79-02 work.

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4 36 FIELD SERVICES

SUMMARY

September 1983 H.

Administrative: The overtime percentage for the month of August was 23-percent with 121,699 5 straight-time hours and 37,078 overtime hours. As of August 31, 1983, year-to-date overtime percentage was 21-percent, 1,549,856.5 straight-time hours and 41,165 overtime hours. -The overall' goal of the overtime percentage is 17-percent.

4 i '

The O&M budget for August was $3,060,725 and the expenditures were $321,078 with-year-to-date budget being $30,546,240 and actual year-to-date i

-expenditures being $27,281,814. The capital budget was $3,548,626 and the expenditures were 48,148,624 with year-to-date budget being $38,745,046 and actual year-to-date expenditures being $31,562,373 Overall budget was

$6,930,429 and the overall expenditures were 48,472,233 with year-to-date budget being $69,591,286 and actual year-to-date expenditures being I

$59,314,481.

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1 4 TENNESSEE VALLEY AUTHORITY Browns Ferry Nuclear Plant P. O. Box 2000 Decatur, Alabama 35602

'OCT 111983 Nuclear Regulatory Commission Office of Management Information and Program Control Washington, DC 20555 Gentlemen:

Enclosed is the September 1983 Monthly Operating Report to NRC for Browns Ferry Nuclear Plant Units 1, 2, and 3 Very truly yours, O

TENNESSEE VALLEY.UTHORITY k-G. T.

ones Power Plant Superintendent L

Enclosures cc: Director, Region II INP0 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 Power Research Institute P. O. Box 10412 Palo Alto, CA 94304

\\

11 An Equal Opportunity Employer L