ML20070R046

Monthly Operating Repts for Nov 1982

ML20070R046
Person / Time
Site:	Browns Ferry
Issue date:	12/01/1982
From:	Throm T TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20070R011	List: ML20070R008 ML20070R046
References
NUDOCS 8301270258
Download: ML20070R046 (39)

Text

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TENNESSEE VALLEY AUTHORITY ,

DIVISION OF NUCLEAR POWER BROWNS FERRY NUCLEAR ItANT MONELY OPERATING REPORT l'ovember 1,1982 - November 30, 1982 DOCKET NUMBERS 50-259, 50-260, AND 50-296 s

'i LICENSE NUMBERS DPR-33, DPR-E2, AND DPR-68 1

w l D1 Submitted by: M i Plant Superintendent l

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l 8301270258 821208 T'

PDR ADOCK 05000259 i

R PDR

TABLE OF CONTENTS

. Operations So inary. . . . ... . . . . . . . . . . . . . . . . 1*

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

- Significant Operational Instructions. . . . .. . . . . . . .. 5 Averge Daily Unit Power Level . . . . . . . . . . . . . ... . 11

. Operating Data Reports. . . . .-. . . . . . . . . . . , . . 14 Unit ShutdowaJ and Power Reductions . . . . . . . . . . . . . 17

Plant Maintenance . . . . . . . . . . . . . . . . . . . . . . 20 Field Services Summary. . . . . . . . . . . . . . ... . . . . 31 4

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l' Ooerations Si===ry November 1982 The following stamary describes the significant operation activi, ties during the reporting period. In support of this stamary, a chrcnological log of significant events is included in this report.

, here were 21 reportable occurrences and two revisions to previous reportable occurrences reported to the NRC during the month of November.

Unit 1 here was one scram on the unit during the month. On November 3, the reactor scrammed when the. main turbine tripped due to a power. supply failt.re on' the turbine supervisory instrtmentation. This gave a false indication of high vibration on the main and reactor feed pump- turbines.

Unit 2 The unit was in its EOC-4 refueling outage the entire month.

Unit ~4 here was no scrams on the unit during the month. ,

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l Principally prepared by B. R. McPherson.

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Operations Si-nary (Continued)

November 1982 o .

Fatigue Usage Evaluation

. The etznulative usage factors for the reactor vessel are as follows:

Location Usage Factor Unit 1 _ Unit 2 Unit ~4 Shell at water _line 0.00561 0.00448 0.00388 Feedwater nozzle 0.27410 0.19544 0.14701 Closure studs 0.21621 0.15641 0.12638

' NOTE: This acetraulated monthly information satisfies Technical

{

Specification Section 6.6.A.17.B(3) reporting requirements.

Cr=non Svates Approximately 6.13E45 gallons of waste liquids were discharged containing approximately 1,09E+00 curies of activities.

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Ooerations Si-aarv (Continued) .

~ November 1982

.Hgfueling Information Unit 1 Unit 1 is scheduled for its fifth refueling beginning on or about March 18, 1983 with.a scheduled restart date of Jul; 18, 1983. This refueling will' involve loading 8 X 8 R (retrofit) fuel assemblies into the core; finishing the torus modification; turbine inspection; finishing TMI-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 storage pool presently contains 52 new fuel assemblies; 260 E00-4 fuel.

assemblies; 232 EOC-3 fuel. assemblies; 156 EOC-2 fuel assemblies; and 168 EOC-1 fuel assemblies. The present capacity is 1,148 locations.

Modification work and testing are in progress to increase the spent fuel pool capacity to 3,471 assemblies.

j. ,7 Unit 2

='-. Unit 2 began its fourth refueling on July 30, 1982 with a scheduled restart date of January 25, 1983. This refueling outage will involve completing relief valve modifications; torus modifications; "A" low-pressure turbine inspection; generator inspection; MG net installation for LPCI modification; loading additional 8 X 8 R fuel assemblies into the core; TMI-2 modifications; post-accident sampling facility tie-ins; and changeout of jet pinp hold-down beams.

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Ooerations Si- wry (Continued)

November 1982 Refueling Information

• Unit 2 (Continued) here are no fuel essemblies in the reactor vessel. At the end of the month there were 248 new fuel assemblies; 764 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 pool. Be present available capacity of the spent fuel pool is 97 locations.

Unit ~4 Unit 3 is scheduled for its fifth refueling on or about Octcber 1, t 1983, with a scheduled restart date of January 31, 1984. nis refueling will involve loading 8 X 8 R (retrofit) assemblies into the core; finishing the. torus modifications; post-accident sampling facility tie-in; core spray changeout; finishing THI-2 modifications; turbine inspection; and changeout of jet pump hold-down beams.

D ere are 764 fuel assemblies presently in the reactor vessel. Bere

- are 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 993 locatiens.

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5 Significant Operational Event Unit 1 Date Time Event 11/01/82 '0001.

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

.11/03/82 0010 Reactor Scram No. 161 from 995 thermal powei due to false high turbine vibration and main steam line isolation on low pressure. 1his was caused by failure of the 15-volt power supply to the turbine supervisory instrumentation. Unit remains offline for maintenance and repairs. Items include: changeout of spare 500-kV transformer to 1B transfonmer, replace HEPA filters on primary containment purge assembly, replace connectors on "A" and "B" IRM's and replace coil on "B" IRM

-drive light.

1530 Change out of spare 500-kV transformer to 1B

-a . transformer completed.

1830 Primary containment purge system failed flow test (SI.4 7.F-5) HEPA filters dirty.

11/04/82 0700_ Started replacing connectors on "A" and "B" IRM's.

1530 Replacement of connectors on "A" and "B" IRM's complete.

2230 HEPA filter replacement complete and SI 4.7.F-1, 2, and 5, (Pressure Drop, DOP, and Flow Test) performed on primary containment purge system.

Holding for SI 4.7.F-3 (Freon Test on Charcoal i Filters).

11/05/82 0015 Started replacement of coil on "B" IRM drive 7 light.

0200 Coil replacement on "B" IRM drive light complete, holding for SI 4.7.F-3 (Freon Test) on primary containment purge system.

1130 SI 4.7.F-3 complete, holding due to problems with computer.

1935 Cannenced rod withdrawal for startup.

2125 Reactor Critical No. 180, holding dce to maintenance on EHC logic.

11/07/82 1003 Maintenance complete on EHC logic, commenced rod withdrawal for startup.

1130 Rolling main turbine.

1136 Stopped rolling main turbine, EHC system problems.

1200 Rolled T/G.

1255 Synchronizd generator, commenced power ascension.

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Significant Doerational Event Unit 1 Date Time Event 11/08/82_ 0340 Commenced PCIOMR from 79% thermal power (sequence "B").

11/09/82 0800 Reactor thermal power at 995, maximum _ flow, rod 1 limited.

11/13/82 0120 Connenced reducing thermal power for turbine control valve tests and SI's.

0300 Reactor thermal power at 975 for turbine control valve test and SI's.

0330 Turbine control valve tests and SI's completed, commenced power ascension.

0400 Reactor thermal power at 995, maximin flow, rod limited.

11/19/82 2200 Commenced reducing thermal power for control rod pattern adjustment and turbine control valve test and SI's.

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11/20/82 0100 Rcactor thermal power at 74% for control rod pattern adjustment and turbine control valve test and SI's.

11/20/82 0330- Control rod pattern adfustment, turbine control valve test and SI's canplete, commenced power ascension.

,g 0700 Commenced PCIOMR from 79% thermal power (sequence l- "B").

- 11/21/82 1330 Reactor thermal power at 995, maximum flow, rod l- limited.

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l' ~11/27/82 2230 Commenced reducing thermal power for turbine l, control valve tests and SI's.

l_, 2240 Reactor therma power at 91% for turbine control i valve tests and SI's.

2249 Turbine control valve tests and SI's complete, commenced reducing thermal power for control rod

pattern adjustment.

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Sinnificant Ooerational Event Unit 1 nate Tine Event 11/28/82 2100 Reactor; thermal power at 74% for control rod pattern adjustment. .

- 0130- control rod pattern adjustment complete, commenced PCIOMR (sequence "B").

11/29/82 0415 Reactor thennal power at 995, maximta now, rod limited.

11/30/82 2400 Reactor thermal power at 99%, maximta now, rod 4 - limited.

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Sinnificant Operational Event

1. dnit 2 Date Time Event I

11/01/82 .0001 ECC-4 refuel outage continues.

11/30/82 2400 EOC-4 refuel' outage continues.

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9 Sinnificant Ooerational Event Unit 3 Dat.e Time Event 11/01/82 0001 Reactor thermal power at 995, maximta flow, rod limited.

11/06/82 .0150 Comenced reducing thermal power for recirculation ptaps MG set brush replacement.

0400 Reactor thermal power at 47% for MG set brush replacement.

0447 NG set brush replacement complete, connenced power ascension.

0630 Commenced PCIOMR frca 815 thermal pcwer (control

, cell core).

. 1000 Reactor thermal power at 995, maximta flow, rod limited.

11/13/82. 0525 Commenced reducing t.hermal power due to hit..

vibration on "C" reactor feedwater ptnp.

0545 "C" reactor feedwater pump taken out of service, reactor power at 75%.

0800 Reactor power at 74% due to "C" reactor feedwater ptap high vibrations.

Commenced increasing thermal power, "C" reactor

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0845 feedwater ptap vibration limited.

1000 Reactor themal power at 76%, "C" reactor feedwater pinp vibration limited.

1050 Rolling "C" reactor feedwater pump for vibration check, reactor power at 765.

1300 Increasing thermal power, "C" reactor feedwater pump limited.

l - 7 11/14/82 0100 Reactor thermal power at 80%, "C" reactor feedwater ptap vibration limited.

l 11/19/82 0660 Rolled "C" reactor feedwater plup for vibrat,lon check, commenced power ascension.

0700 Reactor power at 81%, "C" reactor feedwater pinp off.

0825 "C" reactor feedwater panp in service. Commenced power ascension.

1700 Comenced PCIOMR from 87% thenial power (control

, cell cere).

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SignifirJuLt Ooerational Event Unit 3 Date Time Fvent 11/20/82 2230 Received 1/4 isolation on "C" main steamline low pr(ssure, commenced reducing thermal power from 985.

'11/21/82 0200 Reactor themal power at 965 due to 1/4 isolation "C" main steamline low pressure, holding load to check "C" main steam line.

1300 SI's commplete on "C" main steamline, commenced power ascension.

1400 Reactor thermal power at 995, maximm flowr rod limited.

11/21/82 1425 Received 1/4 isolation on "C" main steamline low pressure.

1600 Reactor thermal power at 97% due to "C" main steamline low pressure.

11/23/82 1500 Reactor thermal power at 965 due to "C" main steamline low pressure.

11/24/82 1820 Commenced' power ascesson from 96% thermal power.

2120 Reactor themal' power at 995, maximm flow, rod limited.

11/25/82 0313 Received 1/4 isolation on "C" main steamline low pressure, commenced reducing themal power.

{ 0600 Reactor thermal power at 97% due to "C" main steamline low pressure.

v 11/26/82 1100 Commenced power ascension from 975 thermal power.

. 1200 Reactor themal power at 995, maximm flow, rod limited.

2300 Commenced reducing thermal power for turbine control valve tests and SI's.

f 11/27/82 0100 Reactor thermal power at 95% for turbine control valves tests and SI's.

0320 Turbine control valve tests and SI's complete, commenced power ascension.

0400 Reactor thermal power at 995, maximum flow, rod limited.

11/28/82 0120 Reduced thermal power to 96% for SI 4.3.A.2 (control rod exercise).

0135 SI 4 3.A-2 complete, increased thermal power to 99%, maximum flow, rod limited.

11/30/82 2400 Reactor tharmal power at 99%, maximm flow, rod limited.

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. 11 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-259 UNIT Browns Ferry - 1 DATE 12-1-82 COMPLETLJ BY Ted Thom TELEPHONg - 205 729 0834 MONTH NOVEMBER DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe-Net) - (MWe-Net )

3 1058' 37 1060 2 1015 I8 1067 3 -3 19 1034 4 -11 20 869 5 -11 21 1034 6 -10 22 1065 7 261 -

1065 33 8 891 1067 24 9 1048 1063 33 10 1072 26 1070 g 1058 1058 27 12 1063 913 28 13 1056

, 29 g4 1081 078 30

" 15 1069 3, 16 1065 INSTRUCTIONS

- On this format. list the aveiage dail) unit power leselin MWe Nel for each day in the icporting in.inth.Coinpute to the nearest whole nwgawait.

(9/77) 3

-77 * *98  ;* *.W-WE lprf.}e *.N*y.,"y %7 *

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1 AVERAGE DAILY t! NIT POWER LEVEL

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DOCKET NO. 50-260 UNIT . Browns Ferry - 2.

12-1-82 DATE.

COMPLETED BY Ted Thom

- TELEPHONE 205,729 0834 7

MONTH-NOVEMBER DAY- - AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe-Net) 1MWe-Ne:)

1

-2 -3 37

.2 -2 lg. _3 3- ~3 -2 39

-3

4. 20 -3

"' -3 -2 5

-3 -3 6 22

'7 23

-3 8

~4 -3 24

-2 -2 9 25 10 = -3' -2

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' -3 28 -3

~3 -2

,.13 29

-3 -2

'14 30 15

-3 31 16 -3 s

INSTRUCTIONS

'" '# "' ##' F I" 'I'# '#P"'"E '"'nitii. Cinnpute in Ih are t ibi g v3 01/77) 4 i

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AVERAGE DAILY UNIT POWER LEVEL

. DOCKET NO. 50-296 UNIT.

Brosins Ferry - 3 DATE

• 12-1-82 COMPLETED BY Ted Thom

~ TELEPHONE 205 729 0834 MONTH NOVEMBER DAY- AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 'MWe-NetI g 1061 g7 843 __

2 1057 gg 844

3. 1061 39 863

.: - 1061 20 '1004

=

5

'1063 1028 21 6

960 ,3 1024 7- 1066 1017

. 23 -

8 1066 1027 24 __

-9 1059 25 1038 10 1067 1047 26

, 1059 1064 27 g; 1061 1050 28 13 -

881 1066 7

g4 8 '.2 1077

- 30 834 15 . 3, 16 838 s

INSTRUCTIONS On this forinai,hst the averat;e daily unit power fewl in MWe-Nei Ibr each day in the icporting inonth. Compute to the nearest whole mepwait.

(9f77)

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OPERATING DATA REPORT DOCKET NO. 50-259 i .- DATE 12-1-52 COMPLETED BY Ted Thom TELEPHONE . zu) uw 0834

' OPERATING STATUS b 1. Unit Name: Bro m 'Fe m - 1 Notes

. 2. Reporting Period. November 1982

, ' 3; Licensed Thermal Power (MWt): 3293

4. Nameplate Rating (Gross MWe): 1152 5 - 1. Design Electrical Rating (Net MWe): 1065 1098.4

6. Maximum Dependable Capacity (Gross MWe):

7. Maximum Dependable Capacity (Net MWe): 1065 8.' If C' 2nges Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:

-V NA i

9. Power Level To Which Restricted,1f Any (Net MWe): . NA h 10.' Reasons For Restriction:; If Any: NA r

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'L. This Month Yr to-Date Cumulative

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l I1. Hours in Reporting Period 720 8,016 73,058

12. Number Of Hours Resctor Was Critical 650.75 7,387.87 _46,702.67 13 Reactor Reserve Shutdown llours 59 464.98 5,680.18

14. Hours Generator On-Line 611.25' 7,286.77 45.716.94

15. Unit Re:<rve Shhtdown flours 0 0- 0 22,701,859

. . .I'~.. ' 16. Gross Thermal Energy Generated (MWH) 1,985,489 129,576,766

• 17.. Gross Eledrical Energy Generated (MWH) 646,390 7,378,330 42,670,780

.M. Net Electrical Energy Generated (MWH) 629.474 7,169,391 _41,438,300

'19.' Unit Service Factor 100 92.3 62.7 N . 20.' Unit Availability Fa_ :or 100 , 92.3 62.7

21. Unit Capacity Factor IUsing MDC Net) 82.1 84.0 53.3

-. 22. Unit Capacity Factor (U>ing DER Net) 82.1 84.0 53.3

- 23. Unit Forced Outage Rate 8.4 8.5 24.6 2 24. Shutuwnr Scheduled Oser Next 6 Months (Type. Date,and Duration of Eacht:

! a

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

- 26. Units In Test Status (Prior io Commercial Operation): Forecast Achieved INITIA L CRITICALITY INITIAL El ECTRICITY COMMERCIAL OPER ATION l

(9/77)

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.i re OPERATING DATA REPORT

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-a~ DOCKET NO. 50-260 DATE 12-1-82 COMPLETED By _ Ted Thom TELEPilONE 203 /a 0834 OPERATING STATUS

1. Unit Names Brows Fe m - 2 Notn

2. Reporting Period: ' November 1982 3293

3. Licensed Thermal Power (MWt):-

1152

'- 4.' Nameplate Rating (Gross MWe):

5. Design Electrical Rating (Net MWe): 1065

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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:

NA

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

= 10. Reasons For Restrictions. If Any: NA This Month Yr.-to.Date Cumulative I1.' Hours In Reporting Period 720 8.016 67,999

.12. Number Of flours Reactor Was Critical 0- -4,846.51 43,293.47

.3. ' Reactor Reserve Shutdown flours . 0 203.06 13,684.82

( 14. Hours Generator On.Line 0 J .778.36 41,975.45

.15. Unit Reserve Shutdown llours 0 -0 0

. 16. Gross Thermal Energy Generated (MWH) 0 13,827,550 120,480,340

• j, - 17.. Gross Electrical Energy Generated (MWH) 0 __

4,592,260 40,024,90E

[ IF.-Net Electrical Energy Generated (MWhl 0 4.450.929 38.873.075 ,

19.~ Unit Service Factor 0 59.6 61.7

!20. Unit Availability Factor 0 59.6 61.7

- 21 J Unit Capacity Factor (Using MDC Net) 0 52.1 53.7

22. Unit' Capacity Factor (Using DER Net) 0 52.1 53.7

23. Unit Forced Outage Rate 0 5.5 27.1

j. 24. Shut' downs SUeduled Over Next 6 Months IType. Date.and Duration of Each t:

L t

25. If Shut Down At End Of Report Period. Estimated Date of Startup: January 1983

26. Units in Test Status Prior to Connnercial Operationi: Forecast Achiesed INITIAL CRI TICALITY I

INITIAL El.ECTRICITY CO\lMERCIA L OPER A TION I

(9/77) me A esy, 4

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OPERATING DATA REPORT y

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DOCKET NO.' _50-296 DATE _12-1-82 COMPLETED BY _ Ted Thom

. :e TELEPflONE 205 729 0834 E

+ ~ OPERATING STATUS I.. Unit Name:

Browns Ferry - '3 Notes

2. Reporting Period': November 1982

3. Licensed Thermal Power (MWt):

3293-iE4.' Nameplate Rating (Gross MWe)i 1152

5. Design Electrical Rating (Net MWe):

~

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

7. Maximum Dependable Capacity (Net MWe): 1065

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

NA

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

c , ; .NA-

4g , ,' 10. Reasons For Restrictions,if Any: _ .

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, This Month Yr.-to-Date Cumulative II. Hours in Reporting Period 720 8,016 50,424  !

- 12. Number Of Hours Reactor Was Critical 720 4,401.30 36,86f>. 28

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13. Reactor Reserve Shutdown Hours 0- 1,230.62 3,372.15

, II4. Hours Generator On Line 720 4.279.28 36.030.06

- J 0 0 0

' ' - 15. Unit Reserve Shutdown llours . i

.16. Gross Thermal Energy Ger. crated (MWH) 2,230,090 13,151,238 -107,009,858 .<

- 17. Gross Electrical Ene:gy Genersted (MWil) 737.970- 4.274,810- 35.273,000

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i 18"' Net Electrical Energy Generated (MWH) . 720,029 4,144,683 34,232,729

' 19.' Unit Service Factor 100 53.4 -71.5 i ~ ,20 ' Unit Availability Factor. 100 53.4 71.5

21/ Unit Capacity Factor (Using MDC Net) 93.9 48.5 63.7-

~22. Unit Capacity FactorIUsing DER Net) 93.9- 48.5 63. 7 i

_23. Unit Forced Outage Rate 0 23.3 17.7

. 24.- Shutdow~ns Scheduk d Oser Next 6 Months (Type. Date,and Duration of Each t:

L

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

26. Units in Test StatuslPrior to Commercia! Operationi: Forecast Achieved INITIA L CRITICALITY INITIAL ELECTRICITY

' COMMERCIAL OPERATION 1" -;; (9/17)

. s Ih e i 4- .- -f .'  %  % + , ,

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50-259

. UNITSifUTDOWNS AND POWER REDUCTIONS DOCKET NO.

.$ UNIT NAME Browns Ferry - 1; DATE 12-1-82 November COMPLETED BY -Ted Thne REPORT MONTH TELEPHONE 105 729 0834 y

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Present Recurrence 244 11/03/82 F 6.83 A '3 Reactor scr.as due'to false high turbine vibration.

245 11/03/82 S 52.5 P 3 Unit remains offline for change out of spare 500 kV transformer to IB, replace HEPA filter on primary con- O-tainment purge assembly, replace

. connectors on (A&B) IRMs and repl? ice coil on B IRM drive light.

246 11/05/82 F 49.42 A 3 Unit remains offline due to probler.s with computer 247 11/19/82 S H Derated for control rod pattern ad-justment e d turbine control valve tests md SI's 248 11/27/82 S B Derated for turbine control valve tests and r.ontrol rod nettern ad-justment.

I 2 3 4 F: Forced Reason: Method: Exhibit G - Insituctions S: Scheduled A Equipment Failure (Explain) I-Manual for Preparation of Data B-Maintenance of Test 2-Mar ual Scram. Entry Sheets for Licensee C Refueling 3 Automatic Scram. Event Report (LERI File iNUREG.

D Regulatory Restriction 4 Other (Expiain) 0161)

E-Operator Training & License Examination F Administrative 5 G Operational Error (Explain) Exhibit 1 Same Source (9/77) Il-Other (Explain)

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DOCKET NO.' sn_9An:

y UNIT SHUTDOWNS AND POWER REDUCTIONS Browns Ferry - 2 1

UNf7 NAME ~

DATE- 12-1-82 ,, r >

COMPLETED BY. Ted'Thom REPORTMONTH November . TELEPHONE" 205 729 0834 .

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Cause'h Currec'tive -

No.' Date i 3g j jg5 Event , ~?

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n.? . : Action to H-5E 5 .-

35 e - =g Repor * ' .mV o

8' Prevent Recurrence -

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243 11/01/82 :S -720 H '2 EOC-4 Refuel Outage continues

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, F: Forced Reason: Method: Exlubit G Instguctions l S: Scheduled A Equipment Failure (Explain) 1-Manual fiir Preparation of Data ~

B-Maintenance of Test 2-Manual Scram. Entry Sheets for Licensee --,

C Refueling 3 Automatic Scram. Event Report (LERI File (Nt!RIL

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D-Regulatory Restriction . 4 Other (Explain) 0161) 1:-Operator Training & License Examination F-Administrative 5 j G-Operational Error (Explain) - Exhibit I - Same Source

! ("/77) Il-Other (Explain) .

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f UNIT SIIUTDOWNS AND POWER REDUCTIONS DOCKETNO.-. _50-296 y UNIT NAME Browns Ferry - 3 DATE 12-1-82 A COMPLETED BY TaA h =

' ' REPORT MONTF1 November TELEPif0NE 205 779 ORM

, .! E 3g .Y Licensee ,E-t, h

$9.,3 Cause & Corrective g

No. Date 3g jg$ En it gg- Action to

• $E -5 T:i gg Report a mV E' Prevent Recurrence

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115 11/06/82 S B Derated for recirculation pump MG set brush replacement 116 11/13/82 F A Derated due to high vibration on "C" reactor feedwater pump G

l I 2 3 4 f Forced Reason: Method: Exhibit G. Instguetions S Seeduled A Equipment Failure (Explain) l-Manual for Preparation of Data B Maintenance of Test 2 Manual Scram. Entry Sheets for Licensee C.Rcfueling 3 Automatic Scram. Event Report (LER) File (NURI.G-D-Regulatory Restriction 4-Other (Explain) 0161) .

E-Operator Training & License Examination F Administrative 5 G Operational Error (Explain) Exhibii ! - Same Source I'l/77) 11-0ther ( Explain)

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, l BROWNS FERRY tiUCLEAR ' PIANT. UNIT - Common CSSC EQUIPMENT MECHANICAL MAINTENANCE SUIDIARY ,

' For the Month of' 3 November 19 82

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~

EFFECT ON SAFE. ACTION TAKEN DATE SYSIEt COMPONENT NATURE:0F OPERATION OF CAUSE OF RESULTS OF TO PPICLUDE.

MAINTENANCE Tile REACTOR- MALFUNCTION It\LFUNCTION RECURRENCE 0-29 Radiation RM-90-127 belts cracked' none belts worn excess- belts on the verge replaced belts on Monitoring EM-90-126~ and' broken ively- of malfunction both CAM Units.

TR# 252612' I

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HECHANICAL HATitTENANCE

SUMMARY

. C;;--

19 82'

~

I For' the Month ~.'ofl November -

]-

EFFECT ON SAFE ~

< ACTION TAKEN DATE SYSTEM COMPONENT NATURE'0F ' OPERATION 0Ft- CAUSE OF' RESULTS-OF 10 PRECLUDE? - ll MAINTENANCE THE REACTOR -MALFUNCTION MALFUNCTION- RECU?RENCF' 1-06 Diesel D/G C #1'airL air' leak none blown headgaskets air leak; replaced headgasket's?

Generator' compressor TRf.274736- g 1-06 Diesel- 1&2C, B compressor noca. faulty headgasket blown headgasket replaced headgasket'sl Generate,r' compressor- nonfunctional TRf 266979 l-04 Diesel C diesel A air air leak on none unloader valve air leak at base of repaired unloader-i Generator. compressor -sensing lin2; causing air leak . compressor valve ' '

3 on sensing line , TRf 274735~

1-05 Liquid iB. equipment coupling none unknown coupling dropped repaired. coupling Radwaste drain sump pump nonfunctional I down approximately. TRf 315150 1/4 " 4

,1-10

~

HPCI upstream of water leak none weld leak on 3/4" water leak repaired weld HCV-73-563 pipe ,

nipple TRf 311937 f

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l -CFSC'EQUIPN NT^

MECHANICAL MAINTENANCE

SUMMARY

~~ '

~~ For the Honth'of' November ~

j. 19 _82 EFFECT ON SAFE ACTION TAKEN

DATE SYSTDI ' COMPONENT NATURE OF OPERATION'0F. CAUSE OF' RESULTS.0F R)' PRECLUDE ILSINTENANCF. THE REACTOR R\LFUNCTION FLSLFUNCTION RECURRENCE _

1-06 RHR Set- ' 2C RHR pump' nipple on vent none. broken nipple nipple nonfunctional replaced brokr.-

Water suction Vent line inoperabic nipple with new onp.-

line TRf 276239 5 0-20 CRD HC*i-85-560 faulty valve none valve seat & valve nonfunctional lapped coppet and poppet. eroded- valve body seat by.

hand TRf.315141 h

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ELECTRICAL MAINTENANCE SL N Y PWh B' .

CSSC EQUIPMENT 9/29/82' -

~

For the Month of November 19; 82 -

Effect on Safe Action Taken Nature of- Operation of. Cause of Results of 'To Preclude Date -System Component Ibintenance The Reactor Malfunction Malfunction Recurrence 10/26/82 Contain- "B" H,02 Anal- 0 Inlet Pump 2

.None -Handswitch HS- 0, Inlet pump y iReplaced the R5 ment. yzer 0 Inlet 2 in Perable. 76-59 on panel inoperable. relay contacts.

Inerting Pump control 9-55 had erratic TR #207581 was.

relay.R5. operation when written to're-turned to " Dry- place HS-76-59 well" position. during the next

.This' erratic unit outage. "Te operation re- failure of this suited in the . ,

type relay con-failure of the , tacts is being Drywell sample investigated in line valves to conjunction with w open, this re- LER 259/82031 with sulted in the results expected 0 Inlet Pump by March 1, 1983.

2 repeatedly TR #291634 starting and stopping in rapid succes-sion which caused relay R5 contacts to burn.

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$r Page -

BROWNS.FERRh NUCLEAIE PLANT UNIT 1 and CEunon Appendix B. 3 "CSSC EQUIPMENT' . ELECTRICAL MAINTENANCE SUhfARY.

[. 9/29/82 1

For the Month of November 19 82

. Effect on, Safe Action Taken Nature of Operation of Cause of Results of To Preclude Data System Component Maintenance The Reactor Fb1 function Halfunction Recirrence l 1

0/29/82 Fire Pro- Smoke detector XS-39-66KM None The detector was XS-39-66XM gave a A-fire watch was '

tection XS-39-66KM initiated a wetted from false alarm which established. The false alarm. water coming could have maskeo water was removed through the signals from other from the detector ceiling from a , detectors which are and.the detector leaking building ' required to be was successfully secondary heat operabic. tested per SI pump. 4.11.C.1&5 and

. returned to ser-vice.

TR #291621-LERfBFRO-50-259/ Z 8294 ,

.1/3/82 Radiation CAM-251 CAM-251 pump _None Pump motor fuse CAM-251 was inoper- The blown fuse Monitoring inoperable. blown. able. was replaced and the CAM pump oper-ated properly.

TR #341043 I

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CSSC EQ'11PMENT

'IELECTRICALMAINTENANCESUEIART' ':

' 9/29/82':

j. IFor;theMonthof November, 19 82. . -

.. 5 Effect on Safa Action Taken Nature of. . Operation' oft .Cause of- _Results of iTo Preclude 1 Datst ~ Syste s Component Maintenance The Reactor Malfunction Malfunction Recurrence L1/3/82- :EECW Sys. _480V Diesel Breaker would None ' Compartment door -Breaker was inop- . l Closed compartment and Com- Auxiliary Bd. not close. was nc fully. erable..  : door which allow-municatior B breaker 8E. closed, lockout ~ ed. lockout device RHRSW & EECW device'not. fully to fully' seat.

j, 'I trace htr. B seated. TR #266971'

, and C emeg.

fdr. and'480V evacuation alarm fuse .

. panel _ alt. , l fdr.

lU"

' Ll/4/82 250 Volt Cell #98 on Cell replace- None Cracked cell. Required cell #98 Replaced'the DC System main battery. ment. _to be junpered' .

. cracked cell around in March 82. (battery) per-

' SEMI 38 and.SI 4.9.A.2.C.

TR #196476 l}/22/82 it1/4/82 Main Steam MSIV l-26 Trip channel. None LSf3 actuator _ ~ Intermittent trip- . Tightened actua--

limit switch relay SAK3D  : arm loose. ping of trip' channel . tor arm and ad-

1. 3. on panel 9-17 justed limit-dropped out. . y

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switch.

. TR"f237259

.TR #266866 I

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CSSC EQUIPMENT -.

ELECTRICAL'MAINTENANCESUdfARY PPen & B:

9/29/82; Q}

^ '

For the MonthLof November- 19 82 - -

l' Effect on Safe i Action Taken.

Nature of' Operation of- .. Cause of. Results of - To Preclude Date' a System -Component Maintenance The Reactor Malfunction Malfunction Recurrence l'/16/82- ,

.1/4/82- Neutron'~ "A" and'"B" "A" and "B" -None Center conduc-! "A" and "B" IRM Repaired,the .  ;

Monitor- IRM' cable IRM. channels tors on both channels. inoperable.  : broken connectors. "

.ing.

connectors inoperable. - "A" and "B" IRM , During repairs' at inboard connectors'at" -

to the IRM con-penetration.. the inboard- inectors the SRM I

penetration was "A" and "B" broken.- channel connectors <

were inadvertently jarred loose

. making SRM chan-nels '%" and "B" 7 inoperable. The .-

f. SRM connectors

-were cleaned and returned to ser-vice. The IRM i and'SRM channels operated properly.

TR #252374-

-TR #252375

-TR #252619

'.1/4 /82 Neutron IRM "B" Received both None Burned coil on. IRM "B" channel ' Replaced the bad Monitor- channel relay .in and cat- relay 7CK-7F. -inoperable. relay coil. IRM ing 7CK-7F locat- annunciation . channel'"B" ed in panel on panel 9-5 operated properly.

. 25-14. for IRM "B" ' TR #341051 l- channel.

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. Appendix B' CSSC EQUIPMENT- ELECTRICAL MAINTENANCE SUI 9 FART ~- .

9/29/82- .;

1

-For the Month of1 November: '19 82- -

~

Effect on Safe .

Action Taken

.. Nature of Operation of Cause of . Results:of' To Preclude.

Data System Component ' Maintenance The Reactor Malfunction Malfunction Recurrence

.1/6/82- Diesel- .D/G "1C" "B" ' Air compres- None', Burned motor "B". air compressor- Replaced,the Genera- air compres- sor tripping. contactor con- ' inoperable.- burned contacts.

tors sor. tacts.  : compressor oper-ated properly.

TR #266977

.1/9/82' Diese'1. D/C "1D" During the .D/G."lD" Bad microswitch Diesel generator The governor con-Genera- goverr.or performance inoperable.

• in the Woodward "1D" $noperable, trol-microswitch tors control. of SI4.9.A.1.a Governor ,

was replaced. SI the control Controller. . ~4.9.A.l.a success-room operator

. fully completed 0.

was unable to -

and.the diesel raise the .Fenerator returned diosel gener- to service. -

ator speed. TR #341085-LERfBFRO-50-259/

8291

.1/10/82 Fire Pro- Smoke detectoi Receive an None Bad detector Detector XS-39-66XM Replaced the bad tection XS-39-66XM. intermittent (XS-39-66XM). inoperable. detector, detec-trouble alarm tor operated pro-for zone X 'perly per.SI on panel 25- 4.11.c.1&5.

286 (alarm TR #256985 XA-39-66XB). .

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. BROWNS FERRY NUCLEAR PLANT UNIT .I nd M ' 8* -

u Appendix.B' CSSC EQUIPMENT ELECTRICAL MAINTENANCE SIMMARY.

9/29/82' I'

For the Month of' November 19 82 -

Effect on Safe Action Taken-Nature of Operation of' Cause of Results of To Preclude Data System Component ' Maintenance The Reactor Malfunction Malfunction - Recurrence

.1/12/82 CRD C"D control ~ HS-85-48 was None Broken mechani- Required care to be Replaced.the switen (HS- not operating cal stop, taken by operator' broken stop.

85-48) on properly. to avoid operating switch operated panel 9-5. the switch past the properly.

desired setting. TR #291978 e

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.CSSC EQUIPMENT ELECTRICAL MAINTENANCE Sid ARY:

9/29/82- ~

b- ;For the' Month of November -19 82 - <

Effect on Safe Action Taken_

'Naiure of . Operation.of: Cause of.' . Results of .To Preclude

, Date System ~ Component -Maintenance The Reactor' Malfunction ~ Malfungtion Recurrence

.0/27/82 CRD. Scram accum. .During . the .. .None, unit in- Removed switches . Switches'26-11 and Chased instrument.

.hrough , ulator level performance- refueling out-'

26-11 and 26-15 26-15 could not be. ;bic As threads-

'.1/9/82 switches for of EMI 50 the age.- for cleaning. ' screwed bacE into for 26 7

1Ll'and .

CRD's 26-11, . listed com- (per EMI 50).and .-instrument blocks ?6-15 and instal-j 26-15, 10-51, ponent items found. switch ~ enouGh to seal prop- hd new switches. -

j and 06-43. faired. ~ threads to be. erly to 0-rings.- .

! Replaced switches; bad, instrument ' Switches 10-51"and 10-51 and 06-43.

., -block would not 06-43 were inoper-- Each switch oper-able..

allow switches' ated properly per to be screwei *

- D!I 50.

t. in' fully. :TR #319510-l Switches-10-51: TR #319530 1 4 -

and 06-43 fai?ed TR #319556

't to actuate. TR #3195$7 TR #2T'4045 i

'1/10/82

. Standby SLC pump 2A- SLC pump-2A None- The feeder SLC pump 2A some- . Adjusted breaker Liquid feeder breaker failed to breaker's trip times 1 failed to trip. mechanism.-

j_ Control 470V shtd. bd. start from latch mechan- start from HS-o3- pmp controls and .,

2A, compart- HS-63-6A on ism'was out-of- 6A. breaker operated; ment 7B. control panel udjustment, properly.

9-5. TR #245084 I

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}.0f7/82 CRD Control trans- Fuses 5A-F233 None, unit in Bad control Scram. valves open Replaced the bad

'.1/15/82; former 5A-Tlc blowing. refueling. transformer. ' indicators and . trannformer, in panel outage. scre2' accumulator- systum' returned 25-22. -low pressure /high -to service.

) ,

level alarms,inop- TR #274742' erable.

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[CSSC EQUIPMENT-' .,

ELECTRICALMAINTENANCE[SUMARY  ; 9/29/82.

c.. ' , u

-For th,e Month or.iNovember' / 19 82 ^

~ '

1: --

. o Effect on Safe .

l. l Action Taken-

,Cause of-Nature of. L Opera tion 1. of. 7 'Resultisi of 'To ?reclude-

-: Dace System'. -Component ' Maintenance 'The Reactor Malfunction ' Malfunction' Recurrence 10/31/82 Dieselj D/G.3D annun- Received a None Bad snnunciator Received.a false l Replaced the had:

Generators .ciator cir- false start circuitry.' card. ' start failure alarm annunciator. card.-

cuitry. .fallure alarm for. D/G - 3D.' _ the alarm circuit-in control ' operated properly.

' room. 'TR'#275228" ll/12/82 'Annuncia- Alarm panel XA-55-3Bf None Annunciator cir- .XA-55-3B alarm- ' Replaced the

, tor &' XA-55-3B on ~ . alarm panel cuitry: card'was l panel.'inoperpble. . annunciator card..

Sequential panel 9-3.- failed.co not-seated pro- , ' panel operated-

!" Events . test properly. .perly, retainer properly.-

Recording pin broken. TR #269531 W

L1/16'/82 Off-Gas 3A stack Damper motor. .None Bad damper. Fan damper.'inoper ' - Replaced '. the

dilution fan . inope rable .-' motor, able.. damper. motor.-fan

-damper motor, damper operated-

' . properly.

TR #313141 l

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N.- 31 FTM n SERVICES

SUMMARY

November 1982 Maior Work Areas

• I. Work Synoosis Work completed this monthly period: Jet pump hold down beam i

s eplacement, invesel ISI, X-ray welds for P0538, LLRT of "B' feeduater valves, unit 1 "B" transfonner placed into service wLh 2B received frm power service shop, shrunk-on-wheel inspection for the turbine and 2A and 2B recirculation MG set maintenance,.

On-going work during this month: Began torus sandblasting and painting. Contractor arrived onsite to begin SRV test /instrunentation for the torus. Began preparation installation of thertrocouples in the "B" low pressure turbine. The electrical / mechanical work for the

, scram, discharge header continued.

. II. Maior Work Areas A. Refuel area - the jet ptanp hold dwn beam replacement was j completed in October. After completion of the jet ptanp work the ISI group c'onducted an invessel inspection of the RPV and a UT analysis of the RPV flanges. All ISI inspections were acceptable.

B. Tbrbine - the results of the shrunk-on-wheel inspection required that two thennocouples be installed in the "B" low pressure t I turbine to give operations a temperature reading during startup.

At this time the final design drawings and associated paperwork have not been received onsite. With the current return to service date of January 25, 1982 the thennocouple modification needs to be completed by December 17, 1982.

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132 -

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~$

Fmn KrRVI.Qfa.

SUMMARY

November 1982

-II. . Maior Wrk Arana (Continued)- *

, 1 B. - (Continued) e-

, --The "A" low pressure turbine was reassembled and work started on boring 18 coupling holes in the No. 1 coupling. 'All repairs have a been'made to the LP "B" diaphragms and spindle. All RFTT's and RFP' have been reassembled. The RFTP's still require governor

' ' ~

checks, alignment of controls and installation of vibration probes. e C. Electrical - the completed work in support of unit 2 cycle 4 '

lo fs; outage-a.civities during the past month are: placed'three GE-

_500kV transformers in storage. The repaired 500kV transfomer for location 2B arrived from the power service shop on November

,. 15, and the defective 2B unit was transported to the power service shop for repair. Transfonner 1B previously installed was  ;

3.

~

placed'into service during a unit 1 short cutage in mid-November.

7 . The recirculation punp MG set maintenance for 2A and 2B was

< finished. All welds and QC torque verifications for all LPCI MG l

sets were made, as well as grounding of MG sets 2EA and 2DN

,, completed. One-hundred percent completed on work for ILRT 1

connector cable installations. The AC power for recirculation i

I' controls and the three second time delay was finished.

L

[ On-going activities include: LPRM testing and connector 5

installation. Conduit for overheading lighting in unit 2 control room is at 98 percent, wiring at 35 percent and removal of old l1 conduit at 40 percent; however, problems related to conduit hangers slowed down this work. LPCI installation of conduit and

ly IF - _ _ ,

~* '

33 1

FIELD SERVICES.

SUMMARY

November 1982 i-II. Maior Work Areas (Continued)

• l C. (Continued) hangers as well as internal wiring and junction box work l* continues; the pulling of power cable from MG sets to 480 volt l

shutdown boards and the installation of voltage regulators for l '2EA and 2DN is underway. Preparations are in progress for making l

( LPCI Loop I tie-ins. EMI-71 motor and EMI-7 breaker maintenance i

work is 94 and 95 percent cumpleted, respectively. Cable i e tenmination work for the ILRT connector modification is 98 i

percent with work continuation on terminal blocks, junction baxes and conduit. Preparations are underway for pulling cables related to the two new MSRV's.

l Bnergency lighting work was restarted and 39 battery packs /19 cases have beeen installed; some conduit installations have begun Lo in the reactor building. Conduit / brackets for LPCI bypass is at l

90 percent with anticipated tie-ins the first week of December.

=>-

l Heat cure cable splicing for the torus has started and is 90 percent completed overall. The reciret.lation MG set brush holder covers and rigging has been sent to the PSS for that portion of the modification. Scram discharge header continues with conduit

- and cable pull work at 81 percent, 35 percent for internal j wiring, and cable terminations at 32 percent. This work has had problems with equipment; namely, level transmitter response time and which type of valve to use.

34 2

w FTFrn SERVICES

SUMMARY

November 1982 II. Maior Work Areas (Continued) >

D. Mechanical - the trojor work performed in the mechanical section during the month of November was scram discharger header (P0392) modifications, CRD flush connection modification ((P0548) and HSIV poppeu/ guide rib modifications (P0613) . P0538 was

. completed this month after receipt of gasket for the blind flanges.

P0392 is still in work. Ten of eleven six inch X-ray welds have been complete and the last weld is being repaired. Design informatin receipt and material delivery has delayed completion of the instrtmentation piping portion of P0392. P0613 is still in work. All poppet welding was completed this month and the inboard reassembly and LLRT was completed on "B" and "C" inboard MSIV's. "A" inboard is being worked and should be ready for LLRT 3

soon. "D" inboard did not require modification this outage. The I

work effort is being channeled toward the inboard MSIV's to support fuel loading. Some workk was accorrplished on the outboard MSIV's and this work will be complete in time to support l the ILRT.

E.- -Modifictions - reviewed work plans in support of the unit 2 cycle l; 4 outage. Expedited the solution of modification related problems through EN DES via Chattanooga Field Services I

modification troup. Started preoperation work for unit ! cycle 5 outag% Responded to LER's and CCPR's.

l

\

J

35 s.o 4

FTFfD SERVICES

SUMMARY

November 1982

~II. Maior Work Areas (Continued)

.F. Planning and scheduling - the report period for November ended with unit 2 cycle 4 work in progress on day number 123 of the current outage. Work is nearing completion in several major areas of involvement, however, the timely completion of work items affecting system outage durations has not been done as was

' originally planned. This will, no-doubt, have an affect on the overall outage schedule. Significant events for the month that are related to the outage effort includes:

-Completion of fuel inspection. No bundle reconstitution will be required for relnad.

-Torus sandblasting started November 18 and coating work began shortly thereafter.

-Main steam isolation. valves (MSIV's) - 7 of 8 valves failed the a "as found" local leak rate testing early in the outage. The 7 consisted of 3 (of the 4) drywell location MSIV's and all 4 of 7

the steam tunnel MSIV's. The 3 drywell MSIV's requiring maintenance will be given' priority attention in order to support core reload prerequisites.

-There were 40 weld joints identified as requiring more sensitive

UT inspection techniques to check for intergranula. stress corrosion cracking. Thirty-six of these were evaluated as satisfactory and 4 remain.

"B" feedwater line valves passed required local leak rate testing.

36 -

Fin n SERVICES

SUMMARY

November 1982 II. Maior Work Areas (Continued)

• F. (Continued)

-Low pressure "B" turbine shrunk-on-wheel inspection revealed indications that will require revising the turbine warmup procedure (based on GE recommendations) this will necessitate installation of a utennocouple in the LP "B" interna]s.

Drawings and materials are needed for this work.

-Completed PO450 jet pump hold down beam repa.acement.

-2B main transformer arrived from the Power Service Shop.

-Material i.oblems continue to plague P0392 scram discharge header modification. -

The Planning Eepartment Programmer Analyst attended a Project Software and Development, Inc. class on advanced PROJECT /2 techniques. This was a very worthwhile effort in order to o maximize the benefit of the computerized project management system currently being used. A schedule update was perfonned w

November 12, 1982 and it was announced that work had slipped approxim&tely 6 days behind schedule.

C. Torus

. Williams Sandblasting Contractor moved onsite November 15, and l started sandblasting. By the end of November bays 5, 6, 7, 8, 9, j 10, and 11 were completed with painting and heateure equipment  ;

was set up in bay 9 ready for checkout. Sandblasting was completed in bays 12, 13, and 14 and sand removal continued.

I 3-

• ^- 37- ,

,if F m.D SERVICES

SUMMARY

November 1982 II.- Mai r Work Areas (Continued)

• G. (Continued)

Painting efforts are on schedule. Teledyne moved onsite November 30 to start SRV test / instrumentation in bays 5,' 6, and 7, however, these bays lacked two additional coats of paint and were not released to Teledyne until December 2,1982 for instrtment work inside the torus. '

H. Administrative - the overtime percentage for the month of October was 22 percent, with 154,865 straight time hears and 44,014 overtime hours. As of November 28, year-to-date overtime percentage was 25 percent, 285,332 hours0.00384 days <br />0.0922 hours <br />5.489418e-4 weeks <br />1.26326e-4 months <br /> of straight time and 94,259 overtime hours. The overall goal of the overtime percentage is 17 percent. The O & M budget for November was 2,426,626 andothe expenditures were $2,394,999. ne capital

, budget $3,773,786 and the expenditures were $1,828,760. Overall budget was $6,200,412, with the overall expenditured being

$4,223,759. Re November overall budget is $6,308,834.

_ _ _ _- ._