ML20082T066

Monthly Operating Repts for Oct 1983

ML20082T066
Person / Time
Site:	Browns Ferry
Issue date:	11/01/1983
From:	Jones G, Thom T TENNESSEE VALLEY AUTHORITY
To:	NRC
References
NUDOCS 8312150140
Download: ML20082T066 (38)

Text

,.

TENNESSEE VALLEY AUTHORITY DIVISION OF NUCLEAR POWER BROWNS FERRY NUCLEAR PLANT MONTHLY OPERATING REPORT TO NRC Catober 1, 1983 - October 31, 1983 DOCKET NUMBERS 50-259, 50-260, AND 50-296

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

Plant - erintendent 8312150140 831101 gh PDR ADDCK 05000259 R

PDR

TABLE OF CONTENTS 1

Operations Suasary......................

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

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

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

11 14

' Operating Data Reports....................

Unit Shutdowns and Power Reductions.............

17 20 Plant Maintenance......................

Field Services Summary.............'.......

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9 4

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-1 Doerations Sn--cy October 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 15 reportable occurrences and three revisions to previous report-able occurrences reported to the NRC during the month of October.

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

Unit 2 There was one scram on the unit during the month.

On October 7, the reactor scrammed on generator load rejection during repair of the No. 3 turbine control valve.

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.

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EDerations Summary (Continued)

October.1983 Fatiana U:name Evaluation The cumulitive usage factors for the reactor vessel are as follows:;

Location Usaae Factor Unit 1 Unit 2 Unit 1 Shell at water line 0.00583 0.00473 0.00403 Feedwater nozzle 0.28294 0.20239 0.15429 Closure studs 0.22349 0.16 % 9 0.13233

~ NOTE:

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

Cor.1aon System Approximately 7 00E+05 gallons of waste liquids were discharged containir.g approximately 1.54E-01 curies of activities..

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-. Onerations Summary (Continued)

October 1983 e

Refualina Information Unit ~1-Unit 1 began its fitth. refueling outage on April ~ 16, 1983 The sched-

~

uled. restart date is October 7,1983

. This refueling will involve loading 818R (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 0' fuel assemblies in the reactor vessel. The spent ruel stor-age pool presently contains 252 new fuel assemblies, 764 EOC-5 fuel assen-blies, 260 EOC-4 fuel assemblies; 232 EOC-3 fuel assemblies; 156 EOC-2 fuel assemblies; and 168 EOC-1 fuel assemblies.

The present capacity is 3,471 1

locations.

Unit 2 Unit 2 is scheduled for its fif th refueling beginning on or about June 8, 1984 with a-scheduled restart data 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 inspection, finishing TMI-2 modifications; post-accident samplirs 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 EOC-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.

a

4-Onorat ions Summarv (Continued)

'Jctobhr1983

- Unit 1 Unit 3 shutdown for its fif th refueling outage on September 7,1983, with a' achedtiled restart date of May 4,1984. This refueling involves loading 8X8R (retrofit)' assemblies into the core, finishing the torus modifications, post-accident 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 0 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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. Minnificant Operational Events

Date Ti-Event Udt 1

'10/01-

'0001 End-of-cycle 5 refuel. outage continues.

-10/31

~ 2400 cad-of-cycle 5 rettel outage continues.

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Sinnificant Operational Eventa Date Time Event Unit 2 10/01 0001 Reactor thermal power at 64-percent for control rod pattern adjustment and "C" reactor feedwater pump maintenance, increasing thermal power.

0205 "C" reactor feedwater pump in service, control rod

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pattern adjustment in progress, reactor power at 67-percent.

0250 control rod pattern adjustment complete, commenced power ascension from 67-percent thermal power.

0330 Commenced PCIOMR from 74-percent thermal power.

s 10/02 1600 Reactor thermal power at 100-percent, maximum flow, rod limited.

l 10/ 07 1623 Commenced reducing thermal pcwer for maintenance on "C" control valve.

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1653 Reactor thermal power at 74-percent for maintenance on "C" control valve.

1720 Reactor Scram No.144 from 74-percent thermal power on "B" control valve closure (turbine generator load reject.)

k 10/08' 0231 Commenced rod withdrawal for startup.

?

0425 Reactor critical No. 155.

j 1012 Rolled turbine / generator.

1 1033 Synchronized generator, commenced power ascension.

1925 Commenced PCIOMR from 82-percent thermal power.

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10/09 0045 Stopped PCIOMR.at 86-percent thermal power for turbine control valve test and SI's.

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0300 Reactor power at 85-percent for turbine control valve tests and SI's.

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0330 Turbine control valve test and SI's complete, commenced PCIOMR.

1745 Stopped PCIOMR at 95-percent due to isolation of "A" 2

string high-pressure heater.

2100 Reactor power at 94-percent, "A" string feedwater heater limited.

2245 "A" string high-pressure heaters back in service, reactor power at 93-percent, commenced PCIOMR.

10/10 0555 Stopped PCIOMR at 95-percent maximun flow, rod limited.

1400 Reactor thermal power at 94-percent, maximum flow, rod L.

limited.

2205 Commenced reducing thermal power for control rod pattern adjustment.

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==

.- - Sfanificant Operational Events Date Tina Event Nnit 2 (Continued)

- 10/11:

0300 Reactor thermal power at 79-percent control rod pattern

. adjustment in-progress.

0400 Control rod pattel'n adjustment complete, commenced PCIONR from 79-percent thermal power.

.2035 Reducing thermal power from 96-percent for SI 4.5.A.1.b (Core Spray Pump Operability,) and SI 4.5.B.1.b (RHR Pump Operability.).

2100 Reactor thermal power at 94-percent for SI 4.5. A.1.b and SI 4.5.B.1.b. "

J2130 SI's complete, commenced PCIOMR.

10/12 0500 Reactor thermal power at 100-percent, maximum flow, rod limited.

1100

- Reactor thermal power at 99-percent, limited by condensate demineralizer high delta P.

1800 Reactor thermal power at 98-percent, limited by

' condensate _ demineralizer high delta P.

1910 Commenced power ascension from 98-percent thermal power.

2000 Reactor thermal power at 100-percent, maximum flow, rod limited.

10/14 0700 Reactor thermal power at 99-percent, maximum flow, rod l:

limited (100-percent electrical.)

T10/16 0015

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

0030 Reactor thermal power at 90-oercent for turbine control valve test and SI's.

0115 Turbine control valve test and SI's complete, commenced power ascension.

0130 Reactor thermal power at 100-percent, maximum flow, rod limited.

10/.18 0100 Commenced -reducing thermal power for removal of "C" high-pressure heaters from service for maintenance.

0110 Reactor thermal power at 90-percent "C" high-pressure heater limited.-

0120 Commenced power ascension due to lack of maintenance support on high-pressure heater leaks.

0200 Reactor thermal power at 100-percent, maximum flow, rod limited.

2245 Commenced reducing -thermal power for "C" high-pressure

-heater uaintenance.

2400 Reactor thermal power at 90-percent for maintenance on "C" high-pressure heaters.

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Rienifiannt Operational Events

. Date Tina Event

~ Unit 2 (Continued)

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0335

" Increased ' thermal power. to 91-percent, "C" high-pressure

' heater ~1imited.

0520-Increased thermal power to 94-percenl, 202 high-pressure heater limited.-

Increased thermal powe' ' to 95-percent, "C" high-pressure 1500 r

heater limited..

2200 "C" high-pressure heaters back in-service, commenced PCIOMR from 95-percent.

. 10/20 0300 Reactor thermal power at 100-percent, maximum flow, rod limited.

10/22

-2325 Commenced reducing' thermal power for turbine control

. valve test and SI's.

- 10/23!

0030-Reactor thermal power at 93-percent for turbine control valve test and.SI's.-

0105:

Turbine. control-valve tests and SI's complete, commenced

power ascension.

0230 iReactor thermal power at 100-percent, maximum flow, rod limited.

10/25

'2145.

Commenced ~ reducing : thermal power to repair leaks _ on moisture separator drain pump.-

1 0/ 26 0300 Reactor thermal power at 50-percent for_ repair of leak

~

on moisture; separator drain pump.

-0900-Reactor thermal power at 52-percent, moisture separator drain pump limited.-

1141 Moisture ceparator drain pump in service, commenced power ascension.

1745-Commenced reducing thermal power from 96-percent due to problems with demineralizers.

10/27 0300 Reactor ' thermal' power at 83-percent, due to problems

~

with condensate desineralizers.

0345 Commenced power ascension from 83-percent thermal power.

0500 Commenced PCIOMR from 91-percent thermal power.

2000 Reactor thermal power at 100-percent, maximum flow, rod limited.

2345 Commenced reducing thermal power due to condensate demineralizer problems.

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F Significant Operational Events Date Time Event Unit 2 (Continued)

- 10/28 0200 Reactor thermal power at 89-percent, condensato demineralizer limited.

0300 Reactor thermal power at 90-percent, condensate demineralizer limited.

0700 Reactor thermal power at 91-percent, condensate demineralizer limited.

0716 Commenced power ascet sivn from 91-percent thermal power.

0830 Commenced PCIOMR from 96-percent thermal power.

1330 Reactor thermal power at 100-percent, maximum flow, rod limited.

2030 Reactor thermal power at 99-percent, maximum flow, rod limited.

2100 Increased thermal power to 100-percent, maximum flow, rod limited.

10/29 0700 Reactor thermal power at 99-percent, maximum flow, rod limited.

1430 Increased thermal power to 100-percent, maximum flow, rod limited.

1815 Reduced thermal power to 95-percent due to isolation of "C" string high-pressure heaters.

1835 "C" string high-pressure heaters back in service, commenced power ascension.

2000 Commenced reducing thermal power from 100-percent due to problems with condensate demineralizers.

2100 Reactor thermal power at 95-percent, condensate demineralizers limited.

2130 Commenced power ascension from 95-percent power.

2200 Reactor thermal power at 100-percent, maximum flow, rod limited.

10/30 0130 Commenced reducing thermEl power for turbine control valve test and SI's.

0200 Reactor power at 87-percent for turbine control valve test and SI's.

=

0220 Turbine control valve test and SI's complete, holding for control rod pattern adjustment.

0300 Control rod pattern adjustment complete, commenced power 1

ascension.

0400 Commenced PCIOMR from 97-percent thermal power.

Reactor thermal power at 100-percent, maximum flow, rod 0600 limited.

10/31 2400 Reactor thermal power at 100-percent, maximum flow, rod limited.

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- 'Stanificant Operationni Events

'Date Tina Event Unit 3 10/01 0001 End-of-cycle 5 refuel outage continues.

10/31

'2400-End-of-cycle 5 refuel outage continues.

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4VER AGE DAILY UN!T POWER LEVEL s

DOCKET NO. 50-259 UNIT Browns Ferry-1

/1/83-DATE.

COMPLETED BY Ied Thom TELEPHONE 205/729-0834 October-

? MONTH DAY-AVERAGE DAILY POWER LEVEL.

DAY AVER AGE DAILY POWER LEVEL '

- 1MWe Net) _

(MWe-Neti I

-2

-2 i7

-2

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3 3 -.

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INS TRUCTIONS On tim format. list the.netag, Jaits tant p.,wer lesel in slwe.Nei siir ca.1, da> in t he :ci.iet.ng mienth. C.irne it. iii

- flie nearest whole nwpwari.~

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_ _.. WER AGI DAILY llNIT POWER LEVEL DOCKET NO. 50-260 UNIT Bron s Fe m -2 11/1/83 DATE COMPLETED BY Ted Thom TELEP110NE 205/729-0834 MONDI QC.Laber DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL

- (MWe Net) 65we. Net) 879 1075 g7 1076 1065 l8 3

1078 j9 1001 1063 1081 20 1076 1071 3

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6 1083 22 1076 763 1081 7

y; 348 1077 g

9 956 25 1044 10 1005 728

3 932 1016 gg 7

1067 1060 12 28 13 1078 1062 29 1100 1058 g4 39 1050 1086 15 31 1066 in

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f INSTRUCTIONS 3

On this forinal. hst the aserage danis unii p..w er lesci ni \\lwe.%i 1.n each da> in tht reportine inonth. Con.puir to the nearest whole nwgawatt.

g i8/771 m

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AVFRAGE DAIL9IJNJ T POhER LEVEL -

DOCKET NO. 50-296 3

IJNIT

. D ATE ' 11/1/83 COMPLETED By Te'd Thom 205/729-0834 TELEPHONE MONTH October DAY AVER AGE DAILY POWER LEVEL DAY AV(R AGE DAILY POWER LEVEL

- (MWe-Net)

IMWe-Neti 1

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18

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-9 16 INSTRUCTIONS On ilus forinat.hst the aserage da:!) inut p. mci lesci m MWe %:t t.it cadi das ni line reta.iiing unmih L "npute t..

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. OPERATING DATA REPORT DOCKET NO. 50-259 DATE 11/1/83 COMPLETED BY Ted Thom TELEPflONE 20s 729-0834 OPERATING STATUS

1. Unit Name:

Browns Ferry - 1 Notes October 1983

2. Reporting Period.

3293 d

3. Licensen Thermal Power (MWii.

1152

-4. Nameplate Rating (Gross MWe):

5. Design Electrical Rating (Net MWe): 1065

6. Maximum Dependable Capacity (Gross MWe):

1098.4 1065

7. Masimum Dependable Capacity (Net MWe):

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

N/A

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

N/A

"!^

10. Reasons For Restrictions. If Any:

This Month Yr. to-Date Cumulatise

11. Ilours In Reporting Period 745 7296 81.098

12. Number Of flours Reactor Was Critical 0

2,363.25 49,752,79 0

47.71 5,785.02

13. Reactor Reserve Shutdown flours

14. Ilours Generator On-Line 0

2,317.52 48,717.64

15. Unit Resene Shutdown llours 0

0 0

16. Gross Thermal Energy Geiisisted (MWil) 0 6,

5 13 5

9 l Gross Electrical E tergy Generated (MWil) lx % crectrical Energy Generated (MWH) 2,175,546 44,325,32/

19. Unit Senice Factor 0

31.8 60.2

20. Unit Availability Factor 0

31.8 60.2 0

28.0 R3

21. Unit Capacity Factor (Using MDC Net)

22. Unit Capacity Factor (Using DER Net) 0 28.0 51.3 0

23. L' nit Forced Outage Rate 8.1 23.8

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

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

11/1/83

20. Units in Test Status IPrior o Commercial Operationi:

Forecast Achiesed INillA L CitillCALIIY INIIIAL ELECTRICITY COMMERCIAL OPER AIlON P8/77)

_... OPERATING DATA REPORT DOCKET NO. 50-260 DATE 11/1/83 i

COMPLETED BY Tod Thom TELEPil0NE 205/'r?o nR34 OPERATING STATUS N08'5 Browns Ferry - 2

1. Unit Name:

Octoter 1983

2. Reporting Period:

3293

3. Licensed Thermal Power (MWt):

1152

4. Nameplate Rating (Gross MWe):

1065

5. Design Electrical Rating! Net MWe):

1098.4

6. Maximum Dependable C;pacity (Gross MWe):

1065

7. Maximum Dependable Capacity (Net MWe):

8.11 Changes Occur in Capacity Ratings (items Number 3 Through 7) Since Last Report.Give Reasons:

N/A N/A

9. Power Leiel To which Restricted. If Any INet MWe):

N/A

10. Reasons For Restrictions,if Any:

This Month Yr..to Dait Cumulative 745 7296 76,039 i1. Ilours In Reporting Period 733.92 5,262.21 48,555.68

12. Number Of Ilours Reactor Was Critical 11.08 160.04 13,844.86

13. Reactor Reserve Shutdown flours 727.78 5,131.01 47,106.46

14. Ilours Generator on Line 0

0 0

15. Unit Resene Shutdown flour, 2,291,782 15,402,992 135,812,839

16. Gross Thermal Energy Generated (MWil) 768,450 5,123,220 45,148,128 17 Gross Electrical Energy Generated (MWH) 748,846 4,975,864 43,848.939

18. Net Electrical Energy Generated IMWH) 97.7 70.4 62.0

19. Unit Senice Factor 97.7 70.4 62.0

20. Unit Availability Factor 94.4 64.0 54.I

21. Unit Capacity Factor IUsing MDC Net) 94.4 64.0 54.1

22. Unit Capacitv Factor IUsing DER Net) 2.3 5.4 25.2

23. Unit Forced Ontage Rate

24. Shutdowns Scheduled Oser Next 6 Months IType. Date.and Duration of Eachl:

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

26. Unit, in Test Status t Prior to Commercial Operation):

Forecast Achiesed INill \\ L L RillCALITY INillAL ELECIRICITY CO\\tMERCI AL Ol't:R \\ IlON 19/77) m

4 OPERATING DATA REPORT DOCKET NO. 50-296 DATE 11/1/83 COMPLETED BY Ted Thom TELEPHONE ?ns/7?o n834 OPERATING STATUS ~

1. Unit Name:

Browns Ferry - 3 Notes

2. Reporting Period:

October 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 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 e

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

N/A

10. Reawns For Restrictions,if Any:

N/A This Month YrAo.Date Cumulative

-- 11. Hours la Reporting Period 745 7296 58,464

12. Number Of Hours Reactor Was Critical

'0 5,475.52 43,087.80

13. Reactor Reserve Siiutdown Hours 0

505.98 3,878.13

14. Hours Generator On.t.ine 0

15.' Unit Reserve Shutdown Hours 0

__ 5.A19.65 42,193.71 0

0 16.' Gross Thermal Energy Generated (MWH) 0 16,971,607 126,307,711

17. _ Gross Electrical Energy Generated (MWH) 0

_.__,_. id57,.830 41.597.620 i

18. Net Electrical Energy Generated (MWH) 0 5,394,352 40,375,256

, 19. Unit Service Factor 0-74.3 72.2 0

74.3 72.2

20. Unit Availability Factor

21.. Unit Capacity Factor IUsing MDC Net) 0 69.4 64.8 22.7 Unit Capacity Factor IUsing DER Net) 0 69.4 64.8

23. Ur.it Forced Outage Rate.

0 9.3 16.4

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

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

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

Forecast Achiesed INITIAL CRITICA LITY INIIIAL ELECTRICITY COMMERCIAL OPERATION

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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKETNO. 50-260 -

. UNIT NAME Br wns Ferry-2 DATE 11/1/83 REPORT MONTH October.

COMPLETED BY Ted Thom TELEPHONE 205/729-0834 s

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7sX Licensee gL.

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5 Cause & Curreceive N" -

Date i

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Action to 2$E 3 @ =5 Report =

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Prevent Recurrence e

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d 273 10/7/83 F

17.22 H

3 Reactor scram on "B" control valve closure (turbine generator' load rej ect. )

274 10/25/83 F

B Derated for moisture separator drain pump maintenance.

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F.uced Reason:

Method:

Exhibit G. Instructions S S.hedu!c1 A l quipmen' Failure I..splain)

!-Manual for Prepar.ition of Data s

11 Maintenance of Test

2. Manual Scram.

Entry Sheets for Licensee C. Refueling 3-Autorn.itic Scrain, Event Report (i.ERI File (NtiRI.G D-Regulatory Restiwtion

. 4-Other (Explain) 0161) l 1 -Operater Trainmg A l tienw I umo..sinon I -Adnu nist rai r.c 5

G Operational 1.our (1% plain t Eshibit 1 Sanne Soonce p"77)

Il-Ot her ilaplam p

__._._)

~50-296 DOCKET NO.

UNIT SifUTDOWNS AND POWER REDUCT10NS Browns. Ferry-3.

UNIT N AME -

DATE. 11/1/83 COMPLETED IBY -Ted Thom

' REPORT HONTil October' TEI.EPHONE 70'; / 77 q_nn'ta

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Y Licensee

[-r; f%.

Cause A Corrective N...

Date r- -

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-E E E Esent u7 E-?

Action to Report r-tE C 5L Prevent Recurrence C

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140 10/1/83 S

745 C

4

.End-of-cycle 5 refuel outage continues Lo t

2 3

4 I. I'.used Reason :

Method:

li.shibit G - Inst ructions S Scheduleil A.I'quipment Failure (lsplain) 1 Manual for Pseparati.m of l>at.:

II.%intenance or Test 2-Manual Scram.

1:ntt> Sheet > foi Licensee C.Reint line 3 Automatie Scram.

. ISent Repoti ei l'Ri hie int Rt G.

1).Hegulatoi) Restriction 4-Ot her Ili.splain )

Ol til i 1 Operator liainme A 1.isense l samination 12 Ad.ninnts.itive 5

G Opeiational i iros Il'.spl.niin i stubit 1 - S.inie Souree to/77I ll.Otla4tl.xpl.inti

.....a.....>...u-t'MC IQUII?95.

FOR ' T *.E. ! C:;.il CF __QCTOBER -

~ 19 83

!U.7 'n.E EFFEC!

s'<. SAFE-CA'JSE I

- ACTIC0; '..*. El '

'J.TE.

' STS7F2:

' CCF.?CiE:.7 '

.CF C1EF.AT:CN CF CE RES'.3 TS _0F

/TO PESCL

--T'i E. f.E>.CTck '

!%LF:!;CTION PiLW::CTIo?:

~RECUFRi PA W.T..v! CZ-s s

. U-l

f -

10/12 85.

CRD Probes

. Repair None:

Short Partial loss of'CRD" None.

Indication 1.

1

. ILO/l 84 LT-84-14A

. Cal.

None iZero Shift-Errorenous~ Indication None LO/8 85 RMCS, lRod Replace None Bad Relay

. Rod:Blockf

None-Permissive t

I k*

.0/20 70 1

LIS-70-2B Repair None Age Annunicator' None-j

.)

)

B'l0/28 77 LIS-77-14A Repair Nond Age Annunicator-None-

.E i

I o

$~

1-I 10/30 74 FR-74-64 Repair No,ne Age Loss of'Reco'rd-None-t:

ki-3 O/10 68 FR-68-5 Repair None.

Age Loss of Record None

.J i

90 RR-90-272 Repair None Agb Loss of Record None

{0/2:

..$3 LI-63-1A Cal.

None Age Errorenous Indication None.

l10/25 I

l t

G 1

l 1

f I

f

BROWNS. FERRY NUCLEAR PLANT UNIT-3L

1. 8' 7 EMSIL 30-A P ndix B P

CSSC EQUIPMENT

. ELECTRICAL MAINTENANCE.

SUMMARY

9/29/82-For the Month of October 19'83 4

Effect on Safe Action Taken:

Nature of Operation of Cause of!

~Results of' To Preclude'

.: Pto System Component Maintenance The Reactor Malfunction Halfunctio'1 Recurrence n

1983 Unit Pre-Unit; preferred Bottom brushes None-Normal wear Brushes worn:to point.None; due.to: normal 9/14.

ferred 120 MG set 1C Con-on MG set nee'd where replacement was wear no recurrence Volt-AC trol Bay.

changing.

negessary.'

problem foreseen.

System MR A205062.

(MR A205081)

~

.g 10/1 Reactor Relay 5AK15D Replace coil in None Bad coil in relay During performance of After replac'ing coil Protection Relay SAK15D sis on SRM, IRM &

in relay, relay was-System SPRM, fuse SA-F15B' checked and was.

in panel 9-17 Aux.

working properly 4 L

Instr. Rm. was blown 7

MR A146888 10/10 Reactor Relay SA-K6C Replace coil on None Coil' burned up Fuse SA-FGC blew Fuse was replaced, Protection CR120 relay on CR120 relay giving half Scram also coil in relay, and relay was System

. f.

functionally checked

[

MR A211546 9

1 1

I i

i l' -

t i

4

~~

y

1. 8 BROWNS, FERRY.' NUCLEAR PLANT UNITi

~2 1

7 3f i

Appendix B !

'l

'CSSC EQUIPMENTA ELECTRICAL MAINTENANCE

SUMMARY

.9/29/82.

m wm

-19:-83.

For' the l Month. ofi October '

3..

Effect on Safe

' Action Taken Nature of

. Operation.of

. Cause;of'

' Rc'sult s lo f ;

'To. Preclude:

~

l bte System Component'

' Maintenance '

The= Reactor Malfunction Malfunction' Recurrence-

}l983

10/12 Conta'in-Hydrogen"Analy-During normal-None', redundant Hanufacturing:

Metal Bellows Corp..

Pump and motor;

~

deficiency pump and' motor' assembly assemblies'were-ment zer A & B.

operation, hy..

systems.were-Inerting drogenLanalyzer available and model MB601'HP, part) replaced with' 'up-- -

~

"A",wasersmoved operableL

1. 40523, serial:no.

graded assemblies.61 System 763 and?765...were de-No further recur '

~

from' service to termined toibe rence control is replace pump-assembly. Later inoperable.

planned.:

hydrogen analy-Ref5 MR A130688-zer "B".was removed to

~MR A142000I LER'BFRO'50-replace., pump

260/8306g assembly.=

.s 10/27 Radiation RM-90-256 During startupc None, Tech. Spec. An additional load Drywell-air sample.. Fuse.was replaced.

Monitoring operation, dry-3.6.C.2 permits.

was. plugged into system was. inoperable and. signs installed-well leak operation for an outlet. fed for approximately.

to restrict use'of.

?

detection.

seven days with from the.same' sixteen ~(16)) hours the' outlet. No radiation moni-air sampling source as the further/ recurrence tor.RM-90-256-system inoperabicmonitor, causing.

-control is' planned... 4 tj.

sample. pump the fuse to clear'

'MR A-132703-tO i

tripped.

MR A-1327Q4

.l MR A-132713-MR'A-732702

l

.i j

.... }

LER BFB0-50-260/

83031'Ti?l 1

1 r

'j i

'J

?

fBROWNS FERRY NUCLEAR' PLANT'UtdT 02 8

"e 30;

.m

'[

'CSSC FQUIPMENT.

ELECTRICAL 1 MAINTENANCE

SUMMARY

9/29/82 4#

~

For the Month of,0ctober' 19 E 83 ~

~

. Action Taken.

.Effect on Safe

. Nature'of

. Operation ofL

. lCause of-Results'of'

To Preclude:

Date-System

' Component Maintenance'

-The Reactor' Malfunction Malfunctio'n Recurr'encel 1983--

1 10/11 Diesel.

Diesel Genera-During normal-None, redundant.

Transformeri Diesel _ ge'neratorL IC '

Transformer was.

Generator tor 1C operation, systems were TFR10-failedi was declared inopera-replaced:and'the l

operator ob-available and bl'effor.eleveni(ll) diesel-generator was I

served diesel operable hours-returned;to service. ;1 This'is considered a generator 1C random failure and; trouble alarm-no-recurrence con-H trol _is~ required.-

t-MR A1429d3-LER BkRO-50-260/

83058-e j

sr 10/12 Diesel Diesel Genera-During normal None, Tech. Spec. Two possibilities: Dieseligenerator-1A Cause cannot' be 'de '

Generator tor lA operation, while 3.9.B.3 allows (1) overspeed trip was inoperable.for termined; therefore,-

performing :

continued _ opera-latch inadequately four-(4) hours.

nol recurrence SI.4.9.A.4.b

., tion for-.seven reset;.(2) fuel control,is. required..

undervoltage

. days with one injector lever start of diesel diesel generator set too high.'Can-LVR BFRO-50-260/-

generator, dies- -inoperable. All not determine if

=83057 ;

el' generator-other require-overspeed was a lA ovesped and

.ments of result of this

.j' tripped.

.T.S 3.9.B.3 i..

were met..

1

.[

l

1. 'l i

1 I

BROWNS, FERRY NUCLEAR PLANT 1. TIT 2

F SIL 30 Appendix B CSSC EQUIPMENT ELECTRICAL MAINTENANCE SOD'.ARY 9/29/82 For the Month of October 19 83 Effect on Safe Action Taken Nature of Operation of

. Cause of Results of To Preclude

'a t e System Component Maintenance The Reactor Malfunction Malfunctio'n Recurrence 1983 9/29 Radwaste Drywell equip-During normal None. The equip - The Cycl-flex 60 The sump fill timer The timer was re-ment drain operation, the ment drain sump minute timer, wa,s inoperable for placed and cali-sump pump drywell equip-pumps, pump out type HPS6A6, 50 minutes brated. This is ment drain timer, discharge failed and would considered a random sump pump "Ex-flow measure-not reset due failure; therefore,

cessive Operatic n" ment equip-to a stuck timer no recurrence con-l annunciation ment, and dry-contact trol is required.

=

was discovered well air to be alarming sampling system '

BFRO-50-260/83059 were still ope'rable,

,w T

10/1 Residual 10 AK-108A Replace relay.

None Eurned coil Relay failed 10AK-108A of Unit 2 was replaced-Heat Panel 9-32 10AK-108A by 10AK-108B of f

Removal Unit 1.

MR A-142996 MR A-142997 MR A-205071 10/6 CO2 Storagc, Fire Panel Replace "EE" None Two defective Trouble alarm would Replaced "EE" Fire Pro-2-25-313 control circuit zone circuit not work on Fire control circuit &

tection &

board and two boards Panel 2-25-313 two zone circuit boards.

Purging zone circuit boards MR A-141120 MR A-205078 MR A-212118

=

l t

o k

L l,

Page 3 i

5 BR0tlNS. FERRY NUCLEAR PLANT CUT - 1 and Common BF EMSIL~30 Appendix B Y

ELECTRICAL MAINTENANCE SDStARY CSSC EQUIPMENT 9/29/82 h

For the Month of October 19 83 2

^

Action Taken Effect on Safe Nature of Operation of Cause of Results of To Preclude Date Systen Component Maintenance The Reactor Malfunction Malfunction Recurrence m

1983 10/17 Residual Relay 10AK-Clean relay con-None Tape on inside Contacts would not Cleaned relay con-f Heat 108A tacts and cover of cover heated make up tacts and cover as needed Removal as needed, up causing residuc 3

on contact and MR A-210414 glass l

l 5

I

~

1 w

j M

c.

g

=W

=

~

1 Ir m.

.j

-v-j I

l t

I l

+

m p 8

... BROLNS. FERRY NUCLEAR PLANT UNIT 1'& Common' Appendix"5

-CSSC EQUIPMENT'

. ELECTRICAL-MAINTENANCE

SUMMARY

9/29/82 For-the Month of october 19:83'

~

'Effect en Safe

Action Taken-Nature of'

.Operaticn of.

Cause'of-

~Results.of

.To! Preclude

-3 ate System Component Maintenance The. Reactor Malfunction Halfunctio'n Recurrence

1983

.E

'ld/4 4 KV Shut-480V Shutdown R'eplace. latch

'None Defective' materia:

~ Relay inoperable

Replaced latch' down Board Board "B" nor-mechanism on' mechanism

&'. Buses mal. lockout lockout relay' MR A-212187 relay

,g i

10/5 Control HS-85-56 Replace hand Replaced hand

!{

None' Defective-Hand switch 85-56 Rod Drive switch switch-eM

%dh 85-56 MR A-138317 i-l 11S-85-47 Replace switch None' Broken stop Hand switch 85-47 Replaced stop. T

.1-10/9 Control stop' plate on plate passes stops plate on hand.

Rod Drive-hand switch switch MR A-211024 4

v 10/9 Control HS-85-48--

Replace switch-None-Broken stop HS-85-48 passes.

Replaced stop. plate Rod Drive stop plate on plate-stops on HS-85-48 hand switch -

I, 85-48 MR -211025 10/16 Standby 9-23-7 Replace meter None Relay coil Annunciation would Replaced relay.and Diesel relay control-burned out not clear on IB annunciation unit Diesel Generator-cleared.

MR A-219199 MR A' 214060

MECHANICAL MAINTE!nNCE

SUMMARY

Common CSSC EOUIPMENT For the Month of October 19 83 ACTION TAKEN EFFECT ON SAFE DATE SYSTEM COMPONENT NATURE OF OPERATION OF CAUSE OF' RESULTS OF TO PRECLUDE MAINTENANCE THE REACTOR MALFUNCTION' MALFUNCT10N RECURRENCE cleaned cap and cap normal wear leaking none surface 10-03 Fire Diesel Fire pressure cap I

Protection Pump on coolant reservoir won't fit snugly no work performed per unknown leak R. Hunkapiller (Ops.)

10-07 Check check valve valve is leak-none ing Valve System 67 inspection per MMI-84 no malfunction none 10-9 26 diesel-driven inspection none fire pump change in air air leaking thru adjusted 10-13 260 doors 485, 298 closer adjust-none flow ment h

normal operation causing constant fixed latch y

10-13 260 door 463 latch is none door open defects sticking installed new gasket normal operation leaking thru 10-14 23 "B" RHRSW pump coupling leak none normal operation leaking adjusted packing 10-22 23 "Cl" RHRSW pump packing leak none normal operation leaking adjusted packing 10-22 23 "C2" RHRSW pump packing leak none normal operation leaking adjusted packing 10-22 23 "Bl" RHRSW pump packing leak none normal operation leaking replaced packing 10-22 23 "C3" RHRSW pump packing 3cak none normal operation leaking replaced packing 10-22 23 "C" RHRSW packing leak none strained 4

MECHANICAL MAINTENANCE

SUMMARY

,. Unit l '-

CSSC EOUIPMENT For the Month'of. October 19 83-EFFECT ON SAFE ACTION TAKEN DATE SYSTEM COMPONENT-NATURE OF OPERATION OF CAUSE OF RESULTS OF-TO PRECLUDE MAINTENANCE THE REACTOR MALFUNCTION MALFUNCTION RECURRENCE 10-01 74 RHR HTX 1B machine 12. plugs

~none normal operation unknown built plug, 10-04 82 D/G air com-change head none normal operation head was leaking changed gasket-l pressor gasket

?

'l unknown

'nir starter engaged. replaced solenoid valvi 10-5 82 "C" D/G trouble-shoot none while engine was running 10-06 82 "1B" D/G check air none normal operation starters would not replaced starter motor starters spin motor 10-06 85 "1A" pump suc-replace strainc e none normal operation high AP changed filters, tion strainer g

i 10-07 85 CRD scram dis-remove blind none normal operation unknown removed blind finnges charge system' flanges and replaced them 10-12 82 "1A" D/G exchange ther-none normal operation unknown replaced the valves mostatic valves 10-12 74 RHR torus replaced spray none personnel error abnormal spray replaced nozzles-spray nozzles pattern 10-13 82 "lC" D/G disassemble, none normal operation unknown replaced starter anti clean & repair all valves air start motor 10-13 82 "lB" D/G disacsemble, none normal operation unknown cleaned and replaced clean and starter l

replace air start motor 10-13 82 1"D" D/G disassemble, none normal operation unknown cleaned and replaced clean and valves and solenoid replace air start motor

MECHANICAL MAINTENANCE

SUMMARY

Unit 1 (Continutd)

CSSC EQUIPMENT For the Month of, - October-

'19 83 EFFECT ON SAFE ACTION TAKEN DATE SYSTEM COMPONENT NATURE OF OPERATION OF CAUSE OF RESULTS OF

10 PRECLUDE i

MAINTENANCE

'IEE REACTOR MALFUNCTION MALFUNCTION I

RECURRENCE l

10-13 PSC pump fabricate none normal operation unknown

-fabricated coupling coupling l

10-13 67 check valve visually none-none none visually inspected l

649,542,648,65]

inspect 656,584,515,585 507,514,521,63]

529,635,627,62E 624,625,522,63C 528,508,634,54]

10-14 85 control rod check &

none normal operation unknown changed vhlve insert needle replace needic valve valve if de-fective 4

e 10-14 85 control rod check &

'none normal operation unknown changed valve insert needle replace needit valve valve if defective

!10-18 63 SLC pump 1B repair oil none worn gasket oil leak replaced gasket leak' 1

10-22 85 CRD Hydraulic replace none left off by none replaced nut control unit missing lock operator nut 10-22 74 1A&C RHR room unplug flow none normal operation none inspected and removed-cooler orifice blockage

- + -

.m 4

MECHANICAL NAINTEUANCE

SUMMARY

2 CSSC EOUIPMENT i

For the Month of. October 19 83 i

ACTION TAKEN EFFECT ON SAFE-

~

DATE SYSTEM

COMPONENT NATURE OF

' OPERATION'OF CAUSE OF '

RESULTS OF

.10 PRECLUDE MAINTENANCE THE REACTOR MALFUNCTION MALFUNCTION RECURRENCE visually. inspect-10-02 74 LPCI MG. set,2Et visual L nspec-none.

none none i

tion l

visually inspect 10-02 74 LPCI MG' set

. visual inspee-none none none-2DA tion visually inspect-10-02 74 LPCI MG set visual. inspec-none none-none 2EA cion

'nonc visually inspect 10-02 74 LPCI MG. set visual inspec-none none 2DN tion normal operation won't work replaced dragon bloc 10-06 001 PDIS'l-13C valve won't none valve operate removed test pressur 10-12 73 HPCI booster remove gage none none none b

gage i

Pump bad filters unknown

. replaced filters 10-19 30 CRD rebuild replace filte-- none room exhaust fan HEPA filte r e

4 i

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... FIELD SERVICES

SUMMARY

October 1983 Maior Work Areas A.

Refuel Floor - On October 1 the' core unload of unit 3 had been only two days in progress and was completed on' October 12' with blade guides loaned from Peach Bottom. Following unit 3 core unload, the core reload for unit

-1 was scheduled but could not be started because several major work items were incomplete; instead local power range monitor (LPRM) changeout on unit 3 was started and completed on October 17 and preparations for unit 3 control blade changeout was started, while attempts to retrieve a lost

" bulb" from. reactor pressure vessel (RPV) was in progress. On October 26 the first of 12 control blades was changed out, but equipment problems prevented any further change out..On October 28, all refuel floor activities were shifted from unit 3--to unit 1 to prepare for core reload.

B.

Turbine

. All unit 1 turbine work was completed this month. The couplings were completed on October 4, started the oil flush on October 8 and completed the flush on October 18. Upon completion of the oil flush, the generator air test preparations were started and the air test was completed on October 26.

The unit 3 turbine work continued during October. The low-presourc "c" turbine was disassembled and sandblasting started on the upper diaphragms.

. FIELD SERVICES

SUMMARY

October 1983 f

. B.

' Turbine (Continued)

All work on the unit 3 main-stop valves cod bypass valves was completed in October.. This released the main steam isolation valves (MSIV's) for maintenance.:

Completed disassembly of the unit 3 reactor feed pump turbine "A".

The jw diaphragus and spindle are ready for sandblasting.

The maintenance work required on the unit 3 reactor feed pump "C" was completed in October and reassembly of the pump is now in progress.

C.

Other Mechanical Work -

1.-

At the beginning of October it was determined that the Emergency Equipment Cooling Water (EECW) piping to Residual Heat Removal (RHR) pump seal heat exchangers and RHR room coolers requires replacing on RHR loop I and II.'

Preparations started immediately and by the end of the month, loop.II was completed and on loop I only the cross-over piping was replaced, since the remaining system had to stay

, operational.

2.

- RHR heat exchanger work and tube cleaning was carried over into October, probolog of all tubes and tube plugging from top and bottom was completed on RHR loop II on Oct iter 7 i-

3.,,* Installed all Main Steam Release Valves (MSRV's) and 12 MSRY vacuum y

s.,

. breakers, lacking insulatit s and electrical to complete MSRV's.

t

-~

. FIELD SERVICES

SUMMARY

October 1983 V

C.

(Continued) 4.

Welding Scryices cut out a section of piping at oore spray weld DCS 2 and field services replaced piping, completed welding and x-ray; weld repair is in progress.

5 Welding Services completed the last overlay on recirculation weld KR-1-3 on October 25 and on RWCU-1-1 A on October 27 followed by grinding on weld and ultraviolet test. All overlay weld interferences were put back into its original oonfiguration.

6.

With the last of torus vacuum breakers repaired on October 19, all torus modifications were completed and divers called in for final inspection.

7 Completed the last attached piping support on Outrber 13 8.

Completed all MSIV's except electrical book up.

9 Control Rod Drive (CRD) Scram Discharge Instrument Volume (SDIV) modification P0392 - During October the F0392 modification instrument checkout was completed to support the post-modification testing.

The post-modification testing was completed on October 11 and CRD rod stroking required five CRD's to be changed out and this was L

accomplished October 23 Af ter the completion of rod change-out the' system was declared operable for fuel loading.

D.

Electrical / Instrumentation - During October all the electrical and instru-mentation work that was required to support fus:

...ing was completed including work plan close-out for. the modifications required for fuel load.

5

,. -. +. _ _ _,.-

- ~.

!~

FIELD SERVICES SUlstARY October 1983 D.

(Continued)

The major work performed to support unit 1 fuel. load was as follows:

1.

Completed reinstalling all cable trays and junction boxes that had been removed to support the overlay welding in the drywell.

2.

Completed the reroute of conduit 1R1674 and associated cables to panel 25-59 (RHR system Po673.)

3 Completed installation of the drywell wide-range pressure monitors and associated sensing lines (Po322.) Some rework is required on the sensing line hanger portion of the modification and it will be accomplished af ter fuel loading is completed.

4.

Completed installation of the torus wide-range level transmitters (P0323.)

5.

Completed installation of the torus temperature monitoring system (P0533) portion required for fuel load. The sequential events recorder ' portion of the modification is still in work and will complete prior to startup.

6.

Supported work on P0126 analog trip. The portion of this modification required for fuel loading was completed.

Other Electrical / Instrumentation:

1.

Completed the recirculation motor / generator set holder modification.

The schedule for tunning recirculation pump motors A and B is now November. This schedule delay is due to weld repairs that had to be made to the RWCU systems.

-\\

T' NNESSEE VALLEY AUTHORITY '

//[ I [ O Browns Ferry Nuclear Plant P. O. Box 2000 Decatur, Alabama 35602-k

.Nuoloar Regulatory Commission Office of Management Information and Program Control

-Washington, DC

.20555 Gentlemen:

Enclosed is the Cotober 1983 Monthly Operating Report to NRC for Browns Ferry Nuclear Plant Units 1, 2, and 3 Very.truly yours, TENNESSEE VALLEY AUTHORITY

.a

.f G. T Jones Pow Plant Superintendent g

Enclosures-00 :. Director, Region II INPO Records Center Nuclear Regulatory Commission Institute of Nuclear Power

-Office of Inspection ano Enforoenent.

Suite 1500 101 Marietta Street 1100 Circle 75 Parkway

~ Atlanta, GA 30303 (1 copy)

Atlanta, GA 30389 Director, Office of Inspection and Enforoenent Nuclear Regulatory Commission Washington, D. C.

20555 (10 copies)

Mr. A. Rubio, Diceotor Electric Power Research Institute P. 0. Box 10412

[

Palc Alto, CA 94304 An Equal Opportunity Employer

_... ~ _ _ _ _..