ML20078K675

Monthly Operating Repts for Aug 1983

ML20078K675
Person / Time
Site:	Browns Ferry
Issue date:	09/01/1983
From:	Jones G, Thom T TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8310190186
Download: ML20078K675 (40)

Text

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L5 2 830909 841 TENNESSEE VALLEY AUTHORITY DIVISION OF NUCLEAR POWER BROWNS FERRY NUCLEAR PLANT MONTHLY OPERATING REPORT TO NRC August 1, 1983 - August 31, 1983 DOCKET NUMBERS 50-259, 50-260, AND 50-296 LICENSE NUMBERS DPR-33, DPR-52, AND DPR-68 i

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TABLE OF CONTENTS Operations Summary....

1 Refueling Information....................

3 Significant Operational Instructions..

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

10 Operating Data Reports....

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

16 Plant Maintenance......................

19 Field Services Summary.....

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1 Operations Summary August 1983 The following summary describes the significant operation activities during the reporting period.

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

There were 24 reportable occurrences and three revisions to previous report-able occurrences reported to the NRC during the month of August.

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

Unit 2

'1-There were no scrams on the unit during the month.

Unit 9 There were no scrams on the unit during the month.

Principally prepared by B. L. Porter.

2 Operations Summary (Continued)

August 1983 Fatigue Usage Evaluation The cumulative usage factors for the reactor vessel are as follows:

Location Usane Factor Unit 1 Unit 2 Unit 1 Shell at water line 0.00583 0.00465 0.00401 Feedwater nozzle 0.28294 0.19836 0.15240 Closure studs 0.22349 0.16837 0.12905 NOTE:

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

Common System Approximately 4.67E+05 gallons of was$ ~ liquids were discharged containing approximately 1.63E-01 curies of activities.

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Operations Summarv (Continued)

August 1983 Refteline 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 TMI-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 EOC-5 fuel assem-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 locations.

Unit 2

~~

Unit 2 is scheduled for its fifth refueling beginning on or about June 8, 1984 with a scheduled restart date of November 8, 1984. This refueling outage will involve loading additional 8X8R (retrofit) fuel assemblies into the core, finishing the torus modification, turbine inspection, finishing inspection, finishing THI-2 modifications; post-accident sampling facility tie-ins, core spray change-out, and feedwater sparger inspection.

There are 764 fuel assemblies in the reactor vessel.

At the end of the month there were 248 EOC-4 fuel assemblies, 353 EOC-3 fuel assemblies. 156 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.

~..

4 Operations Summar'v (Continued)

August 1983 Unit 9 Unit 3 is scheduled for it.a fifth refueling on or about September 7, 1983, with a scheduled restart date of May 4, 1984.

This refueling will involve 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 764 fuel assemblies presently in the reactor vessel. There are 280 EOC-4 fuel assemblies, 124 E0C-3 fuel assemblies, 144 EOC-2 fuel assem-blies, and 208 EOC-1 ' fuel assemblies in the spent fuel storage pool.

The present available capacity of the spent fuel pool is 993 locations.

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5 Significant Ooerational Events Date Time Event 1

Unit 1 8/01 0001 End-of-cycle 5 refuel outage continues.

8/31 2400 End-of-cycle 5 refuel outage continues.

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6 Sinnificant Ooerational Events Date Time Event Unit 2 8/01 0001 Reactor thermal power at 94-percent CMFLPD limited.

0200 Commenced PCIOMR from 94-percent thermal power.

0300 Reactor thermal power at 95-percent, PCIOMR stopped, limited by CHFLPD.

0400 Reactor thermal power at 95-percent, limited by CMFLPD.

0700 Commenced PCIOMR from 96-percent thermal power.

0955 Commenced reducing thermal power from 98-percent CHFLPD limited.

1900 Reactor thermal power at 95-percent, CMFLPD limited.

2400 Reactor thermal power at 96-percent, CMFLPD limited.

8/02 1900 Reactor thermal power at 95-percent, CMFLPD limited.

2200 Reactor thermal power at 96-percent, CMFLPD limited.

8/04 1830 Reduced thermal power to 95-percent, CMFLPD limited.

8/06 0200 Reactor thermal power at 94-percent, CMFLPD limited.

2100 Commenced reducing thermal power for control rod pattern adjustment.

~2130 Reactor thermal power at 70-percent for control rod pattern adjustment, d,ecreasing thermal power.

8/07 0100 Reactor thermal power at 66-percent, rod pattern adjustment in progress, increasing thermal power.

0155 Control rod pattern adjustment complete, reactor power at 76-percent, holding for turbine control valve test

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and SI's.

0400 Turbine control valve test and "I's complete, commenced power ascension.

0700 Commenced PCIOMR from 91-percent thermal power.

1010 Stopped PCIOMR at 96-percent due to CMFLPD limits, reducing thermal power.

1630 Commenced PCIOMR from 94-percent thermal power.

1700 Reactor thermal power at 96-percent, CMFLPD limited.

2100 Reactor thermal power at 95-percent, CMFLPD limited.

8/08 0300 Commenced PCIOMR from 95-percent power.

0500 Reactor power at 96-percent, CMFLPD limited.

8/09 1343 withdrawing four control rods for SI 4 3.B.1.a (Control Rod Coupling Integrity.)

1400 Reactor power at 97-percent, increasing thermal power.

1700 Reactor thermal power at 98-percent, CMFLPD limited.

2000 Reactor thermal power at 97-percent, CMFLPD limited.

7 Significant Ooerstional Events Date Time Event Unit 2 (Continued) 8/13 0135 Commenced reducing thermal power for turbine control valve test and SI's.

0155 Reactor thermal power at 83-percent for turbine control valve test and SI's.

0355 Turbine control valve test and SI's complete, commenced power ascension.

1700 Reactor thermal power at 97-percent, CMFLPD limited.

8/20 0030 Commenced reducing thermal power for turbine control valve test and SI's.

0200 Reactor thermal power at 88-percent for turbine control valve teat and SI's.

0250 Turbine control valve test and SI's complete, commenced power ascension.

0318 Reactor thermal power at 97-percent, CMFLPD limited.

0648 Reduced thermal power to 96-percent, CMFLPD limited.

8/22 1500 Reactor thermal power at 97-percent, CHFLPD limited.

8/24 0950 Commenced reducing thermal power due to high Delta P across condensate demineralizer, 1100 Reactor thermalupower.at 95-percent due to high Delta P across condensate demineralizer.

1210 Commenced reducing thermal power for repair of EHC leak on #1 control valve.

1300 Reactor power at 94-percent for repair of #1 control valve.

1330 Control valve #1 repaired, commenced power ascension.

1400 Reactor thermal power at 97-percent, CMFLPD limited.

8/28 0100 Commenced reducing thermal power for turbine control valve test and SI's.

0200 Reactor power at 92-percent for turbine control valve test and SI's.

0230 Turbine control valve test and SI's complete, commenced power ascension.

0300 Reactor thermal power at 97-percent, CMFLPD limited.

8/30 1151 Commenced reducing thermal power due to low-vacuum half scram.

1200 Reactor thermal power at 75-percent due to low-vacuum scram.

1212 Commenced power ascension from 75-percent power.

1330 Reactor thermal power at 97-percent, CHFLPD limited.

8/31 2400 Reactor thermal power at 97-percent, CMFLPD limited.

8 Sianificant Ooerational Events Date Time Event Unit 3 8/01 0001 Reactor thermal power at 97%, maximum flow, end-of-cycle 5 coastdown.

0058 Reduced thermal power to 96-percent-to insert control rod 54-47 to "00" for accumulator inspection.

0210 Reduced thermal power to 95-percent to withdraw control rod 54-47 0220 Control rod 54-47 withdrawn, commenced power ascension.

0300 Reactor thermal power at 97-percent, maximum flow, end-of-cycle 5 coastdown.

l 8/03 2000 Reactor thermal power at 96-percent, maximum flow, end-of-cycle 5 coastdown.

8/ 06 0120 Reduced thermal power to 90-percent for turbine control valve test and SI's.

0220 Turbine control valve test and SI's completed, commenced power ascension.

0230 Reactor thermal power at 96-percent, maximum flow, end-of-cycle 5 coastdown.

1500 Reactor thermal p6wer at 95-percent, maximum flow, end-of-cycle 5 coastdown.

8/09 1800 Reactor thermal power at 94-percent, maximum flow, end-of-cycle 5 coastdown.

8/12 2300 Reactor thermal power at 93-percent, maximum flew, end-of-cycle 5 coastdown.

~~

8/16 1200 Reactor thermal power at 92-percent, maximum flow, end-of-cycle 5 coastdown.

8/19 2000 Reactor thermal power at 91-percent, maximum flow, end-of-cycle 5 coastdown.

l 8/23 0700 Reactor thermal power at 90-percent, maximum flow, end-of-cycle 5 coastdown.

i 8/27 0700 Reactor thermal power at 89-percent, maximum flow, end-of-cycle 5 coastdown.

9 Significant Operational Events Date Time Event Unit 3 (Continued) 8/28 0140 Commenced reducing thermal power for SI 4 3. A.2 (Control Rod Exercise,) SI 4 3.B.1.a (Control Rod Coupling Integrity Check,) and TI-20 (CRD System Testing.)

0600 Reactor thermal power at 75-percent for CRD SI's 4 3.A.2 and 4.3.B.1.a and TI-20.

0700 Reactor thermal power at 76-percent for CRD tests.

1345 CRD testing complete, commenced power ascension.

1700 Reactor thermal power at 91-percent, maximum flow, end-of-cycle 5 coastdown.

8/29 0700 Reactor thermal power at 90-percent, maximum flow, end-of cycle 5 coastdown.

1500 Reactor thermal power at 89-percent, maaximum flow, end-of-cycle 5 coastdown.

8/30 0700 Reactor thermal power at 80-percent, maximum flow, end-of-cycle 5 coastdown.

8/31 2400 Reactor thermal power at 88-percent, maximum flow, end-of-cycle 5 coastdown.

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. AVERAGE D AILY UNIT POWER LEVEL DOCKET NO.

50-259 UNIT Browns Ferry-1.

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9-1-83 DATE

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COMPLETED BY 205/729-0834 TELEPHONE MONTH August DAY AVERAGE DAILY POWER LLVEL DAY AVER AGE DAILY POWER LFVEL

IMWe-Net) slwe. Net i 1

-2 17

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13 3

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4 20

-2 5

-2

-2 21 6

-2

-2 22

-2

-2 7-

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-2 3

-3 24

-3 9

25

-2 10

-2

-2 26 II

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-2 27

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29 14

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-2 16 INSTRUCTIONS

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(9 '77 )

I1 AVER AGE DAILY UNIT P0hER I.EVEL DOCKET NO. 50-260 UNIT Browns Ferry-2 DATE COMPLETED BY T. Thom 205/729-0834 TELEPHONE MONili August DAY AVERAGE D IL VER LEVEL DAY g AVER AGE DAILY POWER LEVEL (MWe Net)

I 1000 ' * * -

!7 1014 997 33 1012 1014 3

1005 1002 4

0 20 5

999 21 1008 955 6

1008 944 7

1011

,3 1009 g

1011 27 9

1018 25 1018 to 1016 26 1019 ii 1014 1019

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27 12 1040 3

992 13 999 29 1023 1018 14 1020 39 15 1012 31 1016 16 1020 INSTR UCTIONS

)n this format. list the aserage daily unit poveer lesel in MWe. Net for each day in the,eporting mimth Cornpute

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19/77)

12 AVERAGE D AILY UNIT POWER LEVEL DOCKETNO. 50-296 UNIT Browns Ferry-3 DATE 9-1-83 COMPLETED By T. Thom 205/729-0834 TELEPHONE MONTH August DAY AVERAGE DAILIPOWER LEVEL DAY AVERAGE DAILY POWER LEVEL

-(MWe Net)

(Mwe-Nes )

990 17 941 1054 3

931

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,3 960 3

912 19 4

979 877 0

974 5

921 23 963 6

7 970 23 913 8

963 24 912 957 9

907 25 10 948 26 907 11 951 27

_ 901 950 12 851 23 83 948 29 913 14 943

.t o 905 938 15 884 3r lo 927 INSTRUCTIONS Oa thn format, list the aserage daily anit powu lesel m MWe-Net toi cach day in the reporting month.Gunpute to the nearest whnle megawatt.

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13 OPERATING bATA REPORT DOCKET NO. 50-259 DATE 9-1-83 COMPLETED BY T. Thon T ELEl'Il0NE 205/729-0834 OPERATING STATUS

1. bnit Nase - Browns perry - 1 Notes

2. Reporting Period: August 1983

3. Licensed Tidrmal Power (MWt):

3293

4. Nameplate Rating (Gross MWe):

1152

5. Design Electrical Rating (Net MWel: 1065

6. Masirnum Dependable Capa' city (Gross MWel: 1098.4

7. Matirturm Dependable Capdeity (Nei MWe):

1065

8. If Changes Occur in Capacity Ratings (Items Number 3 Throi gh 71 Since Last Report. Giie Reasons:

N/A

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

N/A

10. licasons For Restrictions. lf Any:

N/A ThiQfonth Yr..to.Ilate Obmulative

11. IIobrs In Reporting Period 744 5.831 79.633

12. Npinber OfIlours Rea'etor Was Critical 0

2,363.25 49,752.79

13. Reactor Ret.erve Shtitdown flours 0

47.71 5,785.02

,14. po' rs Generator On.Line 0

2.317.52 48.717.64

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15. Uitit Reserve Shutdown flours 0

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16. Gross Thermal Energy Generated (MWill 0

6.784,675 138.557.679

17. Gnm Electrical Energy Generated (MWill 0

2,244,900 45,645.620 lb. N.el Electrical Energy Generated (MWil) 0 2.175.548 44.325.327

19. Unli Senice Factor 0

39.7 61.3

20. Urst Asailability factor 0

39.7 61.3

21. Unit Capacity Factor (Using MI)C Net 1 0

_35.0

_52.3 2.}. Unit Capacity FactorIUsing DER Net) 0 35.0 52.3

23. Unit Forced Outage Rate 0

8.1 23.8

24. Shutdowm Scheduh d Oser Next 6 Months t I,spe. Date.and !) oration of I ach t-

25. If Shut Down At Fnd Of Report Period. Intimated Date of Startup.

November 1, 1983

26. L' nits in lot Status (Prior to Commercial Operationt I'm ecast dchiesed INill \\ L CRillCAl.11 Y INITI Al. FLFCI RICITY COMMERCl \\ L OPI'R \\11rW (n!77 )

14 OPERdTING IbTA REPORT DOCKET NO. 50-260 DATE 9-1-83 1

'.i..i COMPLETED BY T. Thom

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,"4 F:_i[,' i TELEPil0NE 205/729-0834

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i. Repdllrlhriod:

August 1983

5. Licelised TiitimaiPoOr(blW1): ;32"3

4. NamiplikRitliid/GrEd MWeh 1152

$. Desi)'n Electilcal:Rdtidj(NN hlWe): - 1065

6. Maximant IJehiidable Capicity (Gross MWe): 1098.4

7. Maximum [)ependabie tapacitylNet.\\iwe):

1065

8. If Changes Occd ili Cai acity Ratings litems Number 3 Through 71 Since Last Repert. Giie Reasons-i N/A

9. Power i.evel Tri khich flestricted. If Any (Net MWe):

N/A

10. Reasons For Restrictions. lf Arty:

N/A This 11onth Yr..to Date Cumulative I1. Hoints in Reporting Period 744 5,831 74,574

12. Number Of flours ReIctor Was Critical 744

_3,854.57 47,148.04

13. Reacto,'r Reserve Shutdown flours 0

102.68 13,787.50

14. Ilours Gencralor On-Line 744 3,736.78

_45,712.23

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15. Unit Reseive Shutdown Ilours 0

,0 0

16. Gross Thermal Energy Generated (MWli) 2,347,229 11,067,089 31,476,936 _

17. Gross Electrical Energy Generated (Mwill 773u510 3.683.640_

43.708.548

18. Net Electrical Energy Generated (MWH) 748,518 3,574,712 42,447,787

19. Unit Service Factor 100.0 64.1 61.3

20. Unit Availability Factor 100.0 64.1 61.3 94.5 57.6 53.4

21. Unit Capacity Factor (Using MDC Net) 21 Unit Capacity Factor (Using DER Net) 94.5 S. 6

.53.4

23. Unit I-orced Outage Rate 0

5.6 25.7

24. Shutdowns Scheduled Over Nest 6 Months IType. Date, and. Duration of Fach t

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

26 Units in Test Status (Prior to Commercial Operation L Forecast Achies eil INITIA L CRillCAI 11 Y INIII A L El.ECTRICII Y

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COMMERCI \\l. OPER A flON 01/77)

15 OPERATING DATA REPORT

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DOCKET NO.

50-296 DATE 9-1-83

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Thom

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TELEPilONE - ?05/7?o-0834 dit ING S kbS k

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h. brit Notes 2.

Mherldd:, r' August 1983 <

Licedsid thermal Poker (

3293

d. Namphhich RailqgfG'd5,MWt):Sihd):.

1152.

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5. DeJgn ElectricalRutinil(Nel MWe); : 1065

6. Maxilhum Depenkl' ble Cap 5 city'(Grbss hlWe):

1098.4 d

i. Naxiriibht beperfilable Ca' acity (Net SIWE):

1065 p

8. If Changes Occur in Capacity Ratings (Items Number 3 Thro' gli t) Since Last Report. Gi'e Ikeasons:

u N/A

9. Power Level To WhIchikestricted, N Any (Net 3 thel:N/A

10. Reashns For Restrictioits. If Any:

N/A

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This 31onth Yr. to Date Cumularise p

I i. Ilours Id Re'p'ortInh Period 744 5.831 56.999

12. Number Of Hours ReIctor Was Criti.:al 744 5,325.02 42,937.3

13. Ikenetor Resene Shu' tdo' wr. Hours 0

505.98 3,878.13

14. Hoiiss Generator On Line 744 5,273.03 42,047.09

'!5. Uitit Resene Shutdown llour, 0

. O 0

16. Gross Thermal Energy Generated ($1Will

_2 255,978 16,564,790 125,900,894 t

17 Gross Electrical Energy Generated (51Wil) 721,850 5,426,510 41,466,300

18. Net Electrical Energy Generated (5 twill 696,413 5,272,338 40,253,242

19. l[ nit Senice Factor 100.0 90.4 73.8

-20. Unit Availability Factor 100.0 90.4 73.8

21. Unit Capacity haetor IUsing.\\tDC Net)

_87.9 84.9 66.3 87.9 84.9 66.3

22. Unit Capacity Factor (Using DER Neti 0

9.6 16.5

23. Unit Forced Outage Rate

24. Shutdowns Scheduled Oser Nest 6 Stonths (i3 pe'. Date.and Duration of Exhl:

Refuel _0utage. Sep_Lember 6. 1983

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

26. Units in Test Status (Prior to Commercial Operation).

I orecast Achiesed INITI \\I. CRIIICA LII Y INITI \\ I. Lt.ECTRirl TY

' CO\\1%II:RCI \\ L Ol'l-:R A IlON (9/77)

UNIT SIIUTl) OWNS AND POWER REDUCTIONS DOCKET NO, 50-259 UNIT NAME Browns Ferrv-1 DATE 9-1-83 T*

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REPORT MONTil August COMPLETED BY TELEPHONE 205/729-0834 j

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4 $5 Licensee

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Cause & Correttive No.

Date i

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264 8/1/83 S

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4 EOC-5 Refuel Outage Continues f'

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F: Forced Reason:

Method:

Exhibit G - Instructions l

S: Scheduled

-A. Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance of Test 2 Manual Scram.

Entr> Sheets for Licensee i

C Refueling 3 Automatic Scram.

Event Report (LER) File (NURI.G-D Re;ulatory Restriction 4.Other (Explain) 0161)

E rator Training & License Examination F no:ninistrative S

G-Operational Error (Explain)

Exhibii 1 Same Source (9/77) li-Other ( E xplain) k lq

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!! NIT SifUTI> OWNS AND POWER REDUC 110NS DOCKET NO. 50-260 UNIT NAME Browns Ferry - 2 DATE 9-l-83 REPORT MONTil August COMPLETED HY T. Thom TELEPHONE 205/729-0834 "i-

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267 8/6/83 S

H Derated for control rod pattern ad-justment.

268 8/30/83 F

H One-half scram due to low vacuum.

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F: Forced Reason:

Method:

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

[1 Maintenance of Test 2-Manual Scram.

Entry Sheets for Licensee C Refueling 3 Automatic Scrain.

Esent Report (l.I'R) File t NUREG-D Regulatory Restriction 4 Other (Explain) 01611 E Operator Training & License Examination F Administrati.e 5

G-Operational Error (Explain)

(9/77)

Il-Other ( E xplain)

Exhibit I Same Source

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UNIT SilOTDOWNS'AND POWER REDUCTIONS DOCKET NO. 50-296 UNIT N AME Browns Ferry - 3 DATE 9-1-83 REPORT MONTil August COMPLETED BY T.

Thom TELEPHONE 20s/774-nR14 n.

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F: l'orced Reason.

Method:

Exhibit G -Instructions S Scheduled A-1:quipment Failure (E splaint I Manual for Prtparation of Data 4

13 Maintenance of Test 2-Manual Serarn.

Entry Sheets for Licensee C-Refuehng 3-Automatic Strain.

Event Report (LER) File INUREG-D Reputatory Restri. tion 4 Other iExplain) 0161) l' Operator Training & lisense I sasuination F AJnunistratr.e 3

G. Operational Esion t E splaial Exhibit I Same Sourse 19/77)

Il-Ot her ( E splain )

_BROM:S FERRY-NUCLEAR Pl. ANT UNIT 1 and common "8

F EMSIL.30 CSSC FOUIPMENT ELECTRICAL MAI.*TLNANCE SD: MARY

' Appendix B 9/29/82

' Fo r the Mon t h o f Au gus t,

19 83 Effect on Safe Action Taken ~] -

Nature of Operation of Cause of Results of:

To Proclude fate Systen Cenonent Maintenance The Reactor Malfunction Malfunction Recurrence

./11/83 RIIR LPCI time delay During the

None, The relays were The relays were The. relays were relay 10A-K34A performance of redundant systemofound out of found to operate immediately and 10A-K75B SI 4.2.B-45 were available calibration due outside of their recalibrated and relay 10A,-K34A and operable.

to setpoint allowable setpoints.

the SI successfully was found set a t dri f t.

completed. ~The 8.2 seconds and recurrence cont re relay 10A-K75B will consist of was found set at revising the S1 25.87 seconds as to specify opposed to the notifying shift

[

allowable set-engineer when point range 6 relays are found to 8 seconds an :1 out of tolerance 9(

and replacing thU '

18 to 24 second i.

s relays with Agastat timers by the end of the current re fueling outage.

LER// BFRO-50-259/

83050 i

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SROWNS FERRY NUCLEAR PLANT l' NIT I and common

1. E[MS11 F

, 30 CSSC EQUIPMENT ELECTRICAL MAINTENANCE SUIStARY Appendix B 9/29/82-For the Month of Annust, 19 83 Effect on Safe Action Taken

~

Nature of Operation of Cause of Results of To Preclude ate Systen Cenonent Maintenance The Reactor Malfunction Malfunction Recurrence

/26/8 Reactor RBCC11 Pump IB Excessive None Motor bearings Excessive vibration Replaced motor Building vibration -

bearings - lubricate '

Closed check lugs and motor per EMI-83 Cooling grease MR# A-147958 tJate r

• 26/83 Standby

. Standby Cas-During a routine None, redundant A type tiled Standby Cas-Treatment The breaker was Cas-Treatment Trair inspection, NRC systems were 136090 CE molded train "B" was inspected, reset, Treatment "B".

inspectors noted available and case breaker inoperable beaterstested,andl relative humidity standby gas ope rab l e.

tripped.

treatment train proper current "B" was ve ri fied.

y in perable.

q[

LER# BFRO-50-259/

\\

83046

?

SIR # A-142103 28/83 Reactor IB RPS MG set Motor generator None, unit in Bad voltage RPS MG set IB The voltage regulator Protection volt age output voltage refueling outage re gulat or inoperable was replaced and l

System regulator low.

adjusted per EMI-13.'

(RPS)

FIR # A-154148 i

e e

r l

e e

i i

l

+

i I

~

~ - - ~..

^

BROC!S FERRY WUCLEAR PLANT UNIT 1 and common F EMSIL 30 CSSC EQUIPMENT ELECTRICAL MAIN 7ENANCE

SUMMARY

9/29/82 For the Month of

August, 1983 Effect on Safe Action Taken Nature of Operation ot' Cause of Results of To Preclude ate System Cenonent Maintenance The Reactor Malfunction Malfunction Recurrence 1

l l l /29/8:

4 KV Undervoltage During the None, the loss-of The relay's set-The relays operated The degraded voltage Shutdown relays 27-211-performance of voltage relay points had between 3942 and 3950 relays were immed Boards nnd IB, 27-211-lC SI 4.9.A.4.C channel was appa ren t ly volts as opposed to lately recalibrated Busses.

on shutdown bd, the component available and drifted up due to the allowable setpoint and returned to A.

and 27-211-relays were ope rab le.

This increases in range of 3900-3940 service. The set-A n shutdown (C) hEatbabove drift was in a ambient t empe r-volts.

point drift problem I bd.

C.

their maximum conservative ature since their is now under eval-allowable di re ct ion last calibration.

untion and will lu setpoint.

regarding nuclear addressed in a l

safety.

follocup report to BFRD-50-259/8213 by 3 12-1-83.

i MR# A-062721 Ui i

d'

\\

LER# BFRO-50-259/

83048 l

!/1/83 liigh-Diesel Fire Electrically None Valve vibrates Electrical valve will Installed starting P ressure Pump strainer operated valve when open causing not operate.

capacitor on valve

~

Fire Blowdown valve would not capacitor leads motor and tied leads

}

Protection 0-26-1420 ope rate to break loose.

down.

l MR# 142200 i

3 I

l l/1/83 Diesel "D" diesel Annunciator None, redundant Bad annunciator Annunciator panel Replaced the l

Cencrators Gene rator panel annunciation was circuitry cards.

inoperable.

annunciator cards i

annunciator inope rable available and and returned the panel located ope rab le.

This panel to service.

in the main panel had no l

control room, ef fect. on diesel MR# A-142199 generator operability.

l l

I 1

i

Page 3 BRC'4MS FERRY T4UCLEAR PLANT tl NIT 1 and _ comraon BF EMSgt, 30 E*"

CSSC EQUIPMENT ELECTRICA1. MAI!GENANCE SI'!! MARY 9/29/82 For the Month _of Auguer 19 83 Effect on Safe Action Taken '

I Nature of Operation of Cause of Results of To Preclude-ite Svsten Cmnonent Maintenance The Reactor Malfunction Malfunction Recurrence

'2/83 Control Panel 9-28 Blown fuse in Nong Blown fuse. The Caused rods to be Replaced fuse, i

Rod Drive Panel 9-28 coul<

fuse tab failed to deselected.

verified not be verified punch out thus annunciator and caused rods not giving a blown circuit was to be dese'lectec fuse annunciation working.

MR# A-142430

'5/83 24 volt DC A2-1 + 24 The DC output None The DC output The A channel of The batteries were.

Power Systein volt neutron breaker tripped breaker tripped.

stack radiation charged and the f

monitoring and would not monitor 90-A7 was breaker reset.

The' bat te ry reset inoperable breaker tripped charge r.

again.on 8-25-83 m f

'due to a broken " j-g wire on the i,

equalize switch.

l The broken wire wel, repaired, lowered charger current aad returned the batte.i charger to service.'

?

MR# 147581 e

MR# 138211 1

e

BROQ3S FERRY NUCLEAR PLABIT UMIT 1 and common MS L.30 Appendix B CSSC FQUIPMENT ELECTRICAL MAINTENANCE

SUMMARY

9/29/82 For the Month of August, 19 83 Effect on Safe Action Taken Nature of Operation of Cause of Results of To Preclude ice Systen Connonent Ma in tenance The Reactor Malfunction Malfunction Recurrence

'll/8s Neutron SRM channel D Penetration None Part missing from SRM channel D Replaced the Monitorint drywell showed high penetrat. ion inoperable penetration conner..r System penetration resistance connector which MR# A-202735 connection allowed the connec'.or to be loose. The j

conductor pin was not naking contact.

I

/20/83 Unit Control switch Control switch None Bad keeper on Switch operation was-Replaced the keeper !

Pre fe rred for 120 volt had to be outboard end of

erratic, on the outboard end 120 volt AC preferred wiggled to AC system synchroscope operate the f.

switch.

of switch.

yi MR# A-147127 for breaker synchroscope t

1002.

and incoming voltmeter for breaker 1002.

'20/8 L High-Fire pumps Strainer was None Bad limit switch.

Strainer was not Replaced the bad,

P ressure strainer "B" not alternating alternating directions limit switch.

Fire directions.

e MR# A-138352 P rote c t ior l

/22/8D Reactor -

High drywell Relay None, unit in Bad relay coil.

Failure of this relay The relay coil was Protectior pressure scram inoperable re fueling would result in half replaced and returned System trip relay outage scram (channel A2).

to service.

(RPS) 5A-K4C MR# A-138203

BROWNS FERRY NUCLEAR PLANT UNIT 2

L 30

^IE" CSSC EQUIPMENT ELECTRICAL MAINTENANCE

SUMMARY

9/29/82 For the Month of

August, 19 83 Effect on Safe Action Taken ~ ~ '

Nature of Operation of Cause of Results of To Prcelude see Systen Corponent Maintenance The Reacter Malfunction Malfunction Recurrence

'25/8 ilPCI E G M box Correct Required,IIPCI to llPCI tachometer Following the cali-The wires were dif fe rence be taken out of was out of bration of the reterminated propc ;

r between actual service.

calibration, tachometer (EMI-36) and llPCI was test d llPCI speed at the llPCI was made satis f act orily.

2400 RPM 'in inoperable due to an The procedure will Control Room apparent wiring error be revised by 9-15-8l, and 2570 RPM by maintenance to include wire actual by personnel during cali-labeling.

t Results speed bration of the LER# liFRO-50-260/83 47 detection tachometer.

I eq ui pmen t.

MR# A-142099

'25/81 Core Spray Core Spray NE While pe r-None, the The overload Core Spray NE Room The overlopd relan Cooling Room Cooler forming SI-4.2.

redundant care relays on the Cooler fan would not CE model number spraysystek full-voltage non-operate.

CR124C028, was Fan.

B-60 it was found that the loop and room reve rsin g replaced and motor ;

Core Spray NE cooler were, magnetic starter current verified to !

Room Cooler fan, operable.

tripped.

be acceptable. Thi would not is considered a operate.

random failure and no further j

recurrence control e

is required.

LER# BFP ' 50-260/

83049 MR# A-060421

'29/81 RCIC MX relay for RCIC gland seal None Open coil on che The gland seal The open coil was the RCIC gland vaccum pump htX relay.

vaccum pump was replaced on the MX seal vaccum inoperable.

inope rab le.

relay and the pump vaccum pump returnet to service.

1,!

j MR# A-141016

_ _ _.. =. -.

1. E" 3 BRCWNS FERRY NUCLEAR PLANT UIJIT-9

~

BF EMSEL 30 CSSC EQUIPMENT ELECTRICAL MAIN 7ENANCE SUPD!ARY.

^IE""

9/29/82 For the Month of

August, 19 83' Effect on Safe Action Taken-Nature of Operation of Cause of Results of To Preclude iate Systen Cor nonent Ma in t enance The Reactor Malfunction Malfunction Recurrence

'l/83

!!PCI Inverter During normal llPCI inoperable Bad !!PCI output liPCI was inoperabic

,The t ransformer was t rans forme r T2. operation, liigh inverter trans-for about 15 minutes.

replaced and HPCI.

Pressure Coolant forme r was tested satis-Injection Syster factorily. This (IIPCI) was failure is considere

~

declared a random failure.

r oerable due No recurrence cont' t i

to inverter is planned.

trans f rmer T2 failure.

LER# BFRO-50-260/

j 83046 MR# A-142191 i'11/8 Reactor Reactor Feed-RFP signal None Bad signal Erratic signal The bad amplifiersU.

Feedwa ter wate r Pump '"C" converter was -

converter converter operation.

were replaced, EMI-i System signal con-ope rating amp li fie rs.

84 performed, and ve r te r erratically.

the converter returne to service.

MR# A-142686 j '12 /8:

RilR 2EA LPCI M G M C set drive None Motor fan was Excessive motor noise The fan was adjusteq.

I set drive motor fan was loose on shaft.

and vibration.

e motor fan making excessivo MR# A-142807 j

t i

noise.

i f

l23/8]

RllR RilR Pump 2C While performint None, the The overload relay PJIR Pump 2C Cooler The overload relay j

Cooler fan.

SI-4.2.B-57, it redundan t t ri pped.

f an would not operatt was reset. This was found that residual heat was considered a the RHR Pump 2C removal system random failure and Cooler fan woult loop and room no further j

not ope rate.

cooler were recurrence control operable.

is required.

LER# BFRO-50-260/

il j

i

'83050

BF0WS FERRY NUCLEAR PLANT 1"IIT 3

cF EMSIL 30 CSSC EQUIPMENT ELECTRICAL MAIN'DENANCE

SUMMARY

9/29/82 For the Month of Aucust 1983 a

Effect on Safe Action Taken

~

Nature of Operation of Cause of Results of To Preclude ate System Connonent Maintenance The Reactor Malfunction Malfunction Recurrence

'4/83 of f-Cas Off-Gas post-During normal None, the stack Due to trip of Monitors were out of - Breaker was reset.

treatment reactor opera-radiation motor control se rvice.

Currents were w i-radiation tion, both of f-monitor was center, a normal ficd to be below moni to rs.

gas post-t reat-operabic and no feeder breaker trip value. This ment radiation release limits whlch supplies was a random failur' monitors ( 3-RII-were exceeded.

power to the pump and no recurrence 90-265/266) control is required became inoper-able due to LER# BFRO-50-296 sample pump 83048 power failure.

y

'8/83 Diesel 3B Diesel Received a 3B None Bad annunciator Received a false The circuit card Generators Gene rat or Diesel circuitry card.

control circuit was replaced, 5

Annun ci ato r Generator i;

ground alarm for alarm cleared.

Panel control circuit D/G 3B.

ground alarm.

MR# A-153529 I

'11/8 Diesel Diesel Compressor None Bad motor bearing 4. Excessive motor The motor bearings Gene rat ors Generator 3D motor was noise and vibration.

were replaced and air compressor vibrating and the compressor A.

running noisy.

returned to servicq.

e MR# A-142533 12/8 4KV 4KV Shutdown Corrosion was None Undetermined.

This spare relay was This problem is nod Shutdown' Bd 3ED relay noticed on removed from service under investigatior.

Boards and SAA (spare) relay screws.

for analysis to Humidity and temp-Busses determine cause of crature recorders corrosion.

will be set up in the shutdown board rooms as part of this invest.igation, MR# A-130650 4

$^FEMSIL30 E#

BROCIS FERRY NUCLEAR PLANT tRJIT 3 n

Appendix B CSSC EQUIPMENT ELECTRICAL MAI!TFENANCE

SUMMARY

9/29/82 For the Month of Aunust.

1983 Effect on Safe Action Taken ~l Nature of Operation of Cause of Results of To Preclude 1

ite Systen Cornonent Ma in t enance The Reactor Malfunction Malfunction Recurrence l'16 /81 Diesel Diesel While perform-Nonc liigh speed limit Diesel Generator 3ED The switch was Generator Generator ing SI-4.9. A.1.

switch in the was declared replaced and the 3ED 9, Diesel Woodward inoperable.

diesel was returned Generator governor failed.

to service. This Monthly Test, is considered a dicsc1 random failure and generator 3ED no recurrence l

failed to control requi red.

reach rated LER# OFRO-50-2Jt, spead on an 83052 I

automatic start MR# A-153550 t

1 t

i i

4 0

g i

J

4 INSTRUMENT MAINTENANCE SG M RY I

FOR THE MONTH OF AUGUST 1983 EFFECT OF SAFE ACTION TAKEN NATURE OF OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE.

DATE SYSTEM' COMPONENT MAINTENANCE THE REACTOR MALFUNCTION MALFUNCTION RECURRENCE (U-1) 8-1 77 FR-77-16 Repair None Shorted wire Loss of record None 8-14 74 FT-74-76 Replace None End of life Loss of indication None 8-19 85 PI-85-63 Replace Non'e Age Loss of indication None (U-2) 8-2 73 TR-73-54 Repair None Age Loss of record None 8-15 92 APRM F, Replace None Age Alarm None Thermal trip card 8-15 92 SRM A, Log Replace None Age Faulty indication Nono meter 8-24 90 AR-90-256 Repair Nono Age Loss of record None 8-28 77 LIS-77-1B Replace None End of life Loss of indication None (U-3)

I[

7-27 92 IRMN, DC Repair None Age Faulty indication Hone Amp I

7-29 90 RM-90-134 Repair None End of life Loss of indication None 8-5 64 TI-64-55A Replace None End of life Loss of indication None 8-12 92 RBM-A Repair Nono Age None None 8-15 92 RBM-B Repair None Age None None 8-19 76 PR/FR-76-14 Repair None Age Loss of indication None e

e

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-s

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: 1.

.!: :;t- :..

l fnonc

! unknown

' replaced valve packin 8-01 CRD mod 54-47 repair leak none MRff A142447 8-17 Core Sprayt3B PSC pump i pt.mp leak none gasket blown none

! replaced head gaske I

!!!Rll A210815 I

8-20 Core Spray 3B PSC pump

!leakatunion none unknown none tighten union I.MR/! A142595 i

8-09 RHR LPCI 3DN Inoisy bearing none normal use none

! replace bearing l

MR/! A062164 4

i j

I I

l s

(

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,,. ;, ;, g ;

c MECHA

! CAL 9;A1::T;::a::CE SU:@t\\nY For the Month ef August

_ _1 9 83 i

EFFECf 0:: SAFE AC TIO! TAEE!;

l ti r SYSTE::

CnM:'C:W::I

A iLR E O!'

OPEPJ TTO: OF CAtSE cr RESULTS OF TO PRECI.UDF

_ : A T :'J'::A!;CE T:!E RP3,CTO:1, M.AL:TNCTIt':s l

"ALFU;;CTIO?:

R!:CUnRr.::C:' __

.-02 HPCI gland seal repair leak none blown gasket none replacied head gacke condenser MR# A206650 g

-08 Recirc drain valve replace valve none normal use none replaced valve MR# A133785 i-22 HPCI gland seal repair leak none blown gasket none replaced head gasket condenser

!!R# A210704 u

fg r

O I

'I e

w

.o

.s

,.,I..,.a

. i t.

.__..j__

o"( ii A : cl ! :D T: c..' 'c' v ' a '.\\ D-Fer the '.i;.t!

_ August l '1 83 l e. -..

s..

a.

-~.' t -

v.

,1 I

I I

cc 3 r, 7y

, c.1 :

c 4.rt!. J cF i ' iT l

. ' 1. _. :.._. _.,I. ?.. _: -. '...... a_ _ _ _. 5... t ::c..

l "n: '::c rrtv:

8-05 'EECW EECW header

repair weld none unknown none repaired welc and I

replaced porti.an o,f l

i P pe

'l MR# A133800 i

n 1

8-04 RIIRSW

,ARV 23-560

repair leaks none unknown Inone-torqued bolts to i

i stop leak i

i MRi/ A062365 4

8-01 SBCT charcoal

' change filters l none unknown none replaced filter >

filters MR# A132097 8-02 Vent System 1B reactor i damper won't none unknown none adjusted damper iexhaust fan

open MR# A154162 i

e 1

8-01 iRilRSW ARV-23-501 jrepairleak I nonc junknown none repalced gasket u t

MR# A058966

~

0 t

8-07 RI!RSW rARV-23-0590

valve Icak

none unknown none replaced internals i

i MR# A143002 I

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l i

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e

32 FIELD SERVICES

SUMMARY

August 1983 Major Work Areas A.

Refuel Floor - (1036) fuel movement of high density fuel storage (HDFS) rack shimming was completed on August 18 and the last HDFS rack was com-pleted on August 29 Other activities associated with the refuel floor included completion of boral testing of 28 racks, preparations for replacement of crane rail, maintenance work and cleanup.

B.

Turbine - During August the blade changeout on the low-pressure "A" turbine rotor was completed the low-pressure "A" was reassembled.

This changeout required using unit 3 blades on the unit 1 turbine. The unit 1 blades that were removed have been shipped to General Electric in Schenectady, New York for repair and will be used on unit 3 low-pressure turbine.

The low-pressure "B" turbine blades c'mpleted repair this month by General o

Electric and are currently being installed. The current date for comple-tion is September 9 The front standard bull gear and oil pump gear were also repaired this month and have been received onsite.

The current projected completion date for low-pressure "B" turbine reassembly is September 27

_ ~

33 FIELD SERVICES

SUMMARY

August 1983 MaiorWohkAreas C.

Drywell - During August NUTECH/Gapoo completed 16 overlay welds and Welding Services one sweep-let.

Progress was slow due to special designed welding head requirements which had to be redesigned and fabricated by vendor.

Main steam isolation valve work continued this month with completion of the r

inboard valve assembly and successful leak rate testing.

D.

Electrical / Instrumentation - During the month.of August the prime emphasis continued to be placed on the work required to be completed prior to fuel load.

The status of the modifications and maintenance work is as follows:

1.

Modifications y

a.

P0533 Torus Temperature Monitoring System: The conduit instal-lation was the prime effort on this modification this month. The progress made on Elevation 519 was not as good as planned due to heat problems enccuntered with the torus heateure.

The modifica-

/ ?

tion currently 85-percent complete, b.

P0322/P0323 Drywell wide-range pressure monitors and P0323 torus wide-range level transmitters: The conduit installation con-tinued and all conduit is installed except for 60 ft. on El. 519 Junction boxes were mounted on El. 519 Still need resolution as to where pressure transmitters will be mounted on El. 593

1. 9#

~

34 FIELD SERVICES

SUMMARY

August 1983 Maior Work Areas D.

(Continued) 1.

Modifications (Continued) c.

F0324 Containment Wide-range Radiation Monitors: Completed all cable pulling and started talking and meggering cables. Started fabrication of the junction boxes that are to be mounted inside the drywell. These junction boxes are designed to withstand the pressure during the integrated leak rate test. This modification is approximately 80-percent complete.

d.

PO479 Emergency Lighting: Continued to install lighting battery pack lighting as manpower is available, approximately 95-percent complete.

e.

P0590 Standby Control Ibom Emergency Lighting: Completed conduit and cable installation. Modification is 65-percent complete and will be completed prior to start of fuel load.

f.

Electrical-Maintenance Completed all work associated with EMI-7 and EMI-71 testing.

Completed the recirculation motor maintenance and will test run motors upon completion of recirculation motor-generator set brush holder modification.

r-35 FIELD SERVICES

SUMMARY

August 1983 Maior Work Areas D.

(Continued) f.

Modifications (Continued) f.

(Conti nued)

Expect to complete the brush holder modification on the recircu-lation motor-generator sets on September 15.

Continued the outside electrical support for the three new build-ings and continued electrical support of the torus modification, NUTECH and Welding Services weld overlay repair.

E.

Mechanical - ALARA: The primary ALARA concerns during August were as follows: Support of the weld over repair, refuel floor preparation for reload, overall unit 1 housekeeping and the preparation for the upcoming unit 3 refueling outage.

F.

Planning and Scheduling: Emphasis was placed on identifying and monitoring the work that is required to support fuel load. The major fuel load items were mentioned in the work synopsis. Additional effort was placed on the upcoming unit 3 cycle 5 refueling outage scheduled to start on September 6.

G.

Torus: Williams Paint Contractor cocpleted heateure of the nine remaining bays on August 30, 1983 External modifications of the torus continued, but were slowed due to the heat buildup of the heateure process. Fourteen of 16 torus snubber wall brackets were completed, as well as demineralized water reroute, high pressure coolant injection line reroute, and all external gussets. Efforts continued with ECCS support shim replacement,

~

36 FIELD SERVICES

SUMMARY

August 1983 Maice Work Areas G.

(Continued) torus snubber installation and preparations of HK II weld out. Testing of torus snubbers was completed with 15 of 16 leaking, and vendor delivered unit 3 anubbers for installation on unit 1, of which 50-percent developed leaks and had to be returned to vendor for correction. New targeted torus fill date is September 9, 1983 Attached piping support efforts continued throughout the month and a total of 73 supports were completed, boosting the total to 363 of 407, which includes spring (22) hanger mods received this month and ECCS supports.

By system the following progress was made: HPCI - 100-percent, RCIC percent, RHR Loop I percent,_JHR Loop 2 percent, CS Loop 1 - 100-percent, CS Loop 2 percent, drywell and torus purge percent, PSC ringheader - 100-percent complete.

The total attached piping program is 96-percent complete.

H.

Administrative - The overtime percentage for the month of July was 22-percent with 172,507 straight-time hours and 49,117 overtime hours. As of July 31, 1983, year-to-date overtime percentage was 21-percent, 1,428,157 straight-time hours and 384,087 overtime hours. The overall goal of the overtime percentage is 17-percent.

~

g 37 FIELD SERVICES

SUMMARY

August 1983 Maior Work Areas H.

(Continued)

The O&M budget for July was $2,205,103 and the expenditures were $1,303,375 with year-to-date budget being $27,164,437, and actual year-to-date expend-itures being $26,960,735. The capital budget was $2,574,700 and the expenditures were $4,376,755 with year-to-date budget being $35,495,420, and actual year-to-date expenditures being $23,881,513 Overall budget was

$4,779,803 and the overall expenditures were $5,680,129 with year-to-date budget being $62,660,857, and actual year-to-date expenditures being

$50,842,248.

u l

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~. _

I TENNESSEE VALLEY AUTHORITY Browns Ferry Nuclear Plant P. O. Box 2000 Decatur, Alabama 35602 SEP 091983 Nuclear Regulatory Commission Office of Management Information and Program Control Washington, DC 20555 Gentlemen:

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

/.

sou.s G. T. Dones Power Plant Superintendent Enclosures cc: Director, Region II INPO Records Center Nuclear Regulatory Commission Institute or 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 Instituta P. O. Box 10412 Palo Alto, CA 94304 An Equal Opportunity Employer