ML20086G608

Monthly Operating Repts for Nov 1983

ML20086G608
Person / Time
Site:	Browns Ferry
Issue date:	11/30/1983
From:	Jones G, Thom T TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8401120307
Download: ML20086G608 (37)

Text

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. . . . -r TENNESSEE VALLEY AUTHORITY DIVISION OF NUCLEAR POWER BROWNS FERRY NUCLEAR PLANT

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MONTHLY OPERATING REPORT TO NRC November 1, 1983 - November 30, 1983 DOCKET NU!GERS 50-259, 50-260, AND 50-296 LICENSE NUIEERS DPR-33, DPR-52, AND DPR-68 Submitted by:

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Plant perintendent 8401120307 831130 DR ADOCK 05000259 PDR 5y k

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TABLE OF CONTENTS Operations Summary. . . . . . . . . . . . . . . . . . . . . . 1 Refueling Information . . . . . . . . . . . . . . . . . . . . 3 Significant Ope:*ational Instructions. . . . . . . . . . . . . 5 Average Daily Unit Power Level. . . . . . . . . . . . . . . . 11 Operating Data Reports. . . . . . . .. .. ... . . . . . . 14 Unit Shutdowns and Power Reductions . ... . . . . . . . . . 17

- Plant Maintenance . . . . . . . ...... . . . . . . . . . 20 Field Services Summary. . . . . . . . . . . . . . . . . . . . 29 a

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. Oneratians Summary November 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 14 reportable occurrences and five revisions to previous report-able occurrences reported to the NRC during the month of November.

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

Unit 2 There were two scrams on the unit during the. month. On November 10, while testing "B" channel of the main steam line high flow switch, the reactor scrammed on MSIV closure from a false si6ual on the "A" channel switch. On

' November 15, the reactor scrammed on reactor low water level following load drop for maintenance on a reactor feodwater pump and a loss of a second reactor feedwater pt.mp from loss of suction.

Unit ~4 The unit was in cold shutdown the entire month for the unit's end-of-cycle 5 refueling outage.

l Principally prepared by B. L. Porter.

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ODerations Summarv (Continued)

November 1983 Egj;1gue Usage Evaluation The cumulative usage factors for the reactor vessel are as follows:

Location Usane Factor Unit 1 Unit 2 Unit 9 Shell at water line 0.00583 0.00479 0.00403 Feedwater nozzle 0.28294 0.20583 0.15429 Closure studs 0.22349 0.17103 0.13233 NOTE: This accumulated monthly information satisfies Technical Specification Section 6.6. A.17.B(3) reporting requirements.

Co==nn System Approximately 1.80E+06 gallons of waste liquids were discharged containing approximately 1.01E+00 curies of activities. .

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, Onerations h ---v (Continued)

November 1983 Refueling Information Unit 1 Unit 1 began its fifth refueling outage on April 16, 1983 The sched-uled restart date is December 19, 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 764 fuel assemblies in the reactor vessel. The spent fuel stor-age pool presently . contains 252 EOC-5 fuel assemblies, 260 EOC-4 fuel assemblies; 232 EOC-3 fuel assemblies; 156 EOC-2 fuel assemblies; and 168 E0C-

.1 fuel assemblies. The present fuel pool capacity is 3,471 locations.

2 Unit 2 l Unit 2 is scheduled for its fifth refuelin6 beginning on or about June 8, l

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

. will involve loading additional 8X8R (retrofit) fuel assemblies into the core,

' finishing the torus modification, turbine inspection, finishing piping inspection, finishing THI-2 modifications; post-accident sampling facility tie-ins, core spray change-out, and feedwater sparger inspection.

I 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 i

l 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.

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Operations Summarv (Continued)

November 1983

9. nit 1 Unit 3 shutdown for its fifth refueling outage on September 7,1983, with a scheduled. restart date of May 4, 1984. This refueling involves loading 8X8R (retrofit) assemblies into the core, finishing the torus modifications, post-accident sampling facility tie-in, core spr ay change-out, finishing TMI-2 modifications, turbine inspection, piping inspections for cracks, and change-out of jet pump hold-down beams.

There are O fuel assemblies presently in the reactor vescel. There are 764 EOC-5 fuel assemblies, 280 E0C-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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Sinnificant Operationni Events Date Tima Event Unit 1 11/01 0001 End-of-cycle 5 refuel outage continues.

11/30 2400 End-of-cycle 5 refuel outage continues.

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Rianificant Onerationni Events Data Tima Event Unit 2 11/01 0001 Reactor thermal power at 100-percent maximum flow, rod limited.

11/02~ 0620 Commenced reducing thermal power due to decreasing flow on "A" recirculation loop. Manually locked scoop tube l on "A" recirculation motor-generator (MG) set and l

reduced flow on "B" recirculation pump. '

. 0630 Load stable at 85-percent thermal power. Maintenance working on "A" recirculation pump MG set speed control.

1005 "A" recirculation pump MG set speed control repaired, g commenced power ascension.

(- 1035 Reactor thermal power at 100-percent maximum flow, rod

limitad.

I l 11/ 06 2200 Commenced reducing thermal power for turbine control l valve test and SI's. .

11/ 07 0155 Turbine control valve test and SI's complete, reducing from 72-percent for control rod sequence exchange.

0600 Reactor power at 67-percent control rod sequence exchange in progress, increasing thermal power.

0945 Control rod sequence exchange complete, commenced power ascension from 71-percent.

1500 Commenced PCIOMR from 81-percent thermal power.

11/08 0530 Commenced reducing thermal power from 93-percent due to post treatment high radiation alarm.

0900 Reactor thermal power at 89-percent limited by post treatment high radiation alarm.

1805 SI's complete for offgas post treatment radiation alarm, commenced power ascension.

1900 Commenced PCIOMR from 91-percent thermal power.

11/09 0800 Reactor thermal power at 100-percent, maximum flow, rod limited.

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

2300 Reactor thermal power at 98-percent, maximum flow, rod l limited.

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Sianificant Ooerational Events Date Tima Event Unit 2 (Continued) 11/10 1006 Reactor Scram No.145 from 98-percent thermal power on main steam line high flow. While testing "B" channel switch, it was accidentally jarred, causing second and spurious "A" channel FEL high flow trip. The reactor scrammed on MSIV closure.

11/11 0755 Commenced rod withdrawal for startup.

1125 Reactor Critical lio. 156.

1435 Rolled turbine / generator (T/G).

1450 Synchronized generator, commenced power ascension.

11/12 1700 Commenced PCIOMR from 84-percent thermal power.

1750 Stepped PCIOMR at 85-percent thermal power due to loss of cooling on "B" phase main transformer.

1915- Cooling restored to transformer, commenced PCIOMR from 85-percent power.

2200 Stopped PCIOMR at 92-percent power for control rod pattcrn adjustment.

11/13 014E control rod pattern adjustment complete, commenced power ascension from 92-percent thermal power.

0230 Commenced PCIOMR from 94-percent thermal power.

1230 Reactor thermal power at 100-percent, maximum flow, rod limited.

11/15 0001 Reactor thermal power at 99-percent, maximum flow, rod limited (100-percent electrical) .

1942. Commenced reducing thermal power for removal of "A" reactor feedwater pump (RFWP) from service for maintenance.

2023 Reactor thermal power at 73-percent, "2A" reactor

. feedwater pump out-of-service for maintenance.

2025 Reactor Scram No.146 from 73-percent thermal power following a load drop for maintenance on "2A" RFWP.

With the "2A" RFWP out-of-service, the unit operator inadvertently closed the suction valve for "2B" RFWP.

The "2C" RFWP could not sustain reactor water level at this load and the unit scrammed on reactor low water l level.

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Significant Operational Events Date Time Event Unit 2 (Continued) 11/16 0328 Commenced rod withdrawal for startup.

0530 Reactor CriLical No. 157 1107 Rolled T/G.

1123 Synchronized generator, commenced power ascension.

2210 Commenced reducing thermal power from 78-percent for removal of "C" reactor feedwater pump from service for maintenance.

2225 "C" RFWP out-of-service, reactor power at 70-percent, increasing power.

2300 Reactor power at 74-percent, "C" RFWP limited, decr ssing thermal power. -

11/17 0700 Reactor thermal power at 71-percent, "C" RFWP limited.

0745 "C" reactor feedwater pump in service, commenced power ascension.

1100 Commenced PCIOMR from 93-percent thermal power. _

2250 Reactor thermal power at 100-percent, maximum flow, rod limited.

11/18 0700 Reactor thermal power at 99-percent maximum flow, rod limited (100-percent electrical) .

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

2400 Reactor thermal power at 97-percent, maximum flow, rod limited.

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

11/20 0100 Reactor power at 74-percent for turbine control valve test, SI's and control rod pattern adjustment.

0210 Turbine control valve test and SI's complete, increased thermal power to 82-percent, control rod pattern adjustment in progress.

0320 Reducing thermal power for control rod pattern adjustment.

0330 Reactor power at 71-percent for control rod pattern adjustment.

0400 Control rod pattern adjustment complete, commenced PCIOMR from 71-percent power.

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l Stanificant Ooeratiotial Events Date Tima Event Unit 2 (Continued) 11/21 1210 Stopped PCIOMR at 96-percent thermal power to run a TIP set.

1440' TIP run complete, commenced PCIONR.

2040 Reactor thermal power at 100-percent, maximum flow, rod limited.

11/ 26 0230 commenced reducing thermal power for turbine control-valve test and SI's.

0300 Reactor power at 94-percent for turbine control valve test and SI's.

0415 Turbine control valve test and SI's complete, commenced PCIOMR.

1215 Reactor power at 100-percent, maximum flow, rod limited.

11/30 2400 Reactor power at 100-percent, maximum flow, rod limited.

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Stanificant Ooerational Events Date -Tima Event Unit 3 11/01 0001 End-of-cycle 5 refuel outage continues.

11/30 2400 End-of-cycle 5 refuel outage continues.

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4VER1GE DAILY UNIT POWER LEVEL

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' DOCKET NO. 50-259 Browns Ferry-1 UNIT DATE COMPLETED BY Ted Thom 4 ' TELEPif0NE 205/729-0834-

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MONTli November

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DAY AVER AGE DAILY POWER LEVEL DAY

" AVER AGE DAILY POWER LEVEL (MWe-Net) ~ (MWe-Net)

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-6 16 INSTRUCTIONS l i~

On this ibrinat, h>t the .iser.ip dash unii: p%ti it.u.l m nt.4d M M da) :n th. iepos tine nion ggi ( ,,n: pure i ,

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DATE 4 Ted Thom g *  % COMPLETED BY .

TELEPl10NE 205/729-0834 J 5

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, . )fdNTH November

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, DAV AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVE!!'

IMWe Net) g y w e.Negi s

1 1073 g7 __- s. 946 2 1041 ,g 1047 _.

3 1073 994 1094 854 4

20 -

5 1083 1030 2 ,

6 1066 ,, 1067 OI4 1068 7

23 }

976 1062 8

, 24 n,9 1068 , 1o89 3

"10' 43l 1080

'6 148 g- Il 27 1081 12 790 ,3 1085 if 1038 1081

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On this format, hs: themer.sy: Jaily uint p mer lescl in Mwe-Nei ter ad d.n in Ihe et p 4roniin.. nth. ( ...o;w '

the nearest whole neppit.'

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AVERAGE D ALLY UNIT POhER LEVEL DOCKET NO. 50-296 l UNIT Browns Ferry-3 DATE.

! COMPLETED BY _Ted Thom

, TELEPilONE 205/729-0834 MONT11 November h *

., f DAY' AVERACE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL IMWe Net) iMWe-Neti I -7 -6 g7

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-0 INSTRUCTIONS On this fonnat. fist the aserage daily unit powei lesel in slWe Net foi cuh das ni ihs rep..inna in..nih. r..inpine ,,,

the nearest whole nwpwait.

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t OPERATING DATA REPORT DOCKET NO. 50-259 DATE 12/1/83 COMPLETED BY 73_d Thom TELEPilOSE 205/729-0834 OPERATING STATUS Browns Ferry -1 Notes

1. Uiut Name:

2. Reporting Period: November 1983 3293

3. Licensed 1 hermalibwer (MWt):

4. Nameplate Rating (Gross MWe): 1152

5. Design Electrical Rating (Net MWe): 1065

6. Maximum Dependable Capacity (Gross MWe): 1098.4

7. Masimum Dependable Capacity (Net MWe): 1065

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

N/A

1. 9. Power Lesel To Which Restricted.lf Any INet MWe): N/A

10. Reawns For Restrictions.lf Any: N/A This Month Yr. to-Date Cumulative i1. Hours In Reporting Period 720 8,016 81,818

12. Number O( Hours Heactor was Critical 0 2,363.25 49,752.79

13. Reactor Reserve Shutdown llours 0 . 47.71 5,785.02

14. Hours Generator On Line 0 2,317.52 48,717.64

15. Unit Rewne Shutdown llourn 0 0 0 16.' Gross Thermal Energy Generated (MWH) 0 6,784,675 138,557.679 17 Gross Electrical Energy Generated IMWil) 0 _ _ _ _ , , , ,

2,244,900 45,645,620 lb. Net Electrical Energy Generated IMWH) 0 2.175.548 44.325.327

19. Unit Senice Factor 0 28.9 59.5

20. Unit Availability Factor 0 28.9 59.5

21. Unit Capacity Factor (Using MDC Net) 0 25.5 50.9

22. Unit Capacity Factor IUsing DER Net) 0 25.5 50.9 U * *O

23. Unit Forced Outage Rate

24. Shutdowns Scheduled Oser Next 6 Months qType. Date.and Duration of Each t:

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

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26. Units in lest Status (Prior eo Commercial Operationp: Forecast Achiesed INIII AL CRillCALITY INIIl \L ELECIRICITY COMMERCIAL OPER \IlON (9/77)

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OPERATING DATA REPORT DOCKET NO. 50-260 DATE 12/1/83 Thn, COMPLETED TELEPHONE 205 BY .Ted./ 729-0834 OPER ATING STATUS

1. Unit Name: Brwns Ferry -2 N"'"

j 2. Reporting Period: November 1983 I

3. Licensed Thermal Power (MWt): 3293

4. Nameplate Rating (Gross MWe): 1152

5. Design Electrical Rating (Net MWe): 1065

6. Masimum Dependable Capacity IGross MWe): 1098.4

7. Masimum Dependable Capacity (Net MWe): 1065 l

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

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. N/A

9. Power Level To which Restricted,1f Any (Net MWe): N/A

10. Reawns For Restrictions If Any: .

This Month Yr.-to.Date Cumulative 11, llours In Reporting PerioJ 720 8.016 76.759 b

12. Number Of Hours Reactor Was Critical 685.6 5,947.81 49,241.28

13. Reactor Rewrve Shutdown Hours .

34.4 194.44 13,879.26

14. Ilours Gen (rator On.Line 676.3 5.807.31 47.782.76

15. Unit Resene Shutdown flours 0 0 0

16. Gross Thermal Energy Generated IMWill 2,110,656 17,513,648 137,923,495

17. Gross Electrical Energy Generated lMWH) 707,620 5,830,840 45,855,748

18. Net Electrical Energy Generated (MWH) 688.294 5.664.158 44,537,233

19. Unit Senice Factor 93.9 72.4 62.3

20. Unit Asailability Factor 93.9 72.4 62.3

21. Unit Capacity Factor IUning MDC Net) 89.8 66.3 54.5

! 2.1 Unit Capacity Factor (Using DER Net) 89.8 66.3 54.5

23. Unit Forced Outage Rate 6.1 5.4 25.0

24. Shutdowns Scheduled Oser Ne.st 6 Month = lType. Date.and Duration of Eacht:

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25. If Shut Down At End Of Report Perad. Estimated Da:e of Startup:

2ei. Units in Test Status IPrior to Comm:ercial Operation): Forceast Achiesed INITITL CRIIICALITY INill \ L ELEC T RICITY COMMERCIT L OPFR A I!ON

) P8/77 )

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s OPERATING DATA REPORT DOCKET NO. 50-296

• DATE 12/1/83 COMPLETED BY Ted Thon TELEP110SE 205/729-0834 OPERATING STATUS 1.' Unit Name: Browns Ferrv - 3 Notes

2. Reporting Period: November 1983 3.1,icenwd Thermal Power (Mhti: 3293

4. Nameplate Rating (Gross MWe): 1152 i 5. Design Electrical Rating (Net MWe):

6. Masimum Dependable Capacity (Gross MWe): 1098.4

7. Masimum Dependable Capacity (Net MWe): 1065 N. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:

N/A f

g 9. Power Level To Which Restricted. lf Any INet MWe): N/A

10. Reasons For Restrictions.lf Any: N/A i This Month Yr.-to Date Cumulatise

11. Ilours in Reporting Period 720 8.016 59.184 g 12. Number Of Hours Reactor Was Critieal 0 ,,,,

5,475.52 43,087.80

13. Reactor Reserve Shutdown floars 0 . 505.98 3,878.13

14. Ilours Generator On Line U D'019'DD 0A'193*#A

15. Unit Resene Shutdown llours 0 0 0 Iti Gross 1hermal Energy Generated (MWH) 0 16,971,607 126,307,711 17 Gems Electrical Energy Generated (MWH) 0 5,557,830 41,597,620

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

19. Unit Senice Factnr 0 67.6 71.3

! 20. Unit Availability Factor 0 67.6 71.3

21. Unit Capacity Factor (Using MDC Net) 0 63.2 64.1

22. Unit Capacity Factor (Using DER Net) 0 63.2 64.1

{ 23. Unit Forced Outage Rate 0 9.3 16.4

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

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

j 2ti. Unih in Test Statm iPrior to Commercial Operation): Forecast Achiesed INillA L CRillCA LiTY INI TI A L ELECTRICITY COMM ERCI A L OPER AllON i

( (9/771

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• UNITSIIUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-259 ,

UNIT NAME Browns Ferry-1 l DATE 12/1/83 -

November COMPLETED 8y Ted Thom

.- REPORT MONTH TELEPHONE 205/729-0834 e.

. U No . Date

, . ]? 3 Yk Licensee j-r, *'",

h Cause & Corrective

" ' i 3g 4 1E5 Event g7 9 ?. _ Action to j E E j ji, g Report : vlO Prevent Recuaence

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d 264 11/11/83 S 720 C 4 End-of-cycle 5 refuel outage continuc a 1

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I 2 3 4 F: Forced Reason: Method:

S: Scheduled Exhibit G -instructions A Equiprnent Failure (Explain) I-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram. Entry Sheets for t.icensee C-Refueling 3 Automatic Scram. Event Report (LERI Fi fe (NURI.G-D-Regulator) Restriction 4-Other (Explain ) 0161)

E. Operator Training & License Examination F-Aomimst rative 5 G-Operational Error iExplam) f:shibit 1 - Same Source

, e)/77 ) ll-Other (Explain) 1

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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-260

• UNIT NAME Browns Ferry-2 DATE _12/1/83 REPORT MONTH November COMPLETED BY -Ted Thom TELEPHONE 205/729-0834

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.53 3 j $3 Licensee 5-r, E% Cause & Corrective 3g ( .g g & Event  ? 5? Action to f5 $ _t @ g Report = rE L 5L Present Recurrence

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275 11/5/83 S 11 Derated for turbine CV tests and SI's and control rod sequence exchange.

276 11/10/83 F 28.73 3 11 Reactor scram on ma'in steam line high t flow, while testing "B" channel switch, it was jarred causing spuri-ous "A" channel MSL high flow trip.

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277 11/15/83 F 14.96 li 3 Reactor scram on low water level when "2B" RFP switch was inadvert-ently closed while "2A" RFP was out-of-service for maintenance.

278 11/19/83 S H Derated for turbine CV tests and SI's and control rod pgtern adjustment.

b i 2 3 4 F. Forced Reason: Method:

S Scheduled A Equiprnent Failure (Explain) Exhibit G-Instructions 1-Manual for Preparation of Data B-Maintenance or Test 2 Manual Scram. Entry Sheets for 1 Wensee C Refueling 3-Automatic Scram.

D Regulatory Restriction Esent Report (l.I:a l File iNURI G-

-l-Other ( Explam ) 0161)

E Operator Training & l.iteme Examination F-Administrathe 5 G Operational Error (Explain) pl/77) Il-Ot her ( E xplain) Esinbit I Same Source

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DOCKET P.'O. 50-296 UNIT SilUTDOWNS AND POWER REDUCTIONS UNIT NAME Browns Ferry-3 ,

DATE 12/1/83 -

REPORT MONTil November COMPLETED BY Ted Thom TELEPHONE 205/729-0834

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- E No. Date

-, .! E 3 jY~ Licensee ,Ew, . Cause & Corrective i

38 y5 5 4 2sE Event u7 r$ v l*?

s- Action to g gji g 6.

Report e

]L Prevent Recurrence 140 11/1/83 S 720 C 4 End-of-cycle 5 refuel outage continue s I

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i 2 3 4 F: Forced Reason: Method:

S. Scheduled Exhibit G-Instructions A Equipment Failure (Explain) 1 Manual for Preparation of Data B. Maintenance of Test 2-Manual Scram. Entry Sheets for Licensee C Refueling 3 Automatic Scram. Event Repori (LERI File tNURI G-D Regularor) Restriction 4 01her (Explain) 0161)

F-Operator Training & liense Esanunation F Administrative 5 G-Operational Error (E.splaml Estubit I Same Source (9/77 ) li-Other i Explain)

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. UNITSilOTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-296 UNIT NAME Browns Ferry-3 .

DATE 12/1/83 -

REPORT MONTil November COMPLETED BY Ted Thom TELEPif0NE 205/729-0834

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s ,' p, i ', 'e E 253 Licensee Event g-r. g ,., Cause & Corrective I 25 4 .2 5 a: y7 93 Action to

, 5: E j di j Report e n0 jG Prevent Recurrence 6.

140 11/1/83 S 720 C 4 End-of-cycle 5 refuel outage continue s s.a e

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1 2 3 4 F: Forced Reason: Method:

S. Scheduled Exhibit G - Instructions A-Equipment Failure (Explain) 1 Manual for Preparation of Data B Maintenance of Test 2-Manual Scrarn. Entry Sheets for Licensee C Refueling 3- Automatic Scram. Esent Repor (LERI File tNURi?G-D Regulatory Restriction 4-Other ( Explain) 0161)

F. Operator Training & 1Aense 1% amination F Administrative 5 G Operational Error (Explain) Exhibit I Same Source 19/77) Il-Other ( E xplain)

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DW !!6'! !?l,'] y c n ; .Jy e:;.it C F NOVEMBER 19_83 _

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1-3 74 FR-74-64 Repair None Short in wiring 1-4 Erratic indication None 92 SRM Replace, Relay None Open Relay Rod Block None 7CK9B 1-2E 77 FQ-77-16 Repair None 1-2S 73 Dirty slidewire Erroneous indication None TR-73-54 Repair- None Age Loss of record None i

J-3 0 23 PI-23-4 Repa'ir None Blown fuse Loss of' indication Nonc l-18 23 Pl-23-4 Replace None Faulty wire 1-10 26 Loss of indication New Mire PI-26-115 Repair None . Blown fuse Loss of indication. None 1-25 67 PS-67-20 Repair None Age Erroneous alarm None

. ~

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64 PDIC-64-16 Repair None Oil leak 1-29 77 FR-77-16 Loss'of indi. cation None  ? .

Repair None Age Loss of record None 4

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CSSC EQUIPMENT APP;ndix B.

EI.ECTRICAL MAINTENANCE Sl'MMARY 9/29/82 For the Month of November - 19 83 _.

Effect on Safe Action Taken Nature of Operation _of Cause of Results of To Preclude ice Systen Component Maintenance The Reactor Halfianction Halfunctio'n Recurrence

.983 Ll/4 Neutron Relay Replace relay None Coil burned out Relay failed Replaced coil on Monitoring 7CK9B , relay 7CK9B.

System '

MR A205301 (92)

I

.1/14 Control Roc Control Panel Replace fuse None Fuse placed in No f use failure Removed fuse and Drive 25-32 incorrectly alarm

~

replaccd it cor- .'

System (85) rectly. l MR A130662 .l

?

N Air-c ndi-

.1/8 tioning Pressurization Replace None Adjustment knob Thermostat was not Thermostat wasI  !

(cooling /

unit A thermostat broken adjustable replaced. .

hLg.syst(31) MR A061312  ;

< . t 1/11 Air-condi- 4KV shutdown Fan inoperable None Pressure in room Fan would not start Put summer / winter tioning board, 250V keeping flow

~

switch on winter (cooling / battery room switches.from on panel 25-165 heating supply fans making up will relieve -

system (31) A&B pressure , causing fantoworkproperlp MR A129848 r MR A205398 1/13 Ilinh-Pres . Diesel fire Replace valve None Valve burned out Valve failed Replaced valve, sure Fira pump MR 141083 Protection ,-

System (26) I I

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CSSC EQUIPMENT App: dix 5 -

ELECTRICAL MAINTENANCE St2NLRY

,9/29/82 ,

For the Month of November 19 83 .

Effect on Safe Action Taken Nature of Operation of Cause of Results of To Preclude ic System Connonent Maintenance The Reactor Malfunction Malfunction Recurrence

.983 0/17 Control Switch 85-48 Replace stop None Material defect Random failure of Replaced stop Rod Panel 9-5 plate switch plate. 4 Drive MR A210422 I System (85)

• MR A218372 0/18 Control A CRD , Replace coil None Material defect Valve failed Replaced coil. .

Rod stabilizing MR A210430  !

Drive solenoid System (85) valve f

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.. . . .. , e c.xx t h uuLt.AA ri.a.u oata 1 g7 EMS 1L 30 CSSC EQUIPMENT app:ndix B-ELECTRICAL MAlhTENANCE SUPE \RY 9/29/82 For the Month of November 19 83 Effect on Safe Action Taken Nature of Operation of Cause of Results of To Preclude tce Systen Component Maintenance The Reactor Malfunction Halfunctio'n Recurrence 1983 - .

10/29 Radiation Stack gas Pump A tripped N/A Motor A winding, A & B stack gas Motor A (Reliance Monitoring sample pumps on overcurrent .

bearings and sample pumps tripped model C14G5D2) and System (90) A&B Pump B was capacitors were on overcurrent . pumps A and B were started and bad replaced. After-

. also . _. second event, motor

~ ~ ~

tripped on A and fuses were overcurrent replaced and motors A and B overload }

heater sizes were increased. Follow-up report will be ,

issued by 1/15/84 j after fuse and i' motor evaluation.

LER 259/83064, MR A132706

-. A205305, A130662, A141979, A205240, A205241, A205238, A212123, A211197, ,

A218434 4 (

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App ndix B' -

CSSC EQUIPPINT ELECTRICAL MAINTENANCE SD! MARY ,

9/29/82 i

. For the Month of__ November 19 83 [

Effect on Safe Action Taken Nature of Operation of Cause of Results of To Preclude

.tc Sys t ers Component Maintenance The Reactor Malfunction Malfunctio'n Recurrence

1983 1/30 Associated MG set Troubleshoot None Switch volt meter Unit preferred Replaced meter Electrical and repair on MG set control supply giving relay.

System (57) cabinet alinormal alarm . MR A129789

.0/22 Main Steam XA-55-1-27 Replace coil None, Coil failea XA-55-1-27 comes in Replace coil in System (01; main steam in relay during SI 4.a.A.10 relay CR120 hi rad scram for B&D rad monitors tested OK. .

which is B1 & B2 MR A219090

, PC15  ;.

s  !

i

.1/10 Standby Flow contro.1 EMI None Regular mainte- None Replaced squib i i i Liquid valve 63- nance trigger assembly  ;,

Control 8A & 8B per EMI 1 Exp.

j System (6 3) date May 1984.

, , MR061255 replaced TR 277444 -

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4

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l CSSC EQUIPMENT- Appendix B ELECTRICAL MAINTENANCE S12tMARY-

, 9/29/82-For the. Month of November '19 83' Effect on Safe .. Action Taken Nature of . Operation of ~Cause of Results of' .To. Preclude ice System Component Maintenance The Reactor Malftenction Halfunction' Recurrence 1983 5/20 Reactor Flow control Check valve- None Bad motor Valve. trips on Replaced motor..

Water valve 69-2 for malfunctior attempts to open and MR A153798 i Cleanup close .

System (69:

10/14 RHR Service Relay TD2C Change relay None Bad relay Relay. failed Replace relay. I Water on RHRSW MR 132752 I System (23) pump B3 MR211495 575 #56-00437 A

L1/24 CO2 Storagc Kiddle smoke Y Replace lug None Normal use Detector not working Replace two lugs Fire Pro- detector panel on wire be- properly- per EMI 58.2.

tection 3-25-287 tween batterien MR A216402

& Purging ,

(39) . _

i Ll/17 Air Condi- Shutdown Check coil None Bad coil Fan not operating on Replaced coil.

ditioning board room high speed MR A146947' ,

System (31) exhaust fan 'i

~

ll/17 Residual Valve 74-69 Repair limit None Limit switch Limit switch on HCV.-. Corrected position--

Heat Re- switch stepped on and stuck in open ing of limit switch moval twisted causing position ,

and cleaned it.

System (74) the lugs to short MR A205576 out on terminal block' t

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BROWUS FERRY NUCLEAR FIANT UNIT 1

~

CSSC EOUIPMENT MEQlANICAL MAINTE RNCE

SUMMARY

For the_ Month of- November- 19 83 .

EFFECT ON SAFE ACTION TAKEN DATE SYSTEM COMPONENT NATURE OF OPERATION OF , CAUSE OF RESULTS OF TO PRECLUDE MAINTENANCE Tile REACTOR MALFUNCTION MALFUNCTION RECURRENCE 11-30 82 Diesel Generator Replace coup- None N/A N/A N/A ling spider 11-02 260 Door 249 Adjust None N/A N/A N/A 11-02 260 Door 535 Adjust None N/A N/A N/A 11-01 82 D/G Air Com- Replaced head None N/A N/A N/A pressor gasket 11-04 SBGT Charcoal Filter Replace None .N/A N/A N/A.

11-04 FPC Pump Repack None N/A N/A N/A 4

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~ 2 BROWNS FERRY NUCLEAR PIANT UNIT CSSC EOUIPMEUT MECHANICAL MAINTENANCE

SUMMARY

For the Month of ~ November 19 83 EFFECT ON SAFE ACTION TAKEN.

DATE SYSTEM COMPONENT NATURE OF OPERATION OF . CAUSE.0F RESULTS OF. TO PRECLUDE-MAINTENAPCE THE REACTOR MALFUNCTION MALFUNCTION ' RECURRENCE 11-01 Control Rod Pump Add oil None N/A N/A N/A Drive f

' 11-11 i High Pres- Piping Replace rup- In-Op HPCI Investigation In-op HPCI N/A sure Cool- ture disc underway and Injec-tion e

t 4

a 9

9 e

f 6

9 1 1 ,

e

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

~'

BROWNS FERRY NUCLEAR PIANT UNIT 3 -

CSSC EQUIPMENT MECHANICAL MAINTEFANCE

SUMMARY

For the Month of November 19 83 ,

EFFECT ON SAFE ACTION TAKEN.

DATE SYSTEM COMPONENT NATURE OF OPERATION OF .

C/.USE OF RESULTS OF 11) PRECLUDE MAINTENANCE THE REACTOR MALFUNCTION MALFUNCTION RECURRENCE 11-22 85 Pump discharge Clean None N/A N/A N/A filter i

11-25 -82 A D/G Air Replace head None N/A N/A N/A-Compressor gasket j 11-30j Control Bay Temperature Clean None N/A N/A N/A Chiller Control Valve 11-03 PSC Pump Adjust None' N/A N/A N/A Impeller ,

i i

i'

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1 4

i e 4

a i

J J h

FIELD SERVICES

SUMMARY

November 1983 Maior Work Areas A. Refuel Floor - In preparation of unit 1 core reload, started installation of dunking chambers and cattle chute on November 1; core reload started the next day at 1145 hours0.0133 days <br />0.318 hours <br />0.00189 weeks <br />4.356725e-4 months <br />. Completed core reload on November 13 at 1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br />. After core verification was completed on November 15 and stroking of rods on November 17, efforts were concentrated to reassemble reactor pressure vessel (RPV) for hydro. The moisture separator was set, steam plugs pulled and platforms removed when on Novembsr 22 at 1800 hours0.0208 days <br />0.5 hours <br />0.00298 weeks <br />6.849e-4 months <br /> a breakdown of the overhead crane occurred, stopping all reassembly work.

After electrical and mechanical checkouts, the crane was signed off operable with restrictions on November 27, 1983 at 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br />. Vessel reassembly resumed immediately and on November 30 the vessel head was set and ready for stud tensioning.

B. Turbine - The unit 3 "C" low-pressure turbine inspection and repair con-tinued during November. The sandblasting was completed on the rotor and upper and lower diaphragms. Dovetail pin replacement started along with

the installation of buckets in the 13th stage turbine end.

I i

The reactor feedwater pump "C" maintenance was completed and the pump has i been reaseembled.

l i

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+ a

~

FIELD SERVICES

SUMMARY

November 1983 B. Turbine (Continued)

The reactor feedwater pump turbine "A" rotor and diaphragma were sandblasted and minor weld repairs are currently being made on the diaphragas.

C. Other Mechanical Work -

1. Valve repair 74-66 was carried over into November. Replacement of valve disc was slowed due to weld rod documentation problems and _

unexpected machining requirements of guide ribs. On November 15 valve repair 74-66 was completed, facilitating start of unit 3 torus drain down on November 16. Other valve repair work was performed on 64-series, 76-series and 84-series valves and main steam isolation valve (MSIV) controls. -

2. P0650 Redundant Air Supply was worked thru November with some pipe supports remaining to complete.

3 All control bay duct work inclusive insulation was completed on November 20.

4. Work on the remaining four condensate demineralizer tanks was completed on November 20, except PMT.

5. 79-02 ISI Hanger inspection was worked throughout November with five inspections remaining to complete at the end of the month.

-u s , - . . ..

I FIELD SERVICES

SUMMARY

November 1983 D. Electrical / Instrumentation - The month of November was spent resolving problems with modifications which are required for startup. This work wae as follows:

1. Resolving the design for sensing line hangers on P0322 (drywell wide-range pressure monitors), currently the hangers have been fabricated and installed on Elevation 593 and Field Services Group is awaiting an EN DES memo approving the hangers.

2. Connector problems (P0324 containment radiation monitors) have been a major concern of this modification. Currently trying to clean connectors and get them to function as designed. The connectors are very delicate and are located in the drywell where rubber gloves have to be worn. The post modification testing cannot be completed until the connector problem is resolved.

3 The sequential event recorder associated with P0533 was completed this month and the functional test is being performed now.

4. All work and testing associated with the recirculation motor-generator l

sets and recirculation pump motors was completed this month. This work supported the RPV hydro-1

, S. Surveillance instructions (SI's) are being performed on the P0126 instruments, as of this report no problems are being encountered.

l i

l

FIELD SERVICES

SUMMARY

November 1983 D. Electrical / Instrumentation (Continued)

6. An extensive effort was placed on getting a temporary fix to the cat track, af ter it was damaged during RPV assembly. This temporary fix allowed continuation of vessel assembly and reduced impact of the critical path schedule. It should be noted that af ter hydro is complete and the drywell head installed, the cat track will be replaced.

Other Electrical / Instrumentation:

1. Continued with the inspection of the cable tray supports.

2. Continued installing temporary power to support the unit 3 torus modification.

3. Prepared work plar.s fcr unit 3 cycle 5 refueling outage.

E. ALARA: Supported unit 1 and unit 3 refuel floor work during the entire month of November. Completed the control rod drive header hydrolaze on unit 3 and supported some shielding work on the header. Supported the shielding requirements in the unit 3 drywell for the ISI UT inspection.

Supported the torus group as they started the torus internal modifications l

on unit 3 F. -Planning and Scheduling: Emphasis continued to be placed on monitoring the work required to be completed prior to fuel loading of unit 1 and continued looking ahead to the requirement to support the reactor pressure vessel hydro.

i l

^ '

. _33_

FIELD SERVICES

SUMMARY

November 1983 F. Planning and Scheduling: (Continued)

Continued to review requirements for the unit 3 cycle 5 outage and worked some items such as flushing the recirculation system to lower the dose rates for the unit 3 ISI inspection and hydrolazing the CRD headers to lower the dose rate in general on Elevation 565 unit 3 G. Torus Unit 3: Set up for unit 3 torus and attached piping continued in November with air supply headers, welding machines and leads and torus ventilation system. On November 14 Williams Paint Contractor started overhead decontamination work inside torus and continued with controlled torus drain down starting on November 16. Decontamination and sandblast inside torus was completed on November 24. Set up and layout work started l immediately in preparation for start of modifications. Work inside vent-headers progressed to 95-percent complete. External torus modifications during November included drilling for eight of 16 torus snubber wall brackets and some installation of lapplates.

Torus Attached Piping: Tcrus attached piping crews prefabricated 36 supports in November and installed 51, boosting the totals to 72 fabricated ard 61 installed; in addition support for ISI work was provided. ISI inspected 105 pipe welds out of approximately 191.

~ s e A- M f

i FIELD SERVICES

SUMMARY

November 1983 H. Administrative: Tha overtime percentage for the month of October was 26- e percent with 152,604 straight-time hours and 54,201 5 overtime hours. As this was the first month cf FY 84, year-to-date overtime percentage straight time hours and overtime hours were the same. The overall goal of the overtime percentage is 17-percent.

l The O&M budget for October was 42,386,070 and the expenditures were

$3,893,880 with year-to-date budget being $2,386,070 and actual year-to- ,

date expenditures being $3,893,800. The capital budget was 42,528,500 and the expenditures were $2,063,655 with year-to-date budget being 32,528,535 and actual year-to-date expenditures being $2,063,655. Overall budget was 34,914,570 and the overall expenditures were 35,957,535 with year-to-date budget being $4,914 570 and actual year-to-date expenditures being 3

45,957,535.

I s Ex: -

t TENNESSEE VALLEY AUTHORITY Browns Ferry Nuclear Plant P. O. Box 2000 Decatur, Alabama 35602 DEC 0 91983 Nuclear Regulatory Commission Office of Management Information and Program Control Washington, DC 20555 Gentlemen:

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

/ /

G. .

r W ones we Plant Superintendent Enclosures cc: Director, Region II INPO Records Center Nuclear Regulatory Commission Institute of Nuclear Power Office of Inspection and Enforcement Suite 1500 101 Marietta Street 1100 Circle 75 Parkway Atlanta, GA 30303 (1 copy) Atlanta, GA 30389 Director, Office of Inspection and Enforcement Nuclear Regulatory Commission Washington, D. C. 20535 (10 copies)

Mr. A. Rubio, Director Electric Power Research Institute P. O. Box 10412

! Palo Alto, CA 94304 p

T I An Equal Opportunity Employer