ML20097A453

Monthly Operating Repts for Jul 1984

ML20097A453
Person / Time
Site:	Browns Ferry
Issue date:	07/31/1984
From:	Jones G, Thom T TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8409130274
Download: ML20097A453 (34)

Text

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TENNESSEE VALLEY AUTHORITY DIVISION OF NUCLEAR POWER BROWNS FERRY NUCLEAR PLANT MONTHLY OPERATING REPORT TO NRC July 1, 1984 - July 31, 1984 DOCKET NUMBERS 50-259, 50-260, AND 50-296 LICENSE NUMBERS DPR-33, DPR-52, AND DPR-68 Submitted by:

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[I B409130274 840731

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PDR ADOCK 05000259 R

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TABLE OF CONTENTS Operations Sumary.................... -..

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

3 Sigr.ificant Operational Instructions.............

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

11 Operatir.g Data Reports................

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

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

20

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Outage Maintenance & Major Modification...........

28 4

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Operations Summary July 1984 The following stamary 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 five reportable occurrences and no revisions to previous reportable occurrences reported to the NRC during the month of July.

4 Unit 1 There were no scrams on the unit during the month.

Unit 2 There were no scrams on the unit during the month.

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

Prepared principally by B. L. Porter.

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2 Operations % - arv (Continued)

July 1984 Fatigue Usage Evaluation The cumulative usage factors for the reactor vessel are as follows:

Location Usage Factor Unit 1 Unit 2 Unit 3 Shell at water line 0.00609 0.00490 0.00403 Feedwater nozzle 0.29185 0.21223 0.15429 Closure studs 0.23676 0.17302 0.13233 NOTE:

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

Comon System Approximately 6.82E+05 gallons of waste liquids were discharged containing approximately 7.47E-01 curies of activities.

. ~.., -,. -..

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Ooerations S = nary (Continued)

July 1984 Egfuelire Infomation e

Unit 1 Unit 1 is scheduled for its sixth refueling beginning on or about March 22, 1985 with a scheduled restart date of October 8,1985. This refueling will involve loading 8x8R (retrofit) fuel assemblies into the core, replacing recirculation piping, work on "A" and "B" low-pressure turbine, upgrade hangers and anchors, and environmentally qualify instrumentations.

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

Unit 2 Unit 2 is scheduled for its fifth refueling beginning on or about September 14, 1984 with a scheduled restart date of January 31, 1985. This refueling outage will involve leading additional 8X8R (retrofit) fuel assemblies into the core, finishing the torus modification, turbine inspection, finishing piping inspection, finishing TMI-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 E0C-4 fuel assemblies, 352 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 61 locations.

j.

All old racks have been removed from the pool and new HDR's are being i-l installed.

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4-4 Ooerations Sumary (Continued)

July 1984 Unit 1 Unit 3 shutdown for its fifth refueling outage on September 7,1983, with a scheduled restart date of September 1, 1984. This refueling involves load-ing 8X8R (retrofit) assemblies into the core, finishing the torus modifica-tions, postaccident sampling facility tie-in, core spray change-out, finishing TMI-2 modifications, turbine inspection, piping inspections for cracks, and changeout of jet pump hold-down beams.

There are O fbel assemblies presently in the reactor vessel. There are 248 new fbel assemblies, 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 150 locations.

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t Significant ODerational Events Date Tima Event Unit 1 7/ 01

0001 Reactor thennal power at 86-percent (%), power ascension in progress 0030 Comnenced PCIOMR from 865, thennal power 1230.

Reactor thennal power at 915, maximum flow, rod limited 1600 -

Reactor thermal power at 90%, maximum flow, rod limited 1900

. Reactor thermal power at 895, maximum flow rod limited 2100

. Reactor thennal power. at 88%, maximun flow rod limited 7/02 0100 Reactor thermal power at 875, maximun flow rod limited 1000 Reactor thennal power at 865, maximum flow rod limited 7/03 2340 Comnenced reducing thennal power for control rod pattern adjustment.

2400 Reactor thennal power at 76% for control rod pattern adjustment, increasing thermal power.

7/04 0425 Comenced power ascension from 865 thennal power.

0530 Comnenced PCIOMR from 915 themal power.

1605 Reactor. thermal power at 1005, maximum flow, rod limited.

7/crt 0200 Comenced reducing thermal power for turbine control valve test and SI's.

0210 Reactor thermal power at 93% for turbine control valve i

test and SI's.

0340 Turbine control valve test and SI's complete, comenced PCIOMR.

0730 Reactor thermal power at 1005, maximun flow, rod.

limited.

7/13 2200 Comenced reducing thermal power for a control rod sequence exchange.

7/14 0200 Reactor thennal power at 55% for control rod sequence exchange.

0515 Control rod sequence exchange in progress, increasing thermal power.

1011 Control rod sequence exchange complete, commenced power i

ascension from 64% thennal power.

1100 Comenced PCIOMR from 71% thermal power.

1310 "R" factor out-of-limits, reduced thennal power from 74%

to 735.

1700 "R" factor back in limits, comenced PCIOMR from 73%

power.

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

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

6 Sinnificant Ooerational Events Date Tima Event Unit 1 (Continued) 7/15 2130 Reactor thermal power at 100%, maximum flow, rod limited.

0215-Comenced reducing thermal power at request of load dispatcher.

0230 Reactor thermal power at 90% at request of load dispatcher.

0240 Comenced power ascension at request of load dispatcher.

3500 Reactor thermal power at 1005, maxima flow, ' rod limited.

7/19 0215 Comenced reducing themal power at request of load dispatener.

0230 Reactor thermal power at 90% at request of load dispatcher.

0240 Comenced power ascension at request of load dispatcher.

0500 Reactor thermal power at 1005, maximun flow, rod limited.

7/21 2227 Comenced reducing themal power for control rod pattern adjustment.

i 7/22 0100 Reactor themal power at 79% for control rod pattern adjustment, increasing thermal power.

0255 Control rod pattern adjustment complete, comenced power ascension from 85% themal power.

0430 Commenced PCIOMR from 86% thermal power.

1730 Reactor thermal power at 1005, maximm ficw,. rod limited.

7/28 0030 Comenced reducing thermal power for turbine control valve test and SI's.

0050 Reactor thermal power at 94% for turbine control valve test and SI's.

-0303 Turbine control valve test and sI's complete, comenced power ascension.

0700 Reactor thermal power at 100%, maximm ficw, rod.

limited.

I 7/30 1630 Comenced reducing thermal power due to condensate demineralizer problens.

1800 Reactor thermal peor at 90%, condensate demineralizer limited.

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Significant Ooerational Events Date Tim Event Unit 1 (Continued)

. 7/30 1945 Ccanenced power ascension from 905 the: mal power.

1955 Comenced PCIOMR from 96% thennal power.

2230 Reactor thermal power at 100%, maximm flow, rod limited.

7/31 2400 Reactor thermal power at 1005, maxim a flow, rod limited.

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8 Sinnificant Ooeraticnal Events Date Tima Event Unit 2 7/ 01 0001 Reactor thermal power at 59% to extend fuel cycle, and adninistrative hold because all ADS valve cables are routed through the same cable tray.

7/03 2300 Reactor thermal power at 60% to extend fuel cycle and adninistrative hold.

7/ 06 2300 Reactor thermal pcwer at 615 to extend fuel cycle and administrative hold.

7/08 0200 Reactor thermal power at 60% to extend fuel cycle and adninistrative hold.

7/12 2200 Commenced reducing thermal power to extend fuel cycle.

2400 Reactor thermal power at 55% to extend fuel cycle.

7/14 1600 Reactor thermal power at 56% to extend fuel cycle.

7/16 0525 Increasing thermal power from 56%.

0600 Reactor thermal power at 61% to extend fuel cycle and adninistrative hold (ADS valve control cables).

1400 Reactor thermal power at 60% to extend fuel cycle and administrative hold.

1900 Reducing thermal power to extend fuel cycle.

2100 Reactor thermal power at 53% to extend fuel cycle, 7/ 17 1315 Commenced power ascension from 53%.

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1600 Reactor thermal power at 61% to extend fuel cycle and administrative hold.

1730 Reducing thermal power from 61%.

2100 Reactor thermal power at 51% to extend fuel cycle.

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7/18 1025 Commenced power ascension from 51% thermal power.

l 1100 Rector thermal power at 60% to extend fuel cycle and administrative hold.

l 1800 Commenced reducing thermal power to extend fuel cycle.

2100 Reactor thennal power at 51% to extend fuel cycle.

7/19 1230 Increasing thermal power from 51%.

1300 Reactor thermal power at 53% to extend fuel cycle.

9 Rinnif'icant Doerationni Events L

'Date Time Event Unit 2 (Continued) 7/ 21 1215 Comenced power ascension from 535 themal power.

1500 Reactor thermal power at 615 to extend fuel cycle and administrative hold.

2000 Reactor thermal power at 605 to extend fuel cycle and administrative hold.

7/22 1300 Reactor themal power at 595 to extend fuel cycle and administrative hold.

7/23 0700 Reactor thermal power at 605 to extend fuel cycle and.

a&iinistrative hold.

0900 Comenced power ascension from 605 thermal power i

(administrative hold lifted).

1300 Reactor themal power at 755, maximum flow, rod limited.

1700 Reactor themal power at 755, maximum flow, rod limited.

2100 Reactor thermal power at 735, maximum flow, rod limited.

7/24 0100 Reactor thermal power at 725, maxima flow, rod limited.

0700 Reactor themal power at 715, maximum flow, rod 1hited.

1800 Reactor thermal power at 705, maximum flow, rod limited.

7/28 2300 Reactor thermal power at 695, maximum flow, rod limited.

7/31 2400 Reactor themal power at 695, maxima flow, rod limited.

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i 10 Sinnificant Ooerational Events Date Tima Event Unit 3 7/1 0001 End-of-cycle 5 refuel outage continues.

7/31 2400 End-of-cycle 5 refuel outage continues.-

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11 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO, 50-259 Orie WIT DATE 8/1/84 Ted Thom COMPLETED BY TELEPHONE (205)729-0834 MONTH July 1984 DAY AVER AGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe NetI (MWe-Net) 907 1046 37 836 1049

2

,3 871 1047 3

19 4

975 1046 20 1017 1026 5

21 018 969 6

22 7

1028 23 1046 1048 1046 8

24 1034 1043 9

5 1043 10 26 1041 gi 1045 1056 27 1040 1036 12

,3 1048 13 29 14 685 1034 30 955 3,

1048 15 1041 INSTRUCTIONS On this format,hst the average daily unit power leselin MWe Nei for each day in the reporting anonth. Compute to the nearest whole megawatt.

19/77)

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12 AVERAGE DAILY UNIT POWER LEVEL

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DOCKET NO. 50-260 UNIT Two DATE -8/1/84 COMPLETED BY Ted Thom TELEPHONE.(205)729-0834

' MONTH July 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net)

(Mwe. Net)

I 585 510 g7 582 521 '

2 gg 3

19 4

590 20 497 578 534 5

21 574 578 6

22 589 6d2 7

23 593 709 8

9 585 694 25 584 694 10 26 585 731 gg 7

12 583 701 33 582 702 13 29 530 698 g4 3g 15 533 687 3g 556 16 INSTRUCTIONS On this format.hst the average daily unit pinur leulin MWe Net for each day in the reporting inonth. Compute to the nearest whole nwgawatt.

e (9/77)

13 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-296 Thiee UNIT DATE COMPLETED BY (205)729-0834 TELEPHONE MONTH July 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (Mwe.NetI (MWe Net) 1

-5 17

-6 2

-5

-5 is

-5

-6 3

9

~

~

4 20

-5 23

-7

-5

~7 6

22

-5

~7 7

23

-5 7

8 24

~5

_7 25

-6

-/

10 26 II

-4 27

-6

-4

-7 12 3

-5

~7 13 29

-5

-8 g4 30

-5

-7 IS 31

-6 16 INSTRUCTIONS On this forrnas, list the average daily umt power lesel in Mwe.Ne' for each day in the reporting inonth. Compute to the nearest whole megawati.

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14 OPERATING DATA REPORT DOCKET NO. 50-259 DATE 8-1-84 COMPLETED itY Ted Thom TELEPilONE.(205)729-0834 OPER ATING STATUS

1. Unit Name:

Browns Ferry - One b" 8 '

2. Reporting Period:

July 1984

3. Licensed Thermal Power (Mht):

3293 1152

4. Nameplate Rating IGross MWe):

5. Design Electrical Rating (Net MWe):

1065

6. Masimum Dependable Capacity IGross MWe):

1098.4

7. af asimum Dependable Capacity (Net MWe):

1065

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

N/A

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

N/A

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10. Reawms For Restrictions.lf Any:

N/A This Month Yr. to Date Cumularise i1. Ilours in Reporting Period 744 5,111 87,673

12. Numher Of Hours Reactor Was Critical 744 4,629.10

_54,435.22

13. Reactor Reserve Shutdown flours 0

465.58 6,250.60

14. Ilours Generator On Line 744 4,508.95 53,226.59

15. Unit Resene Shutdown llour, 0

0 0

16. Gross Thermal Energy Generated (MWH, 2,383,044 13,799.488 152,357,167

17. Gross Electrical Energy Generated (MWill 768,640 4,556,830 50,202,430

18. Net Electrical Energy Generated IMWH) 748.596

_4.437,358 48,762.685

19. Unit Senice Factor 100 88.2 60,7

20. Unit Asailability Factor 100 88.2 60.7

21. Unit Capacity Factor IUsing MDC Neti 94.5 81.5 52.2

~

22. Unit Capacity FactorIUsing l>ER Neti 94.5 81.5 52.2 0

11.2

23. Unit Forced Outage Rate 22.9

24. Shutdowns Scheduled Oser Nest 6 Stonths IT.spe. Date,and Duration of Eacht:

I

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

26. Units in les Status irrior to Commercial Operationi:

Forecast Achiesed INillT L CHillCALf rY INiilT L ELECTRICITY CO\\f MERCI \\ L OPER A TION 19/77)

15-OPERATING DATA REPORT DOCKET NO. 50-260 DATE 8-1-84 COMPLETED BY _Ted Thom TELEPflO.NE (205)729-0834 OPER \\ TING STATUS N"

1.' Unit Name:

Browns Ferry - Two

2. Reporting Period:

July 1984

3. Licensed Thermal Power tmh ti: 3293 1152

4. Nameplate Rating (Gross MWe):

5. Design Electrical Rating (Net MWel:

1065

6. Masimum Dependable Capacity (Gross MWel: 1098.4

7. Masimum Dependable Capacity (Net MWel:

1065

8. If Changes Occur in Capacity Ratings (ltems Number 3 Through 7) Since Last Report.Gi e Reawns:

N/A

9. Power Lesel To Which Restricted.lf Any (Net MWel:

60%

10. Reawns For Restrictium. lf Any:

All automatic depressurization system relief valve,

cables are routed through same cable tray.

This Month Yr..to.Date Cumulatise

11. Hours in Reporting Period 744 5.I11

,82.614

12. Number Of Ilours Reactor was Critical 744 4,810.92 54,775.10

13. Reactor Reserse Shutdown llours 0

300.08 14.200.44

14. Ilours Generator On Line 744 4,760.59 53,253.43

15. Unit Resene Shutdown flours 0

0 0

16. Cron Thermal Energy Generated (MWH) 1.508.141 10.834.215 150.079.260

17. Gross Electrical Energy Generated (MWHi 463,030 3,465,920

,50.La3.208 447,4f9 3,366,978 46.:.'5,581

18. Net Electrical Energy Generated (MWill

19. Unit Senice Factor 100 93.1

_6. 5 100 93.1 64.5

20. Unit A$ailability Factor 56.5 61.9 n.3

21. Unit Capacity Factor (Using MDC Neti 56.5 61.9 55.3

22. Unit Capacity Factor (Using DER Net) 0 5.0 23.3

23. Unit Forced Ourage Rate

24. ShutJowns Scheduled Oser Nest 6 Months iT3 pe. Date.and Duration of Each t:

September 1984 - refuel 2L If Shut Down At End Of Report Period. Estimated Date of Startup:

26. Units in Test Status irrior to Commercial 0perationi:

Force.ast Achiesed INill t L CRIIICAlliY INI TI A L ELECTRICITY CO\\l\\ll:RCI \\L OPER A flON 19/77)

16 OPERATING DATA REPORT DOCKET NO. 50-296 DATE R-1-84 COMPLETED BY h1 Nm TELEPil0NE (2051729 0834 OPER ATING STATUS I. Unit Name:

Browns Ferry - Three Not**

2. Reporting Period:

July 1984

3. Licensed Thermal Power IMht):

3293

4. Nameplate Rating IGross MWel:

1152

5. Design Electrical Rating INet MWep:

1065

6. Maximum Dependable Capacity (Grou MWe):

1098.4

7. Maximum IH endable Capacity (Net MWe):

1065

8. If Changes O..ur in Capacity Ratings (ltems Number 3 Through 71 Since Last Report. Gise Reasons:

N/A

9. Power Lesel To Which Restricted.lf Any INet MWe

.N/A

10. Reasons For Restrictio.m. lf Any:

NA l

This Month Yr..to Date Cumularise

11. llours in Reporting Period 744 5.I11 65.039

12. Number Of flours Reactor Was Critical 0

0 43.087.80

13. Reactor Newne Shutdown flours 0

0 3,878.13

14. Ilours Generator On Line 0

0 42,193.71

15. Unit Rewrve Shutduan llours 0

0 0

16. Cron Thermal Ener;y Generated tMWill 0

0 126.307,711

17. Cros. Electrical Energy Generated lMWil) 0 0

41.597,620

18. Net Electrical Energy Generated IMhHp 0

.0 40.'i75.256

19. Unit Senice Factor 0

0 64.9

20. Unit Availability Factor 0

_0 64.9

21. Unit Capacity FactorIUsing MDC Neti 0

,0,,,,,,,

58.3

22. Unit Capacity Factor IUsing DER Net; O

O 58.3

23. Unit Forced Outage Rate 0

0 16.4

24. Shutdowns Scheduled 0ier Nest 6 Months tType. Date.and Duration of Eacht:

25. If shut Down At End of itepara Period. Estimated Date of Startup: Augunt 1984

26. Units 14 Test SlJeus iPrior to Commercial Operationi.

l'orecast A(hieted j

INill;\\ L ClllllCAlll Y INI TITI. El.tCTRICIT Y 00\\l\\1LitCI \\ L Ol'LH A IlON 19/77i

UNITSIIUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-259 UNIT NAME One DATE 8/1/84' COMPLETED BY Tod h=

REPORTStONill luiv 1984 TELEPHONE (205)729-0834

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Cause A Currectne

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Action t.e N'*-

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55 4

$E 5 5, =1 Rep we :

E0 5'

Prevent Recurrente u

d 28S 7/13/84 S

II Derated for control rod sequence j

exchange e==

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3 4

l F: F.wceJ Reas.m:

Stethe=l:

Estubit G-Instrisethnis

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S SshedureJ A-Eigurpment Fat!ure(Esplaini I 4tanual for Preparati.in of I)ata B-Wintenanceof Test 24fanual Scram-Entry Sheets Isw Licemec C-Refueling 3-Autimutic Stram.

Esent Repent iEl.10 File iNLiRI G-D-Regulat.wy Restri. cts w 44hher ( Esplaml 0161i F4)peratos Tsainingi tieuw I ununation F-AJannntrathe 5

G4)peratiosul E:rus iEaplaia)

Eshibit I Same S.msce rs/77)

III)ther (Esplaml l

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UNIT SilUIDOWNS AND POWER REDUCTIONS DOCKET NO. 50-260 UNIT NAME Two DATE 8/1/84 REPORT MONTH Julv 1984 COMPl.ETED BY Ted Thom TELEPHONE (7051724-0R14 E

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4 75 Ixensee h

h Cause A Currectise Na-Date i

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.555 Event sf 9?

Action to 2:_

E 5 5, =!

Repius

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Present Recurrence O

d 296 7/1/84 S

H Derated to extend fuel cycle and ad-ministrative hold because all ADS relief valve cables are routed through the same cable tray.

297 7/13/84 S

11 Derated to extend fuel cycle.

298 7/16/84 S

Same as 296.

299 7/16/84 S

11 Same as 297 g

300 7/17/84 S

H Same as 296 301 7/17/84 S

11 Same as 297 302 7/18/84 S

H Same as 296 303 7/18/84 S

H Same as 297 304 7/21/84 S

H Same as 296 l

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2 3

4 F: ForccJ Reasem:

Method:

Emhihis G - Instructi =ts i

l S-Ssheduled A-Equipment F.iilure(Esplain) 14tanual for Prep.iratisin of Data Bataintenanceof Test 2 Manual Scram.

Entas Sheets for Licensee

[

C Refueling J-Autornatic Ssram.

Esen's Repor iI.I RII'ile tNURI.G-l D-Regulatory Restristiim 44hher iExplain) 01616 l

1 -Operator Trainingi 1Aense Eunusunion F-Administrati.e 5

G-Operational Erros (Emplaial Estubit 1 - Same Source t**/77)

Ilfhher(Emplain) e' e

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.i UNITSilUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-296 UNIT NAME Three DATE 8/1/84 REPORT MONTig July 1984 COMPLETED gy Ted Thom TELEPHONE (205)729-0834

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Cause & Currectise Ud'c i

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4 jse Event u ~1 5-3 Attion to 55 ji-Repus E0 y'

Presen: Recurrente d

140 7/1/84 S

744 C

4 End-of-cycle 5 refuel outage continues (Controlled shutdown 9/7/83) 5 I

2 3

4 l'

F: FortrJ Reason:

ElethoJ:

1:stubit G - instructiimis l

S.: Ssheduled A Eqmpment Failure (Esplaint

!-mnual for Preparatii n sii Daia B-minnenance of Tes 2-mnual Scram.

Eni:3 Sheets (in t.acenwe C-Refucting 3 Autinn.stic Scram.

lhen: Repor I1.110 I~ileiNLiRI G-D-Regulatiny Restricti w 4Dahen IEsplaml Oltil i

1. Operator Training & 1Aenw Eumination F-Administrati<e 5

i G4)perational Enros tEsplaint I:shibit I - Same Source 49/77) 1IOther (EsplainI L

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11 J

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BR015S FERRY NLCLEAR PLANT UNIT 0 BF EMSIt. 30 CSSC Er!UIPME'.'T ELECTRIC.L :tAINTENANCE SLHMARY 9/29/82 For the M0 nth of July 19 84 l

Effect on Safe.

Re.wlts of l To Precin!c

'~l Operat Jon of Causo.of-8

[ Action i.sken

'.an:re of

=

Da:e systen Ca:.panent Maintenance The Reactor Malfunctian Malfunction i Re currese j

l1984 j 6/11 Standby 0-RLY-82-NVR.teplaced NVR None Vendor recom-Possible inoperability Installed new modelj presel relay mendation of diesel generator A NvR relay.

pknera tor loss of voltage alarm I

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MR # 254813

.I L 6/27 b'kVshut-

'l own board i

'and buses 0-BDAA-211-A Replace test None Bad trip and Not able to test trip Replaced bad trip ;

. trip and close close station and close breaker in and close station.

l station pushbutton compt. 17 of 4kV shutdown board A MR i 266174 w I

2storagd,0-BAT-39-25-30hReplaced 7/13 CO None Bad battery Low cell voltage Replaced bad battery fire pro-I battery tection &

{purging MR # 322740

,7/25 Air-condi-0-CHR-031-Replace sole-None Bad solenoid on Valve inoperable Replaced bad sole-tioning 0007B -

noid valve on purge unit noid valve.

chiller purge unit.

MR # 322846 7/25 Ventilating.O-FS-30-603 Replace flow None Paddle missing Flow switch inoperable Replaced bad, flow switch switch.

MR f 266192 i

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1 f

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A3 U

J 21 J

4A 5

J 3 14 in-aJ

--48

s7 J

J

=J 371

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~Ci BROWNS FERRY NUCLEAR PLANT UNIT I

B EM IL.30..,

CSSC EOUIPME'.'T ELECTRL L ::AINTENANCE SDIMARY 9/29/82 For the Month of July 19 84 1:ffect on Safe.

.\\c t ion ~JI:cen e

Nature of Operation of Cause.of Re.vilts of

TO Preci..le Date Sv st er C =ponent

!!aintenance The Reactor Malfunctian

? a1 funct ian Recurre ne a

1984 1/27 Raw servic 2 1 & 2-ANN Replace AFI air None Bad switch Aanunciation Replaced bad'swit'ch.

water 41A flow switch MR # 207922 l

ji 1/27 Raw servic'e 1 & 2-ANN-25 gReplace AFl air None Bad switch Annunciation Replaced bad switch.l water 41C flow switch 1

MR # 207923 3/9 6 Air 1-FAN-31-161A; Replace fan None Bad fan motor Fan motor trips on Replaced bad fan f

condition-.

notor overload motor.

I"E MR # 140633 l

w 3/13 L' nit pre-1-000-252-000 Replace switch None Bad switch volt-Annunciation Replaced bad switch ferred voltmeter on meter g

120VAC unit preferred local control MR # 267850 cabinet 5/30 Standby 1 & 2-CEN-82-B. Replace overload None Bad overload Lube oil circulating Replaced bad over-diesel relay relay pump will not run load relay.-

generator MR # 252792 RIIR service 1-LA-23-80A Replace level None Bad level switch Anc.tuciation Replaced bad level 8

1 6/22 i

water switch switch with new model' switch.

MR.# 265985 I

6/26 Main 1-FCV-1-1-55 Replace rela 3 None Bad coil FCV-1-1-55 will not Replaced bad coil j i

steam coil operate from control switch on pal 9-3 MR # 267386 l

None Unknown 1-PCV-001-0004 Valve tested 0.K.

j 6/27 Main 1-PCV-1-4 gTest operated prematurely

, steam l

g during unit startup MR # 266175,

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EMS R 30 CSSC D!!!!P tE'.T ELECTRIC.U.'!L\\INTENANCE SD12tARY 9/29/82 84 For the Ibnth of

. July gg t

Effect on Safe, j Act ion 7

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i Na:are of i

Operation of Caus. of Results of f, To Prec N!e Date Svste :

Cc.=ponent Staintenance l The Reactor Malfunctian

!!alfunctinn i Recurrcnce 1984 J

6/30 Control 1-HS-85-48 Replace spring None Broken springs HS-85-48 inoperable Replaced bad switch rod drive in switch MR #'257451 t

7/10

' Residual I l-MG-74-lDN Replaced motor None Failed generator Motor-generator set Installed new motor l

land generator inoperable and generator.

heat re-e moval MR # 263352 7/16

' Reactor 1-FAN-64-12C None Bad breaker Fan trips off Replace bad breaker.

Ibidg. beat feplacebreaker MR # 266027 ling&

l tventilatioc l 7/28 RHR service 1-MIR-23-8 Replace R1 relay None Bad relay Cl RHRSW pump failed Replaced bad relay.

vater to start during per-g formance of l,

SI 4.9.A.3.a MR # 322596 i

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M BROWNS FERRY NUCLEAR PLANT UNIT BF EMSIL.30 Appe: dix B CSSC EQt*!P?tD.T ELECTRIC?.L !!AINTENANCE SRDIARY 9/29/82 For the Lnth of July 19 84' T.ffect on Safe, j Act ion 's n en -

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Nature of Operation ot ~

Ca u s.* of Results of-

[ To Prcelode Date !

Svste= '

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>*aintenance The Reactor Malfun t..w.

Stal f unc t ion i Recurre ee

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1984 7/12 Unit pre-

,2-CEN-252-2 Replace exciter 1>ne Bad belt Unit preferred MC Installed new ferred belt set inoperable exciter belt.

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MR #.322568 4'

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.o CSSC Ent?!P'!ENT ELECTRICALP.INTE*;A*;CE SL7: MARY 9/29/82 For the SDnth of July 19 84 F.i f ec t on Sa:e,

acti.,n l'.en i

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'.ature of Operation at Ca i r. - o' Re..alts ci Ta Prc. ;

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3/8 Standby l 3-RLY-82-TRB-3 Replace rela; None Cracked coil spoo'l None

, Replaced bad relay. l hdiesel t

,enerator rJt # 254754 g

g 3/21 AkV shut-l3-RLY-211-275/jReplacerelay

ene l Cracked coil spoo L None

' Replaced bad relay

!down boards'3CX coil coil.

f5 buses

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MR # 254769 l

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,fdewnboard,l Spare 4/11 AkV shut-3-RLY-211-l Replace relay None lCrackedcoilspoolNone l Replaced bad relay

' coil coil.

h& buses fMR # 254774 I

I 7/1 CO3 storagd.3-TA-39-113 jReplace kl relay None i Bad relay Annunciation Replaced bad relay.

!firepro-i ea ltection &

MR # 257739 fpurcine 7/9

Radiation 3-Cr!-90-251 l Replace power None Toggle switch Possible fire hazard.

Replaced bad switch.

• =cnitoring switch burned up MR # 257642 7/10 acontrol 3-FCV-85 Replace sole-None Coils in scran lValveinoperable l Replaced bad sole-rod drive noids pilot solenoid I

'noids.

E MR # 257645 7/26

.,RHR servic 3-RHRL'-Pu=p

, Replace R1 relay None Bad relay RHR service water Replacedbadrel%.,

water

, start pu=ps B1, C3. & D1 did not auto start during S1 4.2.B-39A MR # 312616 7/27 gSattery 3-FU-2SO-3C Replaced in-None Oversized fuses Inadequate fuse Replaced with correct

.bcards correct fuses protection for I&C bus fuses.

I l1.2.3&4 MR # 254952 i

7/23

, Residual 3-!TIR-74-39 Replaced secondy ';one i Bad secondary No green light when Replaced secondary iheat re-ary disconnect l block breaker is racked in; disconnect block.

• = oval block does have green light MR # 314317 in test position.

'. 4 BROWNS FERRY E0 CLEAR H. ANT UNIT Comunon CSSC ECU11"ENT MECHANICAL MAINTENANCE SOfftARY For the Month or Juiv 19 84 l

l EFFECT ON SAFE ACTION TAKEN i

DATE SYSTEM COMPONENT NATURE OF

. OPERATION OF CAUSE OF RESULTS OF 70 PRECLUDE l

MA I!,TEXAMCE THE araCTOR MAfFUNCTION MAf_ FUNCTION aret!335W'F 7/3 85 0-ACU-85-3847 Rchuild water None None N/A N/A l

ac..wl..t or and i

store for spare l

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CSSC ECUIPEEET MECHANICAL MAINTENANCE SUlefARY For the Month of J"IY 84 19 EFFECT ON SAFE ACTION TAKEN DATE SYSTEM COMPCNEIT NATURE OF GPERATION OF CAUSE OF RESUL.S OF TO PRECLUDE MATETENANCE THE araCTOR MALFUNCTION MAfFUNCTION RECDsaract 6/25 85 2-ECv-85-22-07 Rcpair water None Defective 0-ring.s Leak Repaired on accumulater MR A-252811 0/30 SS 2-ECV-85-38-47 Repair accumulato r Kone Normal usage Accumulator Repaired on alarm would MR A-257554 not clear u

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CSSC EQUIPMENT MECHANICAL MAINTENANCE

SUMMARY

^

For the Month of July 19 84 ACTION TAKEN EFFECT ON SAFE DATE

, SYSTEM COMPONENT NATURE OF OPERATION OF CAUSE OF RESULTS OF TO-PRECLUDE L

MAINTENANCE THE REACTOR MALFUNCTION MALFUNCTION RECURRENCE 6/18 67 1-CLR-67-0909 Clean Coolers None Routine Mainte-N/A N/A nance 6/28 85 1-FCV-85-0039A Repair leak None Unknown Control rod Repatred'on MR was in past-

'A-257383 "00" 7/16 85 1-PMP-85-001 Replace gasket None

' Normal use

_ Leak Repaired on MR A-266148

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.0UTAGE MAINTENANCE & MAJOR MODIFICATION MANAGEMENT F

JULY 1984 I.; ' Work Synoosis-A.

During the July report period the unit 3 outage progressed through.

day number 329 of what is presently scheduled to be a 371-day outage.

Projected milestone dates from the July 31,-1984, schedule update were as follows:

Open Fuel Pool Gates 8/3/84-

' Start Core Reload 8/9/84 Start RPV Reassembly 8/24/84 Start Reactor Vessel Hydrostatic Test 8/29/84 Return Unit 3 to Service 9/12/84 B.

Major field activities for the unit 3 outage effort during the July report peried include progression of ECN P0392 CRD-Syste::1 Scram Discharge Instrument Volume Modification work to the point of completion of post-modification testing which allowed preliminary CRD testing to begin July 30,- 1984.

II. Mechanical Summarv - Modifications Section A.

Jet pump instrumentation nozzles weld overlays were completed and Non-Destructive Examinations (NDE) reported satisfactory.

B.

Main Steam Isolation Valves - valve restoration lacks completion of ECN P0621 installation of locking tags and limit switch mounting plates. Limit switch bracket installation and mounting of the switches was reported at 65-percent complete on inboard valves.

C.

ECN P0730 removal of RHR head spray piping (from unit 3) was reported.

i field complete.

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29 OUTAGE MAINTENANCE & MAJOR MODIFICATION MANAGEMENT JULY 1984 II. Mechanical Si===ry - Modifications Section (Continued)

D.

Diesel generator modifications (electrical and mechanical) were completed on the "1A," "B," and "C" diesel generators. These modifications include:

P0585 Replacement of Existing Speed Sensing Equipment with Solid State Equipment P0185 Loss of Field Trip Bypass When in Emergency Mode-P0275 Degraded Voltage Relays P0709 Throttle Valve Installation in EECW Piping -to the Cooling Water Heat Exchangers L1970 EECW Piping Changeout (Carbon Steel to Stainless) - partial i

Note that these modifications were previously completed on the 3A, B, C, and D diesel generators.

E.

Three recirculation system snubbers were removed for maintenance.

F.

ECN P0361 Modification work on torus attached piping progressed through field completion of 447 of 457 required supports.

G.

The 79-02 hanger inspection program effort reported 337 of 387 complete at the end of July.

H.

Preparations are in progress to coat the lower drywell elevations (including structural steel).

I.

P0569 Replacement of RPV Head Vent Valves 3-98 and 3-99 is approximately 90-percent complete. Solenoid valve hookup and limit a

switch installation was tested satisfactorily from the control room.

J.

P0695 Modification to Selected 84-System valves to allow Local Leak l

Rate Test (LLRT) to the Flange Sides was reported field complete on July 17, 1984.

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OUTAGE MAINTENANCE & MAJOR MODIFICATION MANAGEMENT JULY 1984 II. - Mechanical Summarv - Modifications Section (Continued)

K.

P0691 (similar to P0695 described above) was continued on selected 64-series valves.

L.

P0684 Modifications to the Drywell-to-Torus Vacuum Breakers was.still in progress this month.

M.

RHR Loop I and II maintenance and modification work was completed to a point that allowed release of these systems to the operations section for lineup and tests.

N.

Refuel floor efforts this month have included:

1.

Unit 2 high density fuel storage rack preparation work 2._

Unit 3 refuel platronn maintenance 3.

Lost article search in the unit 3 reactor vessel 4.

SRM dry-tube inspection - no relevant indications found III. Electrical Summarv - Modifications Section A.

ECN PO4151 Temperature Instrumentation on the reactor feedwater

-nozzles was reported field complete on July 19, 1984.

B.

P0399/P0422/P5097 Correcting I&C bus voltage problems and RPS modification to provide redundant class IE protection were continued this month. The bus outages for transformer hookups associated with P0399 were completed. PO422 was reported field complete July 23, 1984.

C.

P3138 Replacement of RHR Pump Room Cooler Fan Motors was reported field complete this month.

E

~31 OUTAGE MAINTENANCE'& MAJOR MODIFICATION MANAGEMENT JULY 1984

'III ' Electrical 9== nary '- Modifications Section (Continued) i D. - _P3006 System-73 Pressure Switch Repoacement was reported field t

complete July 6, 1984.

E.

P0631 Relocation of RHRSW Radiation Detector - Work per this ECN has been delayed due to four-week delivery time for cable connectors.

IV. flp3ning and Scheduling A.-

The principal unit 3 efforts have centered around monitoring the work progress versus the schedule projections in order to identify delays and gains so that this infonnation could be applied to additional 1

schedule refinements.

B.

Unit 2 planning and scheduling work continues in preparation for the presently scheduled September 14, 1984, start of the unit 2 outage.

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.,5 TENNESSEE VALLEY AUTHORITY Browns Ferry Nuclear Plant P. O. Box 2000

)

Decatur, Alabama 35602

~AUG 0 91984 Nuclear Regulatory Commission Office of Management Information and Program Control Washington,-DC 20555 Gentlemen:

Enclosed is the July 1984 Monthly Operating Report to NRC for Browns Ferry Nuclear Plant Units 1, 2, and 3.

Very truly yours, TENNESSEE VALLEY AUTHORITY hb 4)VY G. T. Jones Plant Manager 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.

20555 (10 copies)

Mr. A. Rubio, Director Electric Power Research Institute 4

P. O. Box 10412 Palo Alto, CA 94304 Y

i 39 I

I

.I An Equal Opportunity Employer

_