ML20091K919

Monthly Operating Repts for Apr 1984

ML20091K919
Person / Time
Site:	Browns Ferry
Issue date:	04/30/1984
From:	Jones G, Pittman J, Thom T TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8406070244
Download: ML20091K919 (36)

Text

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TENNESSEE VALLEY AUTHORITY DIVISION OF NUCLEAR POWER BROWNS FERRY NUCLEAR PLANT MONTHLY OPERATING REPORT TO NRC April 1, 1984 - April 30, 1984 DOCKET NUMBERS 50-259, 50-260, AND 50-296 LICENSE NUMBERS DPR-33, DPR-52, AND DPR-68 Q

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I 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 Outage Maintenance & Major Modification . . . . . . . . . . . 27

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April 1984 i

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g following summary describes the significant operation activities during the. reporting period. In support of this suninary, a chronological log of

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significant events is included in this report.

,c There were four reportable occurrences and five revisions to previous

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[y reportable occurrences reported to the NRC,,during the month of April.

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' I 5(,.8Joit 1 i E There- were no' scrams on the unit during the month.

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There were no scrams on the unit during the month.

IlnitL3 The unit was in cold shutdown the entire month for the unit's end-of-cycle 5 refueling outage.

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Prepared principally by B. L. Porter.

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N Operations 9w= nary (Continued)

April 1984 M'g h ..- - '

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

Location Usane Factor i.% 1. .. , '

- 4 Unit 1 Unit 2 Unit 3 Shell at water line 0.00598 0.00486 0.00403 4pf 1: Feedwater nozzle. 0.28846 0.21103 0.15429 h; Closure studs 0.23477 0.17236 0.13233 e.

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

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Common System

1. Approximately 6.10E+05 gallons of waste liquids were discharged containing approximately 5.53E-01 curies of activities.

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3 Operations Sn=narv (Continued)

April 1984

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Refueling Information Unit 1 Unit 1 is scheduled for its sixth refueling beginning on or about February 8, 1985 with a scheduled restart date of August 27, 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 E0C-5 fuel assemolies, 260 EOC-4 fuel assemblies; 232 EOC-3 fuel assemblies; 156 EOC-2 fbel 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 August 1, 1984 with a scheduled restart date of December 31, 1984. This refueling outage will involve loading additional 8X8R (retrofit) fuel assemblies into the core, finishing the torus modification, turbine inspection,finishingpipinginspection,finishingTHI-2hiodifications; 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 E0C-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 601 locations.

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Ooerations Sin == ry (Continued)

April 1984 Unit 'l Unit 3 shutdown for its fifth refueling outage on September 7, 1983, with a scheduled restart date of August 1, 1984. This refueling involves loading 8X8R (retrofit) assemblies into the core, finishing the torus modifications, 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 4own 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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. . 5 Significant Ooerational Events Date Time Event Unit 1 4/1 0001 Reactor thermal power at 57-percent (%) and reducing for control rod sequence exchange.

0300 Reactor thermal power at 52% for control rod sequence exchange.

0600 Increasing thermal power, control rod sequence exchange in progress.

1230 Control rod sequence exchange complete, comenced power ascension from 57% thermal power.

1430 Comenced PCIOMR from 875 thermal power.

4/2 1130 Reactor themal power at 100%, uaximum flow, rod limited.

4/3 0045 Received high vibration alam on "B" recirculation pump,

. reducing themal power.

0200 Reactor themal power at 98% due to "B" recirculation pump high vibration.

1200 Reactor themal power at 97% due to "B" recirculation

. pump high vibration.

1930 Comenced reducing thermal power for removal of "C" reactor feed water (RFW) pump from service for maintenance and control rod pattern adjustment.

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2100 Reactor thermal power at 74% for "C" RFW pump maintenance and control rod pattern adjustment.

2130 Comenced rod withdrawal for control rod pattern adjustment.

4/4 0045 "C" RFW pump back in service, reactor power at 76% and increasing for rod pattern adjustment.

0200 Control rod pattern adjustment complete, commenced power l~ ascension from 80% thermal power.

0400 Comenced PCIOMR from 85% thermal power.

l- 1500 Reactor thermal power at 99%, holding on PCIOMR due to L computer problems.

1835 Comenced PCIOMR from 995 thermal power.

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

l 4/5 1800 Reactor themal power at 995, maximum flow, rod limited.

4/6 0130 Comenced power ascension from 99% thermal power.

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

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Sinnificant Ooerational Events

'Date- Ti r= Event Unit 1 (Continued) 4/7 0030 Commenced reducing thermal power for turbine control e valve test and SI's.

10200 Reactor power at 86% for turbine control valve test and SI's.

~0345 Turbine control valve test and SI's complete, comenced

. power ascension.

'0400 Commenced PCIOMR from 965 thermal power.

0520 -Reactor thermal power at 1005, maximum flow, rod limited.

< 4/8 1200 Commenced reducing thermal power for removal of "B" RW pump from' service for maintenance.

1305 "B" RW pump out-of-service for maintenance, reactor power at 735.

1500 Reactor power at 72% for maintenance on "B" RW pump.

2200 "B" RW pump back in service, reactor power at 73%,

holding for removal of "C" RW pump from service for maintenance.

2215 "C" RW pump out-of-service for maintenance, reactor power at 73%.

4/9 0248 "C" RW pump back in service, commenced power ascension.

0400 Commenced PCIOMR from 97% thermal power.

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

0515 Comenced reducing thermal power due to "R" factor being '

out-of-limit.

0600 Reactor power at 985, "R" factor limited.

0830 Reactor power at 975, an" factor limited.

l 0900 Comenced PCIOMR from 975 thermal power.

1400 Reactor thermal power at 100%, maximum flow, rod limited.

1600 E~ actor thermal power at 995, maximum flow, rod limited.

1845 Comenced power ascension from 995 thermal power.

(. 2100 Reactor thermal power at 100%, maximum flow, rod limited.

4/10 1000 Reactor thennal power at 995, maximum flow, rod limited.

1435 Control rod 34-03 scrammed during performance of TI 60,

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reduced thermal power to 98% (bad solenoid valve on CRD 34-03).

! 1825 Solenoid valve repaired on CRD 34-03, reducing thermal j power for scram timing control rod 34-03.

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p I' 7 Sinnificant Operational Events Date Time Event Unit 1 (Continued) 4/10 1900 Reactor thermal power at 91% for scram timing control

-(Cont'd) rod 34-03 1928 Scram timing complete on control rod 34-03, comenced power ascension.

2030 Comenced PCIOMR from 98% thermal power. ,

2300 Reactor thermal po'ar at 1005, maximum flow, rod limited.

4/14 0106 Comenced reducing thermal power for SI 4.3. A.2 (Control Rod Drive Exercise).

0142 Reactor thermal power at 855 for SI 4.3.A.2.

0330 SI 4 3.A.2 in progress, increasing thermal power.

0600 Completed SI 4.3.A.2, comenced power ascension from 93%.

0637 Commenced PCIOMR from 94% thermal power.

1500 Reactor thermal power at 100%, maximum flow, rod limited.

4/20 2346 Comenced reducing thermal power for turbine control valve tests and SI's.

4/21 0300 Reactor thermal power at 85% for turbine control valve tests and SI'c.

0510 Turbine control valve test and SI's complete, comenced power ascension.

0700 Reactor power at 100%, maximum flow, rod limited.

4/27 2200 Commenced reducing thermal power for turbine control valve test, SI's, and control. rod pattern adjustment.

4/28 0200 Reactor thermal power at 67% for turbine control valve tests, SI's, and control rod pattern adjustment.

0420 Turbine control valve tests, SI's, and control rod pattern adjustment complete, comenced pcwer ascension.

0600 Commenced PCIOMR from 93% thermal power.

0800 Stopped PCIOMR at 96%, holding due to Xenon transient.

1000 Comenced PCIOMR from 96% power.

1300 Reactor thermal power at 100%, maximum flow, rod limited.

4/30 2400 Reactor thermal power at 100%, maxim flow rod limited.

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Sinnificant Ooerational Events Date Time Event Unit 2 4/1 -0001 Reactor thermal power at 62%, derated to extend full cycle.

4/8 2300 Reactor thermal power at 61%, derated to extend full cycle.

4/13 2300 Reactor thermal power at 62%, derated to extend full cycle.

4/14 1500 Reactor' thermal power at 615, derated to extend full cycle.

4/16 0001 Reactor thermal power at 625, derated to extend full cycle.

4/17 0700 Reactor thennal power at 61%, derated to extend full cycle.

4/25 1500 Reactor thermal power at 60%, derated to extend full cycle.

4/29 1500 Reactor thermal power at 61%, derated to extend full cycle.

4/30 2400 Reactor thermal power at 61%, derated to extend full cycle.

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.. . 9 Sinnificant Ooerational Events Date Tima Event Unit 3 4/1 0001 End-of-cycle 5 refuel outage continues.

4/30 2400 End-of-cycle 5 refuel outage continues.

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. . 1n AVERAGE DAfLT' UNIT POWER LEVEL

, DOCKET NO. 50-259 UNIT One

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DATE COMPLETED BY _Ted Thom TELEPHONE 205/729-0834 MONTH April 1984 DAY AYERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe Net) g yg,.3,, ,

1 750 37 1075 2

1060 1082 g3 012 1979-3 g 4 992 1079 20 5 1078 1042 21 6

1083 1977

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7 1062 23 1076 8 923 1078 24 9 1032 1078

's 10 1069 26 1080 11 1081 1050 27 1081 988 12 ,3 g3 1074 1073 29 1038 1072 I4 30 15 1090 1079 16 INSTRUCTIONS On this normat.hst the average daily unit powet lesel m \1We Net tier ca h Ja> in ihe repi'ning month. C. impute eo the ticatest whole megawatt.

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.' l AVERAGE DAILY UNIT POWER LEVEL

- DOCKEINO. 50-260 UNIT Tm DATE 5/1/84 Ted Thom C0\fPLETED BY TELEPilONE 205/729-0834 MONTH April 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE D \lLY POWER LEVEL (MWe Net) IMWe-Neal

, 634 628

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. 639 632 2 IS 3 638 19 627 4

632 626 0

640 5 23 639 624 6 ,,

7 635 620 23 3

632 24 629 619 9 25 10 629 619 26 gg 632 27 629 625 g *, ,

.3 13 629 590 29 633 617 34 30 15 636 31 16 632 INS'IRUCTIONS 8 """ I'""'#' I#'d "' MWe Net it'r e^li <!a) in the re;i..iting in., nth. Ganyim he I e nearest h$1 ga

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. 12 AVERAGE DAILY UNIT POWER LEVEL e

• DOCKET NO. _50-296 UNIT Three

!04 DATE COMPLETED By Ted Thom TELEPif0NE 205/729-0834 MONTH April 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe Net) (MWe. Net) g ~3 -3 37

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~3 ~3 2 18 3 -3 19 -4 -

4 -3 20 -3 5

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-4 6 -3 22 -3

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-3 9 3 25 -3 10 -3 26 -3 ll

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-3 _3 14 30

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_3 INSTRUCTIONS

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• 13 OPERATING DATA REPORT DOCKET NO. 50-259 DATE 5/1/84

' CO\1PLETED tty Ted Thom TEl.EPIIONE ?ns/729-0834 l OPf AtlNG STATUS I. 0 nit Name; Emns Feny - One Noh

2. iteporiing Period: _ April 1984

3. I.icerise'<l thennal Pows (MWt): 3293

4. NamepidliRatirig (D'oss r MWei: 1152

5. Design.th$tricai Miilirijt INel Mhep 1065

6. MaxindN pependsble "Cahacity (Gnm'.\iWel: 1098.4

7. M.uimiini Dependabie l' apScity (Net .\lWe): 1065

8. if Ghanges Occ,br in Cap' acity Ratine litems Number 3 Through 71 Since Last Report. Give Reason 4:

N/A

9. Power Level To Whichi Restricted. if Any INet .\lwep N/A

10. Reasons For kestricli,Un,if Any: N/A ,

~lhis Month Yr. to Date Cumulatise il llohrs in kepUrthig Periud 719 2,903 _ 85,465

12. Numlier Of lidurs Hes'chlr Was Critical 719 _2_,661.28 52.467.4

13. Reactor Reserve Shutdown floan _0 225.40 6.010.42

,14. Ilours Generator On.Line 719 2,565.38 51,283.02

15. Unit Resene Shutdo' n llour, 0 0 0

16. Gross ihermal Energy betterated l31Will 2,294,374 7,562,932 146,120,611 17 tiross Electrical Energy benerated lMwill _772.401,_ _,, M 46.080 48.191.700

18. Nei Electrical Energy Generated IMWill 154,_,120 L481,136 46,806,463 100 88.4 60._0

19. Unit Senich Factor

20. Unit Availability Factor 100 88.4 60._0

21. Unit Capacity Factor IUsing MDC Neti 98.5 80.3 , 51._4

22. Unit Capaciti Factor IU>lhg 1)ER Nei, 98.5 80.3 51.4 23 linit Forced Outage Rate 0 10.6 23.2

24. Shutdowns Scheduled User Neu 6 Months flype. Date.and Duration of 1:ashi Nem

25. If Shut Down At End Of Report Pe riod. Estimatni li. ire ut Startup

26. Units in Test StatusIPrior to Conuncreial operationi. I niecast Achiesed INiil \ L C RlllCAI.11 Y INill \ L I:1.1.C I Ricil y \

COtiMI RCl \1 ol'I'll g lion 07/77) w., wax w a.--.~.

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. OPERATING DATA REPORT DOCKET NO. 50-260 DATE 5/1/84

'a COMPLETED By Ted Thom

• ',-, - TELEPil0NE 205/729-0834 OPEkATINb TATUS*

1. Unit Name: Browho Ferry - Two N"t"

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2. Reporting Period: " 1, April 1984 3293 3.1.icensed Tlierm'al Potrer (MNt):

. 4._ h'ameplath Raling (Giuss MWe): 1152

- 5. Design EINtrical Raths { Net MWeJ: 1065 6.. Maximutd Dependable Capacity (Cross MWel: 1098.4

-7. Maximum bepend'able tapacity,(Net MWe): -.1065

8. if Changes Occur in Capacity Ratings (liems Number 3 Through 7i Since I.ast Report. Gi.e Reasons: .

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N/A 9.- Poder Level To Whlelt Restricted. II Any N/(Net MWe)A

10. Rea>ons For Restrictlos.lf Any: ,

. This Month Yr.to D.ste Cumu!.ith'c II. Hoursin heportinh Period

• 719 2.903 _0.406 8

12. Nulnber Of Hours Re'adtor Was Critical 719 2,612.84 52,577.02 0 _290.16 14,193.52

13. Reactor Resene Sinitdhn flours

- ,14. HoursGenerator Onl.lde ,

719 2,568.14 51,060.98

15. Unit Reserse Shutdown flour, 0 0 0

16. Grow Thermal Energy Generated (MWill 1.452.694 L 487.222 146.632.267

17. Gron Electrical Energy Generated (MWil) 461,900 2,113,070 _

48,710,358

18. Net Electrical Energy Generated (MWil) 450.808 2.056.996 47.315.599

19. Unit Service Factor _100 88.5 63.5

20. Unil Asailability Factor 100 88.5 63.5 21, Unit Capacity Factor IUsing MDC Neil 5_8. 9 66.5 55.3

22. Unit Capacity Factor (Using DER Neti 58.9 66.5 55.3

23. Unit Forced Outage Rate _0 8.3 24.I

24. Shutdowns Scheduled Over Nex16 Months ITy pe.1) ate.and linration of I athi.

August.lS84 - Refuel _ _._

25. If Shut Down At End Ofiteport Period Estimaint Date of startup __

26. Units in Test Status IPrior o Conunercial Operationi I ..reas Achiesed INITIA L CitillCAl.IIY 4

INITIA L Ll.1 C I Rif fi Y _

COMM ERCIT L OPl !! A f lON _

(9/77)

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. .~ 15 OPERATING DATA REPORT DOCKET NO. 50-296

, DATE 5/1/84

. CO.\tPLET ED BY Ted Thom TELEPIIONE 205/729-0834 OPElkAtlNG SYATUS Browns Ferry - Three N"te'

1. l] nit Name:

April 1984

2. Reporting, Period: -

3. Licensed Titdm:ilhower (SIWil: 3293 1152

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- 4. Na'meptale Rating ('Gro,ss htWe):

5. Desigri ElEcNical' Rein (Net $1We): 1065 C. Maximisin Dependabl$ C g $pacily (Gross htWel:

1098.4

'7. Maximism Dehendabl4 Capaciiy (Net SIWE): 1065

8. if Ghanges occur in Capacity katings (items Number 3 Through 71 Since L.nl Report. Gi.e Reasunc N/A

9. Power Level to Which Restricted. If Any (Net SlWel: N/A

10. Reawns For Restrictions.If Any. N/A This Stunth Yr. to Date Cumulatisc I1. Nours Id Reporting Period 719 2,903 62,831 0 0 43,087.80

12. N mlier df flours Reactor Was Critical 0 0 3,878.13

13. Reactor Resene Shutdown liours

,14. Hours Generator On-Line 0 0 42.193.71 -

15. Unit Reserve Shutdown llours 0 0 0 0 126,307,711

16. Gross Thermal Energy Generated (SIWil) _0 17, Gross Electrica! Energy Generated (MWil) 0______. O _ 41.597.620 0 0 40,375,256

18. h,'et Electrical Energy Generated (MWil,

19. Unit Senice Factor 0 0 67.2

20. Unit Availability Factor 0 0 67.2

21. Ilnit Capacity Factor (Using SIDC Nc 1 0 0 60.3

22. (Jnit Capacity Factor (Using i Elt Net 1 0 0 60.3

23. lJnit Forced Outage Rate 0 0 16.4 24; Shutdowns Scheduled Over Nest 6 Stonths iTs pe. Date, and Duration of I acht-

25. If Shut Down At End Of Report Period. E t; mated Date ol~ Startup. _Au. gust 1984

26. Units in Test Status (Prior to Commercial operation): 1:orec.nt Aihiesed INITI A L CRillCAll t Y INITI \ L ELI C I RlCI1 Y CO\t%1ERCI \ L Ol'1 R \IlON 19/77) u% 2.. , w au ~. :. < r n ..w..-.. . ~ . .. ,

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' UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKETNO. 50-259 UNITNAME One DATE 5/1/84 REPORT MONTH April 1984

• COMPLETED gy Ted Thom TELEPHONE 205/729-0834 i .

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3m Event g,7 gg ac,in, ,o oO e 3mj Report ir mo o Prevent Recurrence i 6 277 4/1/84 S B Derated for control rod sequence exchange.

278 4/3/84 F B Derated for "C" reactor feedwater pump maintenance and co'ntrol rod pattern adjustment.

279 4/8/8'. F B Derated for maintenance on "B" reactor g feedwater pump.

280 4/28/84 S B Derated for turbine control val"ve tests, SI's, and control rod pattern adjustment.

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~ 4 F: Forced Reason: Method: Exhibit G.Instructioia S: Scheduled A Equipment Failure (Explain) 1-Manual for Preparation of Data B Maintenance of Test 2 Manual Scram. Entry Sheets for Licensee C Refueling 3 Automstic Scram. Event Report (LE R) File (NUREG-D Regulatory Restriction 4-Other (Explain) 0161)

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

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i 50-260

. }. UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

UNIT NAME Two DATE 9/1/RA

• COMPLETED gy Ted Thom REPORTMONTH April 1984

' TELEPHONE 205/729-0834

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p No. Date g 3g f, ,;g g 5 Event s7 o'8 Action to s $5 ci! ji i =

< t Report = <E u u8' Prevent Recurrence

i. 6 292 4/1/84 S 11 Derated to extend fuel cycle into

August 1984.

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i I 2 3 4 F: Forced Reason: Method: Exhibit G - Instructisms j! S Scheduled A Equipment Failure (Explain) 1 Manual for Preparation of Data

! . B Maintenance or Test 2-Manual Scram! Entry Sheets for Licensee lI C-Refueling 3 Automatic Scram. Event Report (LER) FileiNUREG.

D-Regulatory Restrictism 4-Other (Explain) 0161)

IX)perator Training & License Examination F-Administrative 5

, G-Operational Error t Explain) Exhibit I Same Source ..

{ e8/77) il other (Explain) e +

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o s-a F UNITSHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-2 % *'

[ UNIT NAME Three

[ DATE 5/1/54 t

REFORT MONTH Aoril 1984 COMPLETED BY _Ted Thom

! TELEPHONE 205/729-0834 S.

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I 26 4 .E 5 a: Event  :;; ? c. ? Action to

$3 $ h5j Report : NC 0 Prevent Recurrence k

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I 140 4/1/84 S 719 C 4 End-of-cycle 5 Refuel outage con-tinues (controlled shutdown 9/7/83)

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k Method: Exhibit G -Instructions S: Scheduled A Equiprnent Failure (Explain) I-Manual

_ for Preparation of Data B-Maintenance of Test . 2-Manual Scram. Entry Sheets for Licensee C. Refueling 3 Automatic Scram. Event Report (LERI File (NUREG-D-Regulatory Restriction 4-Other (Explain) 1 0161)

E-Operator Training & Ucense Examination I F-Administrative . 5 Goperational Error iExplaint 19/77) Il Other (Explain) Exhibit 1 - Same Source

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[ '- BROWNS FERRY NUCLEAR FIANT UNIT 0 , ,,

MECHANICAL NAINTEIRNCE

SUMMARY

,{- CSSC EQUIPMENT ,

For the Month of A Pril 19 84 .

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EFFECT ON SAFE ACTION TAKEN COMPONENT NATURE OF OPERATION OF CAUSE OF RESULTS OF 7D PRECLUDE.

DATE SYSIEM I MAINTENANCE THE REACTOR MALFUNCTION MALFUNCTION RECURRENCE

'4-23 i High Pressu re Adjust relief None Unknown Valve relieving at MR-A-260329 01-26 g t Fire Pro- 0-VLV-26-1418 valve setpoint too low a pressure is being revised t6 allc I.

tection (26 ) relief valve adjustment 9

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'l BROWNS FERRY NUCLEAR PIANT UNIT MECHANICAL MAINTEIRNCE

SUMMARY

CSSC EQUIPMENT ,

19 84 I April For the Month of

+ EFFECT ON SAFE ACTION TAKEN COMPONENT NATURE OF OPERATION OF CAUSE OF RESULTS OF 'ID PRECLUDE E SYSTEM I DATE MAINTENANCE *nlE REACIOR MALFUNCTION MALFUNCTION RECURRENCE MR-A-251767 k4-ll Radiation 1-CAM-90-249 Add oil None Normal Use Lov oil level l

rtonitoring h

i system (90)

Emergency 1-FE-67-0039 Unplug orific 2 None Normal use Orifice plugged MR-A-215728

! 4-5 equipment cooling water (67) 4-5 Emergency 1-FE-67-0031 Unplug orifice None Normal use Orifice plugged MR-A-215729 equipment cooling w.

O water (67) 4-9 Drywell 1-HCV-32-2523 Clean filter None Normal use Restricted air MR-A-263415 control air 1-HCV-32-2524 flow Place on PM schecale:

(32) i 4-20 Rx Bldg 1-FCO-64-009 Dissemble None Normal use Affected damper MR-A-207045 ventilation 1-FCO-64-010 clean, and action system (64) replace j solenoid valvo i

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. BROWNS FERRY NUCLEAR PIANT UNIT i

MECHANICAL MAINTENANCE

SUMMARY

,[ CSSC EOUIPMENT .

f.

For the Month of April 19 84 EFFECT ON SAFE ACTION TAKEN NATURE OF OPERATION OF CAUSE OF RESULTS OF 10 PRECLUDE '

6 h DATE SYSTEM COMPONENT E MAINTENANCE THE REACTOR MALFUNCTION MALFUNCTION RECURRENCE 4-25 Fuel Pool 2-FMP-78-0015 Install new None Normal Use Excessive vibration MR-A-155593

, cooling coupling and l system (78) align pump and motor i

6-10 Control Roi 2-FLT-85-0701 Change filters None Dirt / Normal Use A P Approaching MR-A-263324 Drive high setpoint System (85) 4-20 Fx Bldg. 2-FCO-64-011B Install new None Normal Use Damper not closing MR-A-253902 ventilatior bladeguide tightly system (64) kits y 1

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1 BROWS FERRY NUCLEAR FIANT UNIT CSSC EQUIPMEiBT MECHANICAL MAINTENANCE

SUMMARY

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For the Month of April 19 84 EFFECT ON SAFE ACTION TAKEN SYSTEM COMPONENT NATURE OF OPERATION OF CAUSE OF RESULTS OF 10 PRECLUDE lDATE MAINTENANCE THE REACTOR MALFUNCTIO?1 MALFUNCTION RECURRENCE Diesel air 3-CKV-86-0571C Replace check None Normal age and Air receiver MR-A-269470 A-153554 I4-4 start (86)_ valve use leaking down 4 Diesel air 3-CHK-86-5713A Replace check Mone Unknown Air receiver leaking MR-A-269469 start (86) valve down 4-11 Stand by 3-FMP-63-006A Adjust pump None Normal age and Leakage MR-A-251756 liquid seals use control (63) ._

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BROWNS Fh.RRY NUCLEAR PLANT UNIT 0 f

BF D!SIL 30' CSSC EQUIPMENT ELECTRICAL MAINTENA';CE SO M\RY Appendix'B.

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9/29/82 -

h For the Month of April 19 84 p l Ef fect on Safe ; Action Taken

{;Drte Nature of Operation of 'l Cause.of Results of To Preclude Svstem Component Maintenance The Reactor I Malfunction Malfunction '

Recurrence 1984

4/3 4kV shut- 0-RLY-211-52T Replaced coil None i

down boards UIA Bad coil Relay not functioning Replaced bad coil

[. and adjusted j and buses TD relay Mr A263407 t

- 4/7 Standby 0-PX-082-00A diesel Replaced relay None Bad relay lRelaynot functioning Replaced bad relay generator MR A155976 9

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. -.4 BROWNS FERRY NIICLEAR PLANT UNIT 1 F IL 30 .

4 CSSC EOUIPMENT "

• f ELECTRICAL MAINTENANCE SD! MARY

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,s 9/29/82 -

l; For the Month of April 19 84 ij ..

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j i j Effect on Safet  ; Action Taken

(

l Nature of Operation of I Cause.of i Results of I To Preclude liDate Svstem i Component Maintenance The Reactor  ! I Malfunction Malfunction  ! Recurrence-

?

li1983 I I}7/31 Standby 1-00-82-00 Replaced air None Bad solenoid Solenoid will not Replaced bad '

l diesel air solenoid solenoid valve operate solenoid on generator MR A153389 j i

!' 1984 '

l ; 4/2 Containmen t: 1-H2AN-76-104 Replaced motor None Bad motor Motor will not run Replaced bad motor j Intering on MR A264459 4/10 Control 1-00-85-00 Replaced air None Burnt coil Solenoid deenergized Replaced bad rod drive' scram pilot solenoid solenoid on

! , solenoid MR A267334 ,

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! 4/12 Instrumen: 1-XFA-253- Replaced volt- None Bad voltage regu- Low voltage Replaced had volt  ;

& control 0001B age regulator lator & blown age regulator & j 120VAC & fuses fuses blown fuses on power MR A254775 1 4/11 RHR LPCI MG set Adjusted volt- None Setpoint drift High voltage Adjusted voltage 1-MC-74 age on MR A267342 I l-EA '

-4/18 Instrument 1-XFA-253-001E Bypass regulat- None Voltage regulator Low voltage Bypassed the volt-

& control ing transformer problems age regulator on 120VAC TACF 1-84-084-57 power & MR A267304 4/22 RHR LPCI MG set Installed fan None Dead air space Hot environmental Installed fan on 1-MG-74 e conditions causing MR A263683 1 EN '-

bearings to run hotter than normal l

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BROWNS FERRY NUCLEAR PLANT INIT 2 gg,3Sgg33 l*-

Appendix B i[ CSSC EQt*IPMD.'T ELECTRICAI. MAINTENANCE SIXuRY 9/29/82

!il For the Month of April 19 84 -i Ip i j Effect on Safe, Action Taken

!2 Nature of Operation of Cause.of

'I Dato Sys te:a Co=ponent Results of. , To Preclude. j Maintenance The Reactor Malfunction i Malfunction 1 Recurrence

,.-1984 l 12/4 Ten:perature 2-TR-056-004 Pulled new None Bad cable No reading on Replaced bad li jt monitoring therraocouple recorder. thermocouple cable *

!! cable on MR A207714 Ii l? e f

l .4/6 RHR 2-PMP-74-2A Replaced SBM None Bad switch Motor will not start ' Replaced bad SBN switch from control room ,

hand switch on MR A263282

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BROWS FERRY NUCLEAR PLANT UNIT 3 B F D'S I L >,,> .

CSSC E0t*IPME*;T

• ELECTRICAL MAINTENA' ICE SD! MARY .-

9/29/82 For the Month of April 1984

, 3 j Effect on Safe, j ,

Action Taken

! j Nature of Operation of i Cause.of Results cf -

To Preclude l

lato I System t Co:-aonent Maintenance The Reactor I Malfunction  ! Malfunction l Recurrence 984 Core Spray 3-MIS-75-70A Replaced None Open vinding in No voltage output Replaced bad trans-

/27 Cooling trans former transformer former on MR #A-264698

/3 Standby 3-DG-82-3C Replaced motor None Abnormal wear Ene. Found duEng Replaced both end j Diesel endbells and S1 4.9.A.I.d. bells & bearing on ,

Generator bearings MR #A-141739 i

/6 Reactor 3-RLY-99-63X Replace Lexan None None None Replace with Century Protection 8535Al coil spool Series coil on MR j

1. A-202389 j

/9 HPCI 3-RLY-73-23A Replace Lexan None None None Replaced with Centu-K48 coil spool ry Series coil /

spool type on MR

1. A-202388 w

/11 High- 3-0026-00 Re-count smoke None Detector being Smoke detector Remounted smoke Pressure Alarm detector loose from base alarming detector on MR Fire Pro- #A-269479 tection -

/12 HPCI 3-LCV-73-08 Replace coil None Shorted coil None. Found during Replaced bad coil !

EMI 57. on MR #A-155947 i

/17 CO2 St rage 3XS-39-26F Relocate smoke None Improper mounting Non E Found hanging Remounted smoke l Fire Pro- detector by the mount. detector on 'g tect, ion MR #A-140767

/24 RHR 3-} WOP-74-47 Replace motor None Burned commutator Motor will not run Replaced motor on i MR #A-251856 l

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.I * ," 27 OUTAGE MAINTENANCE & MAJOR MODIFICATION MANAGEMENT APRIL 1984 A.- Critical Path Activities

1. P0392 CRD Scram Discharge Header Modification - Piping was complete and ready for hydrostatic test on April 21. Hydrostatic test is pending the completion of tagging all valves.

2. P0392 CRD Scram Discharge Header Hanger / Support Modification - Of 119 hangers, 52 have been completed. Detailed breakdown is as follows:

a. Of twelve locations requiring inspection of existing hangers, 11 are complete.

b. Of 47 locations requiring removal only, 31 are complete.

c. Of eighteen locations requiring renoval and installation of new hangers, 10 are complete.

d. Of 38 locations requiring new hangers, none are complete.

e. Of four locations requiring a modification to an existing hanger, none are complete.

3 POS38 - Installation of blind flanges to control rod drive (CRD) header. This work was mechanically completed on April 16.

4. P0392 (Instrtmentation) - This work continues with the pulling and terminating of cable.

B. Refbel Ficar Work began on April 19 on the high density fuel storage rack removal. At present,11 of 41 racks have been removed. This work is being delayed pending a revision to the work plan. MMI 34 was successfully performed on the unit 3 refuel bridge crane, w~a,. w ~.w s _m._.. _ . . _, , , . . . . . .: . i ..m.

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OUTAGE MAINTENANCE & MAJOR MODIFICATION MANAGEMENT APRIL 1984 C. Balance of Plant Work continued on "A" Residual Heat Removal (RHR) heat exchanger during the month. Ten tube plugs were required after probolog was completed. All work was completed by April 25 and released to Operations. Probolog of the five "B" string feedwater heaters was completed with a total of 11 tubes to plug. After plugging the tubes, "B" string was closed. Probolog was com-plcted on 2A Reactor Building Closed Cooling Water (RBCCW) heat exchanger with no tubes requiring plugging. Maintenance work on the condensers continued.

D. Turbine

, An oil flush was started on April 11. During a routine filter changeout, the pumps were inadvertently started, resulting in an oil spill of approxi-mately 1000 gallons. Cleanup operation delayed work on the turbine for a period of time. The boots were changed on "A", "B", and "C" feed pump turbine. "C" low-pressure turbine, No. 4 exciter coupling was aligned.

E. Ilgil IHSI continued during April. By month end, 92 of 96 identified recircula-tion weld joints were complete. Of the 147 total identified welds, 114 are complete. Heat treatment of residual heat removal weld joints will be con-ducted upon the conclusion of the recirculation weld joints.

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• 29 N i b \~ OUTAGE MAINTENANCE & MAJOR MODIFICATION MANAGEMENT J, s APRIL 1984 F. Other Mechanical Work '

Ii q 1. Valve repair 1-55 and 1-56: Both valves.were mechanically complete on t>

9t April 16. EMI 18 was completed on valve 1-56 on April 26, 1984. The limit switch for valve 1-55 has a mid-May del'ivery date. This work is

'U continuing. i r

, 2. P0547 Replacement,of Recirculation Valves: p'ihismodificationwas m

, complete.

. , 3 Main Steam Isolation Valve (MSIV) Repair: This work is continuing and is approximately 40-percent complete. TheQxpected completion date is

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June 23, 1984. This work is approaching cri ical path.

4. P0612 Install 1/2" Stainless Steel Flex Line} Design of hangers is

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continuing., Main'SteamReliefValve(MSRVNinstallationisrequired

,  ; to complete this modification and is cuyrently being delayed pending i{l ' 'f 6 receipt of replacement solenoids.

5. ' P0691/689 Modify 64-series Valves: This work is continuing. This s ,t ( ,

c work has been slowed due to a lack of 309L welding rods. Efforts are underway to expedite shipment of suitable welding rods.

f 6., ,P0684 Torus Vacuum Bre$ker: Machining /of hinge arms has been com-p "s >.,

d*'pleted.' Waitingonvendorsparepartstordassembleandinstall breakdjt. .

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\ 7 P0547 ?.eplacement of Recirculation Valves: This modification was lompleted.

8. P0569 tieplacement of Reactor Pressure Vessel (RPV) Head Vent Valves:

' This work is continuing.

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Other Mechanical Work (Continued) 3 g,, , uy. .

.- 9. - Valve 74-60 and 61: -Both valves passed local leak rate test (LLRT) on April 19.

" L10. -Valve Repair 74-54

Repair was completed and passed LLRT on April 19.

l 11. L1970/P0709 Emergency. Equipment Cooling Water (EECW) Piping Changeout fj on Diesel Generators: Prefabrication work was completed for 3D diesel generator and was continuing on 3C diesel.

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^ 12J Visual inspection of hydraulic snubbers lacks approximately one week of work and is continuing.

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$L 13.- Remove / Replace Hydraulic Snubbers: This work is continuing and lacks W

. .... . L a minimum of 14 days of work which is dependent upon the as-found m:

. condition of the snubbers upon disassembly..

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-14. MSRV's: This work is continuing. Twelve of 13 valves are onsite with

[b 3 -one.still being repsired at Wyle Labs. -Those 12 have been set in

('y 'y place.

mn 15. P0695 . Modify Valves 24-8A, B, C and D: This work began on April 26 y? ,

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and is continuing.

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') 17 P0688 Modify FCV 76-19: This work began on April 26 and is g continuing.

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18. P0730 Removal of Head Spray Piping: Electrical work plans are in the

= approval cycles while mechanical work plans are still being written.

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-OUTAGE MAINTENANCE & MAJOR MODIFICATION MANAGEMENT o APRIL 1984 F. Other Mechanical Work (Continued) i 19. 'P5019 Remove Valve 3-2-1143 and Cap Torus Penetration X-228: This work was ccepleted.

G. - Electrical / Instrumentation

1. P0399 Provide Long Term Solution to I&C Bus Problems: Work is 15-t

' percent complete and continuing. ,

2. P0533 Torus Temperature Monitoring Devices: Work is continuing and is 90-percent complete.

' 3. PO415 Temperature Instrumentation - Reactor Feedwater Nozzles: Work is 75-percent complete based on the use of anphenol connectors. These connectors have now been found to no longer be manufactured. Another

- type of connector is presently being designed. The effect on the

. modification is unknown at this time.

4. PO422 Provide Redundant Class IE Protection: Work is 60-percent-

, complete and continuing..

5. - TIP Maintenance: This work was resumed April 30 and is presently being worked.

6. PO479 Emergency Lighting: This work is being done as manpower is available. -

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OUTAGE MAINTENANCE & MAJOR MODIFICATION MANAGEMENT APRIL 1984 H. Torus Torus work was as follows:

1. Torus Internal Modifications: Heat cure treatment was completed in all 16 bays on April 25. Touch up painting is being conducted and i near completion.

2. Attached piping and prefabrication work continued during April. At present, 286 of 454 supports are complete.

3.. P0093 Install Catwalk Gratings: This work is continuing.

4. . Repair of baseplate on RHRSW spring support H-59 was completed.

5. The expected torus fill date is May 7.

Planning and Schedulinn

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l l 1. Unit 3 cycle 5: Principal effort has been directed toward the revision of the major schedule with consideration for progress to date on raajor work and the system outage sequencing for return to service.

2. Unit 2 cycle 5: Preliminary schedules for brine prepared and j' reviewed. Planned work scope is not fully known at this time.

J. ALABA

1. Decontaminated floor and outside RWCU pumps rooms.

2. Decontamination efforts continuing in drywell and torus.

l-l 3 High level waste was removed from drywell.

4. Fuel pool spacers were washed down upon removal from unit 2 spent fuel pool in preparation for shipment offsite, 4

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. 33 OUTAGE MAINTENANCE & MAJOR MODIFICATION MANAGEMENT APRIL 1984 J. ALARA (Continued)

5. Decontamination efforts continued on MSIV's.

6. Decontaminated 74-54 valve.

7 RWCU valve 6A-1 was capped off to prevent further leakage of contaminated water.

K. Administrative The overtime percentage for the month of March was 23-percent with 105,873 straight time hours and 31,581 overtime hours. As of March 31, 1984, year-to-date overtime percentage was 20-percent, 801,257 straight time hours and 203,765 overtime hours. The overall goal of the overtime percentage is 17-percent.

The Outage & Maintenance budget for March was $2,730,360 and the expenditures were $2,454,948 with year-to-date budget being $16,532,974 and actual year-to-date expenditures being $16,675,711.

The capital budget was $2,594,500 and the expenditures were $8,700,140 with year-to-date budget being $21,468,800 and actual year-to-date expenditures being $19,281,226. Overall budget was $5,324,860 and the overall expenditures were $11,155,088 with year-to-date budget being $38,001,774 and actual year-to-date expenditures being $35,956,938.

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o TENNESSEE VALLEY AUTHORITY Browns Ferry Nuclear Plant P. O. Box 2000 Decatur, Alabama 35602 MAY 101984 Nuclear Regulatory Commission Office of Management Information and Program Control Washington, DC 20555

-Gentlemen:

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

Very truly yours, TENNESSEE VALLEY AUTHORITY p n ..

A= M j G. T. Jones Power Plant Superintendent Enclosures cc: Director, Region II INPO Records Center

, Nuclear Regulatory Commission Institute of Nuclear Pcwer 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) f Mr. A. Rubio, Director Electric Power Research Institute P. O. Box 10412 Palo Alto, CA 94304

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An Equal Opportunity Employer i