ML20132G166

Monthly Operating Repts for Jul 1985

ML20132G166
Person / Time
Site:	Browns Ferry
Issue date:	07/31/1985
From:	Robert Lewis, Thom T TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8510010487
Download: ML20132G166 (25)

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.e TENNESSEE VALLEY AUTHORITY DIVISION OF NUCLEAR POWER BROWNS FERRY NUCLEAR PLANT 40NTHLY OPERATIllG REPORT TO NRC July.1, 1985 - July. 31, 1985 DOCKET NUMBERS 50-259, 50-260, AND 5.0-296 LICENSE NUMBERS DPR-33, DPR-32, AND DPR-68 l

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TABLE OF CONTENTS Operations Summary.

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

3 Significant Operational Instructions..

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

3 Operating Data Reports.....................

11 14 Unit Shutdowns and Power Reductions.

Plant Maintenance.......................

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1 Operations Summary July 1985 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 seventeen reportable occurrences and no revisions to previous occurrences reported to the NRC during the month of July.

Unit 1 The unit was in cold snutdown the entire month for the unit's end-of-cycle 3 refueling outage.

Unit 2 The unit was in cold shutdown the antire conth for the unit's end-of-cycle 5 refueling outage..

Unit 3 The unit was_in cold snutdown the entire sonth on an administrative hold to resolve various TVA and NRC concerns.

?repared principally by 3. L. ?orter.

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2 Operations Summary (C5ntinued)

July 1985 i

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 0.00620 0.00492 0.00430 Feedwater nozzle 0.29782 0.21319 0.16133 Closure studs 0.24204 0.17629 0.14326 NOTE:

~'his accumulated monthly information Jacisfies 7acnnical Specification Section 6.6. A.17.3(3) repor*,ing reauirements.

Common System Aoproximately 9.$5E+05 gallons of waste liquids were discharged containing approximately 2.58E-02 curies of activities.

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3 Operations Summary (Continued)

July 1985 Refueling Information Unit 1 Unit 1 was in shutdown for its sixth refueling on June 1, 1985 with a scheduled restart date of March 31, 1986.

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. The unit was shut down on' March 19, 1985, and remained in cold shutdown until June 1, 1985, because of unfinished modifications to meet environmental concerns.

~There are 764 assemblies in the reactor vessel.

The scent fuel storage pool presently contains 252 20C-5 1ssemolles, 260 IOC 4 assemolies; 232 IOC-3 assemolies; 156 IOC-2 assemolies; and 168 IOC-1 assemolies.

The present fuel pool capacity *ls 3,471 locacions.

Unit 2 Unit 2 was anut down for its fifth refueling outage on Septemoer 15, 1984 vith a acneduled restart date of December 31, 1985.

This refueling outage will involve loading additional 3X8R (retrofit) assemolles into the core, finisning torus modification, turbine inspection, ?iping inspection, TMI-2 modifications; post-accident aamoling facility tie-ins, core aoray change-out, and feeuwater sparger insoection.

There ~1re no tssemolies in the reactor vessel.

\\t month end. Onere were 273 new assemolles, 764 ECC-5.sssemolies, 248 EOC 4 assemblies, 352 IOC-3 assemolles, 156 EOC-2 assemolies, and 132 20C-1 assemblies in the scent fuel storage pool.

The present availaole caoacity of the apent fuel pool is 77 locations.

111 31d racks have been removed from the pool tnd cew 3DR'3 are being instailed.

4 Operations Summary (Continued)

' July 1985 Unit 3 Unit 3 is scheduled for its sixth refueling outage approximately November

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30, 1985, with a scheduled restart date of November 10, 1986.

This refueling involves loading 8X8R (retrofit) assemblies into the core,-and compl'te reinspection of stainless steel piping. 'The unit was shutdown on March 9, 1985, and will remain in cold shutdown until September 28, 1985, on an administrative hold to resolve various TVA and NRC concerns.

'There are 764 assemblies presently in the reactor vessel. There are 248 ECC-5 assemblies, 280 500 3 assemolles, 12h EOC-3 tasemolies, 144 E00-2 assemolies, and 208 ECC-1 assemblies in the spent fuel storage cool.

The present available capacity of -he spent fuel pool is 914 '.ccations.

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5 July 1985 Significant Operational Events 2

Unit 1 7/01 0001 End of cycle-6 refuel outage continues.

7/31 2400 End of cycle-6 refuel outage continues.

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7/31 2400 End of cycle-5 refuel and modifications outage continues, i

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7 July 1985 Signiffcant Operational Events Unit-3

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i 01 0001 The unit has been placed on adrJ.nistrative hold until various TVA and NRC concerns are resolved.

7/31 2400' The unit has been placed on administrative hold unti' various TVA and NRC concerns are reso.1ved.

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8 AVER AGE DAILY UNIT POWER LEVEL DOCKET NO, 50-259 UNIT Browns Ferry 1

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DATE '8/1/85 COMPLETED BY T. Thom TELEPHONE 205/729-2509 MONTH July DAY' AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net)

(MWe Net) 10 1

17

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- 10 16 INSTRUCTIONS On this tormat. !1st the awr.sge quis ont n.,isa 3, u., n, yw,,,4 ' i"r exh <iar ni t he renurtine inun th. Gunt)ure to the nearest wnoie megawas:

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9 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-260 UNIT Browns Ferry Two DATE - 8/1/85 T. Thom CO%1PLETED BY TELEPHONE 205/729-2509 MONTH July DAY AVER AGE DAILY POWER LEVEL DAY AVER ACE DA!LY POWER LEVEL (Mwe Net)

(MWe. Net) 1

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.WER \\GE DAILY UNIT TOWER LEVEL DOCKET NO.

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8-1 -M COMPLETED BY T. Thom

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11 OPERATLNG DATA REPORT DOCKET NO.

50-259 DATE R /1/R9 COMPLETED BY T.

Thom TELEPHONE 20s/724-2509 OPERATING STATUS

1. Unit Name:

Browns Ferry One Notes

2. Reporting Period:

July 1985

3. Licensed Thermal Power (MWt):

3293 1152

4. Nameplate Rating (Cross MWe):

5. Desagn E;retrical Rating (Net MWe):

1665

6. Maxims.m Dependable Capacity (Gross MWe):

1098.4 1065

7. Maximum Dependable Capacity (Net MWe):

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

N/A

9. Power Level To which Restricted. lf Any (Net MWet:

N/A

10. Reasons For Restnerions. If Any:

WA This Month Yr. to Date Cumuiaine

11. Hours in Reportmg Penod M4 5,087 16. M7

12. Numoer Of Hours Reactor Was Criticai 0

1*NI*78 39*321*38

13. Reactor Reserve Shutdown Hours 0

512* 2 O ' J 9 7 *

14. Hours Generator On Line 0

1.626,67 5 a _ _' 6 7_ 2 4

15. Urut Reserve Shutdown tiours 0

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16. Gross Thermal Energy Generated (MWH) 0 4.950,321 168,066.787 17 Grow Electncal Energy Generated IMWHI 1.052.650 55,398.130

18. Net Electricai Energy Generated IMWH) 7 '10 1,375.196 53.789.017

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19. Unit Service factor 0

12.0 60.4 20 Unit Avadability Factor 0

32.0 60.4 V

?.I. Uma Capacity FactoriUsing MDC Neti

" 7

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22. Unit Caiucity Factor tusine DER Net

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23. Cait Forced Outave Rate 0

35.I 21.n

24. 5hutdowen $sheduled Over Nest e Months a fvpe. Date, and Duratsun of Exhr 25 IIShus On*n 4: End Of Retwert Perind. Euimated thee of Startup.

0/1'./96 26.

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12 OPERATING DATA REPORT DOCKET NO.

50-260 DATE 8-1-85 COMPLETED BY T.

Th m TELEPHONE 205/729 2509 OPERATING STATUS

1. Unit Name:

Browns Ferry Two

Noge,

2. Reporting Period:

July 1985

3. Licensed Thermal Power (Mh t):

3293 1152

4. Nameplate Rating (Gross MWe):

5. Desagn Electrical Rating (Net MWe):

1 65

6. Maximum Dependable Capacity (Gross MWe):

1098.4

7. Maximum Dependable Capacity (Net MWe):

1065

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

N/A

9. Power Lesel To which Restricted. lf Any (Net MWep:

N/A

10. Reasons For Restnctions,if Any:

N/A This Month Yr..to.Date Cumuutise

!!. liours in Reporting Penod 700 3+087 91.370 0

0 35,360.03

12. Numner Of Hours Reactor was Criticat

13. Reactor Rewrve Shutdown Hours 0

0 14,200. a 14 Hours Generator On.Line 0

0 54,338.26

15. Umt Rewrse Shutdown Hours 0

0 0

16 Gross Thermal Energy Generated aMwn) 0 0

153,245.167 17 Grow Electrical Energy Genersico iMhHi 0

0 50,771,798

18. Net Electrical Energy Generated eMwH)

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-17.567 49.235,406

19. Uma Service Factor

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20. Umt Tsailability Factor 0

0 39.5

!. Umt Cap.icity Factor IUsing MDC Neti 0

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22. Uma Capacitv Factor iUsins DER Net O

d 30.o

23. Umt Forced Outave Rate 0

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24. Shutdowns kneduled Oser Nest a Months e Ispe. Date.and Duratum of Eacnt:

25 ff 3hur 16*n nt End t'l Report Peroid, beimated Dale of Startup 2 / 2 'D

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13 Ol'ERATING DATA l'.EPORT DOCKLT NO.

50-296 DATE 8-1-85 C0\\lPLETED BY _ _ T. Th e:s TEI El'!!ONr 20;I'24-2334 t'?F!' A T f NG STATUS

. Unit Name:

Browns Ferry Three Notes i

2. Itep tin.g Period:

f u i t-10 M t'

1. Lien.ed Themi Powcr 151h: :

3293

4. Namep!:te !!: tin;:(Gren '.lWe):

1152 j

5. Cehn E! ctrical Ra:Ing aNet MWe):

1065 6 Mr.imum Depend 21: Car: city (Grou MWe):

1098.4

7. Mnimum D:pendable Cap 2 city (Net MWe):

1065 j

M !f Ch:nges Dei.ur in Capacity llatin.;s ll: ems Number 2 Through 7) Since L;:st Itepura, Ci e ' tea,one N/A

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"I' BliOUNS FtHRY 11UCLEAR PLANT UNIT

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BF EMSIL 30 6

Appendix B

. i ssC _l:qt:117 i M LitC1HICAI. MAINfEHAtlCE

SUMMARY

9/29/82 For it.e lloath of July 19 85 s

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Effect on Safe Action Taken Nature ut Opesation of Cause.of Results of To Preclude ie.: c st.t n

Couponent Itaintenance

'll.a Reactor Malfunction Malfunction -

Recurrence

• 19n W

cas.t t ol

( 1614 19t,o r a uula l e shou t done liurued out motor Chiller would not Replaced motor L..j h a t -

shutdown t.J ps otector and start protector and freeze 14.g, veut si clnller 3Al freeze protection protection overload

....I AC overloa.1 MR 182806

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i s..t s o l Chh-31-19su t a uub ical.oo t donc 11.sd aw t o r Chiller trips after Replaced motor t.ay 1.ca s -

ut...tJ no 1.d protector 30 seconds of opera-protector i..c vca.t tu cl.nlle AA_

tion i,.i

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MR 518671

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o t i m. a I s-ui-o sA laouble hoot done tiarrel of terminal Annunciation on unit Loosened terminal nut

( mee rat ua e 653V stouad ua lug was touching 3 control rm pnl 9-8 readjusted and ;

..u i t.. h in ott-unit 3 46V f>C

.auall bracket on insulated lug g.4 4 Ltd,, arain system fS-65-63A MR 556735 s

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//1, A... t, i n e t'to-so.* 30ti/C troublemboot Joue Auxiliary contact Damper stuck in open Freed and lubricated

t. i d g

$LA di uct au J apers atickind position contact

... t a 1.s t a s..

intet anula-tiou a a.,, cts MR 558844/558845 U 13

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6. tin-31 -134 3 froubieshoot Joue tsad damper motor Chiller tripped on Replaced damper t.a j l.c a t -

outrol I,a y "A"

ct. iller safety switches motor i..;;, tent cheIter 3A FDt 538403

..w e/lc i..r.t t o l (11s-31-1951 1roubleshoot "Is' None tiad daiper motor Damper would not close Replaced damper motor l t,a 3

t. cat-ontrol 4.a y hiller c

MR 584600 as.k. went c h i l l s. a ali

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1/n 66 s GLN-99-bO3h fraubleshoot thine llad coil in 1K IF fuse blew causing Replaced relay coil i

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. _ _ _ _ _ BROlciS FERRY NUCl. EAR PLANT UNIT 3

BF EMSIL 30 Appendix B

' CSEC b ytltits.:.r LIECTRICAI. HAINTENANCE SIM1ARY 9/29/82 e

for the !!auth at July 19 85 l

8 i

~

Effect ca Safe Action Taken Nature ut Operattua of Cause.of Results of To Preclude 9 tt e systcu Cer ponent Maintenance _

The Reactor Malfunction Malfunction Recurrence E

+

d tuti t'CV-/s-ud M xcplacu tutut Huae Motor shorted out Found while perform-Replaced motor tiPCI p uu.p ing QMDS ma{ntenance m

95 di:,, L.cge valv.

.cnnator Ja unttot be.

;1t'- Ji-l W )

fruuLleshout Nonc liad pressure Low suction pressure-Replaced pressure t.ei t, vs.u t,

tu.h ca.illed gauge not within limits gauge

,ua :a.

vaLer c5aca-I a (

..a p ua.p MR 558567 iLI i

/Jo te ioc !

6.ta-n2-oo1C troubleahout tlane Bruken wire on Diesel generator Repaired broken wire

. ede r a t..t AC. tic cl D/G 3C ACB 1832 and bad tripped on overspeed and replaced D/G l

g..aa t ut ficId breaker field breaker E MR 519315

/s eile pro-Xs / nb St 4.ll.C.1 Hur.e nad detector No alarm or red light Replaced smoke

( etsua uu...L c de t es. t o s came in on detector detector t

i.. :,Lu t d..wa when tested L a t u.

3tB MR 565482

<3 u.a ua< i a t oi XA-n-ou:$ E re:,t lug groiand Hat.e tiad anuunciator Did not alarm in Replaced card I

.jc q ueu -

ttuuble aluti card control room

( a.1 Jvc u t.

for autu iire MR 169377

. cording protectiua l

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dC sus. trol bus t

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6

s BROUNS FERRY NUCl. EAR PLANT tR4IT 1

BF EMSIL 30 Appendix B

' (:SSC Eql'IP:tt!.T El.ECTRICAL llAINTENANCE

SUMMARY

9/29/82 i

For the flanth of July 19 85 t

l Effect on Safe Action Taken l

Nature of Operation of Cause.of Results of To Preclude

( b ite S v > t e ca Ce r.oo n e n t tlaintenance

't he Reactor Malfunction Malfunction Recurrence t

1935

//t i:. u t rol t,a til k-3 t -4 t,3 CRL\\

Tronhleshoot lione Loose connection A.T above ambient Tightened connections heating train A char-low temperature on heater element temperature low on heater element vent and coal heater at3 MR 156070

~.... _ - -.

//s n.itiation n:1-90.bl troubleahoot None liad bearing and Cam out of service Replaced bearing and iwn i t os ing continnons ait aio t o r on vacinna V-helt on motor V-belt uionitor -

gump i

r us t.ine tir 61, MR 574312 m

7/11 ut S nl.Y uK 2 5 ts s1 4.1.A-1 None Burned out coil Found open during lieplaced relay coil relay in panel performance of l

9-17 SI 4.1.A-7 MR 572170

// i t, t ro ne s an.1 netuel platfort Tsonbleahoot None Worn ont limit Improper operation of Replaced refuel inter-tio,i a t s refneling switch refuel platform lock limit switch #2 interlock limit switch #,

MR 590156 1

//16 n:.,1, l d g ki 'i-- t>4-i n AK iu k e p t.s c e open None llad coil on relay Fuse FB-6 on 250V Replaced coil and i

3 veptilativi relay in coil on relay 16AK30 battery bd 1 blew and moveable contact arm panel 9-43 16AK30 initiated several on relay engineered safety MR 566695-LER259/8503) features i 7/31

'.niionc ia t i. a Control room Tronhleshoot None Defective horn Loss of audible alarm Replaced horn

,cij ne n--

annunciator huin in control room tihl event horn MR 555731 tc<ording a

9 I

i 6

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.I 8

BROWNS FERRY NUCLEAR PLANT 11 NIT 0

BF EMSIL 30 Appendix B

' CSSC D!!:It' 1rN r ELECTRICAL MAINTENANCE

SUMMARY

9/29/82 For the Month of.Iuly 19 85 l

Effect on Safe Action Taken 8

flature of Operation of Cause.of Results of To Preclude Date

'Svaten Component Maintenance The Reactor Malfunction-Malfunction Recurrence 1985

[20 Co'n t ro l til'R-0 31 -O l 4 3 Troubleshoot IJone Aux contacts were Pump would not operat. Cleaned. contacts on ba'y beat-chilled water chill water sticking and not breaker ing vent circulating puu.p. A dropping out and AL pinap A LLr MR 559690

~..

. _.... _ ~

>/27 ita'd i a l lon PMl' 15 211 Troi.bleshoot None Bad bearing on Motor overheating Change bearing in iaonitoring stack sample Laeaker tripplo g anotor motor pinap 112 out on stack satople punip !$2 MR 519371 U

')/12 Radiation PflP-90-152A Troubleshoot None Ineffective oil Caused pump to. blow Added oil.and reset l

c.ohitoring utael sataple control room system on motor fuses oil system pun.p is t annunciation MR 538316 0

1/ ti Standby FS-65-42A.

Troubleshoot None liad discharge Alarms in control Replaced flow switch t

gal treat-SG l' t an is alarus in flow switch on room u.c h t diacharge flot unit I control SisGT train B fan MR 589906 room l

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13HOWNS FEhHY NUCLEAR PLANT UNIT i

fMSC.fe!.!11'!1ttlI.

HECilANICAL HAINTENANCE

SUMMARY

For the Month or 19 4

a wem

-m g m -- -

EFFECT ON SAFE ACTION TAKEN SYS[fE!!

C011PO!1EllT HATUHE OF OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE l>AIE 4

i JIllIEljMICE Tile _ REACTOR MALFUNCTION MAYFUNCTION RECURRENCE

- 8 5 111 Reactor buildiu s HR 564381 None Shenred. key and Impaired safe Fabricated key amahd shaft-worMng out of stronge luspect drum gears material failure capacity of material I

and brakes ou I

4.25 ton book

. 6 5 67 1CV-67-62 demove raised race lione Seismic evaluation None MR 180668

.>a f1anges by EN DES removed raise face from valve flange i

"9-85 23 RilkSU Pump B3

lk 588817 None None None None cut studs for installation l u*

l pump 85 23 b3 kilR/EECU t1R 571017 Iloue use Inadequate Service pater.

Hepair b3 Hilk pump flow Pump Sil pump impellar

.tsing Belzona StitlI 15.1.5.A I

l Completed 7-9.-b5 l.

l l

I i

I I

~

o Ul(OWNS-FEHHY lluCLEAR l'L ANT UNIT 3

CiSC. EQUlfl1EllT.

ItECliANICAL HAINTENANCE

SUMMARY

For the Month or.fuly 19 85 EFFECT ON SAFE ACTION TAKEN j

liA'f E SYSfEli COllPOllEtJT

.ll ATuftE OF OPEHATION OF CAUSE_OF RESULTS OF TO PRECLUDE

__11AINTEUAUCE

_JJJE_EACTOR MALFUNCTION MAI. FUNCTION RECURRENCE i-)4-65 111 Air cotupressor HH 589659 th,ne unknown Insufficient a:.r Transfer Li-3 pressure on refueling bridge refuel platfor n

crane air ccaupress ar Lo U-l and install I

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TENNESSEE VALLEY AUTHORITY Browns Ferry Nuclear Plant Post Office Box 2000 Decatur, Alabama 35602 AUG 141985 Nuclear Regulatory Commission Office of Management Information and Program Control Washington, DC 20555 Gentlemen:

Enclosed is the July 1985 Monthly Operating Report to NRC for Browns Ferry Nuclear Plant Units 1, 2, and 3.

Very truly yours, TENNESSEE VALLEY AUTHORITY obert L. Lewis Acting 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 P. O. Box 10412 Palo Alto, CA 94304 I g i

An Equal Opportunity Employer.-