ML18025B251

Monthly Operating Repts for Nov 1980

ML18025B251
Person / Time
Site:	Browns Ferry
Issue date:	12/01/1980
From:	Thom T TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML18025B249	List: ML18025B248 ML18025B251
References
NUDOCS 8012160321
Download: ML18025B251 (36)

Text

TENNESSEE VALLEY AUTHORITY DIVISION OF POHER PRODUCTION BROGANS FERRY NUCLEAR PLANT MONTHLY OPERATING REPORT November 1,

1980 November 30, 1980 DOCKET NUMBERS 50-259, 50-'60, AND 50-296 LICENSE NUMBERS DPR-33,

.DPR-52, AND DPR-68 Submitted By: X P. f/..

g6'lant Manager

0 iO

TABLE OF CONTENTS Operations Summary

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Refueling Information

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Significant Operational Events

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Average Daily Unit Power Level ll Operating Data Reports

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Unit Shutdowns and, Power Reductions.

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17 Plant Maintenance

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20 Outage Summary

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30

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'0 erations Summar November 1980 The following summary describes the significant operational 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 reported to the NRC during the month of October.

Unit 1 There was one scram on the unit during the month.

On November 28, the reactor scrammed when-the main turbine tripped due to problems in the transfer of the shutdown bus from Unit 1 station service to Unit 2 station service in preparation for a manual scram for-steam leakrmaintenance on Unit. l.

Unit 2 There was one scram on the unit during the month.

On November 21, the reactor scrammed during startup testing (MRTI) for BOC-4.

The unit was not on line..

Unit 3 There was one scram on the unit during the month.

On Nobember 23, the reactor was manually scrammed to begin its scheduled EOC-3 refueling outage.

~Oerations Summa~ (Continued)

November 1980 Fati ue Usa e Evaluation The cumulative usage factors for the reactor vessel

are, a.

follows:

Location Usa e Factor Unit 1

.Unit 2

Unit 3 Shell at water line Feedwater

nozzle, Closure studs 0.00495 0.23648 0.19698 0.15949 0.11746 0.13360 0.09521 0.00377 '.00315 Note:

This accumulated monthly information satisfies technical specification section 6.6.A.17.3(3) repc)rting requirement0.

Approximately 7.88]E+05 gallons of -waste liquid were discharged containing approximately 9.90E-Ol curie.

of activity.

3'efuelin Information November 1980 Unit 1 Unit 1 is scheduled for its fourth refueling beginning on or about April 10, 1981, with a scheduled restart date of August 23, 1981.

This re-fueling will involve loading additional 8 X 8 R (retrofit) fuel assemblies into the core, the final fix on the sparger modification, power supply on LPCI modification, and torus modifications if all approvals are received.

There are 764 fuel assemblies in the reactor vessel.

The spent fuel storage pool presently contains 550 spent 7 X 7 fuel assemblies, five 8 X 8 fuel assemblies, and one '8 X,S R fuel assembly.

Because of modification work 'to increase spent fuel pool capacity to 3471 assemblies, present available capacity is limited to 1193. locations.

Unit 2 Unit 2 finished its EOC-3 refueling outage and began cycle 4 during the month.

Unit 2 is scheduled for its fourth refueling beginning on or about Harch 26, 1982, with a scheduled restart date of August 8, 1982.

This refueling outage will involve completing relief valve modifications, torus modifications if all approvals are received, "A" low pressure turbine inspection, and loading additional 8 X 8 R fuel assemblies into the core."

There are 764 fuel assemblies in the reactor vessel.

At the end of,the month,. there were 132'ischarged cycle 1 fuel assemblies, 156, discharged cycle 2 fuel assemblies, and 352 discharged cycle 3 fuel assemblies in the spent fuel storage pool.

The present available capacity of the spent fuel pool i;s 160 locations.

With present

capacity, the 1979 refueling was the

Refuelin~Information (Continued)

November 1980 Unit 2 (Continued) last refueling that could be discharged to the. spent fuel pool without exceeding that capacity and maintaining full core discharge capability in the pool.

However, 949 new high density storage. locations have been'nstalled, but cannot be used until Special Test 161 is completed.

Unit 3 Unit 3 began its EOC-3 refueling outage during, the month.

Unit 3 is scheduled for its fourth refueling beginning on or about September 25, 1981, with a scheduled restart dante of February 7, 1982.

This EOC-4 re-'ueling, involves loading additional 8 X 8 R (retrofit) assemblies into the core, relief valve modification, turbine inspection, and torus modi-fications if all approvals are received.

There are 764 fuel assemblies presently in the reactor vessel.,

There are 144 discharged cycle 2 fuel as.,em'blies,,

208 discharged cycle 1 fuel assemblies, and 164 new 8 X 8 R, asseimblies in the scient fuel storage pool.

The present availaible storage capacity of thee spent fuel pool is 1012 locations,.

With present

capacity, the 1980 refu< ling will be the last refueling that could be discharged, to the spent. fuel pool without exceeding that capacity and maintaining full core discharge capability in the poolr

Da te Time 11/01/80 0001 2150 Si nificant 0 erational Events Unit 1 Event C

Reactor thermal power at 99%,

maximum flow Reduced thermal power from 99% to 42% for control rod sequence exchange from "B" to "A" 11/02/80 0220

'0330 0540 1530 Control rod sequence exchange completed, commenced power ascension Reactor thermal.power at '55% holding for maintenance in main steam tunnel Maintenance in main steam tunnel completed, 'commenced

.power ascension Commenced'CIOMR from 73% thermal power 11/04/80 1500 11/08/80 2120 Reactor thermal power at 99%,

maximum flow Reduced thermal power from 99% to 70% for control rod pattern adjustment 11/09/80 0130 2300 Control rod pattern adjustment completed, commenced power ascension from 70% thermal power Reactor thermal power.at 92%, holding due to computer problems 11/10/80 0355 1500 11/15/80 0015 0337 0550 1005 Computer problems resolved, commenced PCIOMR Reactor thermal power at 99%,

maximum flow Reduced thermal power from 99% to 80% for turbine C.V.

tests and SI's Turbine. C.V. tests and SI's completed, commenced'ower ascension Commenced PCIOMR from 94% thermal'ower Reactor thermal power at 99%,

maximum flow 11/18/80 0700 ll/20/80 0700 11/21/80 2340 Reactor thermal power >99%,

maximum flow Reactor thermal power 99%,.maximum flow Reduced thermal power from 99% to 86% for turbine C.V.

tests and SI's 11/22/80 0015 0400 0700 Control valve tests

complete, increased thermal power to 93% and holding for completion of control rod exer-cise and SI's Control rod exercise and SI's completed, commenced power ascension

,Reactor thermal-power at 99%,

maximum flow

Si~n:Lfi.cant Operational Events Unit 1 Date Time Event 11/28/80 1815 2331 Commenced reducing thermal power from 99% for shutdown to perform maiy):~nance on steam leaks (steam seals)

Reactor Scram 'o.

138 from 40% thermal power due to turbine trip (unit preferred breaker problem) while shutting,, down for maintenance outage 11/29/80 1130 1332 1830 1851

Haintenance on steam seal system complete, commenced rod withdrawal for startup Reactor Cr:Ltical No.

159 Rolled T/G Synchronized generator, commenced power ascension 11/30/80 1500 2400 Commenced PCXOMR from 60% thermal power Reactor thermal power at 77% with PCiLOMR in progress

Si nificant 0 erational Events Unit 2 Date Time Event 11/01/80 0001 11/02/80 0500 0639 0940 Reactor at cold shutdown (EOC-3 refueling outage)

Commenced reactor vessel hydrostatic test Hydrostatic test at 100 psig completed, increasing pressure to 300 psig

'Hydrostatic test at 300 psig, increasing. pressure to 500 psig 11/04/80 1008 1900 2120 Hydrostatic test at 500 psig completed, reduced reactor vessel pressure to bel'ow RHRSW pressure for shutdown cooling Increasing reactor vessel pressure to 1000 psig for hydrostatic test Hydrostatic test at 1000 psig completed, reduced pressure to 550 psig, holding for maintenance 11/05/80 1110 1155 Hydrostatic test completed.and maintenance com-

pleted, reduced reactor vessel pressure to below RHRSW pressure for shutdown cooling Drywell head set in place 11/09/80 1203 1500 Increasing reactor pressure for hydro Reactor pressure at 550 psig, holding for hydro-static test and instrument valve"checks.- --- *-"

ll/10/80 0107 0144 0325 Increasing reactor pressure to 1005 psig for hydro-,

static test Reactor pressure at 1005 psig'nd holding for hydro-static test Hydrostatic test complete, reducing reactor pressure to zero ll/19/80 1617 1720 1730 2125 2323 Commenced rod withdrawal for startup Reactor Critical No.

119 Reactor, brought sub-critical due to IRM problems All rods in for maintenance on IRM's Maintenance complete on IRM's, commenced rod with-drawal for startup 11/21/80 0007 1518 Reactor Criti~g No.

120 Reactor Scram No.

110 from (5% thermal power due to HI-HI APRM spike 11/22/80 0010 0120 1925 1939 1940 1942 Startup SI's completed, commenced rod withdrawal for startup Reactor Critical No.

121 Rolled turbine to 100 RPM's,'0% reactor thermal power Tripped turbine Reset turbine Rolled turbine and generator to 1800 RPM's

S:L~ni.ficant ~Oeratiorial E'vents.

Unit 2 Date Time' Event 11/22/80-'038 2150 Turbine overspeed trip test:Ln, piogress Tr:Lpped turbin'e due 't:o high vibrations on No.

8 bearing 11/23/80 0455

'0525 0600 0655 0830.

1155 1215 1230 1240 1252 1255 1311 1334 1500 1840 Turb'ine reset:

Ro.'Lied T/G Turbine at 1800 RPM oil tr:ip te.'t compl'eted Syinchionized generatt)r, commenced power ascension (sequence "A")

Reactor thermal power. at 20%, holding for electricai tests Main turbine oil trip test: complete Commenced reducing, thermal power from 20% for turbine overspeed tests Reactor thernml power at 10%, hiolding f:or turbine over-speed tests

,Turbine.over.,peed trip t'e. t complete Backup overspeed test complete Reset turbine Placed field on generator Synchronized generator, commenced power as'cension Reactor thermal power.,at 25%, hiolding f:or startup.

tests Reduced thermal power to 23%,.holding f:or startup tests 11/25/80 1740 1755 2035 2200 Commenced power ascension from 23% thermal 'power, startup test. in progress Reactor thernml power at 27%, holding,(startup tests in,progress)

Coimmenced power ascension friom 27%,thermal

power, (startup test:s in progres. )

Reactor thermal power 39% holding (startup, te'.ts in, progress) 11/27/80 0033

'0600 1845 Startup tests

complete, commenced power ascension from 39% thermal powder Reduced react:or thermal power from 52% to 43% due to "A"'ec:Lrculation pump being out of service for, mainte-nance "A"'ec:Lrculatiion pump maintenance complete and placedi in serv:Lce, connmenced power, ascension from 43% thermal power 11/28/80 0120 1945 2145 Coimmericed'CIOMR from 62% thermal power Coimmenced redu'cing thermal plower from 82% due to high, "2'B" recirculation pumps lower bearing,oil level "2B" recirculatiom pump problems resolved, commenced PCIOMR from 75% thermal power

Si nificant 0 erational Events Unit 2 Date Time Event 11/29/80 1500 Reactor thermal power at 93%, holding for RTI-23A (Feedwater System) 11/30/80 1215 2100 2125 2400 Reduced thermal power from 93% to 18% for RTI-23A RTI-23A completed, commenced power ascension Reactor thermal power at 40%, holding for RTI-32A (2 recirculation pump trip)

Reactor thermal power at 40%, holding for RTI-32A

10 Si~nificant,.O~eratioria]L'vents Unit 3 Date Time Event 11/01/80 0001 0220 0355

':Rea.ct'or thermal power -at '80%, hold.ing for turbine C.V.

tests and Si's Turbine C;V. tests and SZ's,comIpleted, commenced power asc.ension

Reactor thermal power at 92%,

coastdown 11/02/80 0700 11/03/80 0700 11/05/80 0700 ll/07/80

'2300 Reactor thermal power at 91%,

coastdown

Reactor thermal power. at 90%,

coastdown

Reactor thermal power at:

89%,

coastdown Reactor.

thermal power at 88%,

coastdown 3.1/08/80 0130 0300 0700

RedIuced thermal power'rom 88% to 80% fox'urbine C.'V.

tests,and SI's Turbine C.V. tests and SX's corn]pleted, commenced power asc,ension

Reactor thermal.power at: 88%,

coastdown 11/10/80 0700 Reactor thermal power at 87%,

coastdown 11/12/'80 0700

Reactor thermal power at:

86%,

coastdc)wn 11/14/80 2335

Reduced thermal power from 86% to 80% for tux'bine C.V.

tests and Sl',s ll/15/80 0225

-0700 Turbine C.V.,tes,ts and SI's completed, commenced power

'asc,ens ion

.'Rea,ctor ther'mal'ower at:

86%,

coastdown 11/16'/80 1500 Reactor thexmal pow'er, at: 85%,

coastdpwn ll/19/80 1500 11/22/80 2300 11/23/80 2015 2144 11/30/80 2400

Reactor thermal power, at:

84%,

coastdown

Reactor thermal power at: 83%,'oastddwn Commenced reducing thermal power from 83% for shutdown.

to accommodate EOC-3.refuel outage

Reactor 'Hanual Scram No.

90 from 36% thermal power t6 accommodate EOC-3 refuel outage

EOC-3 refuel outage (1)

.Equipment 'malfunction

AVERAGE DAILYUNITPOWER LEVEL DOCKETlVO.

Browns Ferr 1

12-1-80 COMPLETED AY

'hIOiVTH DAY AVERAGEDAILYPOWER LEVEL (hlWe.jVet)

I 011 1000 DAY AVERAGE DAILYPOWER LEVEL (hfWe.iVet) 1058 l7 1062 1058 1041 1057 1026

'70, 22 23 1049 1054 1055 IQ 13 IS 1026 1058 1057 1024 1059 85 26 27 28

'I9 30 3I 1054 1050 940 761 INSTRUCTIONS Oo thts totlllel,!ISt tile JVet Jeie ilJIIV Ullll pi)'teel level III hl'6'e iNel ILife Jell Jay ttt tile repi>> Ilite lib>!lilt.(iI>tlptlte tu

.tfle tteetest N'lt<>le lttege'Lvett.

I'/77 I

0 12 AVERAC>E l)Alii.YUNIT POWER LEVEL DOCKET NO.

50-260'rows Ferry 2 12-1-80 DATE COMPLE>I'ED BY Ted Thorn Tl.:LEPHONE 205-729-6846

$1ONTH November 1980 DAY AVERACE DAIL'YPOWER LEVEL lMWc >Vei)

I

-3 DI'<Y 17 AVER,iCE DAILYPOWER LEVEL

(>>IWe Net):

-2

'>p 21

-9

-10 7

i'>3 190 10 12 13

,15 16

-3

'>>5 27 28 488 780 822 tNSTRUCTIONS Or> this t'<>nnut.!ist tlt<.',<>a<.'r <~<,'uily >(rtit t>>>>e<.r le<el it)!>I'tV<.-N<'.iit'<)r eul,ll d:ll IIII the tep<><l>>>}'. ltl~ >I>tlt. C>>tuii>ute to tile lleufcst <vitl>!e ttteuux'>">ll.

g<tI771

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13 AVERAGE DAILYUNITPOWER LEVEL DOCI'ET NO.

PATE 12-1-80 CO'tIPLETED BY TELEPHONE 205-729-6846

.MONTH m er 1980 DAY AVERAGE DA'ILYPOWER LEVEL (MWe-Ner )

I 965 970 l7 907 907 DAY AVERAGE DAlLYPOWER LEVEL (ih(WC.Nct I 967 961 956 l9 20 896 896 887 10 938

'948 940 932 926 13 15 27

-12

-10

'15 Ie, 919 912 30 3l

-10 INSTRUCTIONS Ot) this t>>rt>>at.!ist thc accrual'c (I illy ur) tt I>>liver level irt lit'Vc Ner t'<)r cuclt lice trl tire lupi>>ti>>ic tttii>>tlt.(.iltttputl lo lite tlccrcrt all>>k tttccustut t'.

(9/77 )

.14 OPERATING DATA'REPORT OPER'ATING STATUS

'DOCKET,NO. 2}-~2'I DA'TE 12=~II1 CO)1PLI:TED BY TELEPHO<iIE ~~i <)-6846 Notes

l. Unit Nain<<: U~mxs ~rxy -~

2. Reporting Period: JQHi~~~Hg

3. Liccns<<d Tliermal Power (M1Vt):

4. Namephtc Rating (Gross'hI)Ve):

5. Design'Eh.ctrical Rating (Net. <IIWe):

6. Mari)num Dependable Capacity (Grt)ss <4I>Ve):

1098. 4.

7. <<Iax<n)u)n Dependable Capacity (<"<<<I ills'V<<):

1065

8. IfChang<<s Occur'n Chpacit)" Ratings (!ten)s'Nu<nber 3 Th'rough 7) Since-L)st Report. Give Reasons:

9. Power Level To )Vhich Restrictecl, If,.Any(Net I<<IN<<):

10. Reasons For Restrictions, lf.Any:

This Month Yr..to Date

~8040

.'720 394. 04 14; 02 700.67 5,657;79 2~g ~8>>

~ 16 912 '943 727 060 502 960 76.4

<)7. 3

'2,.4 92.4 62.4'92.

4 2~

8;0 ITyp<<. i)at<<. and Duration of Each);,

11. Hours In Reporting Period

12. Nuinbcr Of 1{ours Reactor 'lVas Critical 13.'eactor Reserve Shutdown Hour'

14. Hoiirs Generator On. Line

15. Unit Reserve Shutdown llours

16. Gross Thermal Energy.Generated (M IVH)

I <, Grois Electrical'Energy Gcn<<rated (Xt)VI/I) 18.

<stet Fl<<ctrical En'ergy G<<n'<<rati.'d (M)VII) 19,,Unit Service Factor

.20. Uiiit Availability-Factor

21. Unit-Capiicity Factor (Using.'<<I DC Net) 2

. Unit Capacity-Factor (Using I)EIi,N<'.t)

23. Unit Forced Outage Rite

24. Shu:downs Sch<<dui<<d Over Next 6'51onths uta e

A ril~l981 Cumulative 55, 53,8 34 077;79 5.083.65 33, 27,0. SI2 0

~91 649~436 30,023.,420

~t~K2M

59. 9'-,

49.3 49.3,;

29.7

'5. 11'hut I)own At Eild Of Report I'<iriod, Estimated I) ite of Start'up

'I<, Uoiti'In Tist Status IPri<ir to Co)'i)mercial.OP<<ration l:

Fore<<:)it Achieied INITIALCRITICALITY INITIAL EI.ECTRIICIT'Y CO515IERC'IA L OP I'.RATI0.i

(),i27)

OPERATINC DATAREPORT DOCKET NO

~0-260 DATE ~~

CO4IPLETED BY ~dThom TELEPHONE ~2-72 -6846 OPERATI<VC STATUS

1. Unit Name Browns Ferrv 2

2. Reporting period:

November 1980

3. Licensed Thermal Power (MlVt):

4. Nameplate Rating (Gross <IIWe):

5. Design Electrical Rating (Net <IIWe):

6. Maximum Dependable Capacity (Cross IIIIVe):

7. Ibiaxinium Dependable Capacity (Net <~IIVe):

Notes

8. IfChanges Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Cive Reasons:

9. Power Level Tu Wliich Restricted, IfAny (Net IIIWe):

10. Reasons For Restrictions, IfAny:

This 2<Ionth Yr..to.Date Cumulative 720

11. Hours ln Reporting Period

12. iVumber Of Ilours Reactor Was Critical

13. Reactor Reser've Shutdown Hours

14. Huiirs Generator Oo.Linc

15. Unit'Reserve Shutdown Ilours

16. Gross Thermal Energy Gencratcd (MPH)'7, Gross Electrical Energy Generated (I<I'IVH)

I8. Nct Electrical Fnergy Generated (MWH),

19. Unit Service Factor

20. Unit Availability Factor

l. Unit Capacity Factor (Using MDC iVel)

22. Unit Capacity Iractur (Using DER iVet)

23. Unit F<irced Out:ige Rate

24. Shutdowns Scheduled Over Next 6 AI<7<iths 659.54 5,355.28

10. 6 184.18 0

0 5 048 720

~6 710 90 871 4 898 119 66.6 25.6 66.6 25.6 57.2 11.9 57.2 11.9 (Type. Date. and Duration uf Eacltl; 0 8.61 12 434.48 29,019.59 0

26 998 788 26,229,588 57.5 48.8 48.8 33.3

25. IfShut D<iwiiAt End Of Rep<>rt Periu<l'. Estimated Date uf Startup:

26. Units Io Test Status (I'rior tu Cooimercial Operatiuii);

Force:1st Acll loved INITIAL CR I'I'ICALITY INITIAL ELECTRICITY COil <I ERCIA L Ol'FRATION

(<)I77)

16 OPERATING STATUS OPERATING'DATA'REPORT.

DOCKET VO.

50-296 DATE

.C.OhliPLLTED DY.~~JLQ3L

>>fLEPHOgVE ~~29;=6846

- ~

~

Noites

i. Ung.Nerne:

. Brown; P re -'

g. 'Beporiing periog:

Novemit>er 1.580

-1o80-

'3. Licensed Therinal Power(h(IVt):

4. Namepldte Rating (Gross gg fiVe):

4 g'.

Design Electrical Rating (Net hfV(e):

6. i)faxiinuin Dependable'Capacity.(Gross hf IVe):.MBR. 4

7. hfaxinium Dependable Capacity (Nct hfIVe):

8. IfChaiiges 0'ccur in Capacity Ratipgs (Items Nuiiiber 3 Throughi 7) Since NA List Report Giwe Reasons.

9.'ower Level To,IVhiclg RestrictciII, IfAny (Net hIIVc):

10. Reasons For Restrictions, IfAny:

'NA This'iplont h Yr. 'to;Date Cumulative 720 549.73' tM 152.58 0

~<1~~cf

~49'3 BOP 548 8 835 55O'8645 86e5 83 ~

66. 2 0

11.7

~

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('ype, Diate, and Duration uf Each):

11. Hours In'Reporting Period

12. iVumbe'r Of Hours Reactor (Vas Critical

13. Reactor lteserye Shutdovvn Fiours 14.

labours Generator On'Line IS.,Unit Reserve.Shutdown lfours

16. Gross. Thermal Energy Ggincratcd,'(M'>VH)

17. Gross Electrical Energy Crenerated (hfdf..'I)

18. Nct Electrical Energy Ge'nerdted. (M'IVH)

19. Unit.Service'Factor

20. Unit Availability Factor

21. Unlit Capacity Factor (Using MDC Nct)

. UiiitCap:<<ity factor (Usiiig,DElt Net)

23. 'Unit Forced'Outaeee'Rate

24. Shutdogvns Scheduled Over iVext 6 h'Ionths

~o~Q!i

~~Z3 ~

1 810,8~

o ~QQ-'

65 XQB.

~~32 92k 23~82~4 323

77. 2, 77.2, 8.8

'c. IfShut l)own ggt End Of Rclgnrt period. Estiniated Date uf Staritup:

6, U>>itB liiTest Status (I'riuirtii Con>>nerciail Operation):

1)t8I81 Forecast Achieved 1iVITIAL CR ITICALITY II51ITIAL ELECTR IC11I Y COhfhffiltCIAL Ol'liltATIOeV (4)/77)

UNITSIIUTDOWNS AND POWER REDUCTIONS RFPORT h(ONii(, November 1980 COMPLETED I)y

'I'ed Thorn TELEPIIONE 205-729-9~

Xc).

Dat<<

~h 1

I

-n Cl V' Liccnsec F.vent Rcport =

Cl V

~n cn M CJC 5

Cause A, Corre).t)ve Action to Prcvcnt Rc<<urrcn<<e 15<

801101 Control rod sequence change from IIBII to IIAII 155 801108 Control rod pattern.ad)ustment 156 801115 B

Turbine C.V. tests and SI's 157 801128 F

19.33 B

Turbine trip while shutting down for maintenance (Steam leaks)

F: For<<cd, S

Schedule)i (c)/77)

Reason:

A Equipment Failure (Explain).

8 hlaintcnance or Test C.Refuel)ng D Regula)))ry Restriction li-Operate)r Training A Liccnsc Fxamination; F Actllllnlslrallve G.Opera)iona) Elrclr (Explain)

I I Other (Iixplain) 3 hielhod:

I.hlanual 2.hlanual Scram.

I.hut))n) )tic Sera)n.

4.Other (Explain) 5 Exhibit C ~ Instru<<tions ior Preparation 5)i Data linlrySheets I'or Lice)sec Event Report (LL'R) I'iie (NUREG.

0)6))

Exhibit I.Same Sour<<e I

I h

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UNITSIIUTDOlVNS AND POIVER REDUCTIONS REPORT hfONTII~a)temhex DOCKET NO.

UNITNAh(E DATE COhfPLETED BY TLLEPIIONE Cp

~ll I

I A

Ig~ tl)

Liecnsec Event Rcport ~,

Q tl ill cn'C c~

Cl C ~

0 Cause A Corrective Action lo Prcvcnt Rceurrcnee 153 801123 170.27 EOC-3 Refuel Outage F: Forced S: Sclrcdnicd

<<)/77)

Reason:

A.Equipment Failure (Explain)

B.hlaintenanee or Test C Rcfuclinf, I) Rcyilarory Restriction E Operator Training k Liecnsc Exatuioation F-Ado dlllsl ra I Iac G.Operational (error (Explain)

I I.Other (Explain) hfethod:

I -hfanual 2 hfanual Scram.

3.Autonratie Seraot.

4 Other (Lxplainl 4

Exhibit G Instructions for Preparation of Data Entr)'heets for Lieeruee Fvcnt Report (I.ER) I'ilcINUREG.

01 filI Exhibit I

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LPOTHS PElllT lllJCLL'hl PLhdT llllZT 1 nnd:Conlnon EMCTRXCAL MAINTENANCE SQQfARY

.For the Month of November 19 80 System

Component Natur'e of Maintenance E

ect on'ba e

Opera ti.oii of The Reactor Cause of Malfunction

'Results of Malfunction Action Taken To Preclude

. Recurrence Diesel Generator Diesel Generator 1A Alarm.Bell Malfunctioned NONE Bad alarm bell coil F

I.

Alarm bell inoperative Replaced coil, alarm now, operating properly:

TRfJ 18964!

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BRNS FERliY lVCLEAR PLANT VNXT 2

ELECTRICAL MAINTENANCE SLMhRY Date Systcr

. Component Nature of Haintenance E ectonSae Operation of The Reactor Cause of Halfunction Results of ifalfunction Action Taken To Preclude.

Recurrence 11/12/8 A-1 Drywell Blower A-1 motor tripping out NONE Trip relay failed.to drop nut I.

A-1 Drywell Blower I

and dampers' nnnrtva t'Wrrn J llV8% ~ J ll~

Repaired trip relay, motor and dampers.-

Nnw nperating prnper TRf/ 188680 11/14/8$ Control rt 1%%0Il Drive System FCV 85-11B Limit switche Al~ I AI VUV VJ adjustment NONE l

Limij switches OIIt nf ~juat-ment Improper ligtll indication as to valve position

/IA4%tat QA 14m<t-AUJ%llrl \\

%l JJlaJU switches to proper operat ion.

Indicato lights operating" mn II 1 Ont' properJyt L811/ J.oooo 11/15/80 Reactor Core Isolation 1 4 VVVJ J ~IS System Valve 71-3 Valve will riot close electrically

-at. nann1 0

Ul ItUttUJ NONE Contactor 2C out of adjust-ment Valve not'lectri-cally operable Cleaned and adjusted contactor,

%%AD Anavat4nrr IIVI Vr% J UJttQ properly.

TR8 18879 11/16/80 Contain-Atmosphere Dilution.

System FSV 84-8B'r LtLOseLI nnsition indicating light will

%not burn

'LtALIL 14 VIILt II %% 3 4 nrI 4 r a i 4 n rr lrrlU JIIUJ

% llVJttQ light socket P1 Acarl WnAW rat'%no V

Q light will not burn.

Replaced lieht socket, light wor&

properly.

TR8 17875 11/26/80 ll/10/80

Control, Rod Drive-System RIIR Service Water System HS 85-48 II4v 23-43 HS 85-48 Broken Indicating lights -'ntdica t valve is open when closed NONE NONE Switch springs broken lad limit rr4 l.AI%

I'rJI Utl CRD control switch inoperative Indicating lights indicate valve is open whhn closed Replaced broken spL i1lgs 8 swltch is now operable.

TRP 188641 Replaced limit switch, indicating lights are not oper'a ting properly.]

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BROWHS FERRY NUCLEAR PLANT UNIT 1 2

~

INSTRlAIENT MAINTENANCE S &MARY FOR -THE MONTH OF NOVEMBER 19 80 Unit 1 11.-5 SYSTEM Standby Liquid Control COMPONENT LI-63-1A NATURE OF MAINTENANCE Repair EFFECT ON SAFE OPERATION OF THE REACTOR None

'CAUSE OF MALFUNCTION Partially Clogged Bubbler Tube RESULTS OF MALFUNCTION Indicator Did Not Agree With Stick ACTION TAKEN TO PRECLUDE RECURRENCE None Unit 2 11-5 (Outage)

Control Rod Drive PDS-85-63 Replace None Gage Worn Out Outlet Pressure More Than Inlet None 11-6 11-14

1'1-16 11-19 Reactor Water Cleanup Standby Liquid Control Recircula-.

tion Primary Contain-ment FT-69-13A LI-63-1B 4

FT-68-5 LI-64-66 Replace Calibrate Calibrate Calibrate Nohe None None-None Faulty Transmitte Indicator Zero Shift Zero Shift Zero Shift No Flow Indication Indicator'id Not Agree With Stick Indicated Flow With Discharge Valve Closed Did Not Agree With Redundant Indicators None None None None 11-19 11-21 Reactor Feedwater Residual Heat Removal FI-3-13 TS-74-135 Calibrate and Backfill Replace None None Air in Sensing Line During Outag Faulty Temperatur Switch Indicated Flow With Pump Off Alarm Would Not Clear None None

I BROWNS FERRY NUCLEAR PLANT UNIT~>~mm D MEGSNICAL MAINTENANCE SUE fARY For the. Month of November

. 1980 SYSTEM COMPONENT NATURE OF MAINTENANCE EFFECT ON: SAFE OPERATION OF THE REACTOR CAUSE OF MALFUNCTION.

RESULTS OF MALFUNCTION ACTION TAKEN TO-PRECLUDE RECURRENCE 11/3/80 30 ventil-ation A

6 B control Low fan speed bay air'handli g

units None Loose belts None Adjusted belts'.

11/12 67 EECW FCV-67-48 Will not VPVL41L,V None Lack of lubricant co vaxve,operaror veer hnx None Lubricated valve s'threads and gear-hoax 11/14 23 RHRSW '3-597 D3 pump Leaking trough check valve None.

Bad seat or/and'"

disc Lost of maximum head on header DCR submitted.,to chan; valves 11/19 23 RHRa)w Cl air release

.wr'a 1 urn Leaking,trougt None Bad seat and disc

.Lost of maximum ll40ll Vll ulll Replace seat and disc

CSSC E UIPHENT BROWNS FERRY NUCLEAR PLANT UNIT MECHANICAL MAINTENANCE

SUMMARY

SYSTEM COHPONENT NATURE OF MAINTENANCE EFFECT ON SAFE OPERATION OF THE REACTOR CAUSE OF

. MALFUNCTION RESULTS OF JJALFUNCTION ACTION'TAKEN TO PRECLUDE RECURRENCE

.1/2/80 Ll/3 11/6 11/7.

11/7 Ll/10 Ll/11

!.1'/12 1.1/16 77 Radwast FSV-77-15A 85 CRD FCV-85-11A 85 CRD Module 26-27 85 CRD 85 CRD Pump speed

.increaser Hodule 10-43 74 RNR FCV-74-78 73 HPCI FCV-73-45 85 CRD Hodule 50-27 85 CRD Module 02-39 Will not o erate-Excessive lea throu h Vent valve leakin Low oil level Accumulator blowing air Scram valve leakin throu Opens too Slow Solenoid valv leakin air Accumulator Leakin None None None None None None None None None Low oil level Roller had hole in it Cap not on valve stem Unknown Low'er valve missing diaphragn on exhaust side Teflon seat blown Valve packing to Ti ht Unknown Worn piston None None None None None None None None None Added oil Replaced roller and and asket Replaced vent valve stem cover l Added oil Installed new diaphra~

Replaced seat ring disc askets

.& bod Loosened packing Replaced solenoid

'Rebuilt accumulator'l/19

,11/24 78 Fu'el pool cool-in 67 EECW A Pum'p A & C" core spray room coolers thrott lin valve Packing leak-ing Will not Throttle None None Operation Stem stuck None None Adjusted packing Lubricated stem

CSSC E UIPHENT BROHNS FERRY NUCLEAR PLANT UNIT 1

MECfiANICALMAINTENANCE SUlMARY For the Month of November 19 80 DATE SYSTEM 11/3 64 ventil-ation Rx 11/3/80 73 HPCI COMPONENT Turbine FCV-64-139 NATURE OF lfAINTENANCE Low Oil level Millnot operate EFFECT ON SAFE OPERATION OF TilE REACTOR None None CAUSE OF MALFUNCTION Leak on discharg of Aux oil um Blown seal cup RESULTS OF MALFUNCTION None None ACTION TAKEN TO PRECLUDE RECURRENCE Added Oil Replaced seal cup 11/5 I

ga ~ a 4 1 Ai~ aa aaaaa.a,aa

a. ~ ~

73 HPCI Aux. oil pump Leaking oil line None Loose coupling Lost 90 gallons oil Tiehtened counline ll/17" 78 fuel

)>

A.-.pump pool cvvl inn Leaking pack-JXll1>>

None Operation None Repacked pump 11/20 74 RHR D pump seal heat exchanger High seal water temper-ature None Plugged cooling water valve None Flushed valves 1 1/24 78 fuel pool coolin A puamp Leakiaag pumap MOaa e Operation Norie Adjusted packing 11/24 85 CRD

~

f.l/28 82 diesel enerator 82 diesel enerator A pump dischar F41 a.

i.J Jl.CL C 2 fuel oil um D diesel overnor e

High AP Leaking filae Low oil level None Nono None Dirty filters T.nnoo FC 1 t.oe Unknown None None Cleaned filter da14aaa e anA F4 1 a-oa aaaaJaada aa a a Ja a,

Added oil

30 OUTAGE

SUMMARY

November 1980 The scheduled Unit 3 cycle 3 outage duration prior to shutdown was 46 days.

'The outage duration was revised after -shutdown to reflect deletions of some modification and maintenance work as part of an overall cost reduction program.

The revised outage duration was set at 43 days with the refuel floor work items as the critical path.

There were 961 work items scheduled to be accomplished prior to the start of the outage.

By the end of the report period for this month, 224 items have been added as emergent work.

Approximately 18 percent of the total work items has been completed.

Major work items underway at the end of the November report period include:

Refuel Floor Vessel disassembly complete.

Steam line plug leakage and subsequent repairs have delayed MSIV work and start of maintenance interference bundle removals.

LPCI Modifications MG set installation underway.

Installing conduit.

H 0 Analyzer Near completion of conduit runs.

Working piping installa-tion for west side of torus sample valves.

Working cable pulls.

RCW Pum /Strainer Modification Piping prefabrication in progress.

In-stalled anchor bolts for new strainer.

Two of three foundations have been poured.

Electrical/Instrumentation Working breaker inspection and routine motor maintenance.

Breaker inspection is approximately 6 percent com-piete.

/

changeout complete.

Work will begin following completion of maintenance interference bundle removals.

Torus was opened November 26, 1980.

31 OHMAGE SUEY (Continued)

November 1980 Balance of Plant (BOP /Turbine - Because of the deletinn of HP turbine disassembly and inspection work, the'urbine floor work is no longer critical path.

The zaagor work item vill be maintenance on "3C" rea6tdr feedpump which started November 28,

1980, when main condenser vacuum was broken.

Hydraulic shock arrestor inspection and repair is approximately 70 percent

'omplete.

Hanger inspection per NRC Bulletin 79-14 and anchor inspectons per NRG Bulletin 79-02;is in progress.

Valves MSRV removals for offsite testing.is in progress.

MSIV work has been delayed due to main steam line plug leakage.

Local leak rate testing (LLRT) on selected valves is in progress.

Of the 157 valves t'o be local leak rate. tested, 118 have been tested and 47 have failed.

Failure rate on initial test is 46 percent.