monthly operating repts for mar 1981. · refuelin information march 1981 unit 1 unit 1 is scheduled...

TENNESSEE VALLEY AUTHORITY

DIVISION OF POWER PRODUCTION

BROWNS FERRY NUCLEAR PLANT

MONTHLY OPERATING REPORT

March 1, 1981 — March 31, 1981

DOCKET NUMBERS 50-259, 50-260, AND 50-296

LICENSE NUMBERS DPR-33, DPR-52, AND DPR-68

Submitted By:P nt Superin ndent

'It

*

TABLE OF CONTENTS

Operations Summary ... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

Refueling Information

Significant Operational Events

~ ~ ~ ~

~ ~ ~ ~

~ ~ ~

~ ~ ~

Average Daily Unit Power Level ~ ~ ~ 15,

Operating Data Reports

Unit Shutdowns and Power

~ ~ ~ ~ ~ ~

Reductions. ~ ~ ~ ~ ~

~ ~ ~ ~ ~

~ ~ ~ ~ ~ ~ ~ ~

18

21

Plant Maintenance ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ t ~ ~ ~ 25

Outage Summary ~ ~ ~ ~ 37

*4 4

0 erations Summar

March 1981

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 sixteen reportable occurrences reported to the NRC during

the month of March.

Unit 1

There were no scrams on the unit during the month.

Unit 2

There were three scrams on the unit during the month. On March 7,

the reactor scrammed from a group 1 isolation due to 'high steam flow in

three steam lines caused when "B" inboard MSIV continued to close during

a MSIV 10% closure test. The reactor scrammed on March 13, when the main

urbfh'e==tripped,due'to=.~alse~high=water level-"on-.the, reactor caused-..by-

an open equalizer valve on a water level indicating switch. On March 28,

the reactor scrammed when the main turbine tripped due to a false signal

from thrust bearing wear detector caused when a wire was lifted from a re-

lay during electrical maintenance.

Unit 3

There was one scram on the unit during the month. On March 8, the

,reactor scrammed from an APRM "HI HI" flux caused by a pressure spike when

a broken weld on a samplinp line caused a loss of pressure to a main steam

line pressure regulator which resulted in a turbine trip.

2

~Oeraitfoue Su~mmer (Coutfaaued)

March 1981

Fati ue Usa e Evaluation

The cumulative usage factors for the reactor vessel, are as follows:

Location

Unit 1 Unit 2 Unit 3

Shell at water line

Feedwater nozzle

Closure studs

0.00501 0.00393 0.00331

0. 24257 ' '.'16960' 0. 12530

0. 19832 ' '. 13694' 0. 1011:7

Note: This accumulated monthly i6foRatiln 'sat!isfie's technical

specification section 6.6.A.lj7.8(3) r'epdrting requirements.

Common S stem

Approximately 3.35E+05 gallons of waste liquid were discharged containingapproximately 3e36E-01 curie. of activities.

Refuelin Information

March 1981

Unit 1

Unit 1 is scheduled for its fourth refueling beginning on or about

April 10, 1981, with a scheduled restart date of July 23, 1981. This re-

fueling will involve loaing additional 8 X 8 R (retrofit) fuel assemblies

into the core,. the final fix on the sparger modification, power supply on

LPCI modification, generator breaker and unit station transformer tie-in

(requires Unit 2 to be shutdown),, 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

spent fuel assemblies, 260 new 8 X 8 R fuel assemblies, and one spent 8 X 8

R fuel assembly. Because of modification work to increase spent fuel pool

capacity to 3471 assemblies; present available capacity is limited to 134

locations, Mew hdgh denslty~e~toragawachs have heen installed and

are in the process of being qualified for use in the upcoming fourth refuel-

ing out'age.

Unit 2

Unit 2 is scheduled'or its fourth refueling begi'nning on or about

March '26, 1982, with a scheduled restart date of August .13, 1982. This

refueling outage will involve completing reli'ef valve modifications, torus

modifications if all approvals are received, '"A" low pressure turbine in-

spection, MG set installation for. LPCI modification, and loading additional

8 X 8 R fuel assemblies into the core.

Refuel:L~n Information (Cont:Lnued)

March 1981

Unit 2 (Continued)

There are 764 fuel as. emblies in the reactor ~vessel. At the end of the

month, there were 132 discharged cycle 1 fuel assemblies, 156 discharged

cycle 2 fuel assemblies, and 352 dischaxge'd cycle '3 fuel assemblies in 'the

spent fuel storage pool. The present avai'lable'apacity of the spent fuel

pool is 160 loca.tions. With present capacitp, the 1979 refueling was the

last refueling 'that could be discharged to'he @pent fuel poolwithout'xceeding

that capacity and maintaining fu'll'code discharge capability in

the pool. However., 949 new high density storage locations have been in-

stalled, but canno1 be used unt:Ll Special Test 161 is completed.

Unit 3

Unit 3 is scheduled for its fourth refuelihg 'beginning on or about

September 25, 1981,, with a scheduled restart'da'te 'of February 7, 1982. This

refuleing involues loading additional .8" X 8 R (retrofit) assemblies into the,

core, relief valve modification,, turbine inspection, generator breaker and

unit station transformer tie-in,, and torus'bdific'at:Lons if all approvals

are received.

There are 764 fuel assembl:Les presently in the x'eactor vessel. There

are 124 discharged cycle 3 fuel assemblies, 144 dischax'ged cycle 2 fue).

assemblies, and 208 discharged cycle 1 fuel assemblies in the spent fuel

storage pool. The present avai:Lable storage capacity of the spent fuel

pool is 1052 locat:Lons.

Date Time

Si nifi'cant 0 erational Events

Unit 1

Event

3/01/81 0001

1500

Reactor thermal power at 98%, maximum flow, rodlimited.Reactor thermal power at 99%, maximum flow, rodlimited.

3/04/81 1500 Reactor thermal power at 98%, maximum flow, rodlimited.


3/08/81 0140

030003100400

0420

Commenced reducing thermal power for (MSIV closuretiming) SI 4.7.D.l.B-2 and SI 4.1.A-11.Reactor thermal power at 65%, holding for MSIV SI's.MSIV SI's complete, commenced power ascension.Reactor thermal power at 76%, holding for turbinecontrol valve tests.Control valve tests complete, commenced PCIOMR(sequence "B").

3/09/81 0335

2300

3/~13 81 2300

3/15/81 0025

0145

0202

Reactor thermal power at 99%, maximum flow, rodlimited.Reactor thermal power at 98%. EHC vibration limited.

Reactor thermal power, at 97%,,EHC,.vibration limited.

Reduced thermal power to 85% for turbine controlvalve tests and SI's.Turbine control valve tests and SI's complete,commenced power ascension.Reactor thermal power at 97%, EHC vibration limited.

3/17/81 0840

1000

10121030

Commenced reducing thermal power for a control rodpattern adjustment.Reactor thermal power at 64%, holding for controlrod pattern adjustment.All rods out.Control rod pattern adjustment complete, commencedPCIOMR.

3/18/81 2300 Reactor thermal power at,99%, maximum flow, EOC-4coastdown.

3/19/81 0700 Reactor thermal power at 98%, maximum flow, EOC-'4

coas tdown.

~si nifiennt Operationel Events

Unit 1

Date Time Event

3/20/81 0700

1924

1945

2300

Reactor thermal power at 99%, maximum flow, EOC-4

c'oastdown ~

Reduced reactor thermal power to 97% when the1001breaker tripped los:ing unit preferred power and i

locking out reactor feedwater pumps and. xecirculationMG controls due to loss of power to controller.,Reactor feedwater pumps and recixculation MG setsback to normal and unit prefez;red power placed on1002 breaker, conmlenced power ascension.Reactor thermal power at 98%, maximum flow, EOC-4coa.'tdown

e~

3/21/81 0115

0155

02300700

Reduced thermal power to 85% for turbine controlvalve tests and SI's.Turbine control valve te. ts and SI's completed,commenced power ascension.Commenced PCIOMR from 96% thermal power.Reactor thermal power at 98%, maximum flow~ ETC~4

coastdown.

3/23/81 0815

08250900

2300

Condensate demineralizer momentarily bypassed, re-ducied thermal power to 91%.Commenced power,ascen: ion from 91% thermal power.Reactor thermal power at 98%, maximum flow, EOC-'4

Reactor thermal power't 99%, maximum flow,. EOC-4'-

coastdown.

3/24/81 2300 Reactor thermal power at 98%, maximum flow, EOC-4coastdown.

3/25/81 2300 Reactor thermal'power at 99%, maximum flow, EOC"4coastdown ~

3/26/81 1500

2300

Reactor thermal power at, 98%, maximum flow, EOC 4coa s t(Iown ~

:Reactor thermal power at:.98%, EOC-4 coastdown.

3/28/81 0100

0121

0500

0700

Corrtmenced reducing thermal power fox turbine~control,valve tests and SI's.Reactor power at 82%, hplding for turbine controlvalve test.; and SI's.Turbine control valve tests and SI's completed,~commenced PCIOMR.Reactor thermal power at 98%, maximum, flow', EOC~4,coastdown.

Date Time

Si nificant 0 erational Events

Uni't 2

Event


3/20/81 1225

12351240

3/21/81 0205

0336

0430

0600

Reduced thermal power to 97% for control rod ad-justments.Commenced power ascension.Reactor thermal power at 99%, maximum flow, rodlimited.

'

Reduced thermal power to 91% for turbine controlvalve tests and SI's.Turbine control valve tests and SI's complete,commenced power ascension.Commenced PCIOMR from 96% thermal power (sequenceIIEII )Reactor thermal power at 99%, maximum flow, rodlimited.

3/26/81 1555

1650

220.0.

Reduced thermal power to 82% for removal of Cland C2 high pressure heaters from service forrelief valve maintenance."C" string high pressure heater isolated, reactorthermal power at 82%, holding for relief valvemaintenance."C".. string high pressure&eaters, back in service.„commenced 'power ascension.

3/27/81 0300

0700

0820

2138

2325

Commenced PCIOiiK from 97% thermal power (sequence

Ilail

I)

Reactor thermal power at 99%, maximum flow, rodlimited.Reduced thermal power to 83% for removal of "C"string high pressure heaters from service formaintenance on heater drain line."C" string high pressure heaters back in service,commenced power ascension.Reduced thermal power from 96% to 82% for turbinecontrol valve tests and SI's.

3/28/81 0025

0900

1252

Turbine control valve tests and SI's complete,commenced power ascension.Reactor thermal power at 99%, maximum flow, rodlimited. (3)Reactor Scram No. 117 from 99% thermal power,turbine trip during work on thrust bearing weardetector.

~Si ~nific:ant Operational Events

Unit 1

Date Time Event

3/29/81 2300 Reactor thermal power at 97/, maximum flow, EOC-4coastdown.

3/31/81 2400 Reactor 'thermal power, at 97K, maximum flow, EOC-4coastdown.


Unit 2

Date Time Event

3/01/81 0001

0910

Power ascension in progress from 0 power. (Startupfrom scram on February 28, 1981).Commenced PCIOMR from 64% thermal power (sequenceIIBII)

3/02/81 2010

2047

2225

Reactor thermal power at 99%, maximum flow, rodlimited.Both recirculation pumps tripped reducing reactorthermal power to 36%.SI 4.6.A.6 and 7 complete for "A" recirculationpump, "A" recirculation pump placed in service.Commenced power ascension.

3/03/81 0408

0700

1230

SI 4.6.A.6 and 7 complete for "B" recirculationpump, "B" recirculation pump placed in service.Commenced power ascension.Reactor thermal power at 87%, holding to maintaincore limits.Commenced PCIOMR from 87% thermal power (sequenceIIBII)

3/04/81 0700

1500

2300

Reactor thermal power at 99%, maximum flow, rodlimited.Reactor thermal power at 98%, maximum flow, rodlimit;ed-;. —-Reactor thermal power at 97%, maximum flow, rodlimited.

3/05/81 0700

1500

2300

3/07/81 0408

1430172021152142

Reactor thermal power at 98%, maximum flow, rodlimited.Reactor thermal power at 99%, maximum flow, rodlimited.Reactor thermal power at 98%, maximum flow, rodlimited.

Reactor Scram No. 115 from 98% thermal power(1)while performing SI 4.1.A-'l (MSIV closure), "B"inboard MSIV continued to go closed after the push-button was released, resulting in a full isolationand scram.Commenced rod withdrawal for startup.Reactor Critical No. 128.Rolled T/G.Synchronized generator, commenced power ascension.

3/08/81 2230 Commenced PCIOMR from 75% thermal power (sequenceI IBlI

)


10

6~i„nilicant~Opatatinnal Evanta

Unit 2

Date Time Event

3/11/81 22042237

2243

Commenced reducing thermal power to test MSIV1-26.'eactorthermal power at 73X, holding to tekt P1SIV

1-26.MSIV 1-26 tested and. timed, commenced power ascen-sion.

3/12/81 0100 Reactor, thermal power at 99X, maximum f llaw, rdd1:imited.

3/13/81 2200

2259

Commene;ed reducing thermal power to remove bothrecirculation pumps from service fox bruah replaCe-ment oii recirculation 'Ig set.Reactor Scram No. 116 'rom 50% therma3. powerdue to high water level signal which caused'hemain turbine. and reactor feedwater pumps to tx'ip andreactor. scram on an indicated high water level.

3/14/81 131'6151518301915

Commenced rod withdrawal for startup.Reactor Critical Noa 129.Rolled T/G.Synchronized generator, commenced power ascension.

3/15/81 0330 Commenced PCIOMR from 67X thermal power,'(S'eqdence'I

pll )

3/16/81 0021

0026

01120200

0800

Commenced reducing thermal power from 87X p~ower" forcontro3. rod pattern adjustments.Reactor. thermal power at 78X for control rod adjust',—ments.Rod adjustments complete, commenced power a'scenieon.Commenced PCIOiK from 81% therma3. power '(se~quenc'eIIBII)Reactox thermal power at 99%,. maximum flow, rodlimited.

3/17/81 0600

1500

Reactor thermal power at 98%, maximum flow, rodlimited.Reactor thermal power at 97%, maximum flow, rodlimited.

3/18/81 1018

1045

1335

1355

Commenced reducing thermal power fox a contro3.rod pattern adjustment.Reactox'hermal power at 73%, holding for controlrod pattern adjustment.,Contro3. rod pattern adjuc>tment complete, commencedpower ascension.Commenced PCIOMR from 89% t'hex'mal powex'sequenceI

Idyll�

),


Unit 2

Date Time

3/28/81 20352358

Event

Commenced rod withdrawal for startup.Reactor Critical No. 130.

3/29/81 045505171200

Rolled T/G.Synchronized generator, commenced power ascension.Commenced PClOMR from 67% thermal power (sequenceI IBlI )


3/31/81 1245

1320

1930

2400

Reduced thermal power to 87% for control rodpattern adjustments.Control rod pattern adjustments completed, commencedPCIOHR (sequence "B").Reactor thermal power at 99%, maximum flow, rodlimited.Reactor thermal power at 99%, maximum flow, rodlimited.

~EI ~nifinant OEaratienal Evente

Unit 3

Date Time

3/01/81 0001

0100

0105

0230

Event:

Control rod pattern adjustment complete, in'cre'fasted'eactortherma.'L power to 70/, holdiiag fok t'urbine

control valve tests and SI"..Turbine control valve tests and SI's complete,',commenced PCI011R, (control cell core).Stopped PCI01IR at 71% thermal power, computer outof service.Computer back in servicel commenoed PCIONR frOm 71/.thermal po~er (control ce,ll core).

3/02/81 0801 Reactor thermal power at 99X, maximum flow, .rodlimited.

3/03/81 0419

0615

0705

1005

Reduced therma.'!. power to 86X, to remove "P." condensatedemineralizer vessel from s< rvice, to check'esselselements and resin t:rap for break through; ~also to

'ackwashand precoat: condensate demineraliz'er vesselsI l]l1II and IIJ I I

Condensrate demineralizer proble'm resolved, commencedpower ascen ion.Commenced PCIOlifR from 96X thermal power '(co'ntrol'ellcore) .Reac:tor thermal power at 99%, maximum flow, r<>dlimited.

3/07'/81 2340KH

Commenced reducihg;'thermal power for turbine- con'troI "

valve tests and SI's.

3/08/81 0035

0120

0430

0800

2011

Reac:tox thermal power at 64%, turbine control valvetests and SI's in progress.Turbine cont:rol valve tests and SI's complete,commenl.ed power ascension.Commenced PCIOllfR from 97%'lhermal power (cdnt&ol

chil'ore.)

.Reac,tor thermal power at 99%, maximum flow, rodlimited.Reactor Scram No. 94 from 99% thermal power d'ueto kll flux on "F'I and "C" APRN, caused b'y connectionfailure on the sens:Lng line of the turbine pressureregulator (equipment, malfunction) .

3/09/81 09352230

Commenced rod withdrawal for stax'tup.Reactox Critical No. 106«

3/10/81 024203102210

2300

Rolled T/G.Synchronized gene.rator, commenced power ascension.

'educedthermal power from 73% to 64% for controlrod adjustments.Rod adjustments completel commenced power ascension.

13

Date Time


Unit 3

Event

3/11/81 0100

2300

Commenced PCIOi~K from 76% thermal power (control cellcore).Reactor thermal power at 99%, maximum flow, rodlimited.

3/12/81 1445

1520

21302300

Commenced reducing thermal power due to high river ~~

hT.Reactor thermal power at 73%, holding due to highriver hT.Commenced po~er ascension from 73% thermal power.Commenced PCIOi~K from 97% thermal power (cont'rol cellcore).


3/15/81 0001

0036

0040

0135

--=,.- —..-0200- -- ~

Reduced thermal power to 82% for turbine controlvalve tests ans SI's.Turbine control valve tests and SI's completed,commenced power ascension.Reactor thermal power at 96%, holding for controlrod drive exercise.Control rod drive exercise complete, commenced powerascension.

.-.Reactor"'thermal= power-ae:'99%; Maximumflow,'od'imited.

3/20/81 2355 Commenced reducing thermal power for turbine controlvalve tests and SI's.

3/21/81 0015

0028

0035

0105

0115

0415

0740

0743

Reactor thermal power at 87%, turbine control valvetests and SI's in progress.Turbine control valve tests and SI's complete,commenced power ascension.Reactor thermal power at 91%, holding for control roddrive exercise.Control rod drive exercise complete, commenced powerascension.Commenced PCIOifR from 97% thermal power (control cellcore).Reactor thermal power at 99%, maximum flow, rodlimited.Commenced reducing thermal power for unit shutdowndue to high level alarm in east side scram dischargeheader (personnel error).Plant personnel were performing TI-58 on scram dis-charge header. Stopped reducing thermal power at 73%upon discovery of personnel error.

14

~Si ~~nificant O~erational Event:s

Unfi.t 3

Date Time Event:

3/21/81 07500835

Commenced power ascension from 73% therm@1 ipoker'.Reactor t'herma.'L power, at 99%, maximum flow, rodlimited.

3/25/81 1720

1755

Commenced reducing t:hermal power due to gen'erAtoLbus duct cooling fan siinoking.Reactor therma.'L power at 54X.

3/26/81 070015OO

1800

2200

Reactor therma.'L pbwerReactor thermal powering fan problems.Bus duct cooling fanspoweir ascension.Commenced PCIO],"R fromcell. core).

,at 55%.,at 58% due to bus duct cool-

back:in service,c*mmiended'5%

thermal power (co'ntrol

3/27/81 1306 Reactor thermal power at 99%, maximum flow, rodlimi.ted-

~

GAIA

3/28/81 0010

0020

0035

0700

Commenced reducing thermal power for turbin'e don<trol valve t:ests and SI's.Reactor thermal power at 82X, holding for. turbinecontrol valve tests and SI's.Turbine control y'alve tests and SI's complete„.commenced-power. —,ascensionReac:tor thermal power't'99X.; maximum flow, rodlimi.ted.

3/30/81 0357

0555

06250915

1130

1700

Reduced reactor thermal power to 71% when 3iAreactor. feedwater pump tripped '(hi vibrat;io'n).',Roll,ed 3A reactor feedwater pump for vibiat'iotIicihecks,,3A reactor feedwater pump tripped on high v'ibr'ation.Rolled 3A reactor feedwater pump, commended powerasceinsion.Commenced PCIOl!fR from 93% thermal power i|controlcell. core).Reactor thermal power at 99%, maximum flow, rodlimf.ted.

3/31/81 2400 Reactor thermal power, at 99%, maximum flow, rodlimited;

(1) Equipment malfunct:Lon(2) Unknown — suspected per onnel, error(3) Personnel er'ror

15

AVERAGE DAILYUNITPOWER L'EVEL

DOCKETNO.

Brotens Perry — 1

4-1-81

COMPLETED IIY Ted Thorn

TELEPHONE

IONTH March 1981

DAY AVERAGE DAILYPOWER LEVEL() IWe.)bet)

1045

DAY AVERAGE DAILYPOWER LEVEL(MWC-Net I

17 859

10

12

13

15

16

~ A

1061

1053

1048

1047

1042

1031

912

1057

"1057'041

1046

1044

1031

1032

1033

IS

19

20

21

23

'75

26

27

2S

')9

30

31

983

1042

1048

1038

1047

1038

1075

1045

10'40'*

1041

1023

1033

1027

1025

INSTR UCTIO)VS

On this I'or)nat,!ist thea))era c daily spit Poa').r le)el ii) ~Inc Nct I'))r each day ii) thc rcl)(»til) ~ lni)ilth. C)))ni)t)tc tt)lhc nc Jfcsl ivh))ic IncSa'6'at t.

li)/771

AVERAGE DAILYUNITPOWER LOVEL

DOCI'ET NO.

f rowns, y

DATE

CoiIPLETED BY Te.d Thorn

TELEPHONE

March 1981

DAY AVERAGE DAILYPOPOVER'EVEL(~IWe.Nct I

719

878

833

1056.

1062

1058

201

559

9.52

":10'69

'AY17

l9

OP,

21

23

24

)5

26

-AVERAGE DAILYPOWERLEVEL')))IWe*Net)

i 1048

9991066

~QZ)1056

1062

1064

106rI

1070

1007

ll 1055 27 958

I2

l3

l4

I5

IG

10i60

10,11

'93

8i66

1043

28

') 9,

552

,508

978

1~02

INSTRUCTIONS

Oi> this format.!ist the average daily j)'pit I)i))v'cr Ic)cl ii>!)Inc Nct for each day ir> tl>c icl)i)rtin nl))l>tl>~ Ci)n>pote tothc nearest whole n>c;a)vat t.

I'>/77>

17

AVERAGE DAILYUNITPOWER UsVEL

50-296DOCKET NO.

UNIT Browtls Ferry — 3

4-1-81

COMPLETED BY ~mt 'Ehom

TELEPHOiNE 205-729-6846

MONTH

DAY AVERAGE DAILYPOWER LEVEL(hlWC-Net) '

901

DAY -AVERAGE DAILYPOWER LEVEL(ill

We-Net�

)

107917

10

13

IS

1042

1031

1072

1080

1082

1077

864

-14===.487

959

978

1053

1068

1064

1071

18

19

ap

22

23

24

25

26

27

28

59

3P

31

1071

1074

1079

1053

1066

1068

1072

931

652=

1028

1056

1068

971

1067

INSTRUCTIONS

0» this for»tat.!ist thc ai'crape daily yI)it PI)Micr Icicl i»!II'tVC-Nct I'ol'ar!1 \lay I» thc fc})iiltl»I.»I i»th. Cii»IP»lc lolhc Ilcarcst Ivhiilc»lc~aN:Itt.

I'II77 )

18

OPERATING DATAREPORT

DOCKET NO.DATE 4-1-81

COMPLETED E>Y Ted ThornTELFPfIONE 205-729-6846

OPERATING STATUS

Notesl. Unit Name'

2. Reportine Period: March 1981

3. Licensed Thermal Power (!>IWt):

4. Na>neplate Rating (Gross i>ftVe):

5. Design Electrical Rating (Net MWe): 1065

6. !>Iaxin>um Dependable Capacity (Gross LIOVe):

7 ~fazin>um De endable Ca acitv Net i~Ice:

1098.41065

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

iIA

9. Power Level To.Which Restricted, IfAny (Net MWe):10. Reasons For Restrictions, IfAny:

This Month. Yr.-to.Date Cumuh tive

0

764,657

11. Hours ln Reporting Period 2,160

13. Reactor Reserve Shutdown Hours

14. Hours Generator On-Line 74415. Unit Reserve Shutdown ffours . 0

16. Gross Thermal Energy Gencratcd (MWH) 377- 054

17. Gross Electrical Energy Generated (l>IWII) 786,760 2,226,87018. Net Electrical Energy Generated (MIVH)19. Unit Service Factor20. Unit Availability Factor 100.0 99.121. Unit'Capacity Factor (Usi»g i>IDC Net) 96. 5 94.422. Unit Capacity Factor (Using DER Net) 96.5 94. 4

23. Unit Force<I Out:>gc Rate 0 0.924. Shutdo>vns Scheduled Over Next 6!>Ionth» (Type. Date. and Duration of Each):

Refue1in A >.il 1981

58,44256, 950,15 ———~5,115.29

99 972 69932,990 16032,035,01561.861.8.

51. 5

28.1

5. IfShut l)own At End'Of lfeport I'crif>):E»tin>atcd l)ate of Startup:6. Units I» Tc»t Status II'rior t» Con>n>ercial Operation): Fureca»t Ach>cved

IN ll'IAL ClfIT ICA LIT Y

INll'IAL ELECTRICITYCO.'VDIERCIAL OPI!RATION

(o/77)

'

OPERATI>NG DATAREPORT

OPERATING STATUS

DOCKET >NO. 50 260

CO.'>IPLETED BY ~~It'hornTELEPHONE M>~~29-6846

bootes1. U it N . Brogans Ferry — 2

Reportfnn Per>od; I'farch 19'81

3. Licensed Thermal Povver (!>I)Vt):

4. nameplate Rating (Gross -11)Ve'): 1152

5. Design Electrical Rating (iNet 5'IWe): 1065

6. Ifaximu>n Dependable Capacity (Gross IIIVfe): 1098.47 hfaximum De endable Ca acitv i%et slftVe: 1065

P P u( )8. IfChanges Occur, in Capacity Ratings (Items IIIumber 3 Through 7) Since Last Rel>ort. Give Reasons:

9. Po>ver Level To )Vhich Restricted, IfAny (Net MM(e):

10. Reasons For Restrictions. IfAny: NA.

This lpfonth Yr.~ to.Date Cun>uiative

744 2 1'60I i. Hours In Reporrie8 period

~ -1'.* 13. Reactor Reserve Shutdown Hours14. Hours Generator On-Liine 689.75 i i, 2040.99 .31 781.9515. Unit Reserve Shutdown Ilours 0 , 0

16. Gross Thermal Energy Gencratcd (ilfWH) :! 092 498 . 6 232 974, 99 803 61717. Gross Electrical Energy Generated (ilf)VH)18. Yet Electrical Energy Gencratcd (I>if)VII) 672,804

. . .2,031,060 29,981,367

19. Unit Scrvicc Factor 92.7 '4.5 59.620. l'nit Avaih>l>ilityFactor 92. 7 '94. 5 59. 6

l. Unit Capacity Factor (Use» l4IDC Nct) 84.9 l l l l 88 i3 51.02. Unit Capacity I'actor IU5i»g DER hct) 84.9 88.3 5r .0

23. Unit Forced Out:> c Rate . 7.3. '5.5 ~ . 31.524. Shutdo>vns Scheduled Over Nceet 6!>Idnths ITypce I);>te, and f)urati>»> ul';>ch):

4

Haintenance A.>ril 1981 (21 davs)

25. IfShut Du>vn At End IOf letup>irt I>crit>II:Esli>i>atcd I)r>tc ufStart»p.'6.

Units In Test Status I prior tu Cun»ncrcial Oper:>tiun)> r F>>recast A>.'h'>IeVCItf

IYITIAL Cft'.ITIiCALIT Y

IYll'IAL EL,EC'I'R ICITY, COiliIERCIAL Ol'FRATIO.4

(4)/77)

4

20

OPERATING DATAREPORT

OPERATING STATUS

DOCKET NO.DATE

COlifPLETED LtY Ted ThornTELEPHONE ~~o- 46

Notesl. Unit Name: Brows Ferr — 3

p od Harch 1 98 1

3. Licensed Thermal Poiver (!iIWt):4. Nameplate Rating (Gross IIWe): 1152

5. Dcsien Electrical Rating (Net MWe): 1065

6, alfaximum Dependable Capacity (Gross iiOVe):'i » e endable Ca acit Net iaaf lVe: 10657..fasnnn D p p y( )

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

NA

~ ~

9. Povver Level To Which Restricted, IfAny (Net bfWe):10. Reasons For Restrictions, IfAny

NA

This ilfonth Yr.-to.Date Cumulative

11. Hoiirs In Reporting Period 744 2 160

13. Reactor Reserve Shutdown Hours

14. Hours Generator On. Linc 713.02 1 573.9915. Unit Rescrvc Shutdown floors 0

16. Gross Thermal Energy Gencratcd(MWH) 2 207 040 4 488 641

I i. Gross Electrical Energy Generated (iaaf WH) 744,730 1 511 950

18. Net Electrical Energy Gencratcd (illWkl) 722,574 1 465,667

!I 20. UllltAvailability Factor 95. 8

21. Unit Capacity Factor (Using i~IDC Net) 91. 2 63. 7

22. Unit Caixicity Factor (Using DER Nct) 91. 2

23. Unit Fr)reed Outage Rate 4.2 9.424. Shutdoivns Scheduled Over Next 6 iifonths (Type. 1)ate, and l)oration of Eaclt I:

58;442-.-2-7-- 605 88--1 966.46

~26 60788 626 050 98025,289,990

7

66.366 '9;"7

5. IfShut l)i)i'vllAt End Of ltcport Pcriy):Estin'iatcd l)atc of Startup:6. Units In Test Status (Prior to Coinmcrcial Operation): F >r ast Achieved

INITIAL CI<ll ICALITYINITIAL ELECTltlCITYCOilitii I(CIAL Ol'E RATION

(i)/77)

UNITSIIUTDOWNS AND POWER REDUCTIONS

lREPO T MON'fll

I

DOCKET NO..UNll NAME

DArECOhll'I.ETED IIY

TI!I.EI'IIONE

50-260

r- -81I e(I . I holll.

l)ale

fP

J

CfI

fLie

I:.

Rc

t

cnsccventort ~

ff CP

IJI'

c'

F IJO

Cause A CorrcclivcAction lo

Prevent Rccufrcncc

170 3-&81 B HSIV Closure Timing (SI 4;7.D.l.b.2and SI 4.1.A.-11)

171 3-17-81 Control rod pattern adjustment

F: I'orccdS: Schcdpled

()/77)

Reason:A.EIIuipmcnt Failure (Explain)B.Maintenance or TestC. Rc fuel inI;D.Rct,ulatory Restriction

I'i

Opcfalor Training h. Liccnsc Fxanthtatlon~F.Adtninistrativc f

G Operational Error (Explain)I I Other (Explain)

hlcthod:I hlanual2.hlanual Scram.3-Automalic Scram.4.Other (Explain)

4Exhibit G - Instructionsfor Preparation ol'DatalinlrySheets I'or Licenseefvcnt Rcport (I.l!R) File (NURI'.G.016 I )

Exhibit I ~ Sant' Iur '

VNITSIIUTDOWNS CND POWER REDVCTiONS

REP RThlON'fll

DOCKET NO 50"260

COh(PLETEI) N'ed Thorn

liate

'rr,

v1

LI

R

ccnsccvcnInnrl Ar—

r.0 ~C QG

Cause Lrr. CorrectiveActi(illIo

Prcvcnt Recurrence

179 3-2-81 Derated due to oA" and oBO recircula-.tion pumps tripping

180

181

3- I-81l

3-'11-81

1 I C 1Jl ~ Jl A n ral 4 1 n nnvI nv'Illa 11n CT ll 1 d 1 111 ~ ILLS Ir4LLvLllILll5vL ~ I ~ L ~

board MSIV continued to go closed aftetpushbutton was released, resulting ina full isolation and scram

Derated to test MSIV 1-26

182

183

3-13-81

3-18-81 S

19 ~ 2I

B

I

I

I

Cnvne lI~ In LO hallh llatnr 1 errel 'indi Ca

tion which caused the main turbineand reactor feedwater pumps to trip.Equalizing valve on level indicatorwas open ~

Control rod adjustment

I

F: ForcedS: Scheduleil

Reason:A Equipmcnt Failure (Explain)Bt.h(aintcnancc ol TestC Refuelingii.iRcgulatory RestrictionI!.Operator Training k Lii:ense FxaminationF.AdministrativeG upcrat(ona( Error (Expiain)I I Oilier (ExplJill)

3Method:i h(anual2.Manttal Scram.3.AUtolll'll!cScfJnl.4 OlhCf (I'xpiJIII)

Exhibit G Instrui.lionsfor PICp:IIJIniil ol Dal J

Entry Siiccts I'or LieciiseeEvent Report (Ll!R)File (NVREG-036rl-)

5— Exhi'Ml I - Sa;Ile Soliree

Olt'iVS AND POIVER REI)UCTIONSUNITSIIUTI)

RT hlON fll I larchREPO

l)OCKET NO. 50-260UNI'I' AhlE

I)ATF 4-2-81COhlPLETEI)!IY Ted Thorn

I)atc~A

I

CI

J

h

a

V Vi Re

cciisccvc iilpofl

Cause A ('orrcclivcAclioii lo

Prevent Rccurrcnce

184 3-28-"gl 16.42 Scram due to turbine trip whileworking on thrust bearing weardetector

I': FiircedS: Schedulcil

(9/77)

Reason:A.Equipmcnt Failure (Explain)I).hlaintenancc or TestC.RefuelingI).Regulatory Rcstri«lion, IL Opcral<ir Training 8; Liccnsc ExaniinationF-Administ rat ivcG Operational Error (Explain)I I Other (Explain)

hlcthod:I MJnual2 hlanual Scram.3 Auloinalic Scram.4 Otl)cf (ExplJiii)

Exhibit G - Instructionsfor Preparation of l)at JEntry Sliecls Ior LicciiseeEvent Report (I.I!R) Fil» (NLIREG.OI6I)

Exhibit I ~ Siuue Source

~~ ~ ~

o

I ~ ~ ~

I I ~

~ ~~ ~ I 'o

~ ~

~'

~ ~

0 ~

R~ ~ ~~ I ~

~ ~ ~ I

I

I

vJ

BRO'ZNS FERRY lUCLEA1'. PLANT UllITu

ELECTRICAL HAIHTENANCE SUMMARYl

For 'he ?lonth of Narch 19 81

D""e System Component Nature ofllaintenance

Operation ofThe I Reactor

Cause of."fal function

Results ofa~la 1 func t ion

Action '1'aken

To PrecludeR currence

3/6/81 EEC14 EEL Northheader lowflow alarmrelay (67AL1)

Received afalse low flowannunciationon panel 9-20for units'1 &~ 3

None Bad low flowalarm relaycoil.

Low flow alarminoperable.

Replaced relay, alarmsystem operated pro-perly. TRI't158585

3/8/81 Fire pro-tection

Smoke detector(XS-39-104AA)

Receivedflase alarmson panels25-325 and9-8.

!iNone! Increased sensi- Smoke detector actu-

tivity of smoke ated 3 false alarmsdetector. in a 6 hour period.

Replaced the smokedetector, performedSI4.11.C.1 & 5.TR8204709

~ ~

~ ~

~ ~ ~ I ~ ~ ~ I '~ ~ ~ ~

~ ~

I I ~ I I ~

~ I

~ ~

~ ~ ~ ~ ~ ~

~ I I ~ I ~ I I

~ ~ ~

~ ~ ~ ~

~ ~ ~

~ ~

~ ~

~ ~ '

~ ~ ~ ~ ~

~ ~ ~ ~ ~ ' ~ ~ I

I ~

~ ' I ~ tl ~

~ ~ ~ I

I ~ I

~ ~

~ I ~ ~

~ ~~ ~ ~ ~ ~ I

~ ~ ~ ~

CSSC EOUIPi'1ENT

BROMN

EKE

S FERRY NUCLEPJ; PL!>NT U?lXT

ECTRXCAL >lAXNTENr~CE SUlAlARY

For,'t he Honth,of Harch 19 81

System Component N,.ture ofllaintenance

EkredOpcl)

t on Sakeation of

ReactorCause of

HalfunctionResults of

Halfunction

chic t ion TakenTo Preclu"eR'currence

3/4/81 DieselGenerators

"HVST2 coil" EHX 3in D/G 3Bstart failurebackup circuit

None "llVST2 coil"found to be badduring redundantstart test.

This solenoid coilwas'ot deterioratedto the point of mak-ing the solenoidinoperable. The-coil did cause aspike on the oscillograph trace.

Replaced the bad coil,solenoid operatedproperly. TR//220503

3/8/81 . DieselGenerators

D/G 3A fueloil pressureannunciator

Received afalse fuel

oil'ressure

annunciation.

Nones Bad annunciatorcircuit card.

Received a falseannunciation.

Replaced the badcircuit card, annunci-ator operated properly.TRI'I204848 IV

3/10/81 Residualheat re-moval

FCV-3-74-74 FCV-74-74 feeder breakertripped aftervalve closedduring performance ofSX4.5.B.l.c

Unit in limitincondition foroperation(TS3.5.B.7)

Unknown RllR valve FCV74-74feeder breaker trip-ped after the valveclosed while per-forming SX4.5.B.1.C

The valve operatingcurrent was measuredand found to be accep-table. No loose con-nections were poundin the breaker'com-partment. The valvhas been cycled daily,through 3/18/81.

)

TR8204839LER8BFRO-50-296/8113

CSSC EOUIPINENT

rr

B 'Y tlJCLB/ P PLItt 0!rTT;30.:NS,,PER'Al - .

~ ELt:,CTRICAL tiAINTENANCE Sulau.RY

:il

I

3/13/83

System

Dieselgenerator

Component

3A D/Gannunciator

Nature of';taintenance

D/G alarmsinoperable

Etl Get, on SQreopera,'tion ofThe ,'coactor

None<

t3

Cause of>talfunction

Bad annunciatorcircuit card

Results ofNa 1 func tion

Annunciatorinoperable

Action TakenTo PrecludeR'currence

Replaced bad circuitcard, annunciator.operated properly.TRfI204821

3/13/8 Rad waste RHR pump room LA-77-25Cflood level would not

Mnnunciator testr t I n«nLA II IJL

None Loose connec-tion on annunciator cxrcuxL"Cnl

Annunciator inoper-able.

Corrected connection,annunciator operatedrorteiltr TR ($ 221 558

3/17/81 tlt Itltent Itt Vntl'3 71 /. /.«\rv& r& f'vnttrtA nnVt «r«ttt'Q vr ~

FCV-73-44"Inboarddischarge

IIval've

Valve motorlead "A2" wasgrounded attaped connectiorin limitorntteconnection com-partment.

Valve was placed inopen (operable) po-sition while theconlductor was r'G=

insulated.

Retaped the conductorperformed ENI 71, 18,and 18.1, valveOperated prOperly,TRf/2O5S09

>3/17/81

gener'atorsD/G 3C Received a

"control powerCC a nnJnVLL «I ~ I~ IU~ ~ t J.«t

tion

Nonet

Bad coil on NVR

relay and loose3558 annunciatocard.

Received a falsen ~ J A t j I«IIIIIUIIIJ«tl J.OII I ht«tt

the control powerwas off.

Replaced the baa.relay COil andt tight-ened the annunciatorcard, the annunciato

Ioperated properly.TR/~205434

'/17/81 480 Voltshutdownnnr,rer

Hotor genera-l.or t)a t 3DA

Received abeneLatoi ut ~

dervoltagealarm for noapparent rea-son.

None Bad annuncIatol.c«trd =

Received a falseundervoltage alarm.

Replaced the badannunciator card,

-annunciator checkedOK. TR//205410

CSSC EOIIIPHEHT

NNU!'NS'BNZaT NUCLNAZ PLANT UNIT

ELECTRICAL I~IAINTEN/ACE SmIIIARYII

JIL

II

DI

System Component Nature ofala'ntcnancc

IMtec!t on SateOpej'ation ofTh,i Iicactor

Cause of'.Inlfunc cion

Results ofNa 1 func t ion

Action TakenTo PrecludeR'currence

3/19/81 Diesel 38 D/GGenerators

Received aoverspeedannunciationon 38 D/G

None Bad annunciatorcard

Received a falseoverspeed annuncia-,tion.

Replaced bad annuncia-tor card, annunciatioitested and clearedproperly. TR8205511

I3/20/81I

I

Air-condi-tioning(I'oo1ing-heating)

38 control bay 38 control bayhiller chiller trippe

None.

K '

A

Oil bypass valveopen

Chiller tripped onlow oil pressure.

Closed oil bypassvalve and adjustedoil regulator valve,chiller operatedproperly. TR8220520

(I3/22/81 IIPCI Low level

switch ongland sealcondenser

Low levelswitch inoper-able.

None Level switch73-158 wassticking

Condensate pump con-trolled by LS73-158would not operateautomatically.

Freed the switch, thepump operated properl>TRPT205499

,,i..i II'. Ii i'ICAL Nu'<ItlTEYVICE SU<~i:IARY

;>«. >><<i~> r <

IKCllAi<

For tl>e .Hont.h of Narc'9 81

DATE SYS'1<;H COt IPO"<EHT ltATURE OF'lPAIttTEt<AIICE

EFFI:G'Ll Otl S>" rEOPERPjTIOiV OF

TiiE <REACTOR

C»USF O;t tALFNICTIOtI

RESUI.TS OF

>~«XLFUHCTIO<v<

ACTlOti T<".KE:I

TO Pi(ECI.UDEr<F CUIIREtICE

l! Fj»eiir<>toe t ioh

L

Iti V-26-95fi Broken Pin 1'fi Roll P|n Broken Frozen Valve Replaced )'insTP «KG<<512

5I((1s ~ ~ ),)/

I l.lie'iL siw:I.!..aci t s .>~a a use > A

CSSC ~l'.( UI.VII".NT >K(:IIAI'ICALIM.INTEV~QlCE SUI IlbhliY

For 'the Honth of .. Harch 19 81

D."i'l'. SYG TE! I

3-2-81 C RD

3-2-81 (:RI)

COHPO!KalT

H20 Header

H 0 Header2

NATURE OF

!-DXI!ITEIIAI!CE

Leakage

Leal:age

EFFI'.CT GN SP2'E

Opr.RATION01'II

E 'REAC1OR

'/A

N/A

CAUSE OF

IIALFUIICTION

Loose I'acking

I.oose Packing

RESUI;I'S OF

MAI,FU!!CTION

Leaking at StemPackin

leal:ing at StemPack:in~

~:C 110<1 IA.'r.hTO PRECI.UDE

RECI!RPJ HCE

Tighten PackinTR !220966

<Tighten PackingTI! ir'220967

2-.19-83 HI'CIRCIC

cCheck Valve „Check Va lveTest

N/A Unknown Unknown Perfor'med SI 3.2.7on Check

Valve'R

ff103787

3-4-81 RBCCM Surge Tank Float Hangs Unknown Bene Stem Mas Bindin Straighten StemTP ff220983

3-7-81

t

3-8-81

CRDr

CRD

SDV Drain 6Vent Valve

CRD 34-23

Frozen Valve

Morn Parts

N/A

N/A

Non-lubricatedValve Stem

Strainer Dirty

Non-lubricated Stem

Unknown

Lubricated ValveStemTR fi204516

Changed StrainerTR ~'220873

3-9-81 EF.CI" Fisher ControValve 50-51.-

Dirty Filter N/A Dirty Filter Unknown Replaced Filter ir6750-6751TR fi220845

3-14-8) EECM FCV 67-51 Change OutSt ainer

Filter StrainerDirt ~

Valve MillNot Close Installed New FilterTR Pc221554

3-13-8I Fut.l PoolCooling.'elium LeakDetectorValve 2BFPC Heat Exch.

Hook UpHeliumLeak

N/A Need to Hook UpI!elium Detectoi

Unknown Removed 1/2" Tubingand Hooked UpTesterTR 8216814

3-20-8. RBCCI I Surge Tank Level SwitchHeeds Adjust-ment

N/AH

Level Switch Outof Adjustment

Swatch Stic! s Adjusted Swit'chTR ff207824

CSSC I'.OUIPlI1'.NT

~'" ' " l ' ~

~ti? IEQUd; ICAL III'AI)ITEtI'AI11CE SUM'I'1RY

For 'the'onth of iIarch 19 81

DATIr'. S YS'1 A..t! CO'I"0" FNT IMMATURE OFI'~'A IllTE!tANCE

EFFECT ON SP "EOPERATIOl1 OF

TIIE",RFACTOR

CAUSF. OF

l I tlLFL"i)CTIOH

RESI)LTS OF

Nu<LFUNCTION

O'I Tl'~'.r".ltlic h

TO PRFCLUDEPZCURPZNCE

ttLI OJ

3-27-,81

I tt 1 01CI VJ

RBCCW

gECW

RBCCW

Dttrrt.tAU '4 \r ru

t A tn ttttttli I V CDSludge Tank

FCV-67-50

A D.W1 ~ AirCom ressor

I h-7A 7'Avh tv a u

'rt1 t ttt 4 t 4c JOdl D l Jctt Jllb

Valve Closed

Stopped UpLine

Wil 1 .Int ActIn On LowLevel

tl(A* ~

N)A

H')~ tg

ljl

1

1. 1 nn ~ C r I nl. w nnL JVQt V ~ k\ tlat ~ t)

Valve Was inClosed Pvs Jtlont

Blockage

BaII wires onLimit Switch

"Flo'at Not Sr ickinn

Stoppage

P lugged I.ine

Switch Will NotFunction

Backflushed FloatsTR:7187778

NoneTR Penn~ I t

BackflushedTR tll208404

Installed LimitSwitchTR !I208407

! 8( !:c'!'1p'.1 )KC)IJd 1.('AI )I.~T.'"P"JUDICE SU~ V~(Y

For thc Month of - )')arch 19 81

DATI'. 8'iS') r.) I CO"(PL~')~i')i011 Sr"'I

TION OFLACTO)t

ChliSE OF

) )ALEUII(.'TIONRHSUI:I'S OF

tP.I.FUNC')'ION

ACTIOII T:~HEI)

TO FRECLUDERECURRENCE

2-? 3-81

3-?-81

Fuel PoolCooling

I.PC IN(i Set

Pump 1)otor 3B

AX liG Set

Pump Out ofAlignment

Lubrication

N/A

H/A

Bent Shaf t &

Worn Par ts

Coupling NeededGreasin

Unkno~m

Unkn oem

Replaced Shaf t,Impel)or, Bearings,Sleeves, Wear Ringsand ItepackedTR 8136719

Greased CouplingTR I)182062

')-2-81 LPCIliG Set

3EA IIG Set Lubrication N/A Coupling NeededGreasin

Unknown Greased CouplingTR 8182082

3-3-81 D/C Air Coapressorl!l Leakage

~ ~ N/A Pilot UnloaderBad

Air Line Leak Repaired PilotValv'R

I/22 1503

3-11-81 CRD liodule 38-43 liechanicalProblem

, N/A Seal Problem Will Not Withdraw No Problem FoundWith Normal Pressure TR 8221559

3-11-81 RCIC 3-71-6A Stem Leak Loose PackingGland

Leakage Tighten PackingTR L!221526

3-11-81 CO> Storag& FireProtection

Cardox ValveA

Venting toAtmosphere

N/A Unknown Unknown NoneTR //220510

3-18-81. IIP CI 73-16 Leak„~

Loose Packing . Packing Leak Tigl>ten Packing.TR 8205407

3-17-81 )/PCI Turbine Exhaus Disc Blown N/A Ruptured Disk Blown Disc Replaced DiscTR 8205408

3-18-81 FireProtection

Valve3-26-1132

FlangeCracked

~ I N/A Unknown Unkno~m New FlangeTR 8199138

~ ~

~ ~

~ ~

~ ~ I

~ 4

~ ~

CSSC F UTPIF'IT

Bf(OIJNSi

5L<$

For tl

iiERRY: Ui;Li!AR Pl 'IIT Qil": )a.:

IANICAL IIAINTENANCE SUt'~fhRY

ie Honth of- ~ Harch 19 81

DATE SYS'ia.if COI IPO".1ENT llATURE OF

t IAIttTENANCE

EFFI'.CT GN SAFI?

OPE TION QF'l

'1"ifE: REACTOR

ChUSE OF

l IAI.FUIJCTION

RESVI.TS OF

IIALFUNCTION

AC'1'10:I TAKE:I

TO PIIECI.UDERECUIl"F"C".

2-28-8 EECIJ Strainer C3 Strainer Hal-Iunction

Gears Out ofAlignment

Gears Grinding l)isassembled and0

Turned Gear 180 .

TP, 1 204851

3-20-8'-14-8

FireProtection

RIIR

8" Strainer13asket

IUIRSIJ Pumps

DamagedStrainer

Unknown

"N/A ~

V/A

Unknown

Unl'nown

Strainer Damaged

Unknown

Complete perDCR P2473TRi'3182041

Performed !Cfl 29TR P 198828

3-14-8 EECIJ C3 EECIJ Pump Pump Not Mork-ing Up toRe uirements

1 J/A Coupling Out ofAdjustment

Pump Not HeetingSI Requirements

Adjusted Coupling toRead .048TR Prl99464

3-14-8 F.ECM D3 EECIJ Pump Pump Not IJork-ing Up toRe uirements

Unknown Not Pumping Itut4,000 gpm

Checked Coupling tOkay IIHI-29'fR 8199466

3-22-8 RIIR 3C RIIRSIJ Pump Low Flow /A Unknown Pump Not Pumping Iebuilt PumprR 8148095

3-16-8. I? ECIJ C Strainer lligh DP , '/A " 'nknown Unknown 'low Going Through; 6 D Strainer)ischargerR 8103793

CSSC E UIPffENT

SYSTEM

Unit ]

3-1O StandbyLiquidControl.

Standbv3-17I.iquidControl

n v « t««v' tI L LIIICILyLVContain-ment

Unit

3-3 RadiationHonitoring

StandbyLiquidrnnt rnlt

3-10 FeedwaterControl

3-16 Core Spray

3-12 emergencyf'qttinmentCoolingWater

3-1 7 Emornen('vEquipment(«e«t I « tt ~ ~

NATURE

OF

MAINTENANCECOMPONENT

TE-63-4 Replace

Ronl aceT.T-63-1 R

I'al ihrot oPT-f/. ( 1~ L Cl ~ Jk

Repair/Replace

CalibrateTS-63-4

FH-46-1A Replace

RepairFT-75-21

Dm ca 1DDCL Vl JCQPT-67-68

D 4 I/\ 1OC PClLL / IJCll. ~

P(f(I-67-R 11 onlnro c'tJi tr hoc

tt

BROWNS;

INSTRI

'ERRY NUCLEAR PLANT UNITf

fENT HAINTENANCE SAfffARY

HONTff OP Harch 19 81FOQ T1I

CAUSE

OF

1fALFUNCTION

N SAFE

ON OF

CTOR

EFFEC) 0RESULTS OF

HALPUNCTION

False IndicationShorted toGround

N ne

'I (

Non

t(

Nnn

Faulty Indicator Did Not Agree WithRedundant Indicator

Indicated False HighPressure

Tnst rttment Drift

I

N'aulty FlowControl Honitor

High'low Alarm

Palse Low AlarmSetpoint Driftne

Did Not Indicateteal - ow

Paulty CircuitCom(potient

ne

Faulty Amplifier False Indicationof Core Spray

ne

N

II

,

I

No

II

Tnrnrrert FlowIndication

6R 1fad RadAmplifier, 12BHad InstrumentDrift

~ AC

Paultv Switrhes Alarm 'ant(1�(f Nnt Cl onne

ACTION TAKENTO PRECLUDE

RECURRENCE

None

None

None

None

~ ~

None

None

None

None

Nnno

e as

37

OUTAGE SIR&QKY

MARCH 1981

Preparations continue for the upcoming unit 1 end-of-cycle 4 refueling/

torus modification outage presently scheduled to begin April 10, 1981 (duration

currently estimated't 104 days). Preparation work is also underway forthe'nit

2 outage required to accomplish ECN P0275 — unit station service transformer

modification. This unit 2 short outage is scheduled to begin. shortly after~

~

the start of the unit 1 cycle 4 outage and will .last approximately 23 days.

Significant work in progress at the end of the month includes:

1. ECN P0314 — This modification provides improved post accident

sampling facilities (PASF) for reactor liquid and atmospnere.

Preliminary work is in progress in preparation 'for this .modi-

fication to begin. The instrument mechanics shop in .the unit

3 turbine building has been relocated to allow access for the

PASF.

1C'd-P42'TB-=.Unit-station setnice-ttansdctaenatodidication*" r

Excavation work and installation of conduit and rebar's in

progress. Skid plate fabrication is complete for all 3 trans-

former pads.

3. ECN P0262 — Union Cordova 500kV line - This modification

installs new terminal facilities for a new 500kV transmission

line. Pork is complete on installation of the foundation for

the 500kV PCP and associated BUSS supports. Beginning ez-

cavation at switchyard. cable tunnels for conduit runs.

38

OUTAGE SlRMARY. (Continued)

Harch 1981

4.. ECN P0238 — Condensate Storage Tanks -~=Two additional 500,000

gallon storage tanks have been constructed as a result of thi4

modification. Conduit and cable runs 'fox,'alve and level controls

are approximately 80% complete. ~Inter~ior tank coatings have bee@

applied and .forced curie is in progress.

5. ECN P0027 - Unit 1 Spent Fuel Storage t'ool is 'under'going a setond

partial completion of the. high density fuel storage rackinstalla-'ions.

The original fuel storage racks have been removed and'ar'e

awaiting packaging for shipment as radwaste'. 'Six high density

fuel storage system modules (13 c 13 array each) have recently

been installed. These are in addition. to the '5 HDFSSmodules'nstalled

in August of 1979'ull core, unload capabilities. are'ow

available .for the outage.

&;—.SCN.=.F9078=.—..;Mechanid~a.-prefabr'xc:idion«worK''-is ini progress;.foi>t,e:

fire protection modification at thei pumpiintake structure.

7. ECN Ll!329/L1960 - Cooling tower modifications are in progress.

monthly operating repts for mar 1981. · refuelin information march 1981 unit 1 unit 1 is scheduled...

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