ML20141H323

Monthly Operating Repts for Jan 1986

ML20141H323
Person / Time
Site:	Browns Ferry
Issue date:	01/31/1986
From:	Robert Lewis, Thom T TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8604240297
Download: ML20141H323 (30)

Text

. - -. _ _ _.__

)

i E

TENNESSEE VALLEY AUTHORITY OFFICE OF NUCLEAR POWER BROWNS FERRY NUCLEAR PLANT I

A i

1 MONTHLY OPERATING REPORT TO NRC i

)

JANUARY 1, 1986 - JANUARY 31, 1986 1

f DOCKET IUMBERS 50-259, 50-260 AND 50-296 LICENSE MUMBERS DPR-33. DPR-52, AND DPR-68 Submitted by:

Am f) A I<

Plant Managdt-8604240297 860131 PDR ADOCK 05000259 R

PDR I, 1

CONTENTS I

Operations Susunary......................'......

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

3 Significant Operational Events......................

5 i

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

8 Operating Data Reports.........................

11 l

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

14 1

1

{

Plant Maintenance..

. 17 Addenda.

i 1

I I

I i

i

.I

.i I

d l

l I

i i

i 0053B

\\

1 i

l i,

1 I

b Operations Summary l

JANUARY 1986 I

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.

1 There were seven reportable occurrences and seven revisions to previous occurrences reported to NRC during the month of December.

Unit 1 The unit was in cold shutdown the entire month for the unit's end-of-cycle 6 refueling outage.

't Unit 2 The unit was in cold shutdown the entire month for the unit's end-of-cycle 5 refueling outage.

l l

Unit 3 The unit was in cold shutdown the entire month for the unit's end-of-cycle 6 refueling outage.

l This was prepared principally by B. L. Porter.

l i

1 0058B i

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

i*

j 3

Refuelini Information i

}

JANUARY 1986 1

i I

j Unit 1 i

j Unit I was in shutdown for its sixth refueling on June 1, 1985 with a i

scheduled restart date of March 1989. This refueling will involve loading I

I 8x8R (retrofit) fuel assemblies into the core, replacing recirculation piping, i

work on "A" and "B" low-pressure turbine, upgrade hangers and anchors, and 1

i environmentally qualify instrumentation. The unit was shut down on March 19, I

j 1985, and remained in cold shutdown 'intil June 1,1985, because of unfinished modifications to meet environmental concerns.

There are 0 assemblies in the reactor vessel. The spent fuel storage pool l

presently contains 764 EOC-6 assemblies. 252 EOC-5 asserblies, 260 EOC-4 1

assemblies, 232 EOC-3 assemblies, 156 EOC-2 assemblies, and 168 EOC-1 l

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

I l

Unit 2

[

Unit 2 was shut down for its fifth refueling outage on September 15, 1984, with a scheduled restart date of June 1, 1986. This refueling outage will i

l involve loading additional 8x8E (retrofit) assemblies into the core, finishing l

1 torus modification, turbine inspection, piping inspection. THI-2 modifications; postaccident sampling faellity tie-ins, core spray change-out, and feedwater sparger inspection.

l l

t i

)

i I.

I i

0058B r

1 -.

. ~ ~.

-,a.

~ - - ~

I

+,

1 Operations Summary JANUARY 1986 The following summary describes tl, significant operation activities during the reporting period.

In support of this summary, a chronological log of significant events is included in this report.

l j

There were seven reportable occurrences and seven revisions to previous i

occurrences reported to NRC during the month of December.

Unit 1 The unit was in cold shutdown the entire month for the unit's end-of-cycle 6 refueling outage.

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

1 Unit 3 The unit was in cold shutdown the entire month for the unit's end-of-cycle 6 I

refueling outage.

I l

i I

l This was prepared principally by B. L. Porter.

l 4

00588 l

4

-m

---. -~. - -

i 2

l Operations Summary (Continued) 1 j

JANUARY 1986

\\

l J

i l

Fatigue Usaae Evaluation l

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

Location Usaae Factor I

I Unit 1 Unit 2 Unit 3 Shell at water line 0.00s20 0.00492 0.00430 j

Feedwater nozzle 0.29782 0.21319 0.16133 i

i Closure studs 0.24204 0.17629 0.14326 I

)

NOTE: This accumulated monthly information satisfies Technical l

S?ecification Section 6.6.A.17.B(3) reporting requirements.

l Coasson Systes l

l Approximately 1.18E+06 gallons of waste ligulds were discharged containing

)

approximately 1.07E-01 curies of activities I

i 1

e i

J r

1 1

4 0058B j

l

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

. - _ =

i*

3 4

Refueling Information i

JANUARY 1986 I

j Unit 1_

Unit I was in shutdown for its sixth refueling on June 1, 1985 with a scheduled restart date of March 1989. This refueling will involve loading i

j 8x8R (retrofit) fuel assemblies into the core, replacing recirculation piping,

}

work on "A" and "B" low-pressure turbine, upgrade hangers and anchors, and I

i environmentally qualify instrumentation. The unit was shut down on March 19, j

1985, and remained in cold shutdown until June 1, 1985, becsuse of unfinished i

1 modifications to meet environmental concerns.

I l

There are 0 assemblies in the reactor vessel. The spent fuel storage pool l

j presently contains 764 EOC-6 assemblies 252 EOC-5 assemblies. 260 EOC-4 i

assemblies 232 EOC-3 assemblies, 156 EOC-2 assemblies, and 168 500-1 assemblies. The present fuel pool capacity is 3.471 locations.

Unit 2 Unit 2 was shut down for its fifth refueling outage or September 15, 1984, i

with a scheduled restart date of June 1, 1986. This refueling outage will Involve loading additional 8x8R (retrofit) assemblies into the core, finishing torus modification, turbine inspection, piping inspection. TNI-2 l

modifications; postaccident sampling facility tie-ins, core spray change-out, r

and feedwater sparger inspection.

j i

i

]

i 1

l l

l 00588 i

I 1

_.,-,,,,-_..-.,e.-.

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

. i 4

Refuelina Information JANUARY 1986 There are no assemblies in the reactor vessel. At month end, there were 277 new assemblies, 764 EOC-5 assemblies. 248 EOC-4 assemblies 352 EOC-3 i

assemblies, 156 EOC-2 assemblies, and 132 EOC-1 assentlies in the spent fuel storage pool. The present available capacity of the spent fuel pool is 77 locations. All old racks have been removed from the pool and new HDRs are j

being installed.

Unit 3 Unit 3 started its sixth refueling outage November 30, 1985, with a j

l l

scheduled restart date of March 1987. This refueling involves loading 8x8R (retrofit) assemblies into the core, and complete reinspection of stainless steel piping. The unit was shutdown on March 9, 1985, and remained in cold shutdown untti November 30, 1985, on an administrative hold to resolve various TVA and NRC concerns.

i There are 764 assemblies presently in the reactor vessel.

there are 248 EOC-5 assemblies, 280 EOC-4 assemblius, 124 EOC-3 assemblies, 144 EOC-2 assemblies, and 208 EOC-1 assemblies in the spent fuel storage pool. The present available capacity of the spent fuel pool is 914 locations.

00588

l*

5 Significant Operational Events l

l JANUARY 1986 Unit 1 i

01/01 0001 End-of-cycle 6 refuel outage continues 01/31 2400 End-of-cycle 6 refuel outage continues s

6 00588 1

i

- - ~ - - - - -

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

-e--.er,~~.,,-.n-,.,.,.

...---,-w--ave

_n,.

- - ~ ~

,w-------

~,

-mnr..w..

,,7

4~

6' Significant Operational Events JANUARY 1986 Unit 2 01/01 0001 End-of-cycle 5 refuel and modifications outage continues 01/31 2400 End-of-cycle 5 refuel and modifications outage continues Y

4 M

/

00588

7 Significant Operational Events JANUARY 1986 Unit 3 01/01 0001 Environmental Qualification Outage to comply with NRC requirements.

01/31 2400 Environmental Qualification Outage to comply with NRC requirements continues.

0058B

8 AVER AGE DAILY tJNiT POWER LEVEL DOCKET NO _50-259 UNIT 1

l DATE - 2/1/86 COMPLETED BY

_T.

Thom TELEPHONE 205/729-2509

/

4f0N11f January DAY AVER AGE D AIL Y POWER LEVEL DAY t lkr Neti AVER ACE D AILY POWER LEVEL

\\

IMWe-Net) g

-6 37

-7 2

-6

,s

_7 3

-6 19 4

-6

-7 20

-6' 5

-6 21

-6 6

-6 22

-6 7

-6 23

-6 s

-6 24

-6 9

-6 25

-6 to. _ -

-6 26

-6 II

-6 l

-6

-6 27 a-28 I3

'0

\\

y 4

1 l

I4

-6

-7 30 15

-7 l

31

-6 b

-7.

1 i

l

~

INS TRtlt110Ns On it.=Jormat.hst tr.c.c era te dash.u..t pi.wcr leulin MWe-Net for each day in the reposting m the re4im:

• hole negawatt.

o

. ompute to e

(9 /77 )

9 AVER AGE DAILY UNIT POhER LEVEL DOCKET NO. 50-260

{'

2 UNIT f

DATE 2/1/86 C041PLETED BY T. Thom TELEPHONE 205/729-2509 ht0NTrg _ January

' DAY AVERAGE DAILY POWER LEVEL

{

Igy.

IMN Neti AVER AGE D4ILY POWER LEVEL 1

-6 ggy, g g7

-5 2

--- f?-

IS

-5' 3

-5 19

-5 4

-6 20 5

-6

-6 21

-6 6

-6 22

-6 7

-6 23

-6 3

-6 24

-6 9

-6 25

-6 10

-6 26 16 II

-6 27

-6 1

-6 23

-6 13

-6 3

-6

-6 la

~

30 is

-6 31

-6 16

_-5 INS TR1 CT10NS On th.i.tormat.lat tne 4serdze duh und powu toelin MWe Nei for each day in the seporting m the c:ar~. whole nwgsw.sts.

. ompute to e

(9/77 n

- o-

10 AVER AGE D AILY UNIT POWER LEVEL DOCKET NO. 50-296 3

11 NIT DATE 2'11/86 T

COMPLETED BY _. Thom TELEMIONE 205/729-2509 MONT11 January DAY AVERAGE D AILY P WER LEVEL

^

DAY AVER AGE DAILY POWER LEVEL (MWe Net) 1

-5 17

-5 2

-5 13

-4 '

3

-s to

-5 4

-5 20

-4 5

-s a

-5 6

-4 22

-5 7

-5 23

-4 8

-5 24

-5 9

-5 25

-3 10

-4 26

-3 II

-5 27

-4

-4

)

12 3

-4 I

13 f-L -

^

29

-5 14

-5 15

-5

-5 30

-5 3

16

-1. _-

\\

INS TR11CT10NS On tbijormat.hs the.nera:e Jols uut pi. ace leselin MWe. Net for enh dayin the reporting m the neare,t whole nwgswaii.

o

. ompute to 19177)

11 OPERATING DATA REPORT DOCKET NO. 50-259 DATE 2/1/86 COMPLETED BY T. Thom TELEPHONE 7nsn90 ?509 OPERATING STATUS

1. Unit Name:

Browns Ferry One Not'5

2. Reporting Period:

January 1986

3. Licensed Thermal Power (MWt);

3293 1152

4. Nameplate Rating (Gross MWe):

5. Design Electrical Rating (Net MWe):

1065 1098.4

6. Maximum Dependable Capacity (Gross MWe): --

1065

]

7. Maximusn Dependable Capacity (Net MWe):

j l

S. If Changes Occur in Capacity Ratings (Items Number 3 Thmugh 7) Since Last Report, Give Reasons:

N/A

9. Puwer Level To which Restricted,if Any INet MWe):

N/A

10. Ressous For Restrictions. lf Any:

N/A This Month Yr. to.Date Cumulative 744 744 100.904

11. Hours in Reporting Period

12. Number Of Hours Reactor Was Critical 0

0 59.521.38 0

0 6.997.44

13. Reactor Reserve Shutdown Hours i

14. Hours Generator On.Line 0

0 58,267.26 0

0 0

15. Unit Reserve Shutdown Hours

16. Gross Thermal Energy Generated (MWH) 0 0

168,066,787 0

0 55,398,130

17. Gross Electrical Energy Generated (MWH)

-4,571

-4,571 53,75Z,435

18. Net Electrical Energy Generated (MWH) 0 0

57.7

19. Unit Service Factor 0

0 57.7.

20. Unit Availability Facto,

21. Unit Capacity Factor (Using MDC Net) 0 0

50.0 0

0 50.0

22. Unit Capacity Factor (Using DER Net)

23. Unit Forced Outage Rate 0

0 23.6

24. Shutdowns Scheduled Over Nest 6 Months (Type Date,and Duration of Each):

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

o /1 a /A6

26. Units in Test Status IPrior to Commercial Operation):

Forecast Achieved INITIA L CRi flCALITY INITIAL ELECTRICITY COMMERCI A L OPER ATION (4/77)

~

-g.

12 OPERATING DATA REPORT DOCKET NO. 50-260 DATE 2/1/86!

COMPLETED BY T.

Thom TELEPHONE 7ns/79o-7509 OPERATING STATUS

1. Unit Name:

Browns Ferry Two N08'5

2. Reporting Period:

January 1986

3. Licenwd Thermal Power (MW:): 1291

4. Nameplate Rating (Gross MWe):

1152 1065

5. Design Electrical Rating (Net MWe):

1098.4

6. Masimum Dependable Capacity IGross MWe):

1065

7. Maximwn Dependable Capacity (Net MWe):

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

N/A (Net MWe):

N/A

9. Power Level To which Restricted,if Any/A N

10. Reawns For Restrictions. If Any:

1

]

This Month Yr..to.Date Cumulative 744 744 95,791 i1. Hours in Reporting Period 0

0 55,860.03

12. Number Of Hours Reactor Was Critical

13. Reactor Reserve Shutdown Hours 0

0 14.200.44

14. Hours Generator On.Line 0

0 54,338.36

15. Unit Rewrve Shutdown Hours 0

0 0

16. Gross Thermal Energy Generated (MWH) 0 0

153,245,167

17. Gross Electrical Energy Generated (MWH) 0 0

50,771,798

18. Net Electrical Energy Generated (MWH)

-4,234

-4,284 49,261,080 0

0 30.7

19. Unit Service Factor

20. Unit Avadability Factor 0

0 56.7 0

0 48.3

21. Unit Capacity Factor (Using MDC Net)

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

48.3

23. Unit Forced Outage Rate 0

0 23.0

24. Shutdowns Scheduled Over Next 6 Months (Type. Date.and Duration of Each):

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

June 1986 5

26. Units in Test Status IPrior to Commercial Operation):

Forecast Acheved INITIA L CRITICALITY INITI A L ELECTRICITY COMMERCI A L OPER ATION 19/77)

J.

13 f

OPERATING DATA REPORT l

50-296 DOCKET NO.

DATE 2/1/86 COMPLETED BY T.

Thnm TELEPHONE 205/729-2509 OPERATING STATUS

1. Unit Name:

Browns Ferry Three Notes

2. Reporting Period: January 1986

3. Licensed Thermal Power (M%t):

3293

4. Namepiste Rating (Gross MWe):

5. Design Electrical Rating (Net MWe):

1065

6. Maximum Dependable Capacity (Gross MWe):

1 8.4

7. Maximum Dependable Capacity (Net MWe):

8. If Changes Occurin Capacity Ratings (items Number 3 Threugh 7)Since Last Report.Give Reasons:

N/A N/A

9. Power Lesel To Which Restricted,if Agv Net MWe):

10. Reasons For Restrictions,if Any:

This Month Yr.-to.Date Cumulative

11. Hours la Reporting Period 744 744 78.216

12. Number Of Hours Reactor Was Critical 0

0

_45.306.08

13. Reactor Rese.ve Shutdown Hours 0

0 5,149.55

14. Hours Generator On-Line 0

0 44,194.76

15. Unit Reserve Shutdown Hours 0

0 0

16. Gross Thermal Energy Generated (MWH) 0 0

131,868,267

17. Gross Electrical Energy Generated (MWH) 0

18. Net Electrical Energy Generated iMWH)

-3,236 0

43,473,760

-3,326 42,130,537

19. Unit Service Factor 0

0 56.5

20. Unit Availability Factor 0

0 56.5

21. Unit Capacity Factor (Using MDC Net) 0 0

50.6

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

50.6

23. Unit Forced Outage Rate 0

0 26.4

24. Shutdowns Scheduled Over Next 6 Months (Type. Date,and Duration of Eacht:

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

March 1987

26. Units in Test Status IPrior to Commercial Operation):

Forecast Achieved INITIAL CRITICALITY INITI AL ELECTRICITY COMMERCIAL OPER ATION (4/77) l t

50-259 UNIT SituTDOWNS AND POWER REDUCDONS DOCKET NO.

UNIT NAME Browns Ferry 1 DATE 2/1/86 COMPLETED BY T.

Thnm RI: PORT MONTil Innunry TELEPHONE

?ns1790 75no jg 3

k7 Licensee gg h

Cause & Currective No.

Date g

3=

4 ijE Event g7 g'?

Action to j

5 Ji g =

Report

• v) U Prevent Recurrence H

o s.

u 315 1/1/86 S

744 C

2 End of 6ycle-6 refuel outage (Cont) continues.

5 o

1 2

3 4

F: Forced Reason:

Method:

Exhibst G -Instructions S: Scheduled A Equipment Failure (Explam) 1-Manual for Preparation of Data B-Maintenance of Test 2-Manual Scra m.

Entry Sheets for Licensee C-RcIueling 3-Automatic Scram.

Event Report (LLR6 Fde(NUREG.

D-Regulator) Restrictson 4-01her ( Explain) 01611 E-Operator Trairnng & litense I samination F Administrati.e 5

G-Operational I t ror i E xplain )

Estubit 1 - Same Son ce 19/77) ll-Othes ( E xplain i 8

50-260 1

UNIT SilHTDOWNS AND POWER REDUCMONS DOCKET NO.

UNIT NAME Browns Ferry 2 DALE 2/1/86 COMPLETED BY T.

Th nin REPORT MONT11.Tann nrv TELEPHONE ?ns/77o_?sno c

3E "h

jY5 Licensee p,

{".

Cause & Corrective L.

Dale.

c_

gg g

jgy Event 39 p

Action to H,

fE 5

g' Present Recurrence

~@j Report a mV u

.5 305 1/1/86 S

744 C

4 EOC-5 Refuel Outage (Cont)

(Controlled shutdown 9/15/84) x 4

1 2

3 4

F: Forted Reason:

Method:

Exhibit G - Instnictions S Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B Maintenance ci Test 2 Manual Scram.

Entry Sheets for Lkensee

. J 4cfuehng 3 Autonutie Scram.

Eveni Repori t1.1 R1 File tNURIL D-Regulatory Restriction 4-Other (E xplain) 0161)

E Operator Training & 1.icense Examination F Adnunistrati.e 5

Goperational I.rror i Explain)

Esinbii 1 Saine Source 19/77)

Hother iE welain s

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-296 UNIT NAME Browns Ferry 3 DATE 2 /1/R6 COMPLETED BY T-Thr=

REPORT MONDI January TELEPHONE 205/729-2509

-e "i

5"o Cause & Curreceive ei 3

.=2 _e g

7 s4 Eicensec 5 t, g

Date k

3y 4

255 Event

??

El Action to

$5 5

5 i,i *!

Report "

SC 5'

Prevent Recurrence e

v d

157 1/1/86 S

744 H

Environmental qualification outage to comply with NRC requirements.

E I-Il' I

2 3

4 F Forced Reason:

Method:

Exhibit G -Instructions S: Scheduled A Equipment Failure (Explain) 1 Manual for Preparation of Data B Maintenance of Test 2-Manual Scram.

Ents) Sheets for Licensee C-Refueling 3 Auf omatec Scram.

Event Report (El.'R n Fde (NtlREG-D-Regulatory Restriction 4-Other ( E xplain) 0161i E-Operator Training A Lnense Examination F Administrative 5

G-Operational Erros (Explain)

Exhibii ! Same Source (9/77)

Il-Ot her (E xplain)

)

0

~

BROWNS FERRY NUCLEAR PIANI UNIT CSSC EQUIPMENT MECHANICAL MAINTENANCE

SUMMARY

For the Month of January 19 86 l

EFFECT ON SAFE ACTION TAKEN.

IRTE SYSTEM COMPONENT NATURE OF OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE MAINTENANCE T!!E REACTOR MALFUNCTION HALFUNCTION RECURRENCE l-17 90 Bl Stack Replace dis-None Oil blockage Inaccurate guage Replace discharge e

pressure guage l

, Sample Pump charge pressur.

guage. Cali-brate the guag. t (0-30 PSI) 1-17 90 B1 & B2 Stack Install tubing None TACF changed None N/A Gas Sample Pump per original original configuration design to clos y

TACF #

0-85-32-90 a

G i

4 i

O e

1 ;ekil! L1 I

l

!tE 1p l'3*'

l,'

j I's lk I

o NO d

N EE KDE AUC TLN CE NER 4

ORR IPU T

C COE ATR FN OOI ST TC LN UU SF EL RA M

6 R

I YR 9

_ T A 1 N

_ I M FO N M OI U U T

S EC T

v SN r

UU E

1 1A C a

AF u

CL I N P A n

A N

a N

J R E A T E N L I f C A o

_. U N E

N h

FF L

t AOR Y A n

S O

R C o NT R I M NOC E N OIA F A e TE H h TAR S C t

CR N E EEE W M r FPH

_.. R F

E O

o FOT

_. B EC FN OAN EE RT UN TI AA NM T~

N E

N O

P M

O

.T C

N EM PIUQ M

E E

E

~

T N

C S

O S

Y N

S S

C

~

ET A

I j

jl

-.i 1

1J i1

.iI

,j

b:.[

1,.31 ('j (.

i j 4,.

lft:it4, 5j-I.

8k., 7}

d f e ftn 5

t n ue N

os EE s

KDE h a AUC se TLN ar CE r

NER td ORR n

IPU d a T

C e

COE ne AIR av el l a Cv FN OOI ST TC e

LN n

UU o

SF N

EL RAM u

2 YR 9 e

T A 1 N

v I M FO l

N M OI a

U U T

v S

EC T

SN n

N E y

UU i

A C r

AJ I

N n

CI h

F A i

A s

N m

M a

R E n

r

_ A T J

T E N L I f C A o U M E

l h

FF l

L t

AOR

._ Y A n S

O R C o NT R I M NOC e

_ E N OIA n

_ F A e TE o

H h TAR N

S C t

CR N E EEE W M r FPH O

o FOT R

F E

B E

C n

FN so OA wi N

ot e EE hib s

RT ss UN odd TI e pl e AA v-us NM l d oo aihl V msc T

1 N

5 E

N 7

O 6

P M

V O

C T

C F

N 2

EM P

IU O

M 7

E E

6

_ ~

T C

S S

Y S

S C

~

6 E

1 TA l

D l

i i

i!1i

.4 ii i i 1

11 )

j l

I l

l s

t t

9 e

lo k l s

b a

g e

9 N

g O

EE d

n KDE a

a AUC e

l TLN h

f CE NER d

d ORR e

e G

IPU c

n T

C a

e COE l

t ATR p

h e

g R

i T

FN OO I

ST TC E

LN N

UU O

SF N

EL RAM u

3 YR 9 T A 1 N

I M FO N N OI t

U U T

o S

EC n

T y

SN E

r UU e

IIA C n

AF gt I

N u

CL nh P A n

A ag N

a M

l i R E J

Ft

_ A T E N

_. L I f

._ C A o U M E

N h

FF L

t AOR Y A n S

O R C o NT E

R I M NOC N

e E N OIA O

F A e TE N

H h TAR S C t

CR N E EEE W M r FPH O

o FOT R

F E

e B

r i

f t i E

es eo C

k s n

s FN se i mr OA ar2 r l aea N

gp o

et EE f s l rl t RT eh s

iti a.

UN c gf e osf e

TI aior sg AA lh p

l nlk n NM p

d m eweaa enno uouel R oec Fdflf C -

E a 3 r e

T e

n N

mnn i

E ooe l

N c

g r

l O

e P

rol i

i se o

M O

Ass eer l

T C

2 rio e

N

1. pd C u

E F

M P

IU O

M E

E

~

T 6

2 C

S 8

8 S

Y S

S C

3 4

E 2

2 T

/

/

R 2

2 I

1 1

O

I ji i

• l i

BROWNS FERRY NUCLEAR PLANT UNIT 0

BF ISIL 30 CSSC EQUIPMENT ELECTRICAL MAINTENANCE SQtMARY 9/29/82 For the Month of January 19 86 Effect on Safe Action Taken Nature of Operation of Cause.of Results of To Preclude Data System Component Maintenance The Reactor Malfunction Malfunction Recurrence D85/86 1/8/85 Air Spreader rm Pull motor, None Motor grounded Fan will run for Corrected ground condition-exh fan B motoi clear ground, approx 1 hr*before ing 0-FAN-31-0092 reinstall, &

tripping MR 588681 check rotation i/15/86 CO2 storag.

Batteries-Replace batterie s None Unknown Loss of fire protec-Replace batteries fire pro-fire prot pn1 tion troubleshooting tection &

0-25-296 MR 640662 purging 0-pnl-39

• system' 296 U

1/16/86 CO2 storag.

Detector 39-Check & correct None Bad detector Trouble alarm coming Replaced detector.

fire pro-20CE pn1 25-ann " Trouble" on causing trouble in due to bad detecto r. 39-20CE'with new tection &

324 pn1 25-324 for alarm to come in causing false alarm one purging 0-XS-39-20CE spreader rm B system 1/18/86 RHR service RHRSW C2 Replace station-None

' Contact broken Arcing of contact Replace stationary water bkr ary arcing contacts 0-BKR-23-12 contacts on A-B-C phase MR 632200 o

e i

~~~~ ~

~

s BI:Ote:S FERRY NUCI. EAR PLANT UNIT I

1SIL 30

^PP CSSC EQUIPMENT ELECTRICAL MAINTENANCE SLYMARY 9/29/82 For the Month of January 19 86

}

Effect on Safe Action Taken Nature of Operation of Cause.of Results of To Preclude fDate System Component Maintenance The Reactor Malfunction Malfunction Recurrence

)985/86 L1/21/8S RB heatin>

Cable tray Repair cable None NA None found while Repair per MMI-75 g

& ventila-penetration tray penetra-performing pI4.11.E.3 MR 569365 tion Al-P tion Al-P in 1-Pene-64-Al-5 accordance

't with MMI-75

• 12/11/8D RB heatin>

Fire stop Repair seal on None NA None found while Repair per MMI-75

& ventila-penetration pal 9-22 in performing

[

tion C23-P control rm for SI 4.11.E.3 MR 640497

'i 1-Pene-64-C23F fire stop

[

penetration

m.,

12/11/8' RB heating Fire stop Replace cera-None

.NA None found while Repair per MMI-75'

& ventila-penetration fiber & mari-performing SI4.11.E.3 I

tion C-22P nite pal 9-22 MR 640496 l

1-ENE-64-C22P in control rm for fi.re stop j

penetration i

,1/27/86 CO2 storage Smoke detectoi Replace smoke None Went bad None found while Replaced on i

fire pro-1-XS-39-69XB detector performing SI4.11.C.

MR 569990 tection &

165 purging l

sys i

l 1/29/86 High pres-Smoke detectoi Replace smoke None Went bad None found while Replaced on sure fire XS-39-91-BB detector performing SI 4.11.C. MR 631920 protection 1-XS-26-3991 165 system 3

l

)

' {."D BPOWNS FERRY NUCLEAR PLANT UNIT 2

g IL 30 CSSC EQUIPMENT ELECTRICAL MAINTENANCE

SUMMARY

PE "

9/29/82 For the Month of January 19 86 Effect on Safe Action Taken Nature of Operation of Cause.of Results of To Preclude

Dato System Component Maintenance The Reactor Malfunction Malfunction Recurrence 5585/86 V4/85 CO2 storage Fire alarm Replace bell or None Bell plunger Bell not wo,rking Freed bell plunger fire pro-

. bell repair hanging but showed alarm in tection &

2-Pnl-39 control room MR 572659 gugging 311

D/ll/8'i Residual Indicating Troubleshoot None No jumper per dwp Green light not Installed strap

~

heat light to HCV-74-91 on from GC82 to CC8:

illuminating properly (jumper) removal limit switch' indicating in panel 9-3 2-HCV-74-0091 light MR 591427 11/23/8:. Radwaste Micro-switch Troubleshoot-Non'e Sticking plunger Green light not Lubricated plungers $

system on limit FCV-77-2A found during illuminating properly switch indicating running MR 590967 2-FCV-77-2A light SI 4.7.D.l.b.1

,l/3/86 Emerg equit FSV-67-51 Troubleshoot None Bad switch on Not operating Switch changed out cooling 2-FSV-67-51 switch (SMB)

FSV 2-73-36 properly water M 569977.

1/12/86 High-pres-FCV-2-73-36 Crank valve None Greasy stabs &

Valve appeared to be Cleaned & adjusted sure cool-off seat to recept spread stuck breaker finders ant injec-

' free wedge apart, no contact tion.

being made MR 631817

'!/18/86 Reactor FCV-70-1 red Troubleshoot None Bad limit switch NA Changed bad limit b1dg closet limit switch the red side switch cooling 2-FCV-70-1 limit switch water Mn 635610 I

i h

F

m.

l "h",h43IL30 BR0te:S FERRY NUCLEAR PLANT UNIT 3

g CSSC EQUIPMENT ELECTRICAL MAINTENANCE SODtARY 9/29/82 For the Month of January 19 86 Effect on Safe Action Taken Nature of Operation of Cause.of Results of To Preclude Data System Component Maintenance The Reactor Halfunction Halfunction Recurrence

[985/86 480V uhtd K. watt meter Remove meter None NA Uut 01 calibration Keplace DaG meter li/12/8: bds 3-BKR-231-3B11C for calibration MR 552760 u!/10/8f RB heatin) Annunciation No audible on None Annunciator No audible alarm Replace 4,000 card

& ventila-for drywell annunciation card MR 590566 tion pressure pn1 9-5 abnormal 3-PA-64-56 h2/30/8! Annuncia-Ann pn1 9-6 Not working None NA Not working properly Replace cards as, tor &-

3-XA-55-6C properly necessary sequential events recorder L/2/86 CO2 stor-Fire protection Replace blown None Bad reset switch Loss of fire Bad rectifier on age fire pn1 3-25-32-4 fuse & determin e protection printed circuit protectior 3-PNLA-39 caus IIR 581287

& purging 324 3/4/86 High-pres-Inspect switch Corrective None Abusive treatment Non-operable Repair switch sure far damage action on coolant 3-HS-73-10B damaged switch MR 170548 injection 1/7/86 CO2 storage Smoke detector Replace bad None Unknown Bad detector Replace bad detector fire pro-X5-39-88XA sensor MR 631804 tection &

purging 1/15/86 Emerg core DC bkr DC bkr will None Bad breaker Replace breaker Replaced on cbol analo) 3-INV-256-A not reset MR 631212 trip unit inverters I

G e

e

{ Ih!SIL 30 Ill 0NNS FERRY NUCLEAR PLAN'T UNIT q

CSSC EQUIPMENT ELECTRICAL MAINTENANCE SL12tARY

^EE "

9/29/82 For the Month of.lanuary 19 86 Effect on Safe Action Taken Nature of Operation of Cause.of Results of To Preclude

, I-D r t e System Component Maintenance The Reactor Malfunction Malfunction Recurrence

?

1986

$/18 Ventilatica Exhaust fan Fails to start None Bad motor bear-Bearings locked up Replace bearings A motor in hand or auto ings due to

]

3-IIS-30-246 position moisture MR 631271 1 /20/86 4kV shut-3EA, 3EB, 3EC Check proper None Mis-labeling -

Vendor dwg showed Corrected labeling down bd &

freq & volt-wiring human error meters labeled busses meter wrong MR 631271 g.

3-BDAA-211-j 3EA, 3EB, 3EC lI/20/86 4kV shut-3EC freq & VM Check proper

• None

. Mis-labeling -

Vendor dwg showed Corrected labeling down bd &

3-BDAA-211-3E(

wiring human error meters labeled wrong busses MR 631267 w

i I

I i

l t

4 I

4 t

e 0

• Revision UNIT SilUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-296 UNIT NAME Three DAR 1/1186 COMPLETED BY T.

rw REPORT MONTil December TELEPHONE 205 6

_E E

jg j yi Licensec

,E g

{%

Cause & Correct ne Daie g

3E 4

.2 s 5 Even:

3,7 g?

Action u f*

s j ;ji Report a mV g'

Preveni Recurrence H

d 157 12/1/85 S

744 H

Environmental qualiffcation outage to comply with NRC requirements.

1 2

3 4

F: Forced Reason:

Method:

Exhibit G -Instrucci.ms S: Scheduled A Equipment Failure (Explain)

! Manual for Preparation of Data B. Maintenance of Test 2 Manual Scram.

Entry Shecis for Licensee C-Refueling 9 Automatic Scram.

Esen Report (1.E R n File INURI G-D-Regulatory Restriction 4 Other (Explain) 0161)

E Operator Training & License Examination F-Adnunist rative 5

G Operational Error (Explain t Eshibit I Same Somte 1y77) 11 Other (Explain)

4 Significant Operational Events DECEMBER 1985 Unit 3 12/01 0001 Unit began Environmental Qualification Outage to comply (thNRCrequirements.

12/31 2400 Environmental Qualification Outage continues.

i Revision l

.I u

1 J

l i

0058B r

e

,-w--...

l TENNESSEE VALLEY AUTHORITY Browns Ferry Nuclear Plant Post Office Box 2000 Decatur, Alabama 35602 i

FEB 2 61986 1

Nuclear Regulatory Conunission Office of Management Information and Program Control Washington, D.C.

20555 Gentlemen:

Enclosed is the January 1986 Monthly Operating Report to NRC for Browns Ferry Nuclear Plant units 1, 2, and 3.

l Very truly yours, TENNESSEE VALLEY AUTHORITY

/Ltf a

Robert L. Lewi Plant Manager I

Enclosure ec: Director, Region II INPO Records Center Nuclear Regulatory Comaission Institute of Nuclear Power Office of Inspection and Enforcement Suite 1500 101 Marietta Street 1100 Circle 75 Parkway Atlanta, Georgia 30303 (1 copy)

Atlanta, Georgia 30389 i

Directer, Office of Inspection l

t and Enforcement Nuclear Regulatory Connaission Washington, D.C.

20555 (10 copies)

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

P. O. Box 10412 Palo Alto, California 94304

[!s I

An Equal Opportunity Employer

..,.