ML20076H222

Monthly Operating Repts for Apr 1983

ML20076H222
Person / Time
Site:	Browns Ferry
Issue date:	05/01/1983
From:	Coffey J, Thom T TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF MANAGEMENT AND PROGRAM ANALYSIS (MPA)
References
NUDOCS 8306160482
Download: ML20076H222 (39)

Text

'

ut a

f

~

e N _

(,.,

<l \\ T 4

e s

c q.-

.s s

s s

g Fg_

,I

,s 1

s q

s*

'~

N' -

x.

'y i

i..

- TENNESLEE VALLEY A,UTHORITY r

.x

'* s q_

DIVISION OF NUCLEA_R POWER t.

y BROWNS FERRY NUCLEAR PLANT xn e.

. ~,

9

(

t 1

4 i s MONTHLY OPERATING REPORT April 1, 1983 - April 30, 1983

..-.s.

h Y

'*k t

- r,.

DOC.KET NUMBERS 50-259, 50-260, AND 50-296 s

4

~.

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

\\

3 L.

i.-

,i s

s s

Submittid by:

k.' N.

$ ant Sup'e/ipendent

~~

l'

/

3;,

..\\g\\n q

C306160482 830501

~~

v ny':

PDR ADOCK;05000259

,L

-}

N 1m.

t

.PDR x.

P,

'.'.,.,R w..~.

. +.

3

., $p,

.,~

p

's y.:..

n

. :.n ej' * '::

S"

.s

, J ':?.'y..

j$n R 9 Mi W >?.% C1~1 Hse J=& v

~.d e 94

• - _ i *u + 1n

- - -. h:,w.ks) ll '

. O:$,^)Qfb Q b % l l <> f h.f h _ [r l h5.ll Ll ~

..?'a$1Qj((TN>$$ ^1'~ff$' ~&~

' ?k-l ay u

_j n.

TABLE OF CONTENTS Operations Summary...

1 Refueling Information 3

Significant Operational Instructions.

5 Average Daily Unit Power Level.

13 Operating Data Reports.

16 Unit Shutdowns and Power Reductions.

19 Plant Maintanance.

22 Field Services Simnury.

31 4

.c e

_.i*FM t

5 Y

l' I

1 is9tss' ;w:w: ss' m-;g:2, n,.n m

e+

.z:r J,.

. y.. :.

~

~;r q

a.c

,.7",

4

-- u -

w-w.

e:

n

1 Operations Summary April 1983 The following summary describes the significant operation activities during the reporting period.

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

There were 17 reportable occurrences and two revisions to previous reportable occurrences reported to the NRC during the month of April.

Unit 1 There were no scrams on the unit during the month.

On April 15, the unit was shutdown via a controlled shutdown to start the unit's end-of-cycle 5 refueling outage.

Unit 2 There were no scrams on the unit during the month.

Unit ~4 There was one scram on the unit during the month.

On April 21, the reactor scrammed from a full MSIV isolation when a spurious isolation signal was received on one channel while the other channel was tripped for a surveil-lance test.

..s s

Principally prepared by B. R. McPherson.

f-

-., q'

• s," p.,, m' E.q' -- S n,1 ;m y.

.x f-M' e

~

- e m -

......_1

_4

t. u

_m

2 i

Ooerations Su--ry (Continued)

April 1983 Fatinue Usane Evaluation The cumulative usage factors for the reactor vessel are as follows:

Location Usane Factor Unit 1

, Unit 2 Unit 9 Shell at water line 0.00583 0.00460 0.00395 Feedwater nozzle 0.28294 0.19685 0.14986 Closure studs 0.22349 0.16702 0.12771 NOTE:

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

4 Common System Approximately 5.47E+05 gallons of waste liquids were discharged containing approximately 1.01E+00 curies of activities.

.~

e

'~

1

, whew g... -. -

,7. 7

.. y..

.a 3

Ooerations Sum==ry (Continued)

April 1983 Refueline Information Unit 1 Unit 1 began its fifth refueling outage on April 16, 1983 The scheduled restart date is October 7,1983 This refueling will involve loading 8 X 8 R (retrofit) fuel assemblies into the core; finishing the torus modification; turbine inspection; finishing THI-2 modifications; post-accident sampling facility tie-ins; core spray changeout; and changeout of jet pump hold-down beams.

There are 183 fuel assemblies in the reactor vessel.

The spent fuel storage pool presently contains 216 new fuel assemblies, 581 E00-5 fuel assemblies, 260 EOC-4 fuel assemblies; 232 EOC-3 fuel assemblies; 156 E00-2 fuel assemblies; and 168 EOC-1 fuel assemblies.

The present capacity is 1,148 locations. Modification work and testing are in progress to increase the spent fuel pool capacity to 3,471 assemblies.

Unit 2 Unit 2 is scheduled for its fif th refueling beginning on or about June 8, 1984 with a scheduled restart date of November 8, 1984.

This refueling outage will involve loading additional 8 X 8 R (retrofit) fuel i

assemblies into the core, finishing the torus modification, turbine inspection, finishing TMI-2 modifications; post-accident sampling facility tie-ins, core spray change-out, and feedwater sparger inspection.

There are 764 fuel assemblies in the reactor vessel.

At the end of the month there were 248 EOC-4 fuel assemblies, 353 E0C-3 fuel assemblies, 156 E0C-2 fuel assemblies; and 132 EOC-1 fuel assemblies in the spent fuel storage pool.

The present available capacity of the spent fuel pool is 861 1

4 5mre.,:1***tiO***

2

,,;.c, g;m. f ;..jp ^

g--

_7__

.g q

Operations Stimmarv (Continued)

April 1983 Unit ~4 Unit 3 is scheduled for its fif th refueling on or about October 11, 1983, with a scheduled restart date of May 4, 1984.

This refueling will involve loading 8 X 8 R (retrofit) assemblies into the core, finishing the torus modifications, post-accident sampling facility tie-in, core spray change-out, finishing TMI-2 modifications, turbine inspection, and change-out of jet pump hold-down beams.

There are 764 fuel assemblies presently in the reactor vessel.

There are 280 EOC-4 fuel assemblies, 124 EOC-3 fuel assemblies, 144 EOC-2 fuel assemblies, and 208 EOC-1 fuel assemblies in the spent fuel storage pool.

The present available capacity of the spent fuel pool is 993 locations.

e d

9

4. i f_

I

"' ^ *

>3.r,6 > < >n 2

5 Sinnificant Ooerational Event Udt1 Date Time Event 4/01 0001 Reactor thermal power at 855, maximum flow, end-of-cycle 5 coastdown.

4/13 2205 Commenced reducing thermal power for control rod testing.

2317

. Reactor thermal power at b.2% for control rod testing.

4/14 0653 Control rod testing complete, commenced power ascension.

0825 Reactor thermal power at 845 maximum flow, end-of-cycle 5 coastdown.

4/15 2200 Commenced reducing thermal power from 815, for a con-trolled shutdown for end-of-cycle 5 refuel outage.

4/16 0125 Manually tripped turbine from 175 power.

Unit offline, end-of-cycle 5 refuel outage begins.

0420 All rods at 00, controlled shutdown complete.

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

r l

i i

l

=w l

l

[

l l

,'(t w'.

g'

,9 u 4c,

9 w.

1.

m

u.. n.

.4

6 Significant Operational Event i

~

Udt2 Date Time Event 4/01 0001 Unit shutdown for maintenance on main turbine and "B"

reactor feedwater pump.

1145 Commenced rod withdrawal for startup.

1347 Reactor Critical No. 150.

4/02 0511 Rolled turbine generator.

0514 Tripped turbine at 100 rpm.

0518 Rolled turbino generator.

0550 Synchronized generator, commenced power ascension.

4/03 0305 Reduced thermal power from 71% to 68% for control rod pattern adjustment.

0400 Rod pattern adjusted, commenced PCIOMR from 68% thermal power.

1002 Reducing thermal power from 73% due to an EHC leak at No. 2 control valve servo valve ("0" ring leaking).

1200 Reactor power at 71% for maintenance on oil leak on No.

2 control valve servo valve.

1230 Maintenance complete on No. 2 control valve servo valve. Reducing thermal power to place "B" reactor feedwater pump in service.

1400 Reactor thermal power at 70%, holding to place "B" reactor feedwater pump in service.

1452 "B" reactor feedwater pump in service, increased reactor power to 73%, commenced PCIOMR.

4/04 1725 PCIOMR completed, reactor power at 895, maximum flow, red limited.

Began 12-hour fuel soak.

2300 Reactor power at 88%, maximum flow rod limited,12-hour fuel soak in progress.

4/05 0525 Reactor power at 87%, maximum flow, rod limited, 12-hour fuel sor.k complete.

1500 Reactor thermal power at 86%, maximum flow, rod limited.

2240 Commenced reducing thermal power for control rod pattern adjustment.

2315 Reactor power at 62% for control rod pattern adjustment.

2400 Control rod pattern adjustment in progress, reducing thermal power.

4/06 0200 Reacter thermal power at 60%, control rod pattern adjustment in progress.

0230 control rod pattern adjustment complete, commenced power ascension.

0400 Commenced PCIOMR from 64% thermal power.

4msp+w mp we ;

'g,,* Epgi_ y ',,

' c i.4 s

s

--n u - - -

7 Significant Operational Event Udt2 Date Time Event 4/07 0800 Reactor thermal power at 94%, maximwn flow, rod limited.

1500 Reactor thermal power at 925, maximum flow, rod limited.

2300 Reactor thermal power at 915, maxinum flow, rod litited.

4/08 0700 Reactor thermal power at 90%, maximum flow, rod limited.

2145 Commenced reducing thermal power from 90% for turbine control valve test.

2400 Reactor thermal power at 68% for turbine control valve test.

4/09 0025 Turbine control valve test cocplete, holding for SI 4.1. A-15 (Turbine Stop Valve Closure).

0105 SI 4.1. A-15 complete, holding at 68% for SI 4.1. A.11 (HSIV Closure).

0135 SI 4.1. A-11 complete, holding for SI 4.2. A-8 (MSL High Temperature).

0425 SI 4.2. A-8 complete, commenced power ascension.

0730 Reactor thermal power at 70%, for RTI-23 (Feedwater System).

1100 Reactor thermal power at 71% for RTI-23 1400 Reactor thermal power at 72% for RTI-23 1430 RTI-23 complete, commenced power ascension.

1455 Commenced PCIOMR from 84% thermal power.

1715 Commenced reducing thermal power from 92% due to a Xenon transient.

1745 Reactor power at 89% due to a Xenon transient.

1800 Commenced PCIOMR from 89% thermal power.

2135 Commenced reducing thermal power from 92% for control rod pattern adjustment.

2400 Reactor thermal power at 68%, control rod pattern adjustment in progress, power increasing.

4/10 0240 Reactor thermal power at 72%, control rod pattern adjustment complete, reducing power to bring R factor into limits.

0350 Reactor power at 64%, R factor in limits, commenced power ascension.

0905 Reactor thermal power at 79%, reducing power for RTI-32A (Recirculation Motor-Generator Set Speed Control).

1250 Reactor power at 60%, RTI-32A in progress, increasing power.

1300 Reactor power at 70% for RTI-32A, reducing thermal power.

49my+s, sm.y.

n.,

~

? --"

s s

~7 ~

2 :

_ ma n

. ~,

8 Sianificant Ooerational Event

~

Unit 2 Date Time Event 4/10 1500 Reactor power at 51% for RTI-32A, increasing thermal power.

1600 Reactor power at 70% for RTI-32A, reducing thermal power.

1800 Reactor power at 48% (RTI-32A) complete, holding for checks on core limits.

1825 Commenced rod withdrawal for control rod pattern adjustment.

2130 Control rod pattern adjustment complete, commenced power ascension from 735 thermal power.

2200 Commenced PCIOMR from 78% thermal power.

4/11 1455 Reactor thermal power at 955, maximum flow, rod limited.

4/12 0600 Reactor thermal power at 925, maximum flow, rod limited.

0645 Commenced reducing thermal power for special testing on

. torus (PMI 105).

0800 Reactor power at 65%, PMI 105 in progress, reducing thermal power.

0900 Reactor power at 60% for PMT 105.

1300 Reactor power at 56% for PMT 105, increasing thermal power.

1400 Reactor thermal power at 59% for PMT 105.

1500 Reactor power at 58% for PMT 105, increasing thermal power.

4/13 0026 Reactor power at 62% for PMT 105, increasing thermal power.

0900 Reactor power at 65% for PMT 105, reducing power.

1000 Reactor power at 61% for PMT 105.

1015 PMI 105 complete, commenced power ascension.

1300 Commenced PCIOMR from 68% thermal power.

4/14 0833 "B" reactor feedwater pump tripped, reducing thermal power from 84%.

1100 Reactor power at 72%, "B" reactor feedwater pump out-of-service.

1130 "B" reactor feedwater pump returned to service, commenced PCIOMR.

Reactor thermal power at 985, maximum flow, rod limited.

4/15 1700 4

'e A

4 b

• A g;. '

te n

y-t

9 Sinnificant Onerational Event g

~

Udt2 Date Time Event 4/20 1500 Reactor thermal power at 945, maximum flow, rod limited.

4/23 2030 Commenced reducing thermal power from 94% for control rod pattern adjustment.

2116 Reactor power at 65%, for control rod pattern adjustment, increasing thermal power.

2245 Control rod pattern adjustment complete, commenced PCIOMR from 67% thermal power.

4/25 0730 Reactor thermal power at 975, SI 4.1.A-7 (Reactor Low Water Level) in progress, decreasing thermal power.

1253 SI 4.1.A-7 complete, commenced PCIOMR from 96% thermal power.

4/26 0900 Reactor thermal power at 995, maximum flow, rod limited.

2000 Reactor thermal power at 98%, maximum flow, rod limited.

4/28 1030 Reducing thermal power for SI 4.3.B.1.a (Control Rod Coupling Integrity) 1100 Reactor power at 96% for SI 4 3.B.1.a.

1130 SI 4 3.B.1.a complete, commenced power ascension.

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

4/29 0700 Reactor thermal power at 99%, full load electrical.

4/30 0955 Commenced reducing thermal power for replacement of No.

1 control valve servo valve.

1015 Reactor thermal power at 875 for servo valve replacement.

1123 No. 1 stop valve servo valve replacement complete, commenced power ascension.

1400*

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

2400 Reactor thermal power at 1005, maximum flow, rod

'l limited.

- n i

s w.

A4

,' f 8

4 r

4 Sggya. w1 y rg ; +yq. m,s

p. r u-m

• 1m.

,g

..a d

a+.

..o_.

~

10 4

Stanificant Operational Event Unit 3 Date Time Event 4/01 0001 Reactor thermal power at 100%, maximum flow, rod limited.

a 4/03 0040 commenced reducing thermal power for SI 4.3.A.2 (Control Rod Drive Excroise).

i 0100 Reactor thermal power at 965 for SI 4.3. A.2.

0155 SI 4 3.A.2 complete, commenced power ascension.

0300 Reactor thermal power at 100%, maximum flow, rod limited.

4/04 1210 Reduced thermal power to 98%, computer malfunction.

4/05 1519 computer back in service, commenced power ascension.

l 1620 Reactor thermal power at 100%, maximum flow, rod limited.

4/07 0225 commenced reducing thermal power per request of dispatcher (load not needed.)

0310 Reactor thermal power at 73% (additional load not needed per dispatcher.)

0435 Commenced power ascension from 73% power.

0900 Reactor thermal power at 100%, maximum flow, rod limited.

4/08 0500 Reactor thermal power at 995, maximum' flow, rod limited.

4/10 0005 commenced reducing thermal power for turbine control valve test and SI's.

0025 Reactor thermal power at 92% for turbine control valve 0030 Turbi A c Pol valve t6st and SI's complete, commenced power ascension.

0050 Holding reactor power at 975 for Xenon transient.

0125 Reactor power at 97%, computer malfunction.

l 0700 Reactor power at 985, computer out-of-service for maintenance.

1230 commenced power ascension from 98% thermal power.

1400 Reactor thermal power at 100%, maximum flow.

J 4/11 0700 Reactor thermal power at 995, computer out-of-service.

2233 computer back in service, commenced power ascension.

2300 Reactor power at 100%, maximum flow, rod limited.

4/16 0200 Reducing thermal power for turbine control valve test and SI's.

x:

a y

g m.

m.

T* bWtWWhY?- !.h'NY'V YN' ~! ?

U" i*TWTC!WCN&WW.-b {& ~ f1

'y '

l

~

'."di

.L'i E

f J

~ r : L ~- ~.J.

11 Significant Ooerational Event Unit 3 Date Time Event 4/16 0230 Reactor thermal power at 985 for turbine control valve test and SI's.

0250 Turbine control valve test and SI's complete, commenced power ascension.

0300 Reactor thermal power at 100%, maximum flow, rod limited.

4/21 0903 Reactor Scram No.110 from 100% thermal power. During performance of SI 4.2. A-7 (High Flow Main Steam Line) step 4.10 for P.S.-1-13A, a full MSIV isolation and resulting reactor trip was encountered when 'a four-cycle duration "B" channel isolation was received while "A" channel was tripped per the test procedure.

The reason for the spurious "B" channel signal is undetermined.

4/22 0350 Reactor Critical No. 124.

1853 Commenced rod withdrawal for startup.

2020 Rolled turbine generator.

~

2059 Synchronized generator, commenced power ascension.

4/23 2100 Commenced PCIOMR from 75% thermal power.

4/24 2300 Reactor thermal power at 100%, maximum flow, rod limited.

4/25 0615 A-3 low-pressure heater drain valve failed closed, "A" string low-pressure heater isolated, commenced reducing thermal power.

1500 Reactor power at 905, holding due to isolation of "A" string low-pressure heater.

1631 "A" string low-pressure heaters in service, commenced power ascension.

1705 Commenced PCIOMR from 925 thermal power.

2300 Reactor thermal power at 100%, maximum flow, rod limited.

4/27 0700 Computer out-of-service for repair, reactor power reduced to 995 2226 Computer back in service, commenced power ascension.

2400 Reactor power at 100%, maximum flow, rod limited.

4/28 2220 Commenced reducing thermal power for control rod pattern adjustment.

2400 Reactor power at 74% for control rod pattern adjustment.

~ 2n w;uxy.&rm v.

v5

+

.g

..-c._.

c.

a._

12 Sinnificant ODerational Event Unit 3 Date Time Event 4/30 0020 Control rod pattern adjustment complete, reducing thermal power for recirculation pump motor-generator set brush replacement.

0300 Reactor power at 50% for recirculation motor-generator set brush replacement.

0316 Recirculation pump motor-generator set brush replacement complete, commenced power ascension.

.0830 Commenced PCIOMR from 82% thermal power.

0930 Stopped PCIOMR at 84% power due to computer problems.

1300 Commenced PCIOMR from 84% power.

2400 Reactor thermal power at 93%, PCIOMR in progress.

i This was principally prepared by F. D. Green.

l

~

l l

l

v 2. e(*h]b}e s

.,1

-Jf 7 Nf] W ?

[{

• f'f n i 44 5

uf_

.m ' s,.. m 4.: m

' : 2

~ u i

' :J - _

.a x

u_-

3

.L <

13 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-259 UNIT Browns Ferry-1 5-1-83 DATE T. Thom CO3fPLETED BY TELEPil0NE 205/729-0834 April MONTH DAY AVERAGE DAILY POWER LEVEL DAY AVER ACE DAILY POWER LEVEL (31We-Net)

(31We-Net t 902 17

-12 863

-10 2

18 877

-10 3

39 873

-10 4

'O 871

-10 5

21 864

-9 6

22 865

-9 7

23 855

_10 8

24 9

829

-9 25 845

-9 10 26 846

-9 II 849

-10 12 28 13 819 29

-9 743

-9 14 30 15 820 31 16

-1 s

INSTRUCTIONS On this format. list the average daily umt p >wer lesel m N!We Net fiir e eh <!ay in the reportmg month. Compute tu the nearest whole megawart.

(W77i yvMpNs.a9'ew y_%

, y.y,.

f; 7

5 090.'

3. G : i,; (.: ^

. =. m m

14

=

AVERAGE DAILY UNIT POWER LEVEL 50-260 DOCKETNO.

Browns Ferry-2 g.lT DATE 5-1-83 T. Born COMPLETED BY 04 TELEPHONE MONTH April DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe-Net)

IMWe-Net)

-10 1022 37 319 1018 2

gg 3

761 19 1025 921 1022 4

20 922 1025 5

21 791 1026 6

7 1006 23 987 962 871 8

24 012 1009 9

'S 1

1068 10

'6 977 1070 27 733 1083 I2 33 709 1092 13 826 1061 14 30 1010 35 31 1038 16 INSTRUCTIONS On this forinat,!ist the aserage daily unit power leselin Mwe Net for each day in the reporting inonth. Cornpute to he nearest whole rnegawatt.

(9/77) l

, M'h?h w ww,m,.n;,?.'rfpi?+y :iigekryg,:.-

, y

~x;

. \\ ',,i,

[ff *%,*fi 6h T d.[mma m ! [

,L

,%;(.;:n -

a;m.9 qu.'

^'

F t

9

,.j%

15 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-296 UNIT Browns Ferry-3 DATE 5-1-83 COMPLETED BY T. Thom l

1 TELEPHONE 205/729-0834 MONTH April DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL f MWe-Net)

(Mwe. Net )

1078 1043 37 1036 1059 18 3

1054 39 1061 1047 1060 4

20 1051 391 5

21 6

22 7

1035 23 718 1057 1004 8

34 1054 961 9

25 1033 1055 10 26 gi 1058 1053 27 1068 1062 12

,g 1062 1031 13 29 1057

,14 30 868 1063 15 3,

1084 I6

=

INSTRUCTIONS On this format, list the average daily unit power leselin MWe Net ihr each day m the reporting month. Compute to the nearest whole megawatt.

(4/77) e m'

~

y

^ -

- wm n' ry*Am?p s r.s i w,.

x-

} :' "

-;w

.. m::v v.

)

,s u.

._. c,

-s mg

F 17 OPERATING DATA REPORT DOCKET NO. 50-260 DATE 5-1-83 CO.\\lPLETED BY Thon TELEP110NE '0 /729-0834 OPERATING STATUS

1. Unit Name: Browns Ferry - 2 Notes

2. Reporting Period: April 1983 3293

3. Licensed Thermal Power (3tht):

1152

4. Nameplate Rating (Gross 31We):

5. Design Electrical Rating (Net 5tWe): 1065 1098.4

6. Slasimum Dependable Capacity (Gross AlWe):

1065

7. 31arimum Dependable Capacity INet alwe):

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

N/A N/A

9. Power Level To Which Restricted,if Any (Net gi e):

10. Reasons For Restrictions,if Any:

This 31onth Yr. to Date Cumulative 719 2_,879 71,622

?

11. Ilours In Reporting Period

12. Number Of flours Reactor Was Critical 705.22 989.47 44,282.94

13. Reactor Reserve Shutdown flours 13.78 15.78 13,700.60

14. Ilours Generator On-Line 689.17 919.64 42,895.09

15. Unit Reserve Shutdown llours 0

0 0

16. Gross Thermal Energy Generated (NtWil)

- 1.951.711 2.347.229

_122.827.569

17. Gross Electrical Energy Generated (SlWil) 660.520__ _,,, 769,186 39,642,261 794.240 40.819,148

18. Net Electrical Energy Generated (51Wil) 643,353

19. Unit Service Factar 95.9 31.9 59.9 95.9 31.9 59.9

20. Unit Availability Factor 84.0 23.1 3z.0

21. Unit Capacity Factor (Using alDC Net)

22. Unit Capacity Factor IUsing DER Net) 84.0 25.1 52.0 4.1 8.5 26.8

23. Unit Forced Outage Rate

24. Shutdowns Scheduled Oser Next 6 Stonths (Type. Date.and Duration of Each):

a

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

26. Units in Ted Status IPrior to Conunercial Operation):

Forecast Achiesed INITIA L CRITICA LITY INITIAL ELECTRICITY CO%l%IERCIA L OPER ATION gum,.y. ~,

., y y. ;..,,

(9/77) 9e3 4, ;,,,

.m, e s, c

gL

- - - =._. -

2-

16 a

OPEf1ATING DATA REPORT DOCKET NO. 50-259 DATE 5-1-83 COSIPLETED BY T. Thom TELEPllONE (205)729-0834 OPERATING STATUS

1. Unit Name:

Browns Ferry - 1 Notes

2. Reporting Period: April 1983 3293

3. Licensed Thermal Power (5tht):

1152

4. Nameplate Rating (Gross SIWE):

5. Design Electrical Rating (Net SIWE): 1065

6. Staximum Dependable Capacity (Gross AlWe): 1098.4 1065

7. Staximum Dependable Capacity (Net 31We):

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

N/A

9. Power Level To Which Restricted,If Any-(Net AlWe):

N/A

10. Reasons For Restrictions.lf Any:

N/A This alonth Yr.-to-Date Cumulative

11. Hours In Reporting Period 719 2,879 76,681

12. Number Of Ilours Reactor Was Critical 364.33 2,363.25 49,752,79

13. Reactor Reserve Shutdown llours 0

47.71 5,785.02

14. flours Generator On-Line 361.42 2.317.52 48,717.64 il5. Unit Reserve Shutdown flours -

0 0

0

16. Gross Thermal Energy Generated (SlWil) 957,619 6,784675 138,557.679

17. Gross Electrical Energy Generated (alWil) 315,210 _ __,, 2,244,900 45,645,620

18. Net Electrical Energy Generated (51Wil) 302,196 2,175,548 44,325,327

19. Unit Sersice Factor 50.3 80.5 63.7 50.3 80.5 63.7

20. Unit Availability Factor

• U

21. Unit Capacity Factor (Using alDC Net)

22. Unit Capacity Factor (Using DER Net) 39.5 71.0 54.3

23. Unit Forced Outage Rate 0

8.1 23.8

24. Shutdowns Scheduled Over Next 6 51onths(Type. Date.and Duration of Each t:

.s

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

26. Units in Test Statusirrior to Commercial Operation):

Forecast Achiesed INITIA L CRITICALITY INITIA L ELECTRICITY COilNIERCIT L OPER ATION (9/77) y,yru. p:vmy <

L 2

w

.>v

- n,.

??..

.e 2

. _.y

18 i

OPERATING DATA REPORT DOCKET NO. 50-296 DATE 5-1-83 COMPLETED BY T. Thom TELEPilONE 205/729-0834 OPERATING STATUS

1. Unit Name:

BEowns Ferry - 3 N t'5

2. Reporting Period: April 1983 3293 J. Licensed Thermal Power (Mht):

1152

4. Nameplate Rating (Gross MWe):

5. Design Electrical Rating (Net MWe): 1065

6. Maximum Dependable Capacity (Gross MWe): 1098.4 1065

7. Maximum Dependable Capacity (Net MWe):

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

N/A

9. Power Level To Which Restricted. If Any (Net MWe):

N/A

10. Reasons For Restrictions. If Any:

N/A This Month Yr.-to.Date Cumulatise

11. Hours In Reporting Period 719 2,879 54,047 f

12. Number Of Hours Reactor Was Critical 700.22 2,416.52 40,028.80 18.78 462.48 3,834.63

13. Reactor Reserve Shutdown flours

14. Ilours Generator On-Line 683.07 2.373.50 39.147.56

15. Unit Reserve Shutdown ilours 0

0 0

16. Gross Thermal Energy Generated (MWil) 2.178.312 7.496,501 116,832,605

17. Gross Electrical Energy Generated (MWii) 721,130 2,492,520 38,532,310

18. Net Electrical Energy Generated (MWil) 702.072 2.424.177 37.405.081

19. Unit Senice Factor 95.0 82.4 72.4

20. Unit Availability Factor 95.0 82.4 72.4 91.7 79.1 65.0

21. Unit Capacity Factor (Using MDC Net)

22. Unit Capacity Factor (Using DER Net) 91.7 79.1 65.0

23. Unit Forced Outage Rate 5.0 17.6 17.4

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

s

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

26. Units In Test Status (Prior to Commercial Operationi:

Forecast Achiesed INITIA L CRITICA LITY INITIAL ELECTRICITY COMMERCIAL OPER ATION

'f(

I

>)

swQ ;.W'<psy p c q g o.

.x.g -. r.v. n

+

u n.,g. _

v,,; 2 m,.g 2

_t 2

m___

__ m

l

.a

NT q?g, 50-259 UNITSliUTDOWNS AND POWER REDUCTIONS DOCKET NO.

UNIT N AME Browns Ferry 'l DATE 5-1-83 "J.

5 REPORT MONTH April COMPLETED BY T. Thom TELEPHONE 2U')/ /29-U334

+?

Q

,,,g%

Cause & Corrective

~

=

n 5.a =

. o.

Date y

-j g s

7jy Licensee

,= %

g-2 :s 4

.2 g a:

Event u?-

gE Action to j [5 -

Report =

(N C

$2

E

] L' Prevent Recurrence C

263 4/13/83 S

B Derated for control rod testing.

264 4/16/83 S

357.58 C

4 Manually tripped turbine to begin EOC-5 refuel outage. No reactor scram--

controlled shutdown. One hour adjust-ment for CDT.

G

(.-

I 2

3 4

F: Forced Reason:

Method:

Exhibit G - Inst ructions S: Scheduled A-Equiprnent Failure (Explain) 1-Manual ior Preparation of Data B-Maintenance or' Test 2-Manual Seram.

Entry Sheets for Licensee C Refueling 3-Automatic Scrain-Event ReporI (LE R) File t NUREG-D-Regulatory Restriction 4-Other ( Explain 1 0161)

E-Operator Training & License Exainination F-Adnunistrative 5

G-Operationa! Eiror (Explain)

Estubit I - Saine Soure:

(9/77) li-Ot her ( Explain) l l l

,. ' i

?.

'rq yJ47 -

p$

l g, DOCKET NO. 50-260 UNITSHUTDOWNS AND POWER REDUCTIONS

';/ d '

UNIT NAME Browns Ferry-Z x

DATE 5-1-83 fjh' REPORT MONTH April COMPLETED BY T. Thom 44 TELEPHONE 205/729-0834

+

ll[

, / >:

"L

,5?

3 Y

Licensee

,Eg ho V

Cause & Correceive

j-No.

Date i

3g i

25$

Esent

?

93 Action to

$5 5

j@g Report :

r$ U

'l H

j' Prevent Recurrence d

~;

y 249 4/5/83 S

H Derated for control rod pattern adjustment 3

250 4/8/83 S-B Derated for turbine' control valve test

(,,

and SI's, w

251 4/12/83 F

B Derated for PMT 105 Torus Special Test t

252 4/23/83 S

H Derated for control rod pattern adjustment L

l' L

i,.

I 2

3 4

6 F: Forced Reason:

Method:

Exhibit G -Instructions S: Scheduled A Equipment Failure (Explain) 141anual for Preparation of Data B-Maintenance of Test 2-Manual Scram-Entry Sheets for Licensee

( -(,

C Refueling

3. Automatic Senm-Event Report (LER) File (NURLG-D Regulatory Restriction 4-Ot her ( Explain )

0161)

E-Operator Training & License Examination F-Administrative 5

G-Operational Er ror (Explain)

Eshibit 1 - Same Source (9/77)

Il Other (Exrlain)

V 4

kW

-in i[k w,

Nf,,- *

1. j-UNIT SHUTDOWNS AND POWER REDUCT10NS DOCKET NO.

50-296 tea UNIT NAME Browns Ferry-3, AO DATE 5-1-83

(:Nk REPORT MONTH April COMPLETED BY T.

Thnm 2.f 4 -

TELEPHONE 205/729-0834 mg.

" > ';f

-4 w.

1 ; '6 i.25 i! F

=.

is

=

li enSec 5*L

$L Cause & Corrective d

No.

Date g

5 j

~

fEvent 13 93 Action to

,.O g-3.2 7,

5ge

}L Prevent Recurrence 3 05 g Report e mO

('.

OO

, yQ 6

1

> g.

129 4/7/83 F

H Derated-load not needed t

A..U p'.',Jjk 130 4/21/83 F

35.93 H

3 Reactor scram durinir, SI 4.2. A. 7 (High Flow Main Steam Line) on spurious "B" channel isolation to j.

>-=

?!-

131 4/29/83 S

H Derated for control rod pattern adjust ment

. [

fyi l

~4

.o A,"j" g

y 3

4 C

F: Forced Reason:

Method:

Exhibit G - Inst ructions S: Scheduled A Equipment Failure (ExP ain) 1 -Manual for Pieparation of Data l

B Maintenance or Test 2-Man ua! Scram.

Entr> Sheets for Licensee j*,

C-Refueling 3-Automatic Scram.

Event Report (LERI File (NUREG-D Regulatory Restriction 4-Ot her ( Explain) 01611 E-Operator Training & License Examination F Administrative 5

G-Operational Eiror (Explain)

Exhibit 1 Same Sousee

(,

(9/77)

Il-Ot her ( Explain)

~k 4

g.

v r..

f

,'a

!!.r!.G' PENT PAINTENANCE SU}C"ARY pf3g9 CSSC EQUII~.D T FOR T1!E P.0:illi CF April 19 83 lIkc-g NAT'RE EFFECT ON SAFE-CAUS *-

l ACTIC: TK.E:;

, TEj SYS~Di CC'.PCNENT OF CPEP.ATICN CF CF PJSULTS OF TO PFIC:

L O

MA IY2NANC'd T:!E FIACTOR l'ALFUNCTION Pat.FL NCTION RECU R R:

>- :-t

! U--1 4-3 80 TR-80-1 Repair None Normal Wear Loss of record-None 4-4 90 RM-90-256 Calibration None Inst. Drift Incorrect reading None ir-2 i

'4-9 71 P1-71-,20 Cali,bration None Inst. Drift Incorrect reading None 4-9 71 PI-71-35 Calibration None Inst. Drift Incorrect reading None u.

U-3 i-12 64 TS-64-[0 Replace Nona Normal Wear Incorrect setpoint None w

N L-18 74 FR-74-64 Calibration None Inst. Drift Incorrect record None L-19 71 FT,-21-1A -

Repair None Age Incorrect output None k

F: -

p

~*

W w

f.g 3II e

fh"'.

i 5 5.L r

,n

%)

g.g,

EROWNS. FERRY NUCLEAR PLANT UNIT 3

Pg 3 h

sIL 30 Pptndix B hk CSSC EQUIPMENT ELECTRICAL MAINTENANCE

SUMMARY

f,.

9/29/82 ug d"fi For the Month of

' April 19 83 de*.

tik.

Effect on Safe Action Taken L,1[;L Nature of Operation of Cause of Results of To Preclude

'Dato System Component Maintenance The Reactor Malfunction Malfunction Recurrence

> Recieved a false Cleaned the relay 4/23/83 Diesel "A" battery Received a None Alarm relay (PFC 9.9 Generator charger on 3B abnormal contacts stuck.

alarm " Diesel contacts, the Cd7 125VDC diesel alarm in the generator 3A relay operated

1. (j System generator.

control room battery charger or properly.

for 3A battery exhaust fans MR #A-149453 u.

charger, abnormal" in the control room.

t

. ~.

4/29/83 Air Cou-4KV shutdown Air handling None Chiller low on Chiller inoperable.

Added freon to i

ditioning board room unit tripping freon and water chiller unit and (Cooling-3EC air hand-out.

strainer cleaned water

[.,

Heating) ling unit 3B2, stopped up.

strainers, N

_. j,

.f chiller ' returned to service.

MR #A-147619 t -

L' 5 m 4

s be k

i

=,kj k

N

)

h4

1 end dommon P:'g BROWNS. FERRY NUCLEAR PLANT. UNIT

/?fJ ~

CSSC EQUIPMENT ELECTRICALMAINTENANCESU$ MARY AppIndix B d

-<w 9/29/82

~

For the Month of. April 19 83 J :).

4 Effect on Safe Action Taken Nature of Operation of Cause of Results of To Preclude

'Date System Connonent Maintenance The Reactor Malfunction Malfunction Recurrence 4/20/83 250 volt 250V main Battery None Bad circuit Battery charger Replaced the bad' DC System battery charger was cards.

current unstable.

printed circuit charger #1.

not charging cards, charger properly.

operated properly.

MR #A-140815 y

4/21/83 Diesel Relay TRA-3 Relay coil None, relay Failure of lexan Relay coil retainer The relay was Genera-on panel retainer was operable coil retainer spool cracked. The replaced per SEMI tors25-46A.

(lexan) spool spools. Ref:

relay *was found to 37.

inspection.

HEA Relay Coils have d cracked coil MR #A-059080 Service Advice spool during PSM-721-152.2 inspection.

u

~

FSR 366E8138.

4/22/83 CRD l-PVC-85-23 The valve 1-PVC-85-23 Iron core was 1-PVC-85-23 was Tightened brake l'

breaker trip-inoperable.

loose in the inoperable.

assembly, valve ping during valve brake operated properly.

valve opera-assembly which MR #A-147026 tion.

caused the l'

brake to fail i

to release.

Troca 1

[Y

4 4

L,:

h h

I

1

.. c n.

1 cnd Cbmmon E 3 BROWNS. FERRY NUCLEAR PLANT UNIT s'

$'f4 !

CSSC EQUIPMENT ELECTRICALMAINTENANCESU$1ARY Appendix B 33-9/29/82 h

I For the Month of April 19 83

$5 g,

Effect on Safe Action Taken 4jg (6 Thtm 7i Nature of Operation of Cause of Ecsults of-To Preclude System Component Maintenance The Reactor Malfunction Malfunction Recurrence Ihk2/83 480 volt 480V Rx MOV Inspection of None Incorrect The lugs were im-The lugs were re-4Q Reactor Bd lE normal ITE K-600S splices in properly sized for placed with a lh MOV.

and alter-breakers in wiring for the the wire. The parallel splice

U}

Boards nate feeder response to IE magnetic latch splices would meet for 16-18 AWG breakers.

Information and the trip their required wire in both the f.

Notice No.

coil circuits function. However, 480 volt Rx. MOV

?! <

81-06.

of the ITE the lugs were re-Bd IE normal and D

K-600S breakers, placed with a alternate feeder

(

Wires spliced parallel splice for breakers.

p were 16 AWG and 16-18,AWG wire.

MR #A-061316 4

18 AWG sizes.

This required re-MR #A-140432 The lugs found moving LPCI MG Set MR #A-061336 y

were for 14-16 1EN from service on MR #A-140431 U,

vL AWG wire.

4/12/83 and 4/13/83<

v 4/12/83 Air Con-

"lB" control Unable to None Sensing element Chiller inoperable.

Replaced the ditioning bay chiller regulate broken.

sensing element m.]p (Cooling-chilled chiller.

and returned the c.

Heating) water line chiller to ser-7 sensing vice.

element.

MR #A-140532

[/14/83 Fuel Pool Fuel pool During the None Bad level Fuel pool low level Replaced LS-78-2B i,

Cooling low level performance of

switch, alarm inoperable, and successfully-4 switch scheduled EMI completed EMI 48.

M, LS-78-2B.

48 LS-78-2B MR #A-149766

$ly y failed to j;S operate.

iQ Mg):- ',.

,:y y

$,En N

Y I

i P

)

i..

.S.

h,s, BROWNS. FERRY' NUCLEAR' PLANT. UNIT 1 cud C$mmon.

Pcg2 3 BF EMSIL 30 Appendix B N~

CSSC EQUIPMENT _

ELECTRICAL MAINTENANCE

SUMMARY

9/29/82

.y2,.

For the Month of April.

'19 83

[% b sE VM d.

Effect on Safe Action _Taken

b Nature of Operation of Cause of Results of To Preclude v Data System Component Maintenance The Reactor Malfunction Malfunction Recurrence 3/25/83 Standby Standby gas During the per-SBGT train "B" Bad flow switch.

"B" SBGT train

'The flow switch

.Q Gas treatment formance of inoperable.

inoperable.

was replaced, y;

Treatment train "B" SI 4.2.A-13 SI 4.7.B-1 and flow switch FS-65-42A was SI 4.2.A-13 were

[~

FS-65-42A.

found to oper-successfully ate erratically completed. The g

f.)

_ paddle. type flow

?*

switches presently D

being used are expected to be-

[>

replaced with C-differential Lh pressure, switch s 9

,f-I by.2/15/84.

-y

', [.

MR #074884 s-

,L LERfBFRO-50-259/

[1_

83018 4/10/83

' Fire Smoke detec-XS-39-66XM None Water, from an The. alarm could Replaced the smoke Protec-tor XS gave a false unknown source, have masked signals detector and tion 66XM.

alarm.

1eaking through from other detectors successfully per-a seam in the.

which are required formed SI 4.11.C.

g concrete from to be operable.

1 & 5.

This f'

an upper eleva-smoke detector-i tion entered will be relocated J.

the smoke detec-by 5/17/83.

tor and caused MR #A-149687

WI it to alarm.

LERfBFRO-50-259/

,[

83019 e

2 Y

x,",, s,o w

sj.

BROWNS FERRY NUCLEAR PIANT UNIT Common

,4 CSSC EQUIPMENT

}ECllANICAL MAINTENANCE

SUMMARY

For the Month of April 19 83

',j t

o EFFECT ON SAFE ACTION TAKEN DATE SYSTEM COMPONENT NATURE OF OPERATION OF CAUSE OF-RESULTS OF TO PRECLUDE ~ -'

i MAINTENANCE THE REACTOR MALFUNCTION MALFUNCTION RECURRENCE l4-21 Radwastc' low-level cask b'olt hole in-none normal use of bolt failure to changed inserts #15

..c-serts need holes tighten and 16 I

)

replacing MR 154531 t

73-30 Radwaste low-level cask inserts stripped none frequent removal cask failure to accon.-+eided in new inserts on cask and replacement odate head bolts NR 74238 of head bolts

'4-19 RHRSW valve C2 valve non-none broken nipple valve would not oper-replaced 1" screwed functional ate properly nipple MR 131703 b

O

<s M

h s

s e

I' i

Y

'y u.,

Y[t-w.,

BROWNS FERRY NUCLEAR PIANT UNITE l'

4,

.9;,,

_f HECHANICAL HAINTENANCE

SUMMARY

ik; k,,, ~ ;- CSSC EOUIPMENT m

'l['

For the Month of April 19 83~

n M J J g

,.-s ACTION TAKEN EFFECT ON SAFE p.

j DATE SYSTEM COMPONENT NATURE OF OPEBATION OF CAUSE OF RESULTS OF 10 PRECLUDE.

MAINTENANCE THE REACTOR MALFUNCTION MALFUNCTION RECURRENCE 24 Service Air air compressor head gasket none blown gasket.

air leak on high-replaced high-pressure pressure head and gaskets 1C and safety failure

$1 valve-valve on low pressure MR'149983 l

!'4-12 Fire

'3" fire pro-eroded fire none unknown fire protection line welded in new sections.

Protection tection pipe protection pipo corroded of p.iping and fittingt

}

and fittings and fittings MR 28348 O

e 9

p

,e

=

-4 00

}

i e

a 1

e G

I s

A.

6

}

p.

~

t.-

- - + - - -

3

~

~

2 D '. {y -

7g, BROWNS. FERRY NUCLEAR;PIANT UNIT s

. g.,..--

a n

.g. g.,,

..y--.-

.._;ggNECHANICAL MAINTENANCE

SUMMARY

~

[-TCFSCEQUIPMENT Q[, ; ~ ~

. __,. T S ' ' 'For the Mo' nth 7k"Ioril

19~83'

~.

,. y ACTION TAKEN EFFECT ON SAFE 7

.g -

7DATE

_ SYSTEM COMPONENT NATURE OF OPERATION OF

..CAUSE OF RESULTS OF TO PRECLUDE M

MAINTENANCE THE REACTOR

! MALFUNCTION MALFUNCTION RECURRENCE

~"

4-25 Fire 3" fire protec-fire protec-nonc unknown pipe corroded replaced 3" fire

~

~

'EQ Protection tion line pipe tion line

~~

27 and' fittings leaking protection line & g fittings MR 62208 3.g

,.g..

w, l 4-23 '-

CRD CRD pump 1B pump nonfunc-none normal wear long pump inoperable replaced mech. seal Q

tional time operation and bearing on inboard,

? %,_

side, lube, realigned

<.;a _.

pump

,f~~~

MR 60729 l4-4 EHC FCV-1-80 Servo valve leaking' none.

faulty o-ring EHC fluid lealE came replaced servo valve close to unit shut-MR 130379 (Non-CSSC) Valve ye, down e

.. g 4-31 HPCI LS-73-5 faulty level none age and poor control switch inop-replaced liquid level control switch design erable control switch MR 60670 4-5 HPCI impeller hub broken hub none hub bursted while impeller inoperable welded hub on impeller t-pulling off motor MR 58991

. -7 CAM CAM 90-256 air leak none faulty o-ring air leak on pig on rep' laced o-rings CAM MR 129781

( 4.-7 Control drywell air compressor none compressor went compressor inoperable repacked valve p

Air compressor 2A failed bad MR 63512 p;-

f4-1 RHR Servic( FCV-23-34 valve failure none worn packing valve would not repacked valve

~

lJ.

Water function properly MR 130364 4

^ ^ l

'^

eq I

a.N n

iC W

'Q$

c,'

,q,--

. -w_

I.

'b""'*-

s.

.,.-w

-w

~.

1. e.

_E Y

a e

p ;

f., ;,7-7

. -/-

I ' ' 't pp.

m. a il.

2 ?_'.-

BROWNS FERRY NUCLEAR PIANT UNIT 3

= -- -

.,., -. - ~ : w - :.,u. n -

4:

w.-a

=~ 3

. MD g_.g.' -[5[g [h

%3 f) '[f CEC EOUIPMENT E-;-J ~ ~- = J-hsy;a:

T MECHANICAL MAINTENANCE SU)04ARY

^ ~[~

..['

,Q

-[-~25. " 1 _.._..

,-7 For the Month of April 19 83

&y

. -. ~

y

=

EFFECT ON SAFE ACTION TAKEN

,,g dDATE SYSTEM '_

.. COMPONENT NATURE OF OPERATION OF CAUSE OF RESULTS OF

- 70 PRECLUDE

^

MAINTENANCE THE REACTOR MALFUNCTION MALFUNCTION

' RECURRENCE-s

' 4-8 Diesel 3D diesel air air compressor none blown head gasket air leak on compres-replaced head gasket Q

Cenerator compressor B nonfunctional sor MR 60675 g,

q@.

,4-12 EECW' EECW pump A3 valve inopera-none internal parts valve would not replaced air release L y,.).

air release ble worn out operate valve

, pg valve.- 587 MR 149465

,2 fire t rotectior none unknown fire protection line welded'in new eroded

' 4 19 Fire-

'~

3" fire protec-i Protection tion line non-line nonfunc-leaking 3" fire protection.

functional tional line iQ{

-MR 62207

• L.^

• e F

.f e

t O

- 1;' $

i l

(

t I

t

'I 1.

s, 2

r r

(.f a

'1 l

.y

• }

g

'm.,

Q* %

. _... =

i l

V~

~

31 FIELD SERVICES Sm4HARY

~

April 1983 Maior Wor k Areas A.

Refuel area - a controlled shutdown of unit 1 began on April 15 with cold shutdown being reached April 16, 1983 Vessel disassembly began the following morning but was stopped when the RPV head removal intro-duced airborne contamination to the floor. The airborne problem was resolved and vessel disassembly was completed on April 21.

Fuel unload began at 0600 hours0.00694 days <br />0.167 hours <br />9.920635e-4 weeks <br />2.283e-4 months <br /> on April 22.

At step 130 fuel movement was stopped because the fuel was placed in an untested fuel storage rack.

The fuel was transferred to another rack and fuel movement resumed. On April 28, 1983 the bridge crane was out-of-service for 6-hours due to CAM breaker problems and grapple air leaks.

Repairs were made to the crane and fuel movement resumed with 545 steps of 764 completed at 1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br /> on April 30, 1983 B.

Turbine - following the installation of the main steam line plugs the low-pressure "A" and "B" turbines and bypass valves were disassembled.

Both low-pressure turbine inner cylinders were found to have high-radiation readings requiring them to be wrapped in Herculite before i

moving-to the unit 3 turbine floor. Due to these high-radiation read-ings, many of the turbine components will require decontamination.

C.

Drywell - the initial high-pressure readings in the drywell revealed lower radiation levels than expected, but still very hot and decontamination was required in some areas. Following decontamination the rod gallery IRM/SRM reroute was performed.

%gysqpWsymp~.

- i.

.. +

ju yg& :f

(*

s ;3 ts -

1,

%~,-

~

,a 4 ":

~

,j

32 FIFLn SERVICES

SUMMARY

(C ntinusd)

~

April 1983 Maior Work Areas (Continued)

C.

Drywell (Continued)

All four MSIV lines were tested and failed the LLRT.

Preparations for valve maintenance were started.

Removal of the MSRV's for mainte-nance was started following main steam line plug installation.

i D.

Electrical - prior to the start of the unit 1 cycle 5 refueling outage, preparations were made to support the various maintenance and modifications to be performed by the electrical group.

These included writing work plans, checking material status, installing torus tempo-rary and permanent power supplies, and performing electrical checks on outage related equipment.

Once unit 1 was shutdown, the majority of electrical work consisted of performing EMI-71 motor maintenance, removing TIP indexers and TIP tubing, installing conduit and equipment for ECN P0399, disassembling recirculation motor-generator sets for maintenance, and writing work-plans.

Additional work that supported the outage included relamping the drywell, installing torus power supplies, checking the undervessel hoist for CRD changeout, and repairing the unit 3 overhead turbine crane.

9 9

P "JN 2

N

' f N* 'a k"* N [O[ 7',

y' 6

s 4

i w' } {yy_4 n ' ;. hay g?

,y

' yykl Uc

~,. _

L,, (t u

-' } QL.

• J

33 FIRtn SERVICES

SUMMARY

(C ntinund)

~

April 1983 Maior Work Areas (Continued)

E.

Mechanical - following the completion of unit 2 cycle 4 refueling outage in March, preparations were made for the unit 1 cycle 5 refueling outage.

These preparations included mechanical checks of equipment to be used during the outage, writing work plans, prefabri-cation of ECN P0392 components, and setting up to hydrolaze the CRD header.

Work that commenced with the unit 1 shutdown included units 1 and 2 diesel-generator cooler piping modifications, units 1 and 2 PSC head tank pump repair, hydrolazing and installing shielding to the CRD header, preparations for probolog, mechanical checks of the under-vessel hoist, prefabrication of ECN P0392 and P0612, and RHRSW valve changeout.

The scram discharge header prefabrication, RHRSW check valve, and diesel generator cooler were Section X.I modifications.

F.

Planning and Scheduling - in preparation for the unit 1 cycle 5 refueling outage, the planning and scheduling group prepared overview schedules of the outage work to facilitate manpower planning.

A manpower load-board was prepared indicating all craf t and support per-sonnel required for the outage. Further development of the PROJECT /2 computerized network was performed, including final coordination with the individual engineering groups.

%p;ry%wy# s o

J s'

.', vp r

a s-

[.

34 FIRtn SERVICES

SUMMARY

(Continund)

.. e

~

April 1983 Maior Work Areas (Continued)

F.

Planning and Scheduling (Continued)

Once the outage began, this group reported status and presented schedules indicating the work to be accomplished.

General coordina-tion was provided with daily and weekly coordination meetings.

G.

Torus 1.

External and internal modifications - prior to the start of the outage, work was performed on the external reinforcements.

By April 15 the lapplates were 60-percent complete, ECCS gussets were 80-percent complete, and four out of 16 anubber wall brackets were installed.

Following unit shutdown, work continued on the external modifica-tions and power supplies were set up for the internal modifica-tions.

Williams Contractor began decontamination and sandblast-ing inside the vent headers.

Once the torus was opened and air samples taken, stainless steel grating was installed on the catwalk. Draindown of the torus is awaiting the completion of core unload and closing of fuel pool gates.

2.

Attach piping - the scope of this work changed dramatically during the preoutage time frame, therefore, the major effort was directed toward identifying the work, coordinating with system outage windows, and reviewing drawings.

Hangers were prefabri-cated during this time with 174 of 338 completed by April 15.

.T 7

9

• r

[

[

k d b [ h; "

f N' kY y ; {y ' ; 14 di;;i;g,-

y.

i?f o

- - 1 t

_m

__c_.

35 FIELD SERVICES

SUMMARY

(Ocntinutd) t April 1983 Maior Work Areas (Continued)

G.

Torus (Continued) 2.-

(Continued)

After the unit was taken offline, work continued in the prefabrication shops and baseplate installation began in the field.

Drywell and torus purge, high pressure coolant injection (HPCI), and reactor core isolation cooling (RCIC) systems were released on April 21 for hanger installation.

Due to operational concerns, work on the residual beat removal (RHR) Loop II system could not begin until a safety evaluation from EN DES was completed. This delayed hanger installation on this critical system until April 27 The present status of all torus hanger work is: HPCI and RCIC - two installed, RHR-Loop II - five installed, prefabrication - 192 of 357 H.

Administrative - the overtime percentage for the month of March was 15-percent, with 113,729 5 straight-time hours and 19,873 5 overtime hours. As of March 31, 1983 year-tedate overtime percentage was 4

20-percent, 802,878 straight-time hours and 197,376 overtime hours.

The overtime percentage from April 1 thru April 24 was 25.4-percent.

]

The overall goal of the overtime percentage is 17 percent.

.m ff b

,n'-

' %3#

T ff

-I

,f ;,

A 8

j

-[_

)

y; ssh>J l d f3 %:,

q e,

(-

y f'

~

36 FIRLn SERVICES

SUMMARY

(Ccntinutd)

~

April 1983 Maior Work Areas (Continued)

H.

Administrative (Continued)

The O&M budget for March was $2,309,276 and the expenditures were

$3,382,492 with year-to-date budget being $16,924,095 and actual year-to-date expenditures being $16,557,978. The capital budget t:as

$5,071,392 and the expenditures were $917,290 with yean-to-date budget being $23,202,222 and actual yean-to-date expenditures being

$8,839,099 Overall budget was $7,380,668 and the overall expendi-tures were $4,303,237 with yean-to-date budget being $40,136,317 and actual yean-to-date expenditures being $25,408,658.

Sirnificant Problem Areas Obtaining material for CRD changeout has been a major area of concern.

Additionally, there is much concern over the potential for exposure problems on unit 1.

Increased ALARA attention is going to be necessary.

Administrative and procedure burdens are also significant concerns in accomplishing Field Service work. ' Training needs are even more significant than previous.

.m A

t

/

b" M'

-N(7

• r

(,?

k' E

'Y k k

[' E 5

• [

-N' %

.[&.j;W& ' f,L%;;&h{i 3. ' JQu 4, ! L :Qc,

-'I'

1. .,,.,4

}!;.U;. _

c. f

,+

- T TENNESSEE VALLEY AUTHORITY Browns Ferry Nuclear Plant P. O. Box 2000 Decatur, Alabama 35602

'MAY 111983 Nuclear Regulatory Commission Office of Management Information and Program Control Washington, DC 20555 Gentlemen:

Enclosed is the April 1983 Monthly Operating Report for Browns Ferry Nuclear Plant Units 1, 2, and 3.

Very truly yours, TENNESSEE VALLEY AUTHORITY IN-f,tingPowerPlantSuperintendent

. A. Co fey Ac Enclosures cc: Director, Region II Mr. Bill Lavalee Nuclear Regulatory Commission NSAC Office of Inspectior and Enforcement P. O. Box 10412 101 Marietta Street Palo Alto, CA 94303 Atlanta, GA 30303 (1 Copy)

Director, Office of Inspection and Enforcement Nuclear Regulatory Commission l

Washington, D. C.

20555 (10 Copies)

Mr. A. Rubio, Director Electric Power Research Institute P. O. Box 10412 Palo Alto, CA 94304

[$ //

An Eaual Opportunity Employer