ML20071Q284

Monthly Operating Repts for Oct 1982

ML20071Q284
Person / Time
Site:	Browns Ferry
Issue date:	11/01/1982
From:	Thom T TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20071Q274	List: ML20071Q271 ML20071Q284
References
NUDOCS 8212290287
Download: ML20071Q284 (39)

Text

.

TENNESSEE VALLEY AUTHORITY DIVISION OF NUCLEAR POWER BROWNS FERRY NUCLEAR PLANT MONTHLY OPERATING REFORT October 1, 1982 - October 31, 1982 DOCKET NUISERS 50-259, 50-260, AND 50-296 LICENSE NUMBERS DPR-33, DPR-52, AND DPR-68 G '/ /

/'

em W Subraitted by:/

Plant perintendent l

8212290287 821110 PDR ADOCK 05000259 R

PDR

TABLE OF CONTENTS Operations Summary..

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

3 Significant Operational Instructions.

5 Averge Daily Unit Power Level.

13 Operating Data Reports.

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

19 Plant Maintenance......

22 Field Services Summary..

34

1 Operations Summary October 1982 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 four revisions to previous reportable occurr ences reported to the NRC during the month of October.

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

Unit 2 The unit was in its EOC-4 refueling outage the entire month.

Unit 3 There was no scrams on the unit during the month.

Principally prepared by B. R. McPherson.

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2 Ooerations Summarv (Continued)

October 1982 Fatinue Usave Evaluation The cumulative usage factors for the reactor vessel are as follows:

Location Usage Factor Unit 1 Unit 2 Unit 3 Shell at water line 0.00557 0.00448 0.00388 Feedwater nozzle 0.27208 0.19544 0.14701 Closure studs 0.21555 0.15641 0.12638 NOTE:

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

Common System Approximately 4.67E+C5 gallons of waste liquids were discharged containing approximately 5.75E-01 curies of activities.

l

3 Operations Summary (Continued)

October 1982 Refuelinst Information Unit 1~

Unit 1 is scheduled for its fif th refueling beginning on or about March 18, 1983 with a scheduled restart 'date of July 18, 1983 This.

j refueling will involve loading 8 X 8 R (retrofit) fuel assemblies into the core; finishing the torus modification; turbine inspection; finishing TMI-2

-modifications; post-accident sampling. facility tie-ins; core spray changeout; and changeout of jet pump hold-down beams.

There are 764 fuel assemblies in the reactor vessel.

The. spent fuel J

I storage pool presently contains 52 new fuel assemblies; 260 EOC-4 fuel assemblies; 232 EOC-3 fuel assecblies; 156 EOC-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 1

Unit 2 began its fourth refueling on July 30, 1982 with a scheduled restart date of January 19, 1983 This refueling outage will involve completing relief valve modifications; torus codifications; "A"

low-l pressure turbine inspection; generator inspection; MG set installation for LPCI modification; loading additional 8 X 8 R fuel assemblies into the core; TMI-2 modifications; post-accident sampling facility tie-ins; and changeout of jet pump hold-down beams.

There are no fuel assemblies in the reactor vessel.

At the end of the month there were 248 new fuel assemblies; 764 E0C-4 fuel assemblies; 353 i

E0C-3 fuel assemblies; 156 EOC-2 fuel assemblies; and 132 EOC-1 fuel

4 -

'4 Operations' Su==any (Continued)

October 1982

!Refuelini Information Unit 2 (Continued) assemblies in the spent fuel storage pool.

The present available capacity of the spent fuel pool is 97 locations.

Unit 3 Unit 3 is scheduled for its fif th refueling on or about October 1, 1983, with a scheduled restart date of January 31, 1984.

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

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

The:'e are 280 EOC-4 fuel assemblies; 124 EOC-3 fuel assemblies; 144 EOC-2 fuel assemblies; and 208 E0C-1 fuel assemblies in the spent fuel storage pool.

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

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Significant Ooerational Event Unit 1 Date Time Event 10/01/82 0001 Reactor thermal power at 935 for maintenance on C1 and C2 high-pressure heaters.

0230 Commenced PCIOMR from 935 thermal power.

-0330

. Reactor thermal power at 97%, holding due to maintenance on C1 and C2 high-pressure heaters.

0810 Reduced thermal-power to 91% to remove "A" CCW pump from service due to low oil level.

0830 "A" CCW pump back in service, commenced power ascension.

1 1000 Reactor thermal power at 96%, for maintenance on C1 and C2 high-pressure heaters.

1930 C1 and C2 high-pressure heaters in service, commenced power ascension.

2100 Reactor thermal power at 995, maximum flow, rod limited.

10/02/82 0040 Commenced reducing thermal power for turbine control valve tests and SI's.

0100 Reactor thermal power at 90% for turbine control valve tests and SI's.

0112 Turbine control valve test complete, holding at 90% due to problems with control rod 46-35.

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0137 Reducing thermal power to withdraw control rod 46-35 to position 48.

0145 Reactor thermal power at 85%, contol rod 46-35 withdrawn.

J 0150 Commenced power ascension from 85% thermal power.

0430 Commenced PCICHR from 97% thermal power (Sequence "A").

0630 Reactor thermal power at 99% maximum flow, rod limited.

10/09/82 0048 Commenced reducing thermal power for control rod i

pattern adjustment.

0300 Reactor thermal power at 74% for control rod pattern adjustment.

0330 Commenced power increase 'for control rod pattern adjustment.

0430 Control rod pattern adjustment complete, commenced PCIOMR from 76% thermal power (sequence "A").

2220 Commenced reducing thercal power from 925 control i

rod pattern adjustment.

2230 Reactor power at 88% for control rod pattern adjustment.

2300 Commenced PCIOMR from 88% thermal power (sequence "A").

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'Sinnificant~00erational-Event' Unit 1 Date Time Event 4

10/10/82 0830 Stopped PCIOMR at 955 power to backwash and l

precoat demineralizer.

1030 Holding at 955 power for control rod pattern adjustment.

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1155 Commenced power increase for control rod pattern j

adjustment.

1330 Control rod pattern adjustment complete, commenced PCIOMR from 97% thermal power (sequence "A").

1500 Stopped PCIOMR at 98% power due to problems with

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condensate dcmineralizers.

10/11/82 0007 Reduced thermal power to 96% for control rod pattern adjustment.

0030 Control rod pattern adjustment complete, commenced PCIOMR.

0400 Reactor thermal power at 995, maximum flow, rod limited.

'10/13/82 1700 Reduced thermal power to 95% to pull control rods for core flow adjustment, j

1740 Commenced power ascension from 955 thermal-power.

1800

. Reactor thermal power at 995, maximum flow, rod i

limiued.

)

10/14/82 1350 Reduced thermal power to 97%, when control rod 45-35 scrammed while performing TI-60.

l 10/15/82 0218 Commenced reducing thermal power for scram testing j

control rod 46-35.

j 0300 Reactor thermal power at 79% for scram testing control rod 46-35.

i 0345 Scram test of control rod 46-35 complete.

l commenced power ascension.

j 0430 Reactor thermal power at 995, maximum flow, rod limited.

l 2300 Reduce thermal power to 95% for turbine control i

valve tests and SI's.

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2345 Turbine control valve tests and SI's complete, commenced power ascension.

l 10/16/82 0030 Reactor thermal power at 995, maximum flow, rod l

limited.

l 10/22/82 2345 Commenced reducing thermal power for turbine control valve tests and SI's.

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. st Significant Ooerational Event-Unit 1

'Date Time Event 10/23/82 0100 Reactor thermal power at 95% for turbine control.

valve test and SI's.

0150 Turbine control valve tests and SI's complete, holding for SI 4.1. A.10 (Main Steam High Radiation).

0210 Commenced reducing thermal power when control rod 59 scrammed while performing SI 4.1. A.10. The rod scrammed on "C" main steam 1/2 scram "A" channel.

0400 Reactor thermal power at 87%, holding for SI 4.1.B-10 (Main steam line high rod set point adjustment).

0600 SI 4.1. A.10 performed again after eetpoint adjustment on main steam lines high radiation.

Control rod 38-59 scrammed again on 1/2 isolation on channel "A".

Holding thermal power at 87% for repair of control rod.

0930 Commenced power ascension, control rod 38-59 remains out for maintenance.

1000 Holding power at 97% for backwash and precoat of condensate demineralizer.

1030 Commenced power ascension from 97% power.

1200 Reactor thermal power at 99%, maximum flow, rod limited.

1325 Reactor thermal power at 95% to scram test control rod 38-59.

1343 Scram test complete on control rod 38-59, commenced power ascension.

1400 Reactor thermal power at 99%, maximum flow, rod limited.

10/29/82 2015 Commenced reducing thermal power to remove recirculation MG sets from service for bruch replacement and for a control rod pattern adjustment.

10/30/82 0600 Reactor thermal power at 50% for recirculation pump MG set brush replacement and for control rod pattern adjustment.

0615 Control rod pattern adjustment complete, recirculation pumps MG set brush replacement continues.

0700 Reactor power at 53% for recirculation pumps MG set brush replacement.

1020 Recirculation pumps MG set brush replacement complete, commenced power ascension.

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1320 Commenced PCIOMR from 75% thermal power.

j 1720 Commenced reducing thermal power from 80% for

. control rod pattern adjustment.

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Sienificant Operational Event Unit 1 Date

~ Time Event 10/30/82 1800 Reactor power at 78% for control rod pattern adfastment.

1830 commenced increasing power for control rod pattern adjustments.

10/31/82 0130 control rod pattern adjustment complete, commenced PCIOMR from 845 thermal-power.

2100 Reactor thermal power at 995, maximum flow, rod limited.

l 2400 Reactor thermal power at 99%, maximum flow, rod limited.

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'Significant Operational Event Unit 3 i

date Time Event i

10/01/82 0001 Reactor thermal power at 995, computer limited.

1700 Reactor thermal power at 99%, maximum flow, rod 3.

limited.

A" 10/02/82 0210 Commenced reducing thermal power for turbine i~

control valve tests and SI's.

1 0220 Reactor thermal power at 90% for turbine control valve tests and SI's.

0235 Turbine control valve tests and SI's complete, commenced power ascension.

0300 Reactor thermal power at 95%, holding for SI 4.3.A.2 (CRD exercise).

0330 SI 4.3. A.2 complete, commenced power ascension.

0430 heactor thermal power at 995, maximum flow, rod limited.

t 10/05/82 2155 Commenced reducing thermal power to remove "C"

\\ (, g string high-pressure heater from service for

<g maintenance.

/10/06/82 2220 Reactor thermal power at 875, "C" string i/

high-pressure heaters out of service for maintenance.

2300 Reactor thermal power at 86% for "C" string high-pressure heater maintenance.

2 10/07/82 0830 Commenced power ascension from 86% thermal power.

1400 Reactor thermal power at 96% for "C" string high-pressure heater maintenance.

1500 Reactor thermal power at 955 for "C" string high-pressure heater maintenance.

2245 "C" string high-pressure heaters back in service, commenced power ascension.

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.10/08/82 0310 Commenced PCIOMR from 98% thermal power.

0400 Reactor thermal power at 995, maximum flow, rod limited.

10/09/82 2230 Commenced reducing thermal power for removal of "A" reactor feedwater pump from service for maintenance.

2315 Reactor thermal power at 78% for maintenance on "A" reactor feedwater pump.

10/10/82 1500 Reactor power at 80%, holding for "A" reactor feedwater pump maintenance.

1605 "A" reactor feedwater pump back in service, commenced power ascension.

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11 Sinnificant Operational Event Unit 3 Date Time Event I

10/10/82 1700 Commenced PCIOMR from 85% thermal power (Control Cell Core).

2400 Stopped PCIOMR at 88% due to vibration in "B" recirculation pump.

10/11/82 0500 Commenced PCIOMR from 88% thermal power.

1400 Reactor thermal power at 99%, maximum flow, rod limited.

10/15/82 1150 Reduced thermal power to 97% when control roe 10-35 scrammed.

1310 Reduced thermal power to 75% to set rod pattern for control rod 10-35.

1610 Rod pattern set on control rod 10-35, commenced power ascension.

1830 Reactor thermal power at 99%, maximum flew, rod limited.

10/16/82 0012 Commenced reducing thermal power for turbine 1

control valve tests and SI's.

0100 Reactor thermal power at 955 for turbine control valve tests and SI's.

0142 Turbine control valve tests an SI's complete, commenced power ascension.

0205 Reactor thermal power at 99%, maximum flow, rod limited.

10/20/82 0030 Reduced thermal power to 98% for flux shaping 0035 Increased thermal power to 995, maximum flow, rod limited.

1 10/23/83 0400 Commenced reducing thermal power for turbine control valve tests and SI's.

0430 Reactor thermal power at 94% for turbine control 7

J valve tests and SI's.

i 0515 Turbine control valve tests and SI's complete, commenced poner ascension.

0600 Reactor thermal power at 995, maximum flow, rod limited.

10/30/82 2325 Commenced reducing thermal power for control rod pattern adjustment.

10/31/82 0005 Reactor thermal power at 88% for control rod psttern adjustment.

0030 Commenced power increase for control rod pattern adjustment.

4 12-Sienificant Operational-Event Unit 3 Date Time Event 10/31/82 0100 Commenced PCIOMR from 94% thermal power (Control Cell Core).

0530 Reactor thermal power at 99%, maximum flow, rod limited.

2400' Reactor thermal power at 995, maximum flow, rod limited.

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AVERAGE D AILY UNIT POWER LEVEL DOCKET NO.

50-259 UNIT Browns Ferry - 1 11-1-82 DATE CONIPLETED llY T. Thom TELEPfl0NE 205 729 0834 510NTil October DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (51We Net)

(StWe Net )

1019 1062 i

2 1021 1052 g3 3

1050 39 1061 4

1048 20 1057 5

1050 1059

,g 6

1045 1061 7

1051 1006 33 1046 1070 3

y 9

870 1042 25 10 981 1054 3

1041 1056 1048 1056 12 3

1055 1027 g3 g

34 1048 696 3g i

g5 1062 966 3j 16 1047 s

INSTRUCIlONS On t! ts thritot, hst the,ne'.i.:e.Luh nuit p..c leul i:i \\1W. -% t l'.ir cali.14 tii ihe iepiit tin in..nt ti. ('..nipu't t ai IIIe fiCJTCs! Wlitilt 1110 !.1%.e: f.

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I AVE!tAGE DAILY UNil POWE!! LEVEL

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50-260 I

UNI T Ilr wns Ferry - 2 11-1-02 DATE T. Tho:a C0\\lPLETED IIY TELEPil0NE 205 729 0834

.\\t0NTII October DAY AVEllAGE DAILY POWER LEVEL DAY AVElt AGE DAILY POWER LEVEL t.\\t We-Net )

M we. Net, i

-3

-2 1,,

-2

-2 IS

-2

-2 3

39 4

-2

-2 20 5

-2

-2

-2

-2 6

-2

-2 7

3

-2

-2

,4 9

-2

-2 25

-2

-2 10 c,

-2

-2 i

,,s 12

-2

-2 73 13

-2

~1 29 14

-2

-2 3o 15

-2 33

~2 16 INSTit UCTIONS On ihn t.irniat. ! st the.ncrace dail) :.'ut p..e ci lael ni MWe. Net t.>r each das in the selsiisiin nu, nth. C.iino ite ti Ibe 81eaf 6! W hole it;C'.'t.Ull.

10!77)

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AVE!tAGE 1) ALLY UNIT POWElt LEVEI.

50-296 DOCKET NO.

UNIT Browns Ferry

.3 11-1-82 DATE COMPLE1EI) llY T. Thom 205 729 0834 l

TELEPilONE October MONTil 1

DAY AVER AGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL t MWe NetI (Mwe.Nei g i

1062 1055

7 2

1033 1060 g3 3

1052 1061

,9 1049 1057

,o 1051 1055 5

1037 1060 6

954 1056 7

,3 1025 1078 3

9 1036 1042 25 to 816 1064

,6 4

11 998 1063 27 1046 1063 l,

28 g3 1057 1063 39 13 1059 1059 39 1041 1039 33 3,

16 1042 INSTRUCIlONS On this f orm'a1. !:st t he ate a e d.nh.mt p..ur laci n- \\lL-Wt tiir each i!as in the s qs.iitin ni.iuli. t 'ieiniints to i

I!10 fleJTe\\t Wlltele indg.1*g.a: 1.

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16 OPERATING DATA REPORT DOCKET NO. 50-259 DATE 11-1-82 CO31PLETED ItY T. Thom TELEPilO.NE 705 779 0834 OPERATING STATUS Er wns Ferry - 1

. Notes

1. Unit Name:

2. Reporting Period:

October 1982 3293

3. Licensed Thermal Power ( A!Wt):

1152

4. Nameplate Rating (. Gross 31We):

1065

5. Design Electricalllating (Net A!We):

1090'0

6. 31aximum Dependable Capacity (Gross 31We):

1065

7. 31asimt"n Dependable Capacity (Net 31We):

8. If Chan;;es Occur in Capacity Ratines (Items Number 3 Through 7) Since Last Iteport. Giie Itcasons:

NA

9. Power Lesel To Which Restricted. If Any (Net 31We):

10. Rea3ons For Restrictions. !f Any:

NA Thi3 Month Yr.-t o-Da t e Cumulatise 745 7,296 72,338

11. Ilours In Reporting Period

12. Number Of Ilours Ileactor Was Critical 745 6,737.12 46,051.92

13. Reactor Reserve Shutdown llours 0

405.98 5,621.18

14. Ilours Generator On.Line 745 6,675.52 45,105.69

15. Unit Resene Shutdown lloon 0

0 0

16. Giuss Thermal Energy Generated (MWII) 2,455,054 20,716,370 127,591,277

17. Gross Electrical Energy Generated (albil) 784,240 6,731,940 42,024,390

18. Net Electrical Energy Cencrated (MWil) 764,355 6,539,917 40,808,826

19. Unit Senice Factor 100 91.5 62.4 100 91.5 62.4

20. Unit Avadability Factor

21. Unit Capacity Factor (Using MDC Net) 96.3 84.2 53.0 96.3 84.2 53.0

22. Unit Cap. wily Factor (Using DLit Net)

23. Unit l'orced Ontage Rate 0

8.5 24.8

24. Shutdowns Scheduled Oser Nest 6 Months (Type. Date, and Duration of Fach t:

25. If Shui l)own At End Of Report Period. latimated Date of Startup:

26. Units in l~est Stains (Prior io Commercial Operation):

Forecast Achiesed INil I \\ L Cllli ICAl.II Y INil~l AI. I LEC lit lCil Y CO\\l\\ll:RCI \\I. OPl.It \\ IlON i

t (9/77)

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OPERATING DATA REPORT E

DOCKET NO.

50-260 DATE _11-1-82 CO31PLETED BY T. Il m TELEPl!ONE 205 729 0834 OPERATING STATUS N"'*'

1. Unit Name:

Brcuns Ferry -2

2. Reporting Period:

October 1982 3293

3. Licensed Thermal Power (.\\iht):

1152

4. Nameplate Rating (Gross Slwe):

1065

5. Design Electrical Rating (Net 31We):

i 1098.4

6..\\laximum Dependable Capacity (Gross 31We):

1065

7. 31aximum Dependable Capacity (Net 31We):

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

NA i

NA

9. Power Lese! To Which Restricted. If Any (Net.\\lwe):

10. Reasons For Restrictions. If Any:

NA 1

This J.lonth Yr.-to Date Cumulative i

11. liours in Reporting Period 745 7,296 67,279

)

12. Number Of !!ours Re3ctor Was Critical 0

4,846.51 43,293.47

13. Reactor Reserve Shutdown llours 0

203.06 13,684.82

14. Ilours Generator On-Line 0

4,778.36 41,975.45

15. Unit fleserve Shutdown llours 0

0 0

16. Gross Thermal Energy Generated 131Wil) 0 13,827,550 120.480,340 17 Grow Electrical Energy Generated (N!Wil) 0 4,592,260 40,024,908 0

4,450,929 38,873,07)

18. Net Electrical Energv Gener.ited 151%II)

19. Unit Senice Factor 0

65.5 62.4

20. Unit Availability Factor 0

65.5 62.4

21. Unit Cap.icit3 Factor t Using ilDC N t) 0 57.3 54.3 22 Unit Capacity Factor (Using DER Net) 0 57.3 54.3 l

0 5.5 27.1

23. Unit Forced Outage Rate

24. Shutdowns Scheduled Oser Nest 6 ilonths tT)re. Dale ami Duration of rachi-

25. If Shut Down At End Of Report l'eriod. Estimated D.ite of Startup:

January 1983

26. Units in Test Status t Prior io Commercial Operationi:

Foiecast Acluesed INITI \\ l. C RI FICAll ! Y INI FIT 1. El.I C11:lCl 1 Y CO\\1\\ll RCI \\ L OPi !! A IlON 08/7D

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OPERATING DATA REPORT DOCKET NO.

50-296 DATE 11-1-82 COhlPLETED LtY T. Thom TELEPl!ONE ~203 /zy 0834 I

OPERATING STATUS

1. Unit Name:

Browns Ferrv - 3 N"'*5 October 1982

2. Reporting Period:

3. Licensed Thennal Power (5tht):

3293

4. Nameplate Rating (Gross.1We):

1152 1065

5. Design Electrical Rating (Net 31We):

1098.4

6. 31nimum Dependable Capacity (Gross 31We):

1065 I. 51anaum Dependable Capacity (Net.\\lwe):

S. If Changes Occur in Capacity Rating iitems Number 3 Through 7) Since Last Report. Gi'e Reasons:

NA

9. Power Lesel To Which Restricted. If Any (Net.\\lWep NA NA

10. Reasons For Restriction >. !f Any:

This 5!onth Yr.-to Date Cumulative 745 7,296 49,704

11. Ilours in Reporting Period

12. Number Of !!ours Re>ctor Was Critical 745 3,681.30 -

36,148.28

13. Reactor Reserte Shutdown flours 0

1,230.62 3,372.15

14. Ilours Generator on.Line 745 3,559.28 35,310.06

15. Unit Resene Shutdown lluurs 0

o o

16. Gross Thermal Energy Gererated (51Wlh 2,403,910 10,921,148 104,779,768

17. Groo Elcetrical Energy Generated (\\lWII) 794.050_ _,

3,536,840 34,535.030

18. Net Electrical Energy Generated (MWih 774*649 3,424,654 33,512,700

19. Unit Service Factor 100 48.8 71.0

20. Unit Asailability Factor 100 48.8 71.0

21. Unit Capacity Factor (Using stDr Nei, 97.6 44.1 63.3

22. Unit Capacity Factor iUsing DER Net) 97.6 44.1 63.3

23. Unit Forced Outage Rate 0

26.8 18.0

24. Shutdowns Scheduled Oser Nest 6 Months t ry pe. Date.and Duration of I ach t:

1

25. If Shut Dowis At End Of Iteport Period. Estimated Date of Startup:

26. Units in lest Status it'rior to ronunercial Operation):

l'or ceast Achiesed INI I I \\ L CRI I ! cal.1I Y

!N!!! \\l. El I C1 RICITY CO\\1\\ll RCI \\ L Ol't.R ATION e

(kII)

I.

In DOCKET NO*

50-259 UNIT S!!UTl) OWNS AND F0WER REDUCTIONS UNIT N AM E Browns Ferrv-1 DATE 11-1-82 COMPLETED !!Y I'.

'I hcI?_

RI:l'OR1 MONT!! OC'I,OB ER TELIPI ONE 205 729 0834 i-m 52

'h k h." i 1 icen see Ej.,

h"t C. ruse & Curreet he 3g

?.

ji s 5 ITei t 9!

f ~i Attron to L

D.n e 5

E 5, 5 Repor t i., O E*

Present Recurrence 4

e o

d 241 10/09/82 S

II Derated for control rod pattern adjustment 242 10/15/82 F

B Derated to scran test control rod 46-35 243 10/29/82 F

B Derated for recirculation pump MG e

set brush replacement and control rod pattern adjustment

_ 1*

i 2

3 4

il 1.uce 1 Reason Method:

I xhibit G -Instructions S-5. hat u!cil A-l'qu ;'rnert F.:ilu:c (I splain) 1 -M an ual for Prep u.iti n of Data li.Maintenan.c of Test

. Manual Scram, i.nto Sheets fo: Li.co s -

C Refachn;:

3-Autorn.itic Suarn inent Report t1.l:10 I ile (NURI G-D.R u!ar Jr3 Rest ri;iin, 4-Ot her (INplain )

0101) 1 -0;-::ater Jr.inung i lAcase I sanen. tion F-Adnutust rai r..

5

(; Oper anonal 1.i r or (In p!.na) l'shibit t. Same Smuce tu!77)

II Other (lisp ain)

s W8 DOCKET NO.

50-260 UNIT SilUTDOWNS AND POWER REDUC 110N5 UNIT NAM E Browns Ferry -2 DATE 11-1-87

}

g 0834 COMPLfi RI:!'OR T MON ill OCTOBER 5

E

!?

"h

~ Yl I.icensee

.E t,

{%

Cause & Correetive s,4

_@ y 5 Event 37 g3 Adion to No.

Date 3?

35,5 Report c tr. O E'

Prescut Recurrence j5 H

e u

6 243 10/1/82 S

745 H

2 EOC-4 Refuel Outage continues wo i

2 3

4 I: I orsej Ream:.

Method :

Exhibit G Instructi nis S

S, h e<!.i!e ti A-1: juipment Failure ( Explain)

!.Ma nual for Prepaution of Dat.:

It. Maintenance of Test

2. Manual Scra m.

Entry Sheets for Iicemee C. Refueling 3-Autom.itie Scrant.

Esent Repost I t.11:n I ile (NURI.G.

D. Regulatory Restriction 4-Other ( E xplain) 01611 I..Opciator Training & Iisense lhamination

f. Ad minist ra t i.e 5

GUperatonial 1 iror (INplai.i)

Ex!nliit I S une Somce (9/77)

Il Orl:er ( E xplant) e e

~'

A DOCKET NO. 50-296 UNIT S!!UTDOWNS AND POWER REDUCTIONS UNIT N AM E B rc'?ns Forre - 3 DATE 11-1-82 COMPLET ED !!Y L_ _lhom REl' ORT MON ill OCTOBER El.LPIIONE 205 729 0814 4

m

=_

-i 3

, -o :=4 I Ac nsee

.5 1, c%

(,anse & Currective c

ae

=

$ ~f No.

Date i

3?

4

.s s 5 I:wns a 'g c

At ti,,n t o 5E 5

3 ;f, =

ReporI -

rE U S'

Prevent P.ecurrence O

-4c 113 10/09/82 F

B Derated for "A" reactor feedpump maintenance 1 14 10/15/82 F

H Derated to set rod pattern for control rod 10-35 i

m.

e-i i

2 3

4 i

F: Forced Reau m :

Method:

Exhit+it G -Instructions J

S. S,heduled A.lign:pment Failure (Explain) 1 -Manual for Preparation of Data It Maintenance nilest 2-Man ual Scram.

Entry Sheets f or 1 ieensee 1

C. Refueling 3-Automatic Stram.

Esent Report (LI:R) File (NURI.G-D.Regu!atory Restrictem 4 01her (Explain) 0161l 4

I. Operator Training i I.i.cose l'samina' ion F Adn:inistrati.e 5

G Operational Etrut (Explam)

I shibit 1 Same Soune 08/77) 11 Other (L> plain)

I i

(

. :;rTCH:. ;r t'A !:; ERU;CE SUM..ARY s S N 17'.!! !M-J'-

F r.i

?-

P M : 1:i C F October 19 82

~

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CF G I' E 1.A T : c.: c?

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r ~r e... ;.,.,;.~ s---

2

. ***-~O-

. '. ' sa.'

'_ _1_

1-4 3

PS-3-74B Replace None Age Non-Linear None

>- 17 APRM Relay K 15 Replace None Faulty relay Invalid Alarm None 1

. 2._

~13 APRM Function Replace None Faulty Switch Erratic Switch Actior. None Selector Switch

-1.1 APRM TR-68-2 Repair None Failed Theroo-Incorrect Indication None l'

couple

-3. l'

-1] 76 H R-76-37 Repair None Failed Chart No Chart Drive None 2

Drive Gear w

N

-15 64 PS-64-56C Replace None Faulty Switch Instrument Drift None O

n.

O e

D 4

PROW:iS FEBRY UUCLEAR PiltNT Uf!IT I

PJ:CI/.liICAL PAINTE:DJ1CI-: SUt :MRY 3

C::SC ErUTP:tp:T For the !!onth of October 19 82

.. I 1

EFFECT 0:: liAFE 1,CIION TAFJ;l CACOR OF RESULTS OF TO P:GCLI DE iTr.

1:YSTE 1 CCM?O;!d!

• .\\1Ui1E OF ordrA tit'

  : 07 l'_11:;i'E' ANL2 THY REACTOR

'j.! ?U::CT IO';

aLFliTCTIO::

RFet!iGP :c2

~

24 LPCI LPCI MG Set 1DA beacings noisy none faulty bearings MG set not running replaced bearings on properly motor end of flywheel "D".

I a

TRil 296723 23 1.PCI

,LPCI MG Set 1DN bearings noisy none faulty bearings MG set not running replaced "C" flywheel properly bearing, packed coupling and bearing with pt ner grease TR# 331823 i

4 to t,a 4

4 i

i I

se i,

l f'

I t

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I l

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,-.-,--4

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1;ROWNS FERRY NUCLEAR PIM4T UNIT 2

IEcnANICAL :nILTE::ANC : SUM >tilW CSSC 1:ruTatxt;r I'or the :! oath ei October 19 82

~~~~;

EF FF.Gi 0;;..ld-ACTIW TA:G;I a'.,

S T S 'J:'

CC:!PONEU t IL\\TURE OF OpgnATIO:: o!'

CAUSE OF RESULTS OF

• 10 P:GC1.t!DE

]

nI:, JEN .. c.

TH: R F.i C h'R MI 'cT :CTIC'!

IL(1 FU"CTIC !

RFC N'":CZ 1

L

-28 CRD

.iodule 02-39 solenoid valve none set screw seat valve not functioning replaced valve Valve 85-40A bad worn out properly lTR# 312540 f

i

=

0-7 CRD Efodule 18-35 faulty valve none worn valve valve not functioning changed out solenoid

' solenoid valve properly valves TR# 244858 0-6 Fire

2nd floor col.

pin hold none unknown water leakage welded hole in fire Protection!line R12 T-line causing leakage protection line

{from"B"RUCU TR# 274745 pump

-21 Fire Q" line 2nd

crack in fire none unknown pipe deteriorate'd and welded hole in fire Protectionfloor Rx. b1d.

protection ling cracked

, protection line ht end of RBCCU TR# 317481 heat exchangers y

l

-25 RHR FCV-23-57 faulty seal none faulty worn grease valve not functioning replaced greased Service seal on operator properly seal k'a t e r valve TR# 337855 0-5 CRD Module 34-39 moving drift none seat ruptured module not functioninL; replaced seat disc, past "00" properly retainer & gaskets positica TR# 312564 m

l

?

r i

1, e

BROW:iS FERRY I:UCLEAR PLANT UNIT 3

1iEC';ANICAL MAINTE::ANCI: SU 01ARY CSSC l'rUI.rME:. i 4

82

..er the

.ont.n or-October 1o.

A'I1UU IAE1 I

~~

' ~ j

? EFFECT 0:1 SAI'E CAUSE OF RESULTS Oi

O PRECLUDE V..

SYS T ~:1 COM 'C::.1

!!ATURE OP Ol>ERATION OF

'A T ::TF.': ' ';Ch TIi2 REACTOR

liLFU'.:CTIO!!

PALIT::CTIR!

RECUMEI;CE J

._.p_.__.____.

, >~15{ CRD Module 10-35 faulty valve none pilot valve worn valve non-functional installed new repair.

scram pilot out kit, c:-:haus e. diaphragn "B" valve and pressure.dia-phragm TR0 276280

-29 D/G D/G 3ED problems with none slipping frict, ion cannot load up gener-changed out governer mechanical drive plate past ator TR# 249617 governor 045

-24 D/G DG 3C fil Air air leak none in-line valve 1/8" copper line leak-replaced in-line Compressor i

faulty ing at ferrule fitting check valve TR# 274486 i

-29. Radiation C.ul 3-90-251 handle nissing none unknown handle off replaced handle y

Manitoring on CAM TR# 216615 v'

-21 I.PCI LPCI MG Set faulty seal none coupling seal bad seal replace seal, lube 3DN worn out with Koppers HP grease TR# 312568 j

1-20.D/G DG A Air Comp.

faulty air none blown head gasket air Icak replaced head gasket s

f f

1. 2 compressor TR# 274678 l.

O I

i 4

i j

t i

I 4

-_..___-,,. -._.- _,___...- _.. __,.--.... - ~._.,, - __ _...,_..-,..-.,,_ _-.,~.

BR0h7S FERRY NUCLEAR PLANT UNIT 1 and Common Page 3 Appendix B CSSC EQUIP'1ENT ELECTRICAL MAINTENANCE S10C!ARY 9/29/82 For the Month of October 19 82

~

Effeet on Safe Action Taken

ature of Operation of Cause of Results of To Preclude pate Svstem Component

'fa in tenanc e The I:cactor Malfunction Malfunction Recurrence 10/4/82 Fire K-2 relay in During the per-None, heat, Bad relay, con-Required panel 1 A roving fire Protec-panel 1 formance of smoke, and flow tact 9-10 of K2 334 to be taken out watch was estab-tien 334 S14.11.C.3&4 detector oper-relay failed to of service for re-lished, the relay local panel ability wa's not remain closed.

pairs.

was replaced and 1-25-283 was affected.

These normally the SI successfully put in alarm closed contacts corpleted.

condition.

are used to TR #300553 Central panel supply AC power TR #317524 1-25-334 did for circuit not alarm.

supervision and test functions to only.

e 10/7/82 Fire Fire alarm Survey of re-None Relay retainihg Prompted survey of Replaced missing Protec-panel plugin taining clips clips were found firealarm panels with and tightened tion relay retain-as a result of out of position similar mounting loose relay retain-ing clips.

LER#BERO and missing.

arrangement.

Ing clips in unit 259/8267 dated 1, 2, and.3 fire-9/1/82.

alarm panels. 'Ref.

DFRO-259/8267 TR #225370 0/10/82 Fire Pro-Smoke detector Operators ob-1:one Increased detec-The false alarm in-The bad smoke de-tection XS-39-27A served a smoke tor sensitivity.

itiated by XS-39-27A tector was replaced alarm on panel would have masked and the new detec-9-20.

Smoke signals from detector tor successfully detector XS-XS-39-27B which is test per S14.11.C.39-27A alarmed required to be oper-1 & 5.

and would not able.

TR #266927 clear.

LER#EFRO-50-259/

8285

. i

1. E BROWNS FERRY NUCLEAR PLANT UNIT 1 and Common u IL.30 CSSC EQUIPMENT ELECTRICAL MAINTENANCE SU[ DIARY Appendix B 9/29/82 For the Month of October 19 82 Effect on Safe Action Tal:en Nature of Operation of Cause of Results of To Preclude Date System Connonent Maintenance The ficactor Malfunction Malfunction Recurrence 1

0/13/82 Diesel D/G D governor While perform-None, two off-J During trouble-Diesel generator.D SI 4.9.A-1. Supple-Generator:

control cir-Ing SI4.9.A-1 site power shooting, the was inoperable.

ment A was success-cuitry.

Supplement A, sources were diesel generatort fully performed and the control availabic and mode switch was the diesel genera-room operator all of the CS operated several tor returned to was unable to and R!iR systems times. These

service, manually in-and the remain-operations cor-TR (!245345 crease the ing three units rected the prob-LER(lBFRO-50-259/

diesel genera-1 and 2 diesel lem.

A visual 8280 ter speed.

generators were inspection was operable.

made of the mode i

switch and the OMRD4 relay con-w tacts involved in this circuitry i

with no problems found. The prob-lem is believed to have been caused by slight-ly dirty con-l tacts.

i 0/14/82 Core Spra:

FCV-75-22A During the per-None Valves were out The valves were The valves were Cooling FCV-75-50A formance of SI of timing cali-slightly slow in timed and success-4.5.A.l.C FCV-bration.

closing.

fully tested per 1-75-22A and EMI 18.

FCV-1-75-50A TR #196582 I

failed to meet TR #196583 the required LERf/BFRO-50-259/

)

closing time 8279 of 30 seconds.

4 1

1 and Cbmmon M

BROWNS FERRY NUCLEAR PL NT UNIT CSSC EQl'IP:!ENT ELECTRICAL MAINTENANCE SUdfARY Appendi:< B 9/29/82 For the Month of October 39 82 Effect on Safe Action Taken Nature of Operation of Cause of Results of To Preclude

_pate System Companent Maintenance The Reactor Malfunction Malfunction Recurrence O/23/82 CRD FSV 85-39B Control rod 38-None, this pilot Bad coil on the FSV 85-39B inoper-The bad solenoid (38-59) sol-59 scraruaed valve failure pilot solenold.

able.

coil was replaced, enoid valve during !j scram could not have the rod was (scram channel SI 4.1.A.10.

prevented scram, successfully test.

"B" pilot Rod could be TR t/291651 valve) moved with nor-nal CRD pres-sure.

9 N

00 4

9

?

e

• O

f l

1 and dommon Page 3 DROUNS FERRY NUCLEAR PLANT UNIT CSSC EQUIPMENT ELECTRICAL MAINTENANCF, SUd4ARY Appendix B l

9/29/82 l

For the Month of October 19 82 Effect on Safe Action Tahen Nature of Operation of Cause of Results of To Preclude Wte Svstem Conronent Maintenance The Reactor Malfunction Malfunction Recurrence J/14/82 CRD CRD 46-35A CRD 46-3SA None Bad solenoid CRD 46-35 scrammed.

The had solenoid scram sole-scrammed from

coil, coil was replaced noid valve.

position 48 to with coil from 00 on a half unit 2 CRD 54-31B.

scram on "B" The CRD operated channel.

properly.

TR #245334 TR #317583

~

3/22/82 4-kV Shut-Degraded During the per-None, the other Relay sensitive The degraded voltage The relays were down voltage formance of 2 degraded volt-to temperature relays operated at recalibrated to y

beards relays.

recurrence con-age relays on variation is 3885 and 3897 volts the correct set-and busse:

trol calibra-each board were suspected.

as opposed to the points. The set-tion (BFRO operable, the required 3900 to point drift probler 296/8213) of loss-of-voltage 3940 volt range.

is now being evalu-degraded volt-relay channel or ated by TVA Engine-age relays (SI each board was ering Design and 4.9.A.4.C) de-availabic and will be addressed graded voltage operable.

in a revision to relays 27-211-BFRO-50-259/8213 1C en 4-kV by 3/1/83.

Shtd. Bd. "A" TR #196580 and 27-211-2C LER#BFRO-50-259/

on 4-kV Shtd.

8286 Bd. "B" were found to oper-ate slightly below the re-quired 3900 to 3940 volt rangr

1 and U nmon ge 3 BROWNS FERRY NUCLEAR PL NT UNIT CSSC EQUIP:!ENT ELFCTRICAL MAINTENANCE SUd!ARY Appendir. B 9 /29 /8.,,

For the Month of October 19 82

~~~

Effcct on Safe Action Taken Nature of Cperation of Cause of Results of To Preclude jia te System Co:ponent Maintenance The Reactor Malfunction Malfunction Recurrence 0/24/32 RilR "1DA" LPCI The M/G set None, it has The erratic out-Erratic output volt-The voltage regu-M/G set volt-output voltage been determined put voltage was age.

M/G set was lator was replaced, age regulator, uns erratic.

that C8 capaci-due to the full-taken out of service adjusted, and tor f ailure doe:

ure of feedback to replace the volt-nonitored. The not make the capacitor C8 in age regulator.

voltage remained generator inop-the voltage stable. Similar crabic.

regulator.

failures have been analyzed by the Louis Allis Cocpany This analysis show-ed that the failurq of capacitor C3 g

would not have a significant affect on the generator output. Ref. LER

1. BFRO-50-296/8152 R1 TR #266954 LER#BFRO-50-259/

8287

)/24/82 RilR

" LEA" LPCI Generator out-None M/G set voltage Generator output Adjusted the volt-M/G set volt-put voltage regulator was voltage was high.

age regulator to age regulator, high.

out of adjust-an acceptable volt-ment.

age,(490 volts) ansi nonitored. The voltage remained stable.

TR #266953 9

BROUNS FERRY NUCLEAR PLANT UNIT 2

1. 0 7

7g 39 CSSC EQUIPMENT ELECTRICAL MAINTENANCE SU$1ARY Appendix B 9/29/82 For the Month of October 19 82 Effect ca Safe Action Taken Nature of Operation of Cause of Results of To Preclude Date i

Syr, ten Co monent Maintenance The Henctor Malfunction Malfunction Recurrence

! /29/82 RPS Relay 5AK-10K During inspec-None, relays had Design, Ref. DPM Cracked coil spools.

The relay coils located in tirn of relays not failed.

N74M13 were replaced and panel 9-16 (with Lexan the relays success-(Turb. stop coil spools) fully tested.

l l

viv. close these relays TR #241422 scram trip) were found to TR #241423 and relay 2E-have cracked K14 located in coil spools.

pnl. 9-30 (auto. blow down) d.

i

//6/82 SEGT FS-65-20A and During the per-None Bad flow switches SEGT Train A.inoper-Repla ed FS-65-20A FS-65-203 foraance of SI FS-65-20A able.

and Ff-65-20B and 4.2.A.13 on FS-65-20B successfully com-SEGT trains A, pleted SI4.2.A.13.

B, and C, FS-TR #252147 I

65-20A & B failed to g

operate proper-ly.

4 I

i e

ge 3 EPOUNS FERR* NUCLEAR PLANT UNIT 2

g 30 CSSC EOUIP:1E"T EllCTRICAL MAINTENANCE SU5!ARY EE " ~

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

__t h r e Evstem Component Maintenance The licactor Malfunction Malfunction Recurrence l )/19/82 CRD Accumulator During the per-None, unit in Level switch for The listed two pres-The pressure and level switches formance of EMI refueling outage CRD 42-07 ground-sure switches and level switches for CRD's 46-50 the listed ed, broken wire two scram accumulator were replaced and 19 and 42-07.

conponent items (grounded) on CRD level switches were tested per EMI 50.

Pressure failed.

46-19.

Pressure inoperable.

TR #317591 switches for switch grounded TR #31/592 CRD'd 42-07 on CRD 38-07, TR #317594 and 38-07.

pressure switch TR # 317597 corroded (inop-erable) on CRD

,f 42-07.

U O

8 BROWNS FERR ' NUCLEAR PLANT UNIT 3

F EMSIL 30 CSSC EQUIPMENT ELECTRICAL MAINTENANCE SUNMARY Appendix B 9/29/82 For the Month of October 19 82 l

l Effect on Safe Action Taken Nature of Operation of Cau se of Results of To Preclude

_1)a t e System Cormonen t Maintenance The Peactor Malfunction Malfunction Recurrence l

l )/20/82 Diesel "3C" D/G ann-Received a "4-None Loose annuncia-Received a false Realigned and l

Ceneratort unciator cir-kV breaker tor circuitry annunciation.

tightened card, l

cuitry en pnl. 1832 and 1834 card.

annunciator oper-l 9-23C.

overload" ann-ated properly.

unciation.

TR #274685 l

l l

e I

w l

t l

1 e

f l

e r-

-.c-. - - - - - - - -,

v,

=_

34 s

FIELD SERVICES

SUMMARY

October 1982 Maior Work Areas

. A.

Refuel Area The jet pump hold-down beam replacement and fuel inspection program were started during the month of October.

The jet pump hold-down beam replacement has not proceeded as projected primarily due to deconning delays and GE tooling inspection problems. This work is currently 10-percent complete. The fuel inspection program is approximately 100-percent completed but no firm direction has been determined at this time.

B.

Turbine During the month of October, work on the turbine floor was centered around completion of magnarlux testing of LP turbines, RFWP turbine 4

"A" and the shrunk-on-wheel inspection of the LP "A" and "B" spindle.

This work was accomplished and the repairs that were necessary, based 4

on the magnarlux test, are 95 percent complete.

As of this writing final results from the shrunk-on-wheel inspection have not been received from GE.

In addition to the above work, all valve work and inner cylinder horizontal joint weld repair was accomplished plus 90 percent of the diaphragm weld repair.

One area that continues to be a logistical problem is not having the ability to move equipment / components from one unit to the other due to the. breezeway being cluttered with material.

Resolution of the disposition of the contaminated sand would provide a good deal of additional room.

l l

- =, _..,

35 j

t FIELD SERVICES

SUMMARY

-October 1982 i

Maior Work Areas (Continued)

C.

Electrical The major work items during the past month have been in support of the unit 2 cycle 4 outage.

The 2B transformer was prepared for shipment to the PSS for repair; preparations were completed for making 1B transformer ready for tie-ins in mid-November; maintenance work for I

recirculation pump motors A and B is complete except for EMI 81 on 2B; i

P0392 framework fabrication is. complete and ready for setting at its l

l location; P0129 removal of signal sensors is finished; PO426 feedwater f

control power supply modifications were completed; and MOV limit 2

switches for valve limit torque circuitry has been worked. On going activities include: LPCI conduit / baseplate work and setting of MG

[

sets continues; EMI-71 motor maintenance is at 89 percent, EMI-7 breaker maintenance is at 95 percent, and these items are being worked as systems availability allows; recirculation pump MG set maintenance is approximately 87 percent and expected to be completed in about I

three weeks; unit 2 emergency lighting is 33-percent complete and on hold for manpower diversion; cable pulls for P0392 were initiated and is parallel activity with conduit work.

At present all P0392 work plans have been approved for work, but there have been some delays in obtaining materials. LPRM reconnection work is in progress.

P0089 i

ILRT connector penetrations is underway, P0126 replacement of switches t

with transmitters is being worked in conjunction weith P0392 i

electrical activities; and P0590 unit 2 control room overhead light modification has started and is approximately 33-percent complete.

[

9 36 i

FIELD SERVICES

SUMMARY

October 1982 Maior Work Areas (Continued)

D.

Mechanical The CRD changeout was completed during the early part of October.

With the completion of CRD changeout, the CRD system was tagged out for tie-in work on SDIV modification and CRD flush connection.

During October all 6-inch, 2-inch, and 1-inch pipe removal and removal of SDIV (west header) was completed.

Installed SDIV's (east and west header) and completed 12 of 19 6-inch X-ray welds.

As of this writing.

the 12 welds had not Leen X-rayed.

Hanger work associated with P0392 was also worked this month.

The MSIV work continued with primary.

j emphasis being placed on valve disassembly, poppet decontamination, O

and work plan and procedure preparation.

Welding of poppets and i

poppet guides commenced on October 30; however, weld rod problems have slowed progress on getting the poppets ready for installation.

The balance-of-plant work continued with waterbox expansion joint maintenance, RilR heat exchanger tube cleaning and snubber replacement, rebuilding, and testing.

Local leak rate testing is approximately 70-percent complete, with 14 valves that have not had initial test and 27 valves that require retest. Welding Services, Inc., is performing work on the MSRV vacuum breaker tees and the "M" and "N" tailpipe installation.

The "M" and "N". tailpipe work is just getting underway due to the work plan not i

i getting approved until October 15.

(Revisions required because of differences in TVA and Welding Services weld procedures).

l l-

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..j_

. P-7

,s 3

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+

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37

.,e-yg

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- 3 m

FIRLn SERVICES

SUMMARY

a p

t

?

y; 3 October 1982 4

g J' h gj u

-y Maior Work Areas (Continued)

[,

i D.

Mechanical (Continued) j y ;j J

i 3

x On the vacuum breaker tees Welding Services has completed: six welds.

.y X

)

v 1:

On the six welds, all were X-raped and one weld'will' require rework.

y ',

<f

'a

e The critical path for Welding Services has prevented the 700 mitred j l

N s

elbow and the tailpipe supports in the vent header.

.t i

i; E.

Modifications

),

Reviewed work plans in support of the unit 2 cycle 4 outage.a '"j, b, I -

li

. i.

Expedited the solution of modification-related problems through EN DES (p

u via Chattanooga Field Services modification group.

Started 4<

preparation work for unit 1 cycle 5.

F.

Torus 1

During the month of October, the scheduled worklcsd in the torus h'

steadily increased, but manpower remained approximately 25-percent i

t below scheduled numbers.

As a result, some jobs f ell behind's'hedule such as: tie-bars, 18-inch RHR modifications, 24-inch HPCI l modifications, 10-inch core spray'modificitSons, RHR spray header 5

supports, and wonderbox.

Every effort is conceiltrated to complet5 T?

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bsys 5 thru 14 on schedule in order to start the subcontractor n painting as planned.

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