ML20042A448

Monthly Operating Repts for Jan 1982

ML20042A448
Person / Time
Site:	Browns Ferry
Issue date:	02/01/1982
From:	Thom T TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20042A446	List: ML20042A445 ML20042A448
References
NUDOCS 8203230428
Download: ML20042A448 (36)

Text

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TENNESSEE VALLEY AUT110RITY DIVISION OF POWER PRODUCTION BROWNS FERRY NUCLEAR PLANT MONT!ILY OPERATING REPORT January 1, 1982 - January 31, 1982 DOCKET NUMBERS 50-259, 50-260, AND 50-296 LICENSE NUMBERS DPR-33, DPR-52, AND DPR-68 1

Submitted By: [f' '- - '

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TABLE OF CONTENTS Operations Summary . . . . . . . . . . . . . . . . . . . . . . 1 Refueling Information . . . . . . . . . . . . . . . . . . . . 3 Significant Operational Events . . . . . . . . . . . . . . .'. 5 Average Daily Unit Power Level . . . . . . . . . . . . . . . . 12 Operating Data Reports . . . . . . . . . . . . . . . . . . . . 15 Unit Shutdowns and Power Reductions. . . . . . . . . . . . . . 18 Plant Maintenance . . . . . . . . . . . . . . . . . . . . . . 21 Outage Summary . . . . . . . . . . . . . . . . . . . . . . . . 36

1 heratens_Sgma_ryr January 1982 The following summary describes the significant operations activities during the reporting period. In support of this summary, a chronological log of significant events is included in this report.

There were 16 reportable occurrences and four revisions to previous reportabic occurrences reported to the NRC during the month of January.

Unit 1 There was one scram on the unit during the month. On January 26, the reactor scrammed from a falso reactor high pressure scram signal when personnel erecting a scaffold dropped a tool on an instrument panel.

Unit 2 There were four scrams on the unit during the month. On January 1, the reactor scrammed on a high range trip from two IRMs because of a rapid insertion of reactivity caused by the continuous withdrawal of a control rod (from 04 to 14).

The reactor scrammed on January 1 due to a turbine trip caused by a broken stem in a high level control valve on a moisture separator giving a high level signal.

On January 2, the reactor was manually scrammed due to high leval problems in a moisture separator caused by the same high level control valve as the January 1 scram. The reactor was scrammed on January 5 for maintenance on bad condenser tubes. The tubes were erroded by main steam because bypass line condenser diffuser boxes failed.

Unit 3 The unit was in its EOC-4 refueling outage the entire month.

2 Operations Summary (Continued)

January 1982 Fatigue Usage 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 0.00527 0.00432 0.00361 Feedwater nozzle 0.25113 0.18767 0.14108 Closure studs 0.20920 0.14460 0.10977 NOTE: This accumulated monthly information satisfies technical specification section 6.6.A.17.B (3) reporting requirements.

Common System Approximately 1.57E+06 gallons of waste liquid were discharged containing approximately 1.90E+00 curies of activities.

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3 Operations Summary (Continued)

January 1982 Refueling Information Unit 1 Unit 1 is scheduled for its fifth refueling beginning on'or about March 4, 1983, with a scheduled restart date of June 3, 1983. This refueling will involve loading 8 X 8 R (retrofit) fuel assemblies into the core, finishing the torus modification, turbine inspection, and finishing TMI-2 modifications.

There are 764 fuel assemblics in the reactor vessel. The spent fuel storage pool presently contains 260 EOC-4 fuel assemblics, 232 EOC-3 fuel assemblies, 156 EOC-2 fuel assemblies and 168 EOC-1 fuel assemblies. The pre-sent capacity is 1148 locations. Modification work and testing is in progress to increase the spent fuel pool capacity to 3471 assemblies.

Unit 2 Unit 2 is scheduled for its fourth refueling beginning on or about July 30, 1982, with a scheduled restart date of January 1, 1983. This refueling j outage will involve completing relief valve modifications, torus modifications, "A" low pressure turbine inspection, MG set installation for LPCI modification, and loading additional 8 X 8 fuel assemblies into the core.

There are 764 fuel assemblies in the reactor vessel. At the end of the month there were 352 EOC-3 fuel assemblics, 156 EOC-2 fuel assemblics, and 132 EOC-1 fuel assemblies in the spent storage pool. The present available storage capacity of the spent fuci pool is 160 locations. With present capacity the 1979 refueling was the last refueling that could be discharged to the spent fuel pool without exceeding that capacity and maintaining full core discharge capability in the pool. However, 949 new high density storage locations have been installed and can be used after they are qualified.

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f Operations Summary (Continued)

January 1982 Refueling Information (Continued) i  !

Unit 3

! Unit 3 began its fourth refueling on October 30, 1981, with a scheduled restart date of March 10, 1982. This refueling involves loading additional l

l 8 X 8 R (retrofit) assemblies into the core, relief valve modification,.tur-bine inspection, generator breaker and unit station transformer tie-in, and

torus modifications.

There are 0 fuel assemblies presently in the reactor vessel. There are 1 -764 EOC-4 fuel assemlies, 124 EOC-3 fuel assemblies, 144 EOC-2' fuel assemblies, 208 EOC-1 fuel assemblics, and 288 new fuel assemblies in the spent fuel storage pool. The present available capacity of the spent fuel pool is 221 locations.

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5 Significant Operational Events Unit 1 Date Time Event 1/01/82 0001 Reactor thermal power at 99%, maximum flow, rod limited. .

1/02/82 2340 Commenced reducing thermal power for turbine control valve tests and SI's.

1/03/82 0001 Reactor thermal power at 85%, holding for turbine control valve tests and SI's.

0125 Turbine control valve tests and SI's complete, commenced power ascension.

0230 ~~ Reactor thermal power at 99%, maximum flow, rod limited.

1530 Reduced thermal power to 90%, for rod pattern adjustment.

1545 Rod pattern adjustment complete, commenced power ascension.

1600 Reactor thermal power at 99%, maximum flow, rod limited.

1/05/82 0923 Commenced reducing thermal power to backwash and precoat condensate demineralizers.

1000 Reactor thermal power at 93%, holding for backwash and precoat of condensate demineralizers.

1130 Commenced power ascension f rom 93% thermal power.

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

1/13/82 1310 Reduced thermal power to 97% for SI 4.3.A-2, (CRD exercise). ,

1500 CRD exercise completc.d, commenced power ascension.

1600 Reactor thermal power at 99%, maximum flow, rod limited.

1/18/82 0010 Reduced thermal power to 90% for turbine control valve test.

0030 Turbine control valve test complete, commenced power ascension.

0100 Reactor thermal power at 94%, holding for SI 4.3.A-2 (CRD exercise).

0150 CRD exercise complete, commenced power ascension.

0200 Reactor thermal power at 99%, maximum flow, rod limited.

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1/22/82 2050 Commenced reducing thermal power for control rod sequence exchange from "B" to "A".

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Significant Operational Events Unit 1

_Date Time Event 1/23/82 0100 Reactor thermal power at 53%, holding for control rod sequence exchange.

0205 Control rod sequence exchange complete, holding at 53% for scramming control rods.

0305 Rod scrams complete, holding at 53% for SI 4.3.A-2, (CRD exercise).

0330 Control rod exercice complete, commenced power ascension.

1140 Following the rod swap and TIP set (OD-1) power was reduced to maintain the PCIOMR guidelines.

1345 R factor determined within limits, began power ascension.

1830 Commenced PCIOMR from 80% thermal power (sequence "A").

1/24/82 0005 Commenced reducing thermal power from 85% to 80% for control rod pattern adjustment.

0040 Control rod pattern adjustment completed, commenced power ascension.

0130 Commenced PCIOMR from 85% thermal power (sequence "A").

1845 Stopped PCIOMR due to condensate demineralizer pro-blems. Reactor thermal power at 95%.

1/25/82 2150 Commenced reducing thermal power due to RHR Loop II being inoperable (minimum flow valve 74-30 would not close during SI).

2220 Stopped load reduction, reactor thermal power at 93%,

holding for maintenance on minimum flow valve 74-30.

1/26/82 0130 Minimum flow valve repaired and RHR Loop II operable, commenced power ascension.

0700 Reactor thermal power at 99%, maximum flow, rod limited.

2210 Reactor Scram No. 146 from 99% thermal power when a Field Services carpenter dropped a wrench on panel 25-6A.

1/27/82 0600 Unit remained down for maintenance on IRMs "A", "B" and "C", CRD scram discharge header UT monitor and inspection of locking nuts and studs on MSIVs.

l 1/28/82 2000 MSIV inspection complete, holding for maintenance on IRM's.

l 2300 CRD scram discharge heater UT monitor in service.

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7 Significant Operational Events Unit 1 Date Time Event 1/29/82 0624 Maintenance on IRM's complete, commenced rod with-drawal for startup.

0940 Reactor Critical No. 167.

1300 Rolled T/G.

1334 Synchronized generator, commenced power ascension.

1/30/82 1400 Commenced PCIOMR from 92% thermal power (sequence "A").

1600 lloiding thermal power at 94% due to condensate demin-eralizer problems.

2045 Reduced thermal power to 82% for control rod pattern adj us tmen t .

2110 llolding load at 82% due to computer problems.

2210 Computer back in service, commenced power ascension.

1/31/82 0001 Commenced PCIOMR from 90% thermal power (sequence "A").

0026 Commenced reducing thermal power for rod adjustment frcm 91%.

0230 Reactor thermal power at 65%, holding for rod pattern adjustment.

0345 Rod pattern adjustment complete, commenced power ascension 0531 Commenced PCIOMR from 75% thermal power (sequence "A").

2400 Reactor thermal power at 95%, PCIOMR in progress, (sequence "A").

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8 Significant Operational Events Unit 2 Date Time Event 1/01/82 0001 Reactor in cold shutdown for maintenance outage.

0410 Commenced rod withdrawal for startup.

0527 Reactor Critical No. 141.

0832 Reactor Scram No. 129 from 2% thermal power when IRM's "C" and "11" exceeded 120/125 of their selected range. The high range trip was the result of the rapid incertion of reactivity caused by the con-tinuous withdrawal of control red 26-11 f rom 04 to 14.

1125 Commenced rod withdrawal for startup.

1316 Reactor Critical No. 142.

1702 Rolled T/G.

1747 Synchronized generator, commenced power ascension. '

2130 Reactor Scram No. 130 f rom 45 % thermal power when the turbine tripped on moisture separator high level.

1/02/82 0230 Commenced rod withdrawal for startup.

0340 Reactor Critical No. 143.

- 0530 llolding reactor power at 17% for moisture separator drain valve repair.

0930 Rolled T/G.

1140 Tripped turbine for work on PCB 224.

1330 Rolled T/G.

1423 Synchronized generator, commenced power ascension.

1455 Opened bypass valves to minimize load on turbine due to problems with A2 moisture separator drain pump.

1609 Manually tripped turbine (A2 moisture separator high level dump valves).

1612 Reactor Scram (Manual).No. 131 from 17% thermal power for maintenance on A2 moisture separator high level dump valve.

2145 Reactor in cold shutdown.

1/03/82 1820 Commenced rod withdrawal for startup.

1934 Reactor Critical No. 144.

1/04/82 0245 Rolled T/G.

0432 Synchronized generator, commenced power ascension.

1553 Commenced reducing thermal power from 18% due to condenser tube integrity problems.

1600 Manually tripped turbine due to water chemistry problems and to repair condenser tube leaks. Re-ducing thermal power.

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. Significant Operational Events

, Unit 2 Date Time . _ Event s

', ' i 1/05/82 1020 Reactor Scram (ftanual) No. 132 from <1% thermal power for repair.of condenser tube leaks. '

1440 Reactor in cold shutdown, s 1/06/82 0600 All condensers have been checked.and leaking ' tubes repaired. The unit remained off'itine far repairs to "B" feedwater check valve 3-52 :, and/ installation of condenser diffuser boxes for BPV ll (2A condenser) and BPV #2 (2B condens,ar). '

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1/09/82 0400 "

Maintenance complete on condenser? diffuser boxes.

1/10/82 0001 Maintenance completo'on "B" feedwater check valve 3-572. Commenced rod withdrawal for startup.

,0605 Inserted control rodu to maintain reactor pressure below 30 psi for mais.t'ecance on dontrol rod 46-39.'

1142 Commenced rod witib1'rawalpfor startaf.

1250 . Reactor Critical No.145.

2115 .Y Rolled T/G.

g 2234 'N Synchronized c,'J aerator,Tommenced power ascension. s sA  %

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1 1/11/82 1730 CompencedFQOMRfrom96%,lthermalpower(sequence"B").

' 1 1/12/82 0500 sReactorst.hermal power at 99%, maximum flow, rod '

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0850 Reduced thermp f power to 98% for removal of C2 water-box from service for cleaning. ,

1230 Reduced therma' power to 38% 6 hen 2B SJAE was Icst du,c '

to a pressure regulator.failurei . 'o i 1245 Commenced power ascens' ion from 35% thermal power. '

1900 Commenced PCIOMR from. 91% thermal pcwer (sequence B"). I 1/13/82, 0500 Reactor thermal power at 99%, maximum flow, rod '

limited.

1/15/82 0110

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Reduced thermal power to 77% while attempting to take C1 waterbox out of service for cleaning (C2 waterbox would not charge). ,

0130 All waterboxes back in service, commenced power as-cension.

, 0405 Conmenced PCIOMR from 98% thermal power (sequence "B"). '

0600 Reactor thermal power at 99%, maximum flow, rod limited.

2330 Commenced reducing thermal power for turbine control valve tests and SI's.

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10 Significant Operational Events Unit .

Date Time Event 1/16/82 0130 Reactor thermal power at 80%, holding for turbine control valve tests and SI's.

0312 Turbine control valve tests and SI's complete, commenced power ascension.

0630 Commenced PCIOMR from 98% thermal power (sequence "B") .

,, 0700 Reactor thermal power at 99%, maximum flow, rod limited.

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1/18/82 1643 Reduced thermal power to 95Z, due to "D" condensate demineralizer "U" valve leaking through.

I/20/82 1400 Commenced power ascension from 95% thermal power.

1500 Reactor thermal power at 99%, maximum flow, rod limited.

If2h/82 2040 Commenced reducing thermal power for control rod 5 '

sequence exchange from "B" to "A", "B" RFW pump

, maintenance and "B" recirculation pump MG set brush replacement.

1/30/82 0100 Reactor thermal power at 50%, holding for control rod sequence exchange from "B" to "A", RFW pump "B" maintenance and brush replacement on "B" recir-culation pump MG set.

0350 "B" recirculation pump MG set brush replacement com-

( plete, pump back in service, increased thermal power to 61%, holding for control rod sequence exchange and "B" CrW p' ump maintenance.

1200 Reduceu thermal power,to 50% for control, rod sequence exchange and'"B" RFW pump maintenance.

1335 Control rod' sequence' exchange from "B" to "A" complete, commenced power ascension ("B" RFWP mainte-nance continues).

1410 "B" RFW pump in service, power ascension in progress from 71% power.

2130 Commenced PCIOMR from 87% thermal power (sequence "A").

1/31/82 1130 Reactor thermal power at 99%, maximum flow, rod limited.

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

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_Significant Operational Events Unit 3 Date Time Event 1/01/82 0001 End-of-cycle 4 refueling outage continued.

1/31/87 2400 End-of-cycle 4 refueling outage continued.

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AVERAGE DAILY UNIT POWER LEVEL

, DOCKET NO. 259

UNIT Browns Ferry - 1 DATE 2-1-82 COMPLETED BY - Ted Thom TELEPfl0NE 205 729 6846 l

MONTil January 1982 DAY AVER AGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe-Neo (MWe-NetI i 1060 g7 1063 2 1065 18 1062 3 1063 39 1066

,, 1064 1064 20 5 1062 yg 1061 6 1063 g 1015 7 1063 751 23 3 1071 983 3

9 1063 yg 1009 10 1063 26 978

1064 27 -15 12 1068 28 -13 13 1061 216 29 g ,, 1058 893 30 15 1078 881 3,

16 1063 s

! INSTl!UCTIONS On this format.hst the average daily unit power lesel m MWe-Net for each day m the reporting month. Compute to the nearest whole megawatt.

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-260 UNIT Browns Ferry - 2 DATE 2-1-82 COMPLETED IlY TELEPHONE 205 729 6846 MONTil Jamary DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net ) (MWe-Net) 27 g7 1080 2 -7 18 1067 3 -13 39 1029 4 61 20 1048 5

-16 y, 1077 6 -15 22 1075 7

~9 1068 23 8 -11 24 1072 9 -14 1076 3

10 13 26 1082 Ii 894 27 1074 gy 1020 1078' 28 33 1073 1040 3

14 1072 741 30 15 1083 1039 l -3 16 1046 i

INSTRUCIlONS On this fortnat.hst the acrage J.nly unit power leselin MWe Net for each da) in the -:pturing nionth.C nnpute to the neare>t whole negawait.

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO, 50-296 Browns Ferry a

• UNIT DATE 2-1-82 C0\lPLETED BY Ted Thom TELEP} LONE

_205 729 6846 MONTil January DAY AVER AGE DrlLY POWER LEVEL DAY AVERAGE DAILY P0hER LEVEL (MWe Net) (MWe Neti I

-3 ,7 -3 -3 2 g 3

-3 39

-3

.: -3 20

-2 5

-3 ,

-2 6 -3 22 -2 7

-3 ~3 23 g 9 -2 9 - -3 25 -3 10 -3 26 -3 11 -3 37 12 ~3 -3 28 13 -3 9

-3 14 -3 -3 30 15 -3 3,

-3 I6 -3 4

INSTRUCTIONS On this f ormat,!nt the .nerage da !y umt power lesel in MWe Net for each day in the reporting in., nth. Compute to l the nearest whole mega. wit.

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OPERATING DATA REPORT DOCKET NO.

50-259

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DATE 2-1-82 COMPLETED BY _Ted Thom TELEPliONE ?ns 779 6846 OPERATING STATUS .

1. 1. *##7 - '

1. Unit Name:

2. Reporting Period: J nuary 1982

3. Licensed Thermal Power (MWO: 3293

4. Nameplate Rating (Gross MWe): 1152

5. Design Electrical Rating (Net MWe): 1065

6. Maximum Dependable Capacity (Gross MWe): 1098.4

7. Maximum Dependable Capacity (Net MWe): 1065

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

NA

9. Po'wer Level To Which Restricted. If Any (Net MWe): NA

10. Reasons For Restrictions. If Any: NA This Month Yr.-to-Da t e Cumularise i1. Ilours In Reporting Period 744 744 65,786 '

12. Number Of Ilours Reactor Was Critical 684.50 684.50 39,999.3

13. Reactor Reserve Shutdown llours 11.1 11.1 5,226.3

14. Ilours Generator On-Line 680.6 680.6 _ 39,110.77

15. Unit Resene Shutdown llours 0 0 0

16. Gross Thermal Energy Generated (MWil) 2,188,843 2,188,843 109.063.750 .

17. Gross Electrical Energy Generated (MWil) 714,520 714,520 36,006,970

18. Net Electrical Energy Generated (MWH) 696,983 _ , 696,986 34,965,895

19. Unit Senice Factor 91.5 91.5 59.5

20. Unit Asailability Factor 91.5 91.5 59.5

21. Unit Capacity Factor IUsing MDC Nets 88.0 88.0 49.9 2.1 Unit Capacity Factor (Using DER Net) 88.0 88.0 49.9

23. Unit Forced Ontage Rate 8.5 8.5 26.8

24. Shutdowns Scheduled Oser 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 Io Commercial Operations: Forecast Achiesed INIIIA L CitlTICA LI TY

. INITIAL. ELECTRICITY CO\lMERCIAL OPER ATION (4/77)

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OPERATING DATA REPORT DOCKET NO. 50-260 DATE 2-1-82 COSIPLETED BY Ted Thom TELEPflONE 205 729 6846 OPER ATING STATUS ,

I. Unit Name:

1. " W~ '**

2. Reporting Period: January 1982

3. Licensed Thermal Power (SIWt):

3293

4. Nameplate Rating (Gross alWe): 1152

5. Design Electrical Rating (Net SlWe): 1065

6. Statimum Dependable Capacity (Gross 5tWe): 1098.4 10e

7. Sf aximgm Dependable Capacity (Net SlWel:

8. If Changes Occur in Capacit) Rati gs (!tems Number 3 Through 7)Since Last Report. Give Reasons:

NA

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

^

10. Reasons For Restrictions. If Any: NA This 5fonth Yr..to Date Cumulative

11. Ilours In Reporting Period 744 744 60,727

12. Number Of Ilours Reactor Was Critical 577.78 577.78 39,024.74

13. Reactor Reserve Shutdown flours 157.72 157.72 13,639.48

14. Ilours Generator On-Line 522.38 522.38 37.719.47

15. Unit Resene Shutdown flours 0 0 0

16. Gross Thermal Energy Generated (SIWil) 1,643,575 1,643,575 108,296,365 .

17. Gross Electrical Energy Generated (.\lWil) 539t 910 539,910 35.972.558

18. Net Electrical Energy Generated (51Wil) 524,574 524,574 34,946,720

19. Unit Senice Factor 70.2 70.2 62.1

20. Unit Asailability Factor 70.2 70.2 62.1

21. Unit Capacity Factor (Using NIDC Net) 66.2 66.2 54.0

22. Unit Capacity Factor IUsing DER Net) 66.2 66.2 54.0

23. Unit Forced Outage Rate 29.8 29.8 29.2

24. Shuidowns Scheduled Oser Nest 6 Stanths (Type. Date, and Duration i.f Fach t:

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

26. Units in rest Status (Prior to Commercial Operation): Forecast Achieved INII!T L CRITICA LITY INIIIAL ELECTRICITY CO\l%IERCIAL OPER ATION w

(9/77)

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OPERATING DATA REPORT DOCKET NO. 50-296 DATE 2-1-82 C051PLETED BY Ted Thom TELEPHONE 205 729 6846 OPERATING STATUS

1. Unit Name:

Brom Feny - 3 Notes

2. Reporting Period: January 1982

3. Licensed Thermal Power (5tWI):

3293

4. Nameplate Rating (Gross 51We): 1152 ,

S. Design Electrical Rating (Net SIWE): 1065 -

6. Staximum Dependable Capacity (Gross SIWE): 1098.4

7. Staximum Dependable Capacity (Net SIWE): 1065

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

Na

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

10. Reasons For Restrictions,If Any: NA This Montt Yr..t o.Da t e Cumulatise

11. Ilours in Reporting Period 744 744 43,152

12. Number Of Ilours Reactor Was Critical 0 0 32,466.98

13. Reactor Resene Shutdown llours 0 0 2,141.53

14. Ilours Generator on-Line 0 0 31,750.78

15. Unit Resene Shutdown llours 0 0 0

16. Gross Thermal Energy Generated (NtWil) 0 0 93,858,620 .

17. Gross Electrical Energy Generated (MWil) 0 _ _ ,

0 30,998,190

18. Net Electrical Energy Generated (MWII) 0 0 30,088,946

19. Unit Senice Factor 0 0 73.6

20. Unit Availability Factor 0 0 73.6

21. Unit Capacity Factor (Using MDC Net) 0 0 65.5

22. Unit Capacity Factor (Using DER Net) 0 0 65.5

23. Unit Forced Outage Rate 0 0 9.2

24. Shutdowns Scheduled Oser Nest 6 Months IType. Date.and Duration of Each t:

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

26. Unih in Test Status (Prior to Commercial Operationi: Forecast Achiesed INITI \ L CRITICA LITY

. INITIAL ELLCTRICITY CO\lMLRCI A L OPER ATION s

(4/77)

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h UNIT SilUTDOWNS / ND POWER REDUCTIONS DOCKET NO. 50-259 -

UNIT NAME Browns Ferry - 1 DATE 2-1-82 January COMPLETED BY Tod Thnm R EPORT MONTil TELEPHONE 205 729 6846

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, - 1e E sX l.icensee g -t, Cause & Currective 7

No. DJie i 5? 4 .3 s E Event  ?? 5-3 Action to

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3E E I5: Repori = EC E' Present Recurrence e  ! v 6

196 1-22-82 S 11 Derated for control rod sequence ex-change ("B" to "A"), scramming con-trol rods, SI 4.3. A.2 (CRD exercise).

197 1-26-82 F 63.40 11 3 Reactor scram when maintenance dropped a wrench on panel 25-6A causing , 4 reactor high pressure signal. 0)

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198 1-31-82 S H Derated for control rod pattern adjustment.

r 1 2 3 4 I" Fo ced Reason . Method: Exhibit G - Inst rnelions S Lheduled .\ l quipment Fatime ( Esplain) 1 Manual for Preparation of Data 14 Maintenance (W Iest 241anual Seram. Entry Sheets foi Licensee C-Refueling 3 Automatic Scram. Esen't Report t LI R) File t NtlRI G-D Regulatory Restriction 4.Other i Esplain i , O t til I

. 1 -Operator Iraming & !.itense Esamination F AJnunnisati.e 5 G O;viational 1:nor ti:spleo) Eshibit I - Same Source L U8177 ) li Other (l.splain t s, .

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DOCKET NO. 50-260 UNIT SilUTDOWNS AND POWER REDUCTIONS Brem s Ferry -2 UNIT NAM E

-DATE 2-1-82 January COMPLETED BY TnA Thnm REPORT MONTil 205-729-6846 TELEPif0NE

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Er h y 3E 5 -2 EX l_scensee O C3"5C E Corrective 3 3,,,e 54 N..

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$ 5 $$ Event Report : J/d [d E

Action to Present Recurrence 5 i :!

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218 1-01-82 F 8.53 G 3 Unit remains down for maintenance (2A main transformer).

219 1-01-82 F 9.25 A 3 Reactor scram when IRMs G and H ex-ceeded 120/125 of their selected range 220 1-01-82 F 14.17 A 3 Reactor scram when turbine tripped on moisture separator high level.

221 1-01-82 F 2.72 A Turbine trip for work on PCB-224 (no reactor scram). $

222 1-02-82 F 36.38 A 3 Reactor scram for maintenance on A2 moisture separator high level dump valve.

223 1-04-82 F 18.33 A Turbine trip (manual) due to water o chemistry problem and to repair con-denser tube leaks.

224 1-05-82 F 132.23 A 2 Reactor scram to repair condenser tube leaks.

I 2 3 4 I liiiced Reason . Method: Exhibit G . Instructions S S, hed nt, il XLquipment Failure (Explaml 1-Manual for Preparation of Data Il-Maintenance or Test 2-Manual Seram. Enti> Sheets f or 1.ieensee r C. Refueling 3.Autonniie Stram. Event Report (1.1.:RI File INilR1 G.

D Regulatory Restriction 4 Other (Esplain) 0161)

Il)perJior Tiaining & l.isense I umination I AJaniististrati.e 4 C-OpelJtiolial I. Hor (1.\plJto ) l' Alphil i . Same Source , .

, P3/77) Il Other (1-:splatlil

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i DOCKET NO. 50-296

• UNIT SifUTDOWNS AND POWER REDUCTIONS UNIT N AME Browns Ferry -3 DATE 2-1-82 January COMPLETED BY Tad Tham REPORT MONTil TELEPHONE. 205 729 6846 r

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55 "h 5 'j ' Cauw & Correctnc

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c r 93 1-1-82 S 744 C 2 Reactor scram to accommodate (Cont) EOC-4 refuel outage.- y i

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I 9

i 2 3 4 1 F: Iorced Reason: Method: Exhibit G - Inst ructio.is S S,hed u;eil A l.quipment Failure (Esplain)  !. Manual - for Preparation of Data It Maintenance of Test

~

2 Manual Scram. Ent > Sheets for 1.icensee C. Ret ueling . 4. Automatic Scram. Esent ReporI (! I'RI File (NURl:G.

4 D-Regniator) Restriction . 4-Other ( Esplam ) 01616 l~-Opeiator Training & Lkense I samination II Adnumstrati.e 5 li G Opes.stional laros (l.splaial Eshibit I - Same Source th t'#/ 77 ) Il-Other ti.splain)

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BROWNS FERRY NUCLEAR PLANT UNIT 3 g ,

CSSC EQUIPMENT ELECTRICAL MAINTENANCE

SUMMARY

• For the Month of January 19 82 .

Effect on Safe Action Taken Nature of Operation of Cause of Results of To Preclude System Component Maintenance The Reactor Malfunction Malfunction Recurrence Date 1-25-82 Fire XS-39-27A and SI 4.ll.C.1&5 None During the per- Smoke detector's Replaced the Protec- XS-39-106ER formance of SI sensitivity was low, smoke detectors tion 4.ll.C.165 the and performed sensitivity of SI 4.ll.C.165.

smoke detectors The detectors XS-39-27A and operated properly.

XS-39-106ER was TR #267853 ,

found low. TR #267850  ;

1-25-82 Fire XS-39-71XG Pnl 3-25-287 None Bad smoke detec- The detector would Replaced the bad Protec- zones W and X tor, occasionally initi- smoke detector.

tion had spurious ate a false alarm TR #267861  %

alarms, when local panel 25-287 was reset.

I

BROWNS FERRY NUCLEAR PLANT UNIT 3 g CSSC EQUIPMENT ELECTRICAL MAINTENANCE

SUMMARY

For the Month of January 19 82 l Effect on Safe ZL~ tion Taken Nature of Operation of Cause of Results of To Preclude Date System Component Maintenance The Reactor Malfunction Malfunction Recurrence 1-14-82 Fire XC-39-68YQ Smoke detector None The fixed spray The detector initia- Replaced the Protec- XS-39-68YQ station is adja- ted a false alarm smoke detector tion initiated a cent to a staging which could have and performed false alarm area for health masked alarms from SI 4.ll.C.165, which would physics and other .other detectors the detector not clear. outage personnel, which are required operated properly.

The station was to be operable. TR #280723 ,

being used as a LER#BFRO-50-296/

.. coat rack, an 8201 initiation levcr was apparently operated by a g N

coat thus wetting the detector.

During the per- None Loose annuncia- Intermittent Tightened the 1-21-82 Fire Auxiliary Protec- Instrument formance of tor circuitry failure of the Aux. circuitry card room 3 smoke SI 4.11.C.1&S card retaining Inst, room smoke retaining bar, tion detector's the detectors bar. alarm in the control the annunciator annunciator in Aux. Inst. room. circuitry oper-circuitry. room 3 would ated properly, sometimes not TR #250690 alarm in the TR #250696 control room.

LER#BFRO-50-296/

8202 4

BROWNS FERRY NUCLEAR PLANT UNIT 3 q -

CSSC EQUIPMENT ELECTRICAL MAIM 7ENANCE

SUMMARY

For the Month of January 19 82 Effect on Safe Action Taken-Nature of Operation of Cause of Results of To Preclude System Component Maintenance The Reactor Malfunction Malfunction Recurrence Date Bad motor bear- Excessive motor vi- Replaced the 1-7-82 Diesel 3A D/G lube Excessive motor Unit in refuel-vibration dis- ing outage. ings locked and bration was found motor rotor, Generators oil circula- during annual bearings, and ting pump covered during began to spin in the end bell thus inspection. end bells, per-motor performance of SI 4.9.A.l.d wearing end bell formed SI 4.9.A.l.d.

housing. The pump motor (annual inspec-operated progerly.

tion) - TR #250584 i Valve position None Limit switch Received a open Lubricated the 1-9-82 RHR HCV 74-19 limit switch, limit switch indicating sticking. indication when the U.

lights not valve was closed. the switch~

operated properly.!

operating pro-TR #182612 perly.

None Bad smoke detec- Received false Replaced the' r 1-10-82 Fire XS-39-26F Smoke detector '

was initiating tor, alarms. However, smoke detector Protect- located in and performed I panel 9-7 false alarms. the alarm would tion SI 4.ll.C.165.

clear each time it was received. The detector operated proper- .

I ly.

g TR #280710 e

6 0

BROWNS FERRY NUCLEAR PLANT UNIr 2 ,y CSSC EQUIPMENT ELECTRICAL MAINTENANCE

SUMMARY

For the Month of January 13 82 ,

Effect on Safe Action Taken Nature of Operation of Cause of Results of To Preclude Date System Component Maintenance The Reactor Malfunction Malfunction Recurrence outage by 1-16-82 RPS ECN-P0276.

(continu- LERfBFRO-50-260/

ed) 8202.

Panel 25-103 None Wire to temp- Lost power to panel Insulated wif e 1-17-82 Sampling Panel 25-103

& Water circuitry to feeder breaker erature sensi- 25-103 (condenser and returned (

Quality temperature tripped. ,, tivity switch sampling panel) the breaker to j sensitivity grounded. service.

switch.

TR #282167 5

4 a

e 4

4

2 BROWNS FERRY NUCLEAR PLANT UMIT 5 CSSC EQUIPMENT ELECTRICAL MAINTENANCE

SUMMARY

For the Month of January 19 82 Effect on Safe Action Taken Nature of Operation of Cause of Results of To Preclude System Component Maintenance The Reactor Malfunction Malfunction Recurrence Date 1-7-82 RHR FCV-2-74-54 Valve position None Bad limit switch. Closed limit switch Replaced the bad

' closed' indicating inoperable, limit switch, in-limit switch lights were dicating lights not operating operated proper-properly. ly.

TR #235822 a

1-11-82 CRD HS-85-48 Broken stop Noqq Broken stop Required care to be Replaced stop plate, plate, taken while oper- plate, switch ating switch to operated proper-avoid rotating ly. y switch past desired TR #279343 u setting.

1-16-82 RPS MSIV scram SI 4.1.A-ll "A2" h scram During the per- "A2" scram cir- Relay SAK3G was logic limit circuitry assoc- formance of SI cuitry asseciated placed in trip-switch #4 on lated with 4.1.A-ll the with FCV-1-52 was ped condition MSIV FCV-1-52 FCV-1-52 was MSIV scram logic inoperable. through TACF inoperable. limit switch #4 2-82-024 and on MSIV FCV-1-52 the SI success-failed to open fully completed, and subsequently The SI was revis-drop out relay ed,to allow for SAK3G. the temporary alteration until repairs can be initiated during a future unit shutdown. The switches are scheduled to be changed during the next refueling

III BROWNS FERRY NUCLEAR PLANT UNIT 2 g ll U

CSSC EQUIPMENT ELECTRICAL MAINTENANCE

SUMMARY

jj f;

For the Month of January 19 82

.f Effect on Safe Action Taken '! } ;

Nature of Operation of Cause of Results of To Preclude ;r Date System Component Maintenance The Reactor Malfunction ' Malfunction Recurrence 12-31-8 HPCI Gland Seal A ground was None The level switch LS73-15B was inop- Replaced LS 73- ',

Cond. hot well indicated on was rusted and erable. ISBs the new low level panel 9-43. corroded. level switch ,

switch (LS 73- operated properly.-l 15B) TR #281736 '!

TR #281738

' TR #281721 ,

TR #236053 l i.

1-1-82 Main Outboard MSIV 'Open" posi- None LS-1 was stuck. LS-1 was inoperable. Freed the limit I

Steam (FCV-1-15) tion indicat- switch, perform m '

ing light ed SI 4.7.D.l.b

• inoperable. -2A and the switch l-operated properly.

TR #281748 l

1-7-82 RWC TS-69-30E Open circuit. None~ Wire was off pin Relay 16A-K59A . Soldered wire I circuitry. F in ;onnector. ' could not . receive from CCll-to

~

(connector AJ ./ the isolation .

' pin F in connec-

on panel 25- single initiated by tor AJ. IM's 229) TS-69-30E. performed'SI i 4.2.A-39.

TR #107649 1

6 A

9

^

l BROWNS FERRY NUCLEAR PLA14T UNET 1 & Common ( -

CSSC EQUIPMENT ELECTRICAL MAINTENANCE

SUMMARY

I For the Month of January 19 82 t

Effcct on Safe Action Taken Nature of Operation of Cause of Results of To Preclude Date System Component Maintenance The Reactor Malfunction Malfunction Recurrence 1-27-82 Main "A" main Fail to receivc None Loose annunciator Low-pressure annun- Tightened the Steam steam line a low-pressure circuitry card, ciation would not loose card and low-pressure annunciation alarm on pnl. 9-5.

the annunciator annunciator on pnl. 9-5. circuitry oper-circuitry, ated properly.

4 TR #231995 9

e

BROWNS FERRY NUCLEAR PLANT UNYT 1 & Common g ,

l CSSC EQUIPMENT ELECTRICAL MAINTENANCE

SUMMARY

l l

For the Month of January 19 82 f Effect on Safe Act:~on Taken Nature of Operation of Cause of Results of To Preclude Date System Component Maintenance The Reactor Malfunction Malfunction Recurrence 1-17-82 CRD PCV-85-23 CRD Valve tripping None Brake armature PCV-85-23 Tapped screw pressure con- out. was loose not inoperable. holes and re-trol valve allowing the placed screws.

brake to release. The valve oper-Holding screws ated properly.

stripped. TR #231368 A

1-23-82 Air Condi- 'A' Control Chiller supply Nong

• Oil pump motor 'A' Control Bay Replaced the oil tioning Bay Chiller breaker was grounded. Chiller inoperable. pump motor and (Cooling- oil pump motor tripping. returned chiller-Heating) to service, w TR #282164 1-25-82 RHR FCV 1-74-30 During the per- RHR Loop II'in- Bad relay (10AK FCV-1-74-30 logic The relay coil logic circui- formance of SI operable 1088) coil. circuitry relay was replaced and try (Relay 4.5.B.l.d FCV (10AK' 108B) inop- the SI success-10Ak 108B) 1-74-30 failed erable. fully completed.

to close. TR #281493 LER#50-259/8212 1-27-82 High- "C" Fire pump Received a None Bad annunciator Recieved a false Replaced the bad Pressure annunciator pump running circuitry card. annunciation.' annunciator card, Fire Pro- circuitry annunciation the annunciation tection with pump off. circuitry opera-ted properly.

TR #281491 w n .

t

i BROWNS FERRY WUCLEAR PLANT UNIT 1 & Common g CSSC EQUIPMENT ELECTRICAL MAINTENANCE

SUMMARY

For the Month of January 19 82 Effect on Safe Action Taken Nature of Operation of Cause of Results of To Preclude Date Svstem Component Maintenance The Reactor Malfunction Malfunction Recurrence 12-26-81 CRD Relay 63X Coil retainers None Design Coil retainers The relay coils 35Al panel for these re-

Reference:

GE broken. Although were replaced.

9-15 and re- lays were SIL #44 relays were oper- TR #253076 lay 5A-K10K found to be Supplement No. 2. able, corrective panel 9-17. broken, action was required.

1-4-82 Primary Channel 'D' Logic channel None Coil on relay A k isolation in Replaced the Contain- low low rcac- tripped. i. (16AKlD) burned the B2 trip channel, relay per EMI 23.

ment tor water up. The relay oper-level moni- ated properly.

toring TR #282181 m circuitry. ,

(relay 16AKlD) 1-11-82 Air Con- Re-cycle timer Chiller low None Bad re-cycle The chiller was Replaced the bad ditioning (lA Control low pressure timer. Inoperabic. timer and the (Cooling- Bay Chiller) would not chiller opera-Heating) clear and the ted properly.

chiller would TR #281302 not start.

1-17-82 Fire Smoke detec- The smoke de- None Bad smoke Received a fa'lse Replaced the bad Protec- tor XA-39-29A tector initia- detector, alarm which would smoke detector, tion located in ted a false have masked signals performed SI relay room, alarm and from detectors 4.11.C.165. The would not which are required detector operated clear. to be operable. properly.

TR #267771 LER#BFRO-50-259/

8209

~

• • BROWNS FERRY NUCLEAR PLANT UNIT Common .

CSSC EQUIPMENT MECHANICAL MAINTENANCE SUFNARY ,

f -

For the Month of January 19 8? I EFFECT ON SAFE- ACTION TAKEN DATE SYSTEM COMPONENT NATURE OF OPERATION OF CAUSE OF RESULTS OF 'IU PRECLUDE MAINTENANCE THE REACTOR MALFUNCTION MALFUNCTION RECURRENCE 12-22-E 1 R11RSW Valve 23-505 Water Leak None Worn gasket not Flange leaking Replace gasket sealing off water TR 233297 on flange

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• • BROWNS FERRY NUCLEAR FIANT UNIT MECHANICAL MAINTENANCE

SUMMARY

i CSSC EOUIPMENT ,

For the Month of January 19 82 -

. - . = . .

EFFECT ON SAFE ACTION TAKEN DATE SYSTEM COMPONENT NATURE OF OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE MAINTENANCE THE REACTOR MALFUNCTION MALFUNCTION RECURRENCE 2-21-t 1 HVAC 3A Control Bay Valve will not None Valve rubber seat Valve full of mud Replaced seat &

Chiller Contr. close off bad , & will not close off cleaned valve Valve TRf 250494 I 12 81 D/G 3A D/G #2 Air Reed valve wil l None Faulty relief & Valve will not reset Replaced relief Comp. Reed not reset check valve valve & check valve Valve TRf 280556 i i'

1-6-82 RHR FCV-74-52 Packing Leak None Packing Bad Packing Leak Repacked valve  !

TR# 280481 ,

1-ll-E 2 D/G Pressure Switch Air Leak None Bad pressure Pressure switch air Replaced pressure C Eng. #1 Switch leak switch **

Air Comp. TR# 233119 5 1-10-E 2 F.P. Valve 3-26-82 Faulty Head None Cracked Head Unknown Repalced head M TR# 280709 12 81 D/G "C" D/G Air Inspect air None Faulty Starter Starter needs Rebuilt right bank Start Motors start motors rebuilding starter TR# 233140 1-18-5,1 CRD HCV-14-55 & Faulty valves None Rorn Valves Unknown Installed new D/C 18-03 CRD Mod. valve EP120 and rebuilt' directional flow valve ,

TR# 182357 l l-21-!,2 RHR Serv. HCV-23-37 /alve bad & not None Broken Disc Excessive Vibration Replaced valve &

Water set properly Faulty Valve torqued bolts to 245 lbs.

TR# 230845 1-20-H2 D/G "D" Engine furbocharger None Paulty Turbochrg. Turbocharger would Installed rebuilt Turbocharger 3ad not function properly factory turbocharger TR# 233542 le f e

1

~~ 2 ,

5 ' BROWNS FERRY NUCLEAR PIANI UNIT MECHANICAL MAINTENANCE

SUMMARY

4: .

CSSC EQUIPMENT -  :. ,

For the Month of January 19 82 -

t 9.. .

EFFECT ON SAFE ACTION TAKEN COMPONENT NATURE OF OPERATION OF CAUSE OF RESULTS OF 'IO PRECLUDE DATE SYSTEM MAINTENANCE THE REACTOR MALFUNCTION MALFUNCTION RECURRENCE 82 CRD Dir. control Valves not None Paulty valves Control valve would not Replaced valves valve 85-40B & operating withdraw TR# 233349 l 40C properly.

1-8-82 CRD Module 54-15 Valve malfunc- None Paulty Valve 7alve became non- Replaced valve &

dir. flow vlv tion functional adjusted stem travel TR# 281286 .

I 1-9-82 CRD Module 30-27 Valves Leaking None 3ad Seat Rater Leakage Replaced seat Inlet & Outlet TR# 279357,

• Scram Valve

.,t 1-9-82 CRD Module 54-15 Faulty valve None 3 eat ring disc Unknown Replaced seat i Scram Inlet seat aursted TR# 306357  !

Valve , u $

85-39A - "

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=

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BROWNS FERRY NUCLEAR PIANT UNIT 2 7 MECHANICAL MAINTENANCE

SUMMARY

4 CSSC EOUIPMENT ,

For the Month of January 19 82 _

EFFECT ON SAFE ACTION TAKEN COMPONENT NATURE OF OPERATION OF CAUSE OF RESULTS OF 'IO PRECLUDE DATE SYSTEM MAINTENANCE THE REACTOR MALFUNCTION MALFUNCTION RECURRENCE 2-30-E 1 HPCI FCV-73-45 Water Leak None Faulty Seal Leak at pressure Removed and repaired seal ring bad seal g TR# 232351 i

2-19-E l RHR Heat Exch. A-C- Install Chicag >!!one IJnknown Unknown Cut pipe off, thread D RHR Tank Fittings end of pipe and install ,

pipe Chicago fittings TR# 235060  ;,

r 1-29-8 1 HPCI Gland seal Replace gasket None Casket would not Top gasket blew out Replaced top gasket on ,

condensor hold gland seal.condensor

> TR# 152254 L-19-22 CRD Scram pilot Control air None Faulty 0-rings Air leak on valves Replaced 3 o-rings on y.!

valves on CRD leak . each module modules 30-51,

• TR# 306395 w 26-19, 26-51, .

22-51, 14-15, .

10-35, 10-51, ' ~4f 06-39, 06-35 FSV-85-37B 8; CRD Scram Pilot hange 0-rings None Faulty 0-rings Unknown Replaced 0-ring seals Valves TR# 318575

<l-31-f 1 CRD CRD Scram disch , Faulty disch. None Bad switch Switch would not Replaced Switch vol. level switch function properly TR# 318793 switch .

2-85-45E  :

}

L 4

9 c i e . O

'o

~

BROWNS FERRY NUCLEAR PIANT UNIT 1 - -

MECHANICAL MAINTENANCE SU) MARY Q <

CSSC EQUIPMENT , .

For the Month of Januarv 19 82 -

EFFECT ON SAFE ACTION TAKEN NATURE OF OPERATION OF CAUSE CF RESULTS OF 'IO PRECLUDE DATE SYSTEM COMPONENT MAINTENANCE THE REACTOR MALFUNCTION MALFUNCTION RECURRENCE

L-26-E2 Standby Backdraft Damper damaged None Back draft damper Damper would not Installed new damper Gas Damper in B badly damaged function TR# 233111 SBGT Train l

lL- 5-El D/G "D" D/G Engine Oil Leak None Crack in Gov. oil Oil leaking from Replaced pipe nipple and Engine Governor supply nipple cracked pipe nipple filled gov. with oil TR# 23"ill5 1

1 9 8 s

i e

f h

1 i

• c l

, SROWNS FERRY NUCIZAR PUdiT UMIT 1,2, 6 3 -

ENSTRUMENT MAINTENANCE SUMPARY 9 CSSC EQUIPMENT FOR Tile MONTl! OF January 19 82 i NAll'RE EFFECT 05 SAFE CAUSE ACTION TAKEN

' ATE SYSTEM COMPONENT OF OPEPATION OF OF RESULTS OF TO PRECLUDE MAINTENANCE THE REACTOR MALFUNCTION MALFUNCTION . RECURPINCE nit 1

-9 CRD Probe Buffer Repair None Failed Transistor Lost Rod Position None ,

Card Indication

-11 23 PT-23-26 Replace None Transmitter Incorrect Reading Repaired Heat Frozen Strips

-16 CRD Probe Buffer Rep air None Failed Transist,or Rod Drift Alarm -

s None Card .

nit 2 .

. w

-4 90 PDIS-90-165 Calibrate None Instrument Drift False Alarm None , .

-15 68 TR-68-98~ Repair None Failed Capacitor Failed to Print None nit 3 -

!-15 23 PT-23-18 Replace None Transmitter Incorrect Reading Repaired Heat Frozen Strips

-20 # 92 LPRM A Rep air None Faulty Potentio- Unstable Reading . None o meter

-23 '92

. IRM G Repair None Detector, Connec- Inoperable Channel None tor, Drive Tube

& Detector Drive Destroyed by GE CRD crew

36 FIELD SERVICES

SUMMARY

January 1982 The unit 3 cycle 4 refueling outage overall duration has been revised from 134 days to 146 dyas. This increase in duration was required due to additional requirements in the torus coating schedule.

Major events consisted of: (1) completing the internal portion of the torus modifications in order that sandblast and coating could get underway.

Manpower was reassigned from the external portion of the torus modifications in order to concentrate on the internal portion of the modification. (2)

Disassembly and inspections of the lou pressure "B" and "C" turbines was added to the schedule in order to perform shrunk-on-wheel and ultrasonic test inspections, and (3)

Installation of the generator breakers which is mechanically 86 percent complete and 98 percent completed on the electrical portion.

Other major modifications and routine maintenance work in progress includes the Unit Station Service Transformer installation which is approximately 65 percent complete, security modifications, RHR seal heat exchanger modification, recirculation motor generator and pump maintenance, EMI-7 breaker maintenance, eddy current testing of selected heat exchangers, conduit installation for the hydrogen and oxygen pumps, main steam relief and 1$olation valve maintenance and testing, and control rod drive rebuild.

Significant activities that were completed included the changeout of 62.

control rod drives, installation of RHR heat exchanger 3C flanges per ECN P0194, inservice inspection, the high pressure turbine maintenance, and the low pressure "C" turbine maintenance.

.