ML20066D344

Monthly Operating Repts for Sept 1982

ML20066D344
Person / Time
Site:	Browns Ferry
Issue date:	11/06/1982
From:	Jones G, Thom T TENNESSEE VALLEY AUTHORITY
To:
References
NUDOCS 8211110292
Download: ML20066D344 (39)

Text

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TENNESSEE VALLEY AUTHORITY DIVISION OF UUCLEAR POWER BROWNS FERRY NUCLEAR PLANT

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O MONTHLY OPERATING REPORT September 1, 1982 - September 30, 1982 i

DOCKET NUMBERS 50-259, 50-260, AND 50-296 LICENSE NUMBERS DPR-33, DPR-52, AND DPR-68

<. MtM Submitted by:

Plant uperintendent t

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'yfb 8211110292 821106 DR ADOCK 05000

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TABLE OF CONTENTS i

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 o

Plant Maintenance......................

22 Field Services Summary.....

37

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1 Operations Summarv September 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 25 reportable -occurrences and six revisions to previous reportable occurrences reported to the NRC during the month of September.

Unit 1 There was one scram on the unit during the month. On September 7, the reactor scrammed due to low pressure on the scram pilot air header which was caused by a procedure error and out-of-date drawings allowing unit 1 air supply to the pilot air header to be isolated when unit 2 control air dryer was being isolated to allow maintenance on the dryer outlet valve.

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

Unit 9 There was no scrams on the unit during the month.

Principally prepared by B. R. McPherson.

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',s Operations Summary (Continued)

September 1982 Fatigue Usage Evaluation The cumulative usage factors for the reactor vessel are as follows:

Location Usage Factor Unit 1 Unit 2 Unit 9 Shell at water line 0.00557 0.00448 0.00388 Feedwater nozzle 0.27208 0.19544 0.14700 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 3.37E+05 gallons of waste liquids were discharged containing

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approximately 3 25EWO1 curies of activities.

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Operations Summarv (Continued)

September 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 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 764 fuel assemblies in the reactor vessel.

The spent fuel storage pool presently contains 52 new fuel assemblies; 260 EOC-4 fuel assemblies; 232 EOC-3 fuel assemblies; 156 EOC-2 fuel assemblies; and 168 EOC-1 fuel assemblies.

The present capacity is 1,148 locations.

Modification work and testing is in progress to increase the spent fuel pool capacity to 3,471 assemblies.

Unit 2 Unit 2 began its fourth refueling on July 30, 1982 with a scheduled restart date of January 19, 1983 This refueling outage will involve l

l completing relief valve modifications; torus modifications; "A"

low-pressure turbine inspection; generator inspection; MG set installation for LPCI modification; loading additional 8X 8 R ruel 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 EOC-4 fuel assemblies; 353 EOC-3 fuel assemblies; 156 EOC-2 fuel assemblies; and 132 E0C-1 fuel l

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4 Operations Summary (Continued)

September 1982 Refueling Information Unit 2 (Continued) assemblies in the spent fuel storage pool.

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

Unit 9 Unit 3 is scheduled for its fif th refueling on or about October 1,

- 1983, with a scheduled restart date of January 31, 1983 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 changeout; finishing THI-2 modifications; turbine inspection; and changeout of jet pump hold-down beams.

There are 764 fuel assemblies presently in the reactor vessel.

There are 280 E00-4 fuel assemblies; 124 E00-3 fuel assemblies; 144 EOC-2 fuel 4

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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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5 Significant Ooerational Event Unit 1 Date Time Event 9/01/82 0001 Reactor thermal power at 98%, limited by main steam lina switches (vibration).

0335 Commenced power ascension for vibration check on MSIVs.

0445 Reactor thermal power at 99%, maximum flow, rod limited.

9/03/83 2245 Commenced reducing thermal power for turbine control valve tests and S!s.

2300 Reactor power at 68% for turbine control valve tests complete, holding for sis.

9/04/82 0045 Reduced thermal power to 66%, holding for CRD exercise SI 4.3. A.2.

0312 SI 4.3. A.2 (CRD Exercise) complete, holding at 66%

for SI 4.1.B.2 ( APRM Gain).

0910 SI' 4.1.B.2 ( APRM Gain) complete, commenced PCIOMR from 66% power (cequence "B").

9/05/82 2130 Reactor thermal power at 995, maximum flow, rod i

limited.

9/06/82 0104 Received 1/4 isolation on "B" MSL low-pressure switch, commenesd reducing thermal power.

0500 Reactor power at 96% due to 1/4 isolation on "B" MSL.

0700 Commenced power ascension from 965 power.

1020 Commenced PCICMR from 97% thermal power (sequence "B").

1300 Reactor thermal power at 99%, maximum flow, rod limited.

1603 Received 1/4 isolation on "B" MSL, commenced reducing thermal power.

1700 Reactor power at 97% due to 1/4 isolation on "B" MSL.

9/07/82 1745 Reactor Scram No.160 from 97% thermal power on

" low" scram pilot air headee pressure.

This was apparently caused due to valving on unit 2 air dryer.

9/08/82 0503 Commenced rod withdrawal for startup.

0951 Reactor Critical No.179.

1415 Rolled T/G.

1438 Synchronized generator, commenced power ascension.

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A Sinnificant Operational Event Unit 1 k

Date Time Event 9/09/82 0230 Commenced PCIOMR from 75% thermal power (sequence

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"B").

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9/10/82 0730 Reactor thermal power at 965, maximum flou, rod limited.

2200 Commenced reducing thermal power for control rod pattern adjustment.

9/11/82 0110 Reactor thermal power at 67% for control rod pattern adjustment.

0830 control rod pattern adjustment in progress, commenced power increase.

1430 Control rod pattern adjustment complete, commenced PCICMR from 81% thermal power.

9/12/82 0920 Ho,1 ding up on PCIOMR due to problems with aquatic growth at intake.

Reactor power at 95%.

1230 Commenced PCICHR from 95% thermal power (sequence "B").

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

9/18/82 0100 Reduced thermal power to 97% for turbine control valve tests and sis.

0310 Turbine control valve tests and sis complete, commenced power ascension.

0500 Reactor thermal power at 99%, maximum flow, rod

limited, i

l 9/19/82 0245 Commenced reducing thermal power to insert control rod 38-39 for replacement of fevel switch in accumulator.

t 0300 Reactor power at 83%, holding-for maintenance on control rod 38-39 accumulator.

0415 Maintenance complete on control rod 38-39 accumulator, commenced power ascension.

0505 Reactor power at 935, commenced PCICMR (sequence "B").

0800 Reactor power at 99%, maximum flow, rod limited.

9/20/82 0815 Reduced reactor thermal power to 82% when "C"

reactor feedwater pump tripped which caused I

recirculation pumps to run back on low reactor water level signal.

The "C" reactor feedwater l

pump tripped while maintenance personnel were working on an amplifier.

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Significant Operational Event I

Unit 1 Rate Time Event 0940 Maintenance comlete on amplifier "C",

reactor feedwater pump back in service, commenced power 4

ascension.

4 Commenced PCIOMR from 94% thermal power (sequence 1015 s

"B").

1230 Reactor thermal power at 99%, maximum flow, rod 3

limited.

o 9/23/82 0312 Commenced reducing thermal power for backwash and precoat of condensate demineraliz;ro.

0400 Reactor thermal power at 85% for backwash and precoat of condensate demineralizers.

i 0613 Condensate demineralizer backwash and precoat complete, commenced power ascension.

0700 Reactor thermal power at 995, maximum flow, rod limited.

2210 Co'amenced reducing thermal-power for backwash and precoat of condensate demineralizers.

2300 Reactor thermal power at 85% for backwash and precoat of condensate ~demineralizers.

I 9/24/82 0605 Condensate domineralizers backwash and precoat b

t' complete, commenced power ascension.

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0700, Reactor thermal power at 995, maximum flow, rod f

limited.

l 2320 Commenced reducing thermal power for control rod pattern adjustment.

9/25/82 0100 Reactor thermal power at 72% for control rod pattern adjustment.

~0200 Commenced power increase for control rod pattern 1

adjustment.

0730 Control rod pattern adjustment complete, commenced PCIOMR from 825 thermal power (sequence "B").

9/26/82 0030 Reactor thermal power at 995, maximum flow, rod l

limited, i

j 9/28/82- 0030 Commenced reducing thermal power due to high

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temperature in main steam tunnel. (Investigation revealed that the cause of the main steam line I

high temperature was a leak in C1 and C2 high-pressure heaters).

0040 Isolated C1 and C2 high-pressure heaters, power j j reduction continues.

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Significant Operational Event Unit 1 Date Time Event 0350 Reactor thermal power at 75%, holding due to C1 and C2 high-pressure heater leak.

1000 Commenced PCIOMR from 75% thermal power (sequence "B").

1550 Reactor thermal power at 85%, holding for C1 and C2 high-pressure heater maintenance.

9/30/82 0130 Commenced PCIOMR from 855 thermal power (sequence "B").

0820 Stopped PCIOMR at 965, holding due to C1 and C2 high-pressure heater maintenance.

1645 Reduced thermal power to 93% due to C1 and C2 high-pressure heaters.

2100 Commenced power ascension from 93% thermal power.

2103 Received 1/4 scram on channel "B",

holding load at 93,% thermal power.

2400 Reactor thermal power at 93%, holding due to 1/4 scram on channel "B".

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9 l*2nificant Operational Event Unit 2 Date Time Event 9/01/82 0001 End-of-cycle 4 refuel outage continues.

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10 Significant Operational Event Unit 3 Date Time Event 9/01/82 0001 Reactor thermal power at 97%, control rod pattern adjustment in progress.

0345 Commenced power ascension for control rod pattern adjustment.

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

0700 Commenced reducing thermal power due to "B"

recirculation pump vibration.

1500 Reactor power at 97%, "B" recirculation pump vibration limited.

1930 Commenced power ascension from 97% power.

2000 Reactor power at 995, maximum flow, rod limited.

2100 Reactor power at 98%, "B" recirculation pump limited.

9/02/82 0700 Reactor power at 975, "B" recirculation pump vibration limited.

1500 Reactor power at 97% for test of new computer software.

1710 Computer sof tware test complete, commenced power ascension.

1800 Reactor thermal power at 995, maximum flow, rod limited.

9/04/82 2320 Commenced reducing thermal power for control rod pattern adjustment.

9/05/82 0100 Reactor thermal power at 75%, control rod pattern adjustment in progress.

0345 Control rod pattern adjustment complete, commenced power ascension from 82% thermal power.

0430 Commenced PCIOMR from 85% thermal power.

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

9/11/82 2247 Commenced reducing thermal power for turbine control valve tests and sis.

2300 Reactor power at 80% for turbine control valve tests.

9/12/82 0020 Turbine control valve tests complete, holding for Si 4.1. A-11 (MSIV Closure).

0125 SI 4.1. A-11 complete, commenced reducing thermal power for SI 4.7.D.1.b-2 (MSIV Closure).

0130 Reactor power at 64% for SI 4.7.D.1.b-1 (MSIV Closure).

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Significant Ooerational Event Unit 3 Date Time Event 0237 SI 4.7.D.1.b-2 complete, commenced power ascension.

0647 Reactor thermal power at 91%, holding due to aquatic growth problems at intake screens.

0815 Reduced thermal power to 82% due to high back pressure caused by aquatic growth on intake trash racks.

9/12/82 1055 Commenced power ascension from 825 thermal power.

1100 Reactor thermal power at 88%, holding due to aquatic growth on intake trash racks.

9/13/82 0055 Reduced thermal power to 87% due to high back pressure caused by equatic growth on intake trash racks.

0600 Commenced PCIOMR from 87% thermal power (control ce'll core).

i 1325 Commenced re6ucing thermal power from 94% to l

remove aquatic growth from intake trash racks.

1400 Reactor power at 90%, "A" CCW pump off for cleaning aquatic growth off of trash racks.

1450 "A" CCW pump back in service, commenced power ascension.

9/14/82 0418 Commenced reducing t'termal power from 94% due to high back pressure caused by aquatic -growth on intake trash racks.

0500 Reactor power at 86%, holding due to high back pressure (aquatic growth on intake trash racks).

0526 Commenced power ascension from 86% thermal power.

0600 Commenced PCIOMR from 94% thermal power.

1100 Reactor thermal power at 995, maximum flow, rod limited.

9/17/82 2203 Commenced reducing thermal power for removal of "A" reactor feedwater pump from service for maintenance.

2320 "A" reactor feedwter pump out of service for maintenance, reactor power at 73%.

9/18/82 0520 "A" reacto.- feedwater pump maintenance completed, pump back in service, commenced power ascension.

0615 Commenced PCIOMR from 92% thermal power (control cell core).

0700 Reactor thermal power at 995, maximum flow, rod limited.

12 Sinnificant Operational Event Unit 3 Date Time Event 9/21/82 2210 Commenced reducing thermal powr to remove "A" reactor feedwater pump from service for maintenance.

2257 Reactor thermal power at 695, holding for maintenance on "A" reactor feedwater pump.

9/22/82 0110 "A" reactor feedwater pump back in service, commenced power ascension.

0150 "A" reactor feedwater pump tripped on high vibration, reactor power at 70%.

0152 "A" reactor feedwater pump rolled again and tripped.

Instrument mechanics found a loose connection to a detector on the inboard bearing.

0500 Repairs complete to the loose connection to the vibration detector for "A" reactor feedwater pump, pump back in service, commenced power cscension.

0700 Reactor thermal power at 995, maximum flow, rod limited.

9/26/82 0111 Commenced reducing thermal power for turbine control valve tests and sis.

0130 Reactor thermal power at 87%, holding for turbine control valve tests and sis.

0150 Turbine control valve tests and sis complete, commenced power ascension.

0230 Commenced PCIOMR from 93% thermal power.

0330 Reactor thermal power at 99%, maximum flow, rod limited.

9/30/82 2400 Reactor thermal power at 99%, maximum flow, rod limited.

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AVERAGE DAILY' UNIT POWER LEVEL 4

50-259 DOCKET NO.

UNIT ' Browns Ferry -'l-10-1-82 DATE Ted Thom COMPLETED IlY

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TELEPilONE _205 729 0834 1

MONTil.

September DAY

' AVERAGE DAILY POWER LEVEL

' DAY

' AVER AGE DAILY POWER LEVEL

. (MWe-Net i (MWe-Net)

]

1039 1040 37 1044 2

gg 1032

'E 3

19 I

726 1031 4

20 964 1047 l

5 3,

1017 1050 6

706 1021 7

23 218 1003 8

863 906 9

-25 r

10 1013 1054 26 l

792 1068 982 830 12 73 1029 879 13

,9 i

l 14 1040 967 30 1042 15 3t l

i 1041 16 I

i INSTRUCTIONS On ilus fornut.!ist the aser.ree daily umt power lewi m MWe Net for each day in the seposting m iuth. Compute to j.

the nearest whole mepw.ni.

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14 AVER AGE DAILY UNIT POWER LEVEL DOCKET NO.

50-260 UNIT Browns Ferry - 2 DATE _ 10-1-82 COSIPLETED llY Ted Thom TELEPHONE 205 729 0834 510NTil -

September DAY-AVER AGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (51We Net)

(51We Neti I

-7 17

-4 C

-7

-3 l

2

,3

-4 3

-7 19-4

-7

-4 20 4

5

-7

-4 21

-7

'22

-4' 6

-4 7

-7 23 l

8

-7 24

-4 9

-7

-4 25 10

-7

-4 26

-4 Il

-7 27 12

-6

-4 yg f

13

-5

-4 29

-4

-3 j

I4

, 3g 15

-4 3

16

-4 INSTRUCTIONS l

On this tornut, hst the average dath umt powei lesel in \\1We Nei thr each tla) in the repmting month. Cennpute to the nearest whole megawatt.

j (9/77 )

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AVERAGE DAILY UNIT POWER LEVEL

'50-296=

DOCKET NO.

Browns Ferry - 3 UNIT DATE 10-1-82 Ted Thom CONIPLETED fly 205 729 0834 TELEPHONE MONTH September

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DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL

. IMWe-Net)

(MWe-Net) 1024 1033 I

le 2

1026 977 gg 1046 1048 3

39 1042 1055 4

20 975 5

21 1033 1041 980 6

1050 1056 7

33 1056 8

1048

,4 1050 1053 9

25 i

10 1046 1047

,6

-1021 1058 l1 27 9

1050 12 33 953 1053 13 29 1013 1049 14 39 1048 15 1046 16 INSTRUCTIONS On this tierntat.hst the aserage daily unit pinver lesclin MWe Net foi cach day in ilie reposinig mienth. Compute to the nearest whole nwgawatt.

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16 OPERATING DATA REPORT DOCKET NO. 50-259 DATE 10-1-82 C051PLETED BY Ted Thom TELEPHONE 205 729 0834 OPER ATING STATUS Br wns Ferry - 1 Notes

1. Unit Name:

2. Reporting Period:

September 1982

3. Licensed Thermal Power (5th t):

3293 1152

4. Nameplate Rating (Gross alwe):

1065

5. Design Electrical Rating (Net alwe):

6. Sinimum Dependable Capacity (Gross SIWel:

1098.4

7. Alnimum Dependable Capacity (Net SIWel:

1065

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

o NA NA

9. Power Lesel To Which Restricted,if Any (Net atWe):

10. Reasons For Restrictions. If Any:

W This Stonth Yr..to.Date Cumulatise

11. Ilours in Reporting Period 720 6.551 71.593

12. Number Of Ilours Reactor Was Critical 703.90 5,992.12 45,306.92

13. Reactor Reserve Shutdown llours 16.10 405.98 5.621.18

14. Ilours Generator On-Line 699.12 5,930.52

_44,360.69

15. Unit Reserve Shutdown flours 0

0 0

16. Gross Thermal Energy Generated (SIWil) 2,151,871 18,261,316 125,136,223

17. Gross Electrical Energy Generated (51Wil) 701,52_0 5,947,700 41,240,150

18. Net Electrical Energy Generated (alWil) 683,645 5,775,562 40,J44,471

19. Unit Senice Factor 97.1 90.5 62.0

20. Unit Availability Factor 97.1 90.5 62.0 89.2 82.8 52.5

21. Unit Capacitv Factor IUsing 51DC Neti 89.2 82.8 52.5

22. Unit Capacity Factor (Using DER Neti

23. Unit Forced Outage Rate 2.9 9.5 25.1

24. Shutdowns Scheduled Oser Next 6 StunthsIType.Date.and Duration of Eacht:

l 1

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

26. Units in rest Status iPrior o Commercial Operation):

Forecast Achiesed 1

l INITI \\L CitlTICALITY INITI A L I:1.ECTRICITY CO\\lNIERCI AL OPI:R ATION l

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19/77) l

17 OPERATING DATA REPORT 50-260 DOCKET NO.

DATE 10-1-82 COSIPLETED BY _ Ted Thom TELEPIlONE 205 729 0834 OPERATING STATUS Browns Ferry - 2 Notes

1. Unit Name:

2. Reporting Period:

September 1982 3293

3. Licensed Thermal Power (31Wt):

1152

4. Nameplate Rating (Gross 51We):

1065

5. Design Electrical Rating (Net alwe):

1098.4

6. 51nimum Dependable Capacity (Gross SIWE):

7. 51nimum Dependabl'e Capacity (Net MWe):

1065

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

NA NA

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

10. Reasons For Restrictions,if Any:

This Alonth Yr.-to-Date Cumulative

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720 6,551 66,534

11. liours in Reporting Period 0

4,846.51 43,293.47

12. Number Of Ilours Reactor was Critical

13. Reactor Reserve Shutdown flours 0

203.06 13,684,82

14. Ilours Generator On-Line 0

4,778.36 41,975.45 _

15. Unit Reserve Shutdown llours 0

0 0

16. Gross Thermal Energy Gener.:ted (SIWil) 0 13,827,550 120,480,340 0

4,592,260 40,024,908

17. Gross Electrical Energy Generated (MWil)

18. Net E'ectrical Energy Generated (MWil) 0 4,450.929 38,873,075

19. Unit Senice Factor 0

72.9 63.I

20. Unit Availability Factm 0

72.9 63.1

'i

21. Unit Capacity Factor (Using MDC Net) 0 63.8 54.9 0

63.8 54.9

22. Unit Capacity Factor (Using DER Net) 0 5.5 27.1

23. Unit Forced Outage Rate

24. Shutdowns Scheduled Oser Nest 6 Stonths (Type.1) ate.and Duration of Eacht:

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

January 1983

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

Forecast Achiesed.

INIII A1. CitiTICA til Y INITIA L ELEC11tlCITY CO\\l\\lLRCI \\ L OITR A TION (0/77)

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OPERATING DATA REPORT DOCKET NO.

50-296 DATE 10-1-82 C051PLETED itY Ted Thom TELEPfl0NE 205 729 0834 OPERATING STATUS Bro m Fe m - 3 N tes I. Unit Name:

2. Reporting Period:

Septer.ber 1982 3293

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3. Licensed Thermal Power (5tht):

1152

4. Na wplate Rating (Gross SIWE):

1065

5. Design Electrical Rating (Net atWe):

6. Slaximum Dependable Capacity (Gross 51We):

1098.4 1065

7..\\laximum Dependable Capacity (Net alWe):

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

NA NA

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

10. Reasons For Resttictions,if Any:

This.\\lont h Yr.-to-Date Cumulatise 720 6,551 48,959

11. Ilours in Reporting Period

12. Number OfIlours Heactor Was Critical 720 2,936.30 35,403.28

13. Reactor Reserve Shutdown flours 0

1,230.62 3,372.15 720 2,814.28 34,565.06

14. Ilours Generator On-Line l

15. Unit Resene Shutdown llours 0

0 0

16. Gross Thermal Energy Generated (51Wil) 2,300,357 8,517,238 102,375.858

17. Gross Electrical Energy Generated (.\\lWil) 759,670 2,742,790 33,740,980

18. Net Electrical Energy Generated (51Wil) 740,891 2,650,005 32,738,051 100 43.0 70.6

19. Unit Senice Factor 100 5

43.0 70.6

20. Unit Asailability Factor 96.6 38.0 62.8

21. Unit Capacity Factor (Using.\\lDC Net) 96.6 38.0 62.8

22. Unit Capacity Factor (U3ing DER Net) 0 31.6 18.3

23. Unit Forced Outage Rate

24. Shutdowns Scheduled Oser Nest 6 Stunths (Type.Date.and Duration of Eacht:

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

26. Units in Test Status IPrior io Commercial Operationi:

Forecast Achiesed i

INIIl \\ L CRI TICA LITY INI TIA L ELI:Cl RICI TY CO\\l\\lERCl \\ L Ol'l:R ATION l

l N/77)

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.y U

E UNITSilU1 DOWNS AND POWER REDUCTIONS U

'NA E B s Ferry - 1 lJ, DATE 10-1-82 COMPLETED BY Tod Thnm REPORT MONTil September 1ELEPHONE 205 729 0834

=

5

• E ~s Licensee E-t E).,

Cause & ('or rective-

' =

No.

Date y

j$

3j$

Event y

h3 Action to H

O l.

3:

3 g =!

Report =

v) U 5

Present Recurrence e

u 6

236 9/03/82 S

B Derated for turbine control valve tests and sis.

237 9/07/82 F

20.88 11 3

Reactor scram due to low scram pilot ag header-pressure.

238 9/10/82 S

11 Derated for control rod pattern adjustment.

-c 239 9/24/82 S

11 Derated for control rod pattern adjustment.

240-9/28/82 F

II Derated due to leak in C1 and C2 high pressure heater.

I 2

3 4

i F: Forced Reason:

Method:

Exhibit G Instructions i

S: Scheduled A.1:quipment Failure (Explain) 1 -Manual for Preparation ot' Data H Maintenance of Test 2 Manual Seram.

Entry Sheets for Licensee C Refueling 3 Automatic Scram.

Event Report (LER) Fde (NURI:G-D. Regulatory Restriction 4 Other (Explain) 01611 E Operator Training & License Examination F.Administrati.e 5

G-Operational Error (Explain)

Exhibit I - Same Source (9/77)

Il-Ot her (Explain)

t o.

DOCKET NO.

50-260 UNIT S11UTDOWNS AND POWER REDUC 110NS UNIT NAME Browmt Ferry - 2 DATE 10-1-82 COMPLETED !!Y Ted Thom REPORT MONTig September lELEPIIONE 205 729 0834

.{?

3 Yk Licensee

[-t;,

!t Cause & Correctise No.

Date ME 4

E :E O Esent a7 E?

Action to S

j@

3d}

Report =

cN 0

!0 Present Recurrence u

e g

O 243 9/01/82 S

720 11 2

EOC-4 Refuel Outage continues.

No I

2 3

4 F: forced Reason :

Method:

Exhibit G -Instructions S: Scheduled A Equipment Failure (Explain)

! 41anual for Preparation of Data italaintenance of Test 241anual Seram.

Entr> Sheets for laeensee C Refueling

3. Automatic Scram.

Event Report (1.ER) File INiiRI.G-D-Regulatory Restriction 4-Olher ( Explain )

0161) li-Operator Training & License Examination F-Administ rative 5

G-Operational Eirur (Explaia)

E.shibit I - Same Source 07/77)

Il-Ot her ( Explain)

.. I

.I DOCKET NO. _ 50-296 UNITSilUIDOWNS AND POWER REDUCTIONS

~

UNIT NAM E Browns Ferrv - 3 '

DATE 10-1-82 COMPLETED !!Y. Ted Thom REPORT MONTII September

- TELEPilONE 205 729 0834

~.

E E

.5 ?

3 4 Ef ~i Licensee j-t, f,

Cause & Correctise No D.n e 3

g j

jy Event n7 o?

Auion to f:

5

~@g Report a cE V E'

Prevent Recurrence H

u e.

g O

109 9/04/82 S

11 Derated for control rod pattern adjustment.

a 110 9/11/82 S

B Derated for turbine control valve tests and Si on MSIV closure.

111 9/17/82 F

B Derated for maintenance on "A" l

reactor feegump.

~

112 9/21/82 F

B Derated for maintenance on "A" reactor feedpump.

1 2

3 4

F: Forced Reason:

Method:

Exhibit G -Instrnerions S: Scheduled A Equipment Failure (Explain) 1-Marual for Preparation of Data It Maintenance of Test 2-Manual Scram-Entry Sheets for Licensee C. Refueling 3 Automatic Scram.

Event Report (I.l:R) File iNURI.G-D Regularory Restriction 4 Other (Explain) 016I)

E-Operator Training & License Examination F Administrati.e 5

G. Operational Error (Explain)

Extiibit ! - Same Source p1!77)

Il Other (Explain) 1 4-e r

-t.

INSTRUP.DIT PAINTESANCE SUMP.ARY CSSC EQUIPI';T FOR h:!E HJN111 CF _ September (19 82

.*b NATTc2 EFFECT 05 SAFE CESE l

ACTIO:; TAKEN TE SYSTDI COMPCND.7 OF OPEF.ATION CF CF FIST ~LTS OF TO PF1CL' JOE MAIYrESA';C2 THE FJJ.CTCH PALFC';CTION P.ALFLc :CTIO!;

R E CUR RENCE.

_1 i

-1

.85 Rod Select Repair None Faulty Relay Rod would not select None

-3 64 PDIS-64-7 Repair None Dirty Switch Improper switch None Contacts action

-2

-16 3

LIS-3-56A Repair None Obsolete switches Improper switch action Installed new type switch

-14 3

LIS-3-56B

-17 3

LIS-3-58A

-18 3

LIS-3-SSB y

20 3

LIS-3-58C

-19 3

LIS-3-58D

~

23 3

LIS-3:-52'~

v s

22 3

LIS-3-62

Repair, None Obsolete switches Improper switch action Installed new v

y v

2 type switch e

2 68 FT-68-7 Replace None Failed Transmitter Instrument Drift None 9

e e

0 e

9 4

h e

BR0k'NS FERRY NUCLEAR PIANT UNIT Common g

FECHANICAL MAINTENANCE

SUMMARY

Ji ' ';D

.CSSC EOUTPMENT For the Month of September 19 82 EFFECT ON SAFE ACTION TAKEN DATE SYSTEM COMPONENT NATURE OF OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE MAINTENANCE TIIE REACTOR MALFUNCTION MALFUNCTION RECURRENCE i-1 Fuel Pool two spare pumps pumps worn out

.none pumps need pumps not functioning rebuilt both spare Cooling rebuilding properly-pumps TR# 233106 I

1-26 Diesel D/G D B air blown head Generator.

compressor gasket none abnormal pressure high pressure side replaced high pressure-head gasket blown head gasket out TR# 274628 G

U T

F e

9 4

I m

. BRO ES FERRY NUCLEAR 'PIANT UNIT

'l y

MECHANICAL MAINTENANCE

SUMMARY

CSSC EQUIPMENT For the Month of September 19 82

_y EFFECT ON. SAFE ACTION TAKEN t

DATE SYSTEM COMPONENT NATURE OF OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE MAINTENANCE Tile REACTOR MALFUNCTION MALFUNCTION RECURRENCE

-28 CRD module 46-35 noisy valves none both scram pilot valve making excessive installed rebuilt kits vales worn noise' in both solenoid-l valves' TR# 314767

-28 CRD accumulator water leak none worn o' rings accumulator leaking replaced accumulator, IICV-34-27 through upper &' lower o' rings TRf 314766

-03 CRD module 34-27 later leak none bad seal &o' rings water leak rebuilt Ilfo' accumulatoi TR# 314772-accumulator

-25 CRD module 46-35 valve chattering-none worn diaphragm &

excessive noise -

installed new pressurc-scram solenoid sub-assembly valve chattering

&. exhaust diaphragm &

valve pilot sub-assembly FSV-85-39A repair kit' 5-TR# 249688

-14' Radiation RM-90-53 broxen pump none unknown CAM inoperable replaced belt

• Monitoring belt TR# 309599

-27 Radiation RM-90-250 tubing drain none rubber hose needs CAM inoperable replaced rubber hose-Monitoring loose replacing with clear tygon tubing.

TR# 216586

-28 RilR RllR room cooler water leakage none broken nipple water leakage inside resoldered nipple-B&D casing-TR# 266823 e

T

~

BROWNS FERRY NUCLEAR FIANT UNIT 2

CSSC EQUIPMENT MECIIANICAL MAINTENANCE

SUMMARY

~.

For the Month of sentomsnr 19 g?

- s.

EFFECT ON SAFE ACTION TAKEN DATE SYSTEM COMPONENT HATURE OF OPERATION OF CAUSE OF RESULTS OF 10 PRECLUDE MAINTENANCE THE REACTOR MALFUNCTION MALFUNCTION RECURRENCE

-03 CRD module 10-31 water leak none valve seat valve leaking through replaced valve seat, scram inlet damaged bodygasket&o'rigg valve TR# 274650

-14 Core Spray valves 75-507A fittings needed none no trouble found valves were removed to rewelded existing 75-507C to be re-welded perform SI 3.2.9 fittings to pipe TR# 305017

-04 RIIR RHR pump B&D line is leakint none hole in 3/4" line water leaking from rewelded 3/4" line on suction line B & D suction line TR# 314787

-06 Fire Fire header rx. water leak none fire protection-Protection water cleanup header cracked water leaking welded pin hole transfer pump TR# 274568 y

room

-15 IIPCI 73-6A, 73-6B packing needs none worn packing valves nonfunctional repacked all threc 73-5 replacing valves TR# 317459

-16 Core Spray FCV-75-23 water leak none worn packing valves nonfunctional repacked all three valves TR# 3134 60

-23 D/G D/G D air com-air leak none worn gasket leaking head gasket replaced with new pressor B gasket

~

TR# 274624 8

k

[

BROWNS FERRY NUCLEAR PIANT UNIT 3

.. 'a

'CSSC EQUIPMENT

' MECHANICAL MAINTEPANCE SUMfARY~

For the Month of September 19 32-p

~

EFFECT ON SAFE ACTION TAKEN i~DATE

'CYSTEM.

COMPONENT NATURE OF OPERATION OF

.CAUSE OF RESULTS OF TO PRECLUDE MAINTENANCE THE REACTOR MALFUNCTION MALFUNCTION-RECURRENCE

!-16 Primary Rx. drywell

' door not func-none door lever rod door inoperable straightened door 1cve Containment airlo'ck. doors tioning proper ty

& cam was bent rod and cam I.

TR# 314708,,

-26 Primary drywell air.

reassemble none work performed interlock disassem-assembled interlo'ck Containment lock doors doors on doors bled door.

TR# 269209 3-08 D/G 3D D/G #1 blown head none abnormal pres-head gasket blown.

replaced head gasket

')81) compressor gasket sure causing air leak and valve plate-TR# 227774 J-6 CRD 3-85-590 faulty hand-

.none unknown.

handwheels missing replaced-handwheels:

wheels with T-handles TR# 269236-'

s~

)-9 LPCI 3DN LPCI MG flywheel

'none bad bearings MG set running hot changed bearing, j

Set generator bearing and noisy cleaned and lubricated running hot TR# 269459 7-15 Rx. Bldg.

FSV-64-140 water leak none valve out of valve leaking thru placed_ valve in ventilation position upright position TR# 305060 4

4 3

4 3

1 1 & Comson.

Pag 3 BROWNS FERRY NUCLEAR PLANT UNIT CSSC EQUIPMENT ELECTRICAL MAINTENANCE SU$1ARY

^EE 9/29/82

- s 82 For the Month of September 19 Effect on Safe Action Taken Nature of Operation of Cause of Results of To Preclude Date System Component Maintenance The Reactor Malfunction Malfunction Recurrence

/1/82 Fire Plug-in relay During the per-None A plug-in relay Preaction sprinkler The relay was Protec-on panel formance of (KI-zone 6) was automatic initiation repositioned and tion 25-323 S14.11.C.3&4, found to be circuit for spreader clipped in place.

(KI-zone 6) heat detector loose in its room "A" zone 6 was A survey of 49 zone test socket. The inoperable, firealarm panels switch HS 39-relay retaining with similar 102BB would clip was not in mounting arrange-not alarm test position.

ment is underway.

for panel Several missing 25-323 (Alarm-or loose clips heat detection have been found for "A" and will be o

spreader room) replaced or re p a ired '.

Com-pletion of this survey is expect-ed by 10/15/82.

TR #300552 TR #282795 LER#BFRO-50-259/

8267 I

i

t~

BROWNS FERR NUCLEAR PLANT UNIT 1 & Comdon.

Pag EM IL'30 Appendix B CSSC EQUIPMENT ELECTRICAL MAINTENANCE SU IARY 9/29/82 s-For the Month of September 19 82 Effect on Safe Action Taken Nature of Operation of Cause of

'Results of To Preclude JDate System Component-Maintenance The Reactor Malfunction Malfunction Recurrence

/2/82 Contain-Power supply During the per-None, "B" Test personnel

'"A" hydrogen Relay R2 contacts ment circuitry'for formance of hydrogen inadvertently analyzer was inop-were replaced Inerting 1-FSV-76-57 SI4.7.A.2.g-3 analyzer was lifted.the power erable. Upon re-and SMI 176 and on unit 2, the available and supply lead turn to service,

.S14.7.H were com-unit 1 "A" operable.

wires for 1-FSV-during the' perform-

pleted. The test hydrogen 76-57 instead of ance of SI4.7.H. the engineer involved analyzer be-2 FSV-76-57.

unit 1 "A" hydrogen was reinstructed.

came inoper-The wires in-sample inlet pump

.The panels'involv-able.

volved are locat-was discovered to ed (1-9-54 and-ed in adjacent have failed after 2-9-54) are being panels 1-9-54

.FSV-76-57 closed, relabelled to and 2-9-54 in Investigation're-clearly identify g

the unit 1 and 2 vealed that the each unit. The control room.

relay.R2 contacts procedure is FSV-76-57 is a had failed.

being revised for H0 analyz r clarity. The 9 2 "X

sample failure of relay return valve R2~ contacts is which closed being investiga-when the wires ted in conjuction were lifted.

with LER 259/82031 with results expected by March 1, 1983.

TR #267138 LER#BFR0-50-259/

8268 e

I

?

1 & Com6on.

Page 3 BROWNS FERRY NUCLEAR PLANT UNIT PPendix B CSSC EQUIPMENT ELECTRICAT. MAINTENANCE SU) !ARY 9/29/82' For the Month of September 19 82 Effect on Safe Action Taken Natute of Operation of Cause of Results of To Preclude Date System Component Maintenance The Reactor Malfunction Malfunction Recurrence i

1/3/82 Air Con-

"B" Shutdown Air conditioner None Bad timer motor.

Air conditioner Replaced the bad ditioning board room inoperable.

inoperable, timer motor, the:

(Cooling-air condition-air conditioner Heating) er operated properly.

TR #196555 t/4/82 SBCT (XS-65-3C)

Core spray sys. None Annunciator Test mode annuncia-Re-inserted card, annunciator and drywell circuitry card tion failed to the annunciator card pressure test was loose.

operate on'pnl. 9-3.

operated properly, mode failed to TR #267025 annunciate-g-

on pnl. 9-3.

s/10/82 CRD HS d5-48

( RD control None Switch stop Required care to be Replaced the switch on plate was broken.

taken not to oper-broken stop plate panel 9-5 was ate the switch past and the' switch not operating desired setting.

operated properly, properly.

TR #341488 O

t 1 & Codmon Page 3 BROWNS FERRY NUCLEAR PLAliT UNIT CSSC EQUIPMENT ELECTRICAL MAINTENANCE SUd1ARY App ndix B 9/29/82 For the Month of September 19 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

/14/82 RiiR LEA LPCI MG MG set output None Voltage regulator MG set output volt-Adjusted the set voltage voltage was setpoint had age was low.

regulator set-regulator

low, drifted down point to increase from normal 490V the output volt-1 SV to 471.1 age to an accep-volts.

table level.

TR #266857 Thishouldhavepre-

/18/82 CRD Scram accumu-A fuse failure None, water was Scram accumulator The level switch lator level alarm with not present in leve1 switch vented the level was replaced and switch 38-39 about 30 to 40 the' scram failed in the switch from provid-tested per EMI 50. g accumulator accumulator.

closed (non-ing a control room The switch opera-alarms was re-alarm) position alarm should water ted properly.

ceived. The (contacts welded have leaked into TR #341432 fuse was re-shut).

the scram LER#BFRO-50-259/

placed and the accumulator.

8277 alarms cleared.

A short time later the ac-cumulator alarr for rod 38-39 came in inter-mittently, which resulted in another blown fuse.

The fus.e was replaced and the accumulator l

alarm for rod i

38-39 remained l

in.

l 7

i

9 1&Cohn age BROWNS FERRY NUCLEAR PLANT UNIT p EM IL 30 m

CSSC EQUIPMENT ELECTRICAL MAINTENANCE SU[ DIARY EE "

9/29/82

. 82.

t For the Month of September 19 Effect on Safe Action Taken Nature of-Operation of Cause of Results of

.To Preclude J)at e System Component Maintenance The Reactor Malfunction Malfunction Recurrence t

t l/20/82 RHR "1DN" LPCI MG Received a None Bad annunciator Received a false 480V Rx MOV Bd.-10 i

set under-undervoltage circuitry card.

undervoltage annun-was manually trans-voltage annun-annunciation ciation for "1DN"

'ferred to MG set 4

ciator cir-on panel 9-23 LPCI MG set.

"1DA".

Trouble-cuitry.

which would

' shooting revealed not clear.

a bad annunciator

-[

circuitry card.

The bad card was replaced, tested,-

and the 480V Rx MOV Bd. trans-5 ferred back to MG set "iDN".

TR #266865 i

O t

I i

7

-t.

BROWNS' FERRY NUCLEAR PLANT UNIT. ' 1 & Codmon

- ags 3

~

ELECTRICAL MAINTENANCE SUN!ARY Appendix B CSSC EQUIPMENT 9/29/82 For the Month of SOPtember 19 82 Effect on Safe Action Taken l

Nature of Operation of Cause of Results of To Preclude Date System Component Maintenance The Reactor Malfunction Malfunction Recurrence

/24/82 4KV Shut-Degraded volt-During the per-None, redundant Relay sensitive Degraded voltage The. relays were down Bds.

age relays formance of power was avail-to temperature

. relays operated from recalibrated to and Busset and relay recurrence con-able.

variation is 3883 to 3890 as op-the correct set-

timers, trol calibra-suspected.

posed to'the re-points. The set-tion (BFRO. quired 3900 to-3940

. point drift prob-296/8213) of volt range. The

.lem is now being degraded volt-

. loss-of-voltage re-evaluated by"TVA' age relays (SI lay was found to Engineering Design 4.9.A.4.c) 2 operate at 2935 LER#BFRO-50-295/

relay timers on

. volts,as opposed to

.82075-4KV Shtd. Bd.

the required 2913 to A, 1 loss-of-

'2927 volt range.

g' voltage relay Two timer relays and~1 degraded were found to oper-voltage relay ate.from 4.30 to on 4KV Shtd.

4.35 seconds as Bd.-B, and 1 opposed to the re-degraded volt-quired-3.8 to 4.2 age relay and 1 seconds range. One timer relay on

. relay time was:found 4KV Shtd. Bd.

to, operate at 7.95 D were found seconds as opposed to operate out-to the required 7.06 side.of accep-to 7.80' seconds table limits.

range.

t BROWNS FERRY EUCLEAR PLANT UNIT 1 & Cofumon.

Pag 3 iSIL 30 CSSC EQUIPMENT ELECTRICAL MAINTENANCE SUN 4ARY pp dix B 9/29/82 For the Month of September 19 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 1/25/82 Radiation RM-90-251 RM-90-251 None Bad pump motor Damper "E" would The damper was Monitor-(turbine b1dg.)

bearings.

not close automat-manually closed ing inoperable

ically, and the chemical l

_ laboratory began taking air sampics on the turbine floor. The bad pump motor bear-ings were replaced and the radiation monitor returned b

to service.

TR #245310 LER#BFRO-50-259/~

8276

'/28/82 Annuncia-Annunciator Two.annuncia-None, at no Bad inverter. A The annunciators The bad inverter tor &

inverter on tors.on pnl.

time was the possible generic for the HPCI, RHR, was replaced and Sequentia]

pnl. 9-3 for 9-3 failed.

HPCI, RHR or problem with the and Core spray sys-the annunciator Events XA-55-3E and Core spray power rating of tem on panel 9-3 circuitry returned Recording XA-55-3F system a resistor in were inoperabic, to service. The inoperable.

the inverter

.possible generic-control card is.

problem with-the suspected.

power rating of a resistor in the invertor-control-card is being evaluated for reportability

-under 10CFR21.

TR #252112

t BROWNS FERR' NUCLEAR PLA3T UNIT 2

i' F

SIL 30 Appendix B CSSC EQUIPMENT ELECTRICAL MAINTENANCE S ARY 9/29/82 For the Month of Septe=ber 19 82 Effect on Safe j Action Taken Nature of Operation of Cause of Results of To Pre:;lude Datc System Component Maintenance The Reactor Malfunction Malfunctica Recurrence

/18/82 Fire Pro-Annunciator Annunciator None, heat de-Bad annunciator Annunciator TA 39-1he bad card was tection TA 39-113 TA 39-113 tector opera-card.

113 would not test, replaced, tested, circuitry failed to test. bility was not Control room annun-and operated a

card affected.

ciation for the properly. The affected heat detec-annunciator TA 39-tor zones was still 113 failed again available and oper-on 9/24/82, the able via an alter-card was re-align-nate alarm path ed, tested, and l

through central returned to l

panel 25-313.

service.

TR #274667 5

TR #244839

/23/82 RBCCW 2-FSV-70-20 2-FSV-70-20 None Bad coil.

FSV inoperable.

Replaced the Sol. valve coil appeared burned coil and for RBCCW Dry-to be burned.

cover, returned well Atm.

the FSV to Cooling Coil service.

"A3" TR #282596 I

7

~

?

?

BROliNS FERRh NUCLEAR PLANT 1"IIT2~#

~

1. Ehg37g33

[

p CSSC EQUIPMENT ELECTRICAL MAINTENANCE SUE!ARY 7

~

9/29/82 For the Month of September 19 82 Effe:t on Safe Action Tal:en Nature of Operation of Cause of Results of To Preclude

_Date System Connonent Maintenance The Reactor Malfunction Malfunction Recurrence

/24/82 Contain-Relay centacts Bad contacts.

None, unit in Unkncwn at this Analy r:er A inoper-Replaced bad 3-7 ment on' relay R2 cold shutdown tice. The fail-able.

and 4-8 contaEts Invertint, and R$ located for refueling.

ure of these re-ca relay R2 and in pnl.25-34C lay contacts is 3-7 and 4-8 con-(Analyzer A) being investi-tacts on relay

~~.

gated in conjunc-R5.

tion with LER TR #274674

1. 259/82031.

i

/27/82 RPS Time delay During outage None Bad relay.

Time delay relay Replaced the had 3

relay on 2B maintenance would not operate relay per DII 23, RPS MG set.

the time delay

properly, timed relay per relay was DII 15.

The found to oper-relay operated ate improperly.

properly per D11 13.

TR #317516 1

BROWNS FERRY NUCLEAR PLANT UNIT 3

. r Pago 3 BF EMSIL 30 b

CSSC EQUIPMENT ELECTRICAL MAINTENANCE SU$1ARY Appendix B Z

9/29/82 For the Month of September 19 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

/3/82 HPCI LA-73-8 HPCI exhaust None Bad annunciator Received a false Replaced the bad drain pot "high circuitry card.

"high level" annun-annunciator card, 1cvel" annun-ciation.

the annunciator ciation came 19 operated properly.

and would not TR #269231 clear.

/7/82 Reactor PdCo-64-16 During the per-None Damper limit Dampet would not Adjusted the limit Bldg.

formance of SI switc.cs were operate properly, switches, the Heating 4.2.A-21, PdCo-out-of-adjustment damper operated and Vent-64-16 failed to

properly, p

ilation operate proper-TR #207299 ly.

t

/23/82 Standby TA 63-3 Received a None Loose connection Received a false Tightened the

, Liquid abnormal temp-in the annuncia-annunciation.

loose connection, Control erature alarm tor circuit.

the annunciator on pnl. 9-5.

operated properly.

TR #274480

/24/82 Diesel D/G 3B annun-Received a D/G None Loose annunciator Received a false Tightened card, Generator ciator running annun-circuitry card.

D/G running annun-annunciator oper-circuitry.

ciation with

ciation, ated properly.

generator shut-TR #274491 down..

os-37

.O FIELD SERVICES

SUMMARY

September 1982 Field Service's summary not received in time for publication.

t a

P l

l l

i 1

~

l l

l l

l L