ML20054M077

Monthly Operating Repts for May 1982

ML20054M077
Person / Time
Site:	Browns Ferry
Issue date:	06/01/1982
From:	TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20054M067	List: ML20054M066 ML20054M077
References
NUDOCS 8207090222
Download: ML20054M077 (35)

Text

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TENNESSEE VALLEY AUTHORITY DIVISION OF NUCLEAR POWER BROWNS FERRY NUCLEAR PLANT 4

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MONTHLY OPERATING REPORT May 1, 1982 - May 31, 1982 i

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

Plant erintendent i

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8207090222 820610 PDR ADOCK 05000259 R

PDR

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o TABLE OF CONTENTS Operations Summary......................

1 Refueling Infonmation....................

2 Significant Operational Instructions.............

5 Aver'ge Daily Unit Power Level................

10 Operating Data Reports....................

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

16 Plant Maintenance.......................

19 Field Services Summary....................

31

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1 Ooerations-Simunney May 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 14 reportable occurrences and two revisions to previous reportable occurrences reported to the NRC during the month of May.

Unit 1 u

There were no scrams on the unit during the month.

~~

-Unit 2 s

There were no scra51s on the unit during the month.

^ n Unit 3 There were no scrams on the unti during the month. The unit was down until May 20, when it tied on line after an extended turbine maintenance s

outage.'

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Ooerations Siwmmrv (Continued)

April 1982 Refuelinr Information Unit 1 Unit 1 is scheduled for its fifth 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 TMI-2 modifications; post-accident sampling facility tie-ins; core spray changeout; and changeout of jet pump hold-down beams.

There are 764 fuel assemolies in the reactor vessel.

The spent fuel storage pool presently contains 44 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 1,104 locations.

Modification work and testing is in progress to increase the spent fuel pool capacity to 3,471 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 31, 1983.

This refueling outage will involve completing relief valve modifications; torus modifications; "A" low-pressure turbine inspection; generator inspection; MG set installation for LPCI modification; loading additional 8 X 8 fuel assemblies into the core; TMI-2 modifications; post-accident sampling facility tie-ins, and changeout of jet pump hold-down beams.

There are 764 fuel assemblies in the reactor vessel.

At the end of the month there were 248 new fuel assemblies, 353 EOC-3 fuel assemblies,

3 O

e Operations-Sunnarv (Continued)

April 1982 Refuelinsr-Information Unit 2 (Continued) 156 EOC-2 fuel assemblies; and 132 EOC-1 fuel assemblies in the spent fuel stor' age pool. The present available capacity of the spent fuel pool is 692 locations. There are 169 new high-density storage locations that have been installed and can be used after they are qualified.

Unit 3 Unit 3 is scheduled for its fifth refueling on or about August 1, 1983, with a scheduled restart date of November 28, 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 TMI-2 modifications; turbine inspection; and changeout of jet pump hold-down beams.

Unit 3 ended its EOC-4 refueling outage on April 12,1982; however, it remained down for the rest of the month because of damage to a low pressure turbine sustained during the initial rolling of the turbine during startup.

There are 764 fuel assemblies presently in the reactor vessel. There are 8 new fuel assdemblies; 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 985 locations.

4

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Ooerations Sivrrnarv (Continued)

April 1982 Fatigue Usace Evaluation The cumulative usage factors for the reactor vessel are as follows:

Location Usare-Factor Unit-1 Unit-2 Unit-3 Shell at water line 0.00549 0.00432 0.00377 Feedwater nozzle 0.26690 0.18769 0.14201 Closure studs 0.21353 0.14460 0.12439 NOTE:

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

Common System Approximately 3.99E+05 gallons of waste liquids were discharged containing approximately 1.83E-01 curies of activities.

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Sianificant Ooerational Event Unit 1 Date Time -- -

- - - - Event- --

5/01/82 0001 Reducing thermal power for turbine control valve tests and sis from 97% thermal power.

0200 Reactor thermal power at 93%, holding for turbine control valve tests and sis.

0250 Turbine control valve tests and sis complete, commenced power ascension.

0300 Reactor thermal pwoer at 99%, maximum flow, rod limited.

5/08/82 0245 Reduced thermal power to 97% for CRD exercise (SI 4.3.A-2).

0405 CRD exercise complete, commenced PCIOMR.

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

5/15/82 0505 Commenced reducing thermal power for turbine control valve tests and sis.

0525 Reactor thermal power at 77%, holding for turbine control valve tests and sis.

0603 Turbine control valve tests and sis complete, commenced reducing thermal power for recirculation pump MG set brush replacement.

0620 Reactor thermal power at 50%, holding for recirculation pump MG set brush replacement.

1034 Recirculation pumps brush replacement complete, commenced power ascension.

1201 Commenced reducing thermal power from 62% for scram testing control rods.

1300 Reactor thermal power at 51%, holding for scram testing control rods.

1408 Control rod scram testing complete, holding for control rod sequence exchanged from "B" to "A".

1900 Commenced power increase for control rod sequence exchange from "B" to "A".

2145 Control rod sequence exchange complete, commenced power ascension from 72% thermal power.

5/16/82 0400 Commencd PCIOMR from 75% thermal power (Sequence "A").

5/17/82 1900 Reactor thermal power at 99%, maximum flow,, rod limited.

5/ 21/82 2300 Commenced reducing thermal power for control rod pattern adjustment.

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Significant Ooerational Event Unit 1 Date-

- Tie-Event - - -

5/22/82 0100 Reactor thermal power at 67% for control rod pattern adjustment.

0130 Increasing thermal power for control rod pattern adjustment.

0436 Control rod pattern adjustment complete, commenced power ascension from 75% thermal power.

0500 Commenced PCIOMR from 78% thermal power (Sequence "A").

5/23/82 0500 Reactor thermal power at 99%, maximum flow, rod limited.

5/29/82 0048 Commenced reducing thermal power for turbine control valve tests and sis.

0200 Reactor thermal power at 88%, holding for turbine control valve tests ad sis.

0217 Turbine control valve tests and sis complete, comenced power ascension.

0410 Comenced PCIOMR from 95% thermal power.

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

5/31/82 2400 Reactor thermal power at 995, maximuin flow, rod limited.

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Sinnificant-Ocerational-Event Unit 2 Date- -

Time - - - - - - - - - -

- - - - - - Even t-5/01/82 0001 Reactor thermal power at 90%, maximum flow, EOC-4 coastdown.

5/04/82 0700 Reactor thermal power at 89%, maximum flow, EOC-4 coastdown.

5/05/82 2300 Reactor thermal power at 88%, maximum flow, EOC-4 coastdown.

5/07/82 2235 Comenced reducing thermal power for recirculation pump MG set brush replacement.

5/08/82 0400 Reactor thermal power at 42%, holding for recirculation pmp MG sets brush replacement.

0430 Recirculation pump MG sets brush replacement complete, comenced power ascension.

1200 Reactor thermal power at 915, maximum flow, EOC-4 coastdown.

1500 Reactor thermal power at 90%, maximm flow, EOC-4 coastdown.

2100 Reactor thermal power at 89% maximm flow, EOC-4 coastdown.

5/09/82 0300 Reactor thermal power at 88%, maximum flow, EOC-4 coastdown.

1200 Reactor thermal power at 87%, maximum now, EOC-4 coastdown.

5/10/82 0800 Reactor thermal power at 86%, maximum flow, EOC-4 coastdown.

5/15/82 2300 Reactor thermal power at 85%, maximum flow, EOC-4 coastdown.

5/17/82 1500 Reactor thermal power at 84%, maximum flow, EOC-4 coastdown.

5/21/82 1500 Reactor thermal power at 83%, maximum flow, EOC-4 coastdown.

5/24/82 1600 Reactor thermal power at 82%, maximum flow, EOC-4 coastdown.

5/26/82 2300 Reactor thermal power at 81%, maximum flow, EOC-4 coastdown.

5/28/82 2300 Reactor thermal power at 80%, taaximum flow, EOC-4 coastdown.

5/31/82 2400 Reactor thermal power at 80%, maximum flow, EOC-4 coastdown.

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Significant-Ocerational-Event Unit 3 Date

- -- Time -

- Ev en t-5/01/82 0001 Unit remains offline for maintenance on 3C low pressure turbine.

5/20/82 0628 Maintenance complete on 3C low pressure turbine, commenced rod withdrawal for startup.

0735 Reactor Critical No.118.

1910 Rolled T/G.

2225 Synchronized generator, commenced power ascension.

5/21/82 0156 Generator offline for turbine overspeed trip test.

Reactor power at 20%.

0232 Turbine overspeed trip test complete, synchronized generator, commenced power ascension from 20%

thermal power.

5/22/82 1300 Reactor thermal power at 35% for RTI-5 (Scram Testing Control Rods).

1500 Reactor thermal power at 36%, RTI-5 in progress.

2300 Reactor thermal power at 38%, RTI-5 in progress.

5/23/82 0700 Reactor thermal power at 37%, RTI-5 in progress.

5/24/82 2300 RTI-5 complete, commenced power ascension.

5/26/82 0330 Commenced PCIOMR from 65% thermal power (Control Cell Core).

5/ 27/82 0230 Stopped PCIOMR for envelope development, reactor power at 81%.

0530 Commenced PCIOMR from 81% thermal power.

1426 Reduced thermal power from 88% to 63% when A1 and A2 heaters isolated and B1 and B2 heaters gave high level alarm.

1445 A1 and A2 heaters back in service, commenced power ascension.

1500 Commenced PCIOMR from 76% thermal power (Control Cell Core).

5/28/82 1340 Commenced reducing thermal power from 93% to i

remove "3A" condensate booster pump from service for maintenance.

1405 Condensate booster pump out-of-service for i

maintenance, reactor thermal power at 78% and decreasing.

1800 Reactor thermal power at 75% for maintenance on "3A" condensate booster pump.

2300 Reactor thermal power at 76% for maintenance on "3A" condensate booster pump.

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Significant-Ocerational-Event Unit 3 Late

- Time- ----

- - - - - -- - - - - - - - Ev en tr - - ---- - -- - - -- ----- --------,

5/29/82 0250 "3A" condensate booster pump back in service, commenced power ascension.

0340 Commenced PCIOMR from 77% thermal power (Control Cell Core).

2300 Reactor thermal power at 94% for APRM and LPRM calibration (SI 4.1.B-2 and 3).

5/30/82 0200 Reactor thermal power at 93% for APRM and LPRM calibration.

2020 LPRM and APRM calibration complete, reactor thermal power at 93%, holding for startup testing.

5/31/82 0445 Commenced PCIOMR from 93% thermal power (Control Cell Core).

0930 Reactor thermal power 96%, maximum flow, rod limited.

1530 Commenced reducing thermal power due to high vibraton alarm on "3B" recirculation pump.

1550 Alanm cleared on "3B" recirculation pump at 94%

thermal power.

1630 Commenced reducing thermal power for removal of "3A" recirculation pump MG set from service for electrical maintenance (field ground annunciation).

1740 "3A" recirculation pump out-of-service for maintenance on MG set, reactor thermal power at 54%.

2000 Reactor thermal power at 52%, holding for maintenance on "3A" recirculation pump MG set.

2035 "3A" recirculation pump back in service, holding at 52% power for removal of "3B" recirculation pump from service for maintenance on MG set.

2100 "3B" recirculation pump out-of-service for maintenance.

Reactor thermal power at 52%.

l 2235 "3B" recirculation pump back in service, commenced power ascension.

I 2400 Reactor thermal power at 70% with power ascension in progress.

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AVERAGE DAILY UNIT POWER LEVEL 50-259 DOCKET NO.

UNIT _ Browns Ferry - 1 6-1-82 DATE COMPLETED BY T. Thom TELEPilONE 205 729 0834 M0'NTil May 1982 DAY AVERAGE DAILY PO,WER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net),

(MWe-Net)

I 1039 17 1023 1053 2

18 1041 3

1048 1057 g9 1052 1041 4

20 1047 5

21 1039 1050 6

22 852 1047 7

23 1053 1045 8

24 1032 1050 9

25 1040 1051 1039 10 26 Ii 1051 1047 27 1042 1037 12 g

1045 1917 13 9

1050 1042 14 3g 671 1036 is 3

16 848 S

INSTRUCTIONS On t!iis fortnat.! st the average daily unit power lesel in Mwe. Net for each day ni the reporting inonth. Coinpute to the nearest whole nwgawaii.

(9/77) j I

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s AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-260 UNIT Browns Ferry - 2 DATE 6-1-82 COMPLETED BY T. Thom TELEPHONE 205 729 0834 MAY 1982 MONTil DAY AVERAGE MI PO, ER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe-Net) 957 904 I

7 958 896 2

18 3

954 19 901 4

951 895 20 938 5

21 892 933 876 6

22 7

919 885 23 8

840 872 24 934 866 9

25 918 861 10 26 II 915 858 27 914 848 12 28 13 912 29 839 842 14 30 902 15 3

836 905 16

.s INSTRUCTIONS On this format. fist the userage daily unut power lesel in MWe Net for each day in the reporting month. Compute to t te nearest whole megawati.

(9/771 sus teor.caswe,4.w.w;m -

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12 se AVERAGE DAILY UNIT POWER LEVEL 50-296 DOCKET NO.

UNIT Browns Ferry - 3 DATE 6-1-82 COMPLETED BY T. Thom TELEPHONE 205 729 0834 MO' NTH DAY AVERAGE DAILY PO,WER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Ned (MWe-Net)

-13

-12 g

g7

-13 2

18

-12 3

-12 19

-14 4

-13

-4 20 5

-12 139 21 6

-13 272 22

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322 7

23 8

-11 24 316

-13 9

25 450

-12 10 26 715 II

-12 817 27 12

-12 837 28

-12 13 872 29 14

-13 966 30 15

-13 807 3

-12 16

.s INSTRUCTIONS On this fonnat. fist the avera e daily unit power lesel in Mwe. Net f or each day in the reporting inonth. Compute to g

the nearest whole nw, awaii, g

l (9/77) i WNM' *3"m *verw rew;w v.- r.... g,y.

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OPERATING DATA REPORT DOCKET NO.

50-259 DATE 6-1-82 C051PLETED BY T. Thom TELEPIIONE 7M 774 0834

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OPERATING STATUS Browns Ferry - 1 Notes

1. Unit Name:

2. Reporting Period:

May 1982 3293

3. Licensed Thermal Power (5tht):

4. Nameplate Rating (Gross alWe):

1152 1065

5. Design Electrical Rating (Net SIWE):

1098.4

6. %1asimum Dependable Capacity (Gross SlWe):

I

7. Slasimum Dependable Capacity (Net 51We):

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 51We):

10. Reasons For Restrictions. If Any:

NA This alonth Yr. t0 Date Cumulative 744 3,623 68,665

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11. Ilours in Reporting Period 744 3,353.97 42,668.77

12. Number Of Ilours Reactor Was Critical 0

220.63 5,435.83

13. Reactor Reserve Shutdown llours 744 3,316.57 41,746.74

14. Ilours Generator on-Line 0

0 0

15. Unit Reserve Shutdown llours

16. Gross Thermal Energy Generated (31Wil) 2,392,200 10,337,851 117,212,758

17. Gross Electrical Energy Generated (.\\1Wil) 783,060 3,372,290 38,664,740

18. Net Electrical Energy Generated (51Wil) 757,945 3,279,115 37,548,024

19. Unit Senice Factor 100 91.5 60.8

20. Unit Availability Factor 100

.91.5 60.8 95.7 85.0 51.3

21. Unit Capacity Factor (Using SIDC Net) 95.7 85.0 51.3

22. Unit (.apacity Factor (Using DER Net) 0 8.5 25.9

23. Unit Forced Outage Rate

24. Shutdowns Scheduled Oser Nest 6 Slonths (Type. Date.and Duration of Each):

a

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

26. Units in Test Status (Prior to Commercial Operation):

Forecast Achiesed INITIA L CIllIICA LITY INITI A L ELECTit! CITY CO\\l\\lERCI AL Ol'FRATION (9/77)

14 es

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OPERATING DATA REPORT DOCKET NO. 50-260 DATE 6-1-82 COMPLETED BY I. Inom TELEPilONE 205 729 0834 OPERATING STATUS Browns Ferry - 2 Notes

1. Unit Name:

2. Reporting Period:

May 1982

3. Lice'nsed Thermal Power (MWt):

3293 1152

4. Nameplate Rating (Gross MWe):

1065

5. Design Electrical Rating (Net MWe):

6. Maximum Dependable Capacity (dross MWe):

1098.4 1065

7. Maximum Dependable Capacity (Net MWe):

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

NA

^

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

NA

10. Reasons For Restrictions. If Any:

This Month Yr to-Dare Cumulative 744 3,623 63,606 I

11. Ilours in Reporting Period

12. Number Of Ilours Reactor Was Critical 744 3,456.78 41,903.74 0

157.72 13,639.48

13. Reactor Reserve Shutdown llours

14. Ilours Generator On-Line 744 3,401.38 50,598.4/

15. Unit Reserve Shutdown IIours 0

0 0

16. Gross Thermal Energy Generated (MWil) 2,085,077 10,481,038 117,133,828

17. Gross Electrical Energy Generated (MWil) 693,650 3,525,400 38.958,048

18. Net Electrical Energy Generated (MWil) 668,119 3,429,396 37,851,542

19. Unit Service Factor 100 93.9 63.8

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20. Unit Availability Factor 100 93.9 63.8

21. Unit Capacity Factor IUsing MDC Net) 84.3 88.9 55.9

22. Unit Capacity Factor (Using DER Net) 84.3 88.9 55.9

23. Unit Forced Outage Rate 0

6.1 27.7

24. Shutdowns Scheduled Oser Ne.st 6 Months (Type. Date,and Duration of Each):

Refuel Outage July 1982 s

25. If Shut Down At End 0: Report Period. Estimated Date of Startup:

26. Units in Test Status (l'rior to Commercial OperationP Forecast Achiesed INIIl \\ L CRITICA LITY INITIAL ELECTRICITY COMMERCITL OPERATION (9/77) s w,rreenermwve wwv - --v o

.+

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15 OPERATING DATA REPORT DOCKET NO. 50-296 DATE 6 82 CO5IPLETED BY T. Thom TELEPl!ONE ?ns 779 0834 OPERATING STATUS

1. Unit Name:

Browns Ferry - 3 Notes

2. ReporJing Period:

May 1982

3. Lice' sed Thermal Power (SIWt):

3293 n

4. Nameplate Rating (Gross 51We):

1152 1065

5. Design Electrical Rating (Net SIWE):

6. Staximum Dependable Capacity (dross 31We):

1 98.4

7. Staximum Dependable Capacity (Net 51We):

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

NA NA

9. Power Lesel To Which Restricted,If Any(Net 51We):

10. Reasons For Restrictions.If Any:

NA b

This Slonth Yr.-to-Date Cumulative i1. Ilours in Reporting Pen. d 744 3,623 46,031 I

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12. Number Of flours Reactor Was Critical 280.42 336.55 32,803.53

13. Reactor Reserve Shutdown llours 463.58 902.37 3,043.90

14. Ilours Generator On Line 264.98 264.98 32,015.76

15. Unit Reserve Shutdown llours 0

0 0

16. Gross Thermal Energy Generated (5tWil) 528.859 528,859 94,387,479

f. -

17. Gross Electrical Energy Generated (31Wil) 163.780 163.780 31.161,970

18. Net Electrical Energy Generated (51Wil) 151,465 151,465 30,239,511

19. Unit Senice Factor 35.6 7.3 69.6

20. Unit Availability Factor 35.6 7.3 69.6

21. Unit Capacity Factor (Using SIDC Net) 19.1 3.9 61.7

22. Unit Capacity Factor (Using DER Net) 19.1 3.9 61.7

23. Unit Forced Outage Rate 64.4 77.7 11.5

24. Shutdowns Scheduled Oser Next 6 31onths (Type, D.ite.and Duration of Eachl:

25. If Shut Down At End Of iteport Period. Estimated D.ite of Startup:

26. Units in Test Status (Prior io Commercial Operation):

Forecast Achiesed INITIT L CRITICA LITY INITI A L ELECTRICITY Coil %IEllCI \\L OPER ATION

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bA DOCKET NO.

50-260 7; {}

UNIT SifUTDOWNS AND POWER REDUCTIONS UNIT NAME nrnm a Terrv - 2 py i DATE 6-1-82

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7 COMPLETED BY T. Thom REPORT MONTH May I

TELEPilONE 729 0834 1

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Date g

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Event sa 5

j5g Report a N0

}U Prevent Recurrence j

6 235 5/07/82 S

B Derated for MG set brush replacement C

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2 3

4 F: Forced Reason:

Method:

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

I-Manual for Preparation of Data El-Maintenance of Test 2-Manual Scram.

Entry Sheets for Licensee C Refueling 3 Automatic Scram.

Event Report (LER) FileiNUREG-D-Regulatory Rest iction 4-Other (Explain) 0161)

E-Operator Training & License Examination F-Administrative 5

G Operational Error (Explain)

Exhibit I - Same Source (9/77)

I 11-01her (Explain)

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$i's 50-259 G k DOCKET NO.

UNIT SilUTDOWNS AND POWER REDUCTIONS j

e DATE 6-1-82

~1 UNIT NAME Browns Ferry fi M MAY COMPLETED BY T. Thom REPORT MONTH TELEPilONE 205 7?9 ORu

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222 5/15/82 S

B Derated for turbine control valve tests and SI's, recirculating pump MG set brush replacement, and con-trol rod sequence exchange from "B"

to "A".

223 5/21/82 S

H Derated for control rod pattern adjustment.

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4 F: Forced Reason:

Method:

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

Entr> Sheets for Licensee C Refueling 3 Automatic Scram.

Event Report (LER) File (NUREG.

D Regulatory Restriction 4-Other (Explain) 0161)

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E-Operator Training & License Examination F-Administrative 5

G-Operational Error (Explain)

Exhibit I-Same Source l

(9/77) li-Ot her (Explain) t e

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1

INSTRUPINT PAINTESANCE SU10%RY CSSC EQUIP!'ENT FOR IllE MONTil OF 5

19 82 r

NATURE EFFECT 05 SAFE CAUSE ATE SYSTEM CCMPONENT OF OPERATION OF CF FISL*LTS OF TO PPICLUDE l

ACTION TX:GN FAINTENA' ICE Tr E REACTOR MALFLTCTION P.ALTUNCTION 8

RECUR?ISCE U-1 o

s 5-3 64 PDT-64-137 Calibration None Instrument Drift Incorrect Indication None 5-4 64 PDT-64-137 Replace None Instrument Drift Incorrect Indication Replaced Transmit'-

ters.

_.r 5-17 63 Pl-63-7B Calibration None Instrument Drift Incorrect Indication None U-2 5-10 90 R1-90-143 Repair None Failed Transistors Incorrect Indication None 5-11 90 PDIS-90--165 Calibrate None Instrument Drift

• Incorrect Indication None U-3

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5-3 90 RR-90-135 Calibrate None Instroment Drift Incorrect Indication None e

5-18 71 PDIS-71-1A Replace.

-None Instrument Drift Incorrect Ittdication Replaced

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5-18 71 PD'lS-71-1B Replace None Instrument Drift Incorrect Indication Replaced i

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',1 f 50-296 DOCKET NO.

D UNIT SilUTDOWNS AND POWER REDUCTIONS i

UNIT NA\\tE Browns Ferry - 3 Wy DATE 6-1-8?

TJ COMPLETED BY T

Thn-REPORT MONTH May

'f TELEPilONE 205 729 0834 x eh s

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Nm Date i

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93 Action to y-5 j!! gg =2 Report a mu 5O Prevent Recurrence 1

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94 5/01/82 F

478.42 A

2 Maintenance on "3C" low pressure turbine continues i

95' 5/21/82 S

.60 B

Generator off line for turbine over-i speed trip test 5

96 5/31/82 F

B Derated for maintenance on "3A" re-circulation pump MG sets.

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I 2

3 4

F: Forced Reason:

Method:

Exhibit G - Instructions S: Scheduled A Equipment Failure (Explain) 1-Manual for Preparation of Data 11-Maintenance of Test 2-Manual Scram.

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

Event Repor (LER) File (NUREG-D Regulatory Restriction 4-Other (Explain) 0161)

'?

E-Operator Training & License Examination F-Administrative 5

G Operational Error (Explain)

Exhibit I - Same Source i

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

?

O

BROWNS FERRY NUCLEAR PLANT UNIT 1 & Common a[, f CSSC EQUIPMENT ELECTRICAL MAINTENANCE

SUMMARY

.y

'2 For the Month of May 19 82 Effect on Safe Action Taken

.j Nature of Operation of Cause of Results of To Preclude Dtte System Component Maintenance The Reactor Malfunction Malfunction Recurrence 5/17/82 Air Con-Control Bay Annual main-None During the per-Oil leak at vane The vane drive ditioning chiller "B" tenance (EMI-formance of EMI-drive shaft.

assembly and j

(Cooling-vane drive 60) 60 a oil leak O' rings were Heating) assembly-was found at the replaced and EMI-l vane drive

?

60 successfully

.f shaft completed.

TR #332565 3

3 TR #183963 4

5/17/82 Annuncia-Common Common sounder None Bad horn Annunciation alarms Replaced the bad tor sounder horn horn inoper-could not be pre-horn, the annunid on panel 9-5 able ceived by sound ciator h.orn oper-ated properly.

l TR #338058 TR #337400 5/20/82 Air Con-

1. 2 Spreader Supply fan None Bad fan motor Supply fan inoper-The motor was ditioning room supply inoperable able replaced per (Cooling-fan EMI-33 and the Heating) supply fan returned'to service.

TR #342832

}

3 a.

BROWNS FERRY WUCLEAR PLANT UMZT 1 and Common CSSC EQUIPMENT ELECTRICAL MAINTENANCE SLM!ARY For the Month of May 19 82 i #

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

Date System Component Maintenance The Reactor Malfunction Malfunction Recurrence 5/6/82 RHR 1 EA LPCI MG The fan was None The fan was The fan was scrubbing Realigned and set fan making exces-loose against the end bell tightened the sive noise fan.

TR #188305 5/8/82 RilR 1 EA LPCI MG Output voltage None LPCI voltage Output voltage drift-Adjustments were set voltage drifting regulator out of ing made to the reg-regulator adjustment ulator to increase the output voltage from 461 volts to 490 volts. The g

regulator opera o ted properly.

4 TR #314440 5/10/82 Contain-Relay R2 in H sample None, the "A" Contacts 3-7 and "B" H Analyzer was Relay R2 was 2

2 ment panel 25-341 inlet pump was hydrogen 4-8 of relay R2, inoperable replaced and i

Inerting discovered to analyzer was which supply SI 4.7.H was be inoperable operable power to the H2 successfully peg-sample inlet formed. This e

pump motor event is being failed.

investigated further to determine' the cause for the failure of the relay contacts.

The results of this investiga-tion will be 4

available by 7/15/82.

TR #207405 BFRO-50-259/B231

in '-

hh BROWNS FERRY NUCLEAR PLANT UNIT 1 & Common FI, }

[}

CSSC EQUIPMENT ELECTRICAL MAINTENANCE

SUMMARY

i d

For the Month of May 19 82 i ?,

Effect o.. Safe Action Taken Nature of Operation of Cause of Results of To Preclude l

Date System Component Maintenance The Reactor Malfunction Malfunction Recurrence 5/b6/82 Air Con-

"1A" shut-Excessive None Bad motor Excessive' fan motor Replaced the ditioning down board vibration bearings vibration fan motor (Cooling-room supply bearings, the Heating) fan fan motor operated properly.

4 TR #338094 i

e

,A i

a

h!

it.d'.

BROWNS FERRY NUCLEAR PLANT UNIT 1 & Common CSSC EQUIPMENT ELECTRICAL MAINTENANCE

SUMMARY

I: Ij For the Month of May 19 82 3 Effect on Safe Action Taken f Nature of Operation of Cause of Results of To Preclude Date System Component Maintenance The Reactor Malfunction Malfunction Recurrence 5/25/82 4kV Shut-Degraded volt-- During the None, setpoint Unknown at this These relays' trip All the relays down age relays on performance of drifts were in time. Increased setpoints were found were recalibrated g Boards and 4kV Shtd. recurrence the conserva-temperature in to range from approx-to the correct f Busses Bds. B, C, control cali-tive (higher the boardrooms, imately 3941 to 3951 setpoint. The j and D bration (BFRO-voltage) range due to warmer das opposed to the calibration J 50-259/8213) weather, is required 3900 to frequency has ] of the degrad-suspected 3940-volt range been increased ed voltage until the prob-l relays (SI 4.9 i. lem is resolved. ) A.4.C), 8 out The setpoint of 9 relays on drift problem is y 4kV' shutdown now being eval-N boards B, C, uated by TVA and D were Engineering found to oper-Design. ate above the NOTE: Unit 3 required 3900 shutdown board to 3940-volt relays were range checked 5/24/82 and 5/25/82 with' no problems # found. TR #225027' BFRO-50-259/.8233-4 s I 4 9 I h 9 9 e

if y l4 BROWNS FERRY NUCLEAR PLANT UNIT 3 f* L, ' ! CSSC EQUIPMENT ELECTRICAL MAINTENANCE SUMHARY .,j-For the Month of May 19 82 ,:f 3 e) :) Effect on Safe Action Taken Nature of Operation of Cause of Results of To Preclude Date System Component Maintenance The Reactor Malfunction Malfunction Recurrence 4/28/82 RHRSW Relay TD2A During the None, all other During perform-RHRSW pump A3 failed Relay TD2A was circuitry on performance of RHRSW pumps ance of SI 4.2.B-to automatically replaced per 4kV shutdown SI 4.9 A.l.a were available 14 conductors start when diesel EMI-23 and the .j board 3EA RHRSW pump A3 and operable are lifted and generator 3D was relay setpoint a failed to auto-reterminated on

started during the check was per-j matically relay TD2A.

performance of formed per EMI-j start when During the per-SI 4.9.A.1.a 15. The relay diesel genera-formance of this was functionally i tor 3D was SI on 3/20/82, tested and the i, started conductors were-pump returned to apparently term-service. Re-inated on the currence controhj wrong terminal will consist of by maintenance training classes personnel due to to be conducted I improper imple-by 6/21/82. mentation of These classes will procedural stress proper controls implementation of procedural icontrols. j ,TR #314088 s I BFRO-50-296/8216 .i e e Y e i + + _.. ..y ~+

b BROWNS FERRY NUCLEAR PLANT UNIT 2 NV hk CSSC EQUIPMENT ELECTRICAL MAINTENANCE

SUMMARY

n% p{ For the Month of May 19 82 Effect.on Safe Action Taken 3 Nature of Operation of Cause of Results of To Preclude Date System Component Maintenance The Reactor Malfunction Malfunction Recurrence 4/30/82 Air Con-Shutdown A grounded None Bad fan motor Exhaust fan 2A Replaced the bad ditioning board room circuit was inoperable (grounded) 4 (Cooling-exhaust fan indicated motor, the f Heating) 2A motor exhaust fan s I operated I properly. TR #314079-5/2/82 High-Pres-Fire pump A Received a None Stuck relay Received a false Freed the relay, sure Fire annunciator false " pump " pump running" annunciation Protection circuitry running" annunciation cleared. Z. s + annunciation TR #314078 9 5/3/82 4kV Shut- "C" 4kV shut-Battery charg-None, SI 4.9.A. Bad diode in the "C" 4kV shutdown bd. The spare down down board er breaker 2.b was per-battery charger battery charger battery charge Boards & 250V battery tripped formed and power circuitry inoperable was connected to Busses charger proved battery the battery. The operable normal chager's bad diode was . replaced and I SI 4.9.A.2.b was repeated. The normal charger was returned to service. [ TR #314074 l i i s 9 a

BROWNS FERRY NUCLEAR PIANT UNIT 1 l f,{ ~ MECHANICAL MAINTENANCE

SUMMARY

, f.f CSCC EQUIPMENT

hs For the Month of May 19 82

~ l;- 5 l ACTION TAKEN EFFECT ON SAFE DATE SYSTEM COMPONENT NATURE OF OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE MAINTENANCE Tile PEACTOR MALFUNCTION MALFUNCTION RECURRENCE 4-21 IIPCI IIPCI Booster Leakage None Oil Drain Plug Small oil leak Tightened oil drain 4, Pump loose plug TR# 338964 9 4-01 RCIC RCIC Oil Sump Low Oil None Unknown Oil level low Added 6 qts. STO-1 with inhibitor Pump TR# 306660 [i + 6-07 Core Spray Suction Supply Indicating None Rod loose-Ro'd non-functional Replaced rod Valve 75-11 rod broken TR# 339089 4-26 RIIR Drain line from Leak None Cap missing Water leaking out on Replaced 1/2" cap floor TR# 253406 RllR pump 1-A i ! 4-26 CRD l-A CRD Pump Leak None. Bad water line Water leak at seal Replaced 1/2" line and water line pipe 1/2" union y" union under pump TR# 313712 e 4-21 CRD Module 50-31 Needs rebuild None Faulty Accumu-Accumulator not Replaced O' rings & Accumulator lator operating properly seal TR# 339828 5-19 IIPCI Vent valve Nut missing None Unknown' Nut missing from Replaced nut on valve HCV-73-538 valve gland TR# 273424 s 5-20 llPCI Oil Tank Needs plug in Mone Unknown No plug Install plug' TR# 311912 Drain Line line [ 5-21 Cond. 110 Line Valve Broken valve None Broken fitting Leakage Replaced nipple Demin 221181 on elbow TR# 342809 i c .. ame f e w m m em

n< !) f BROWNS FERRY NUCLEAR PLANT UNIT 3 Id Y k CSSC EQUIPMENT ELECTRICAL MAINTENANCE

SUMMARY

t P } I3 For the Month of May 19 82 ,?b $ .: 3 Effect on Safe Action Taken

j Nature of Operation of Cause of Results of To Preclude Date System Component, Maintenance The Reactor Malfunction Malfunction Recurrence 5/3/82 Air Con-Shutdown Bd.

Shutdown Bd. None Bad overloads Chiller inoperable Replaced the bad ditioning room chiller room chiller overloads, added j (Cooling-33-2 3B-2 tripped freon to the f Heating) chiller, and returned the j chiller to j service. j TR #225803 i. 5/17/82 Neutron Relay 7C-K9H 1RM channel D None Bad relay coil 'IRM channel D Replaced the bad Monitorint inoperable inoperable relay coil, ,j returned.the relay to service. TR #342725 Air Con-Spreading Supply fan None Motor burned up Supply fan inoper-Replaced the ditioning room supply inoperable able burned motor 5/27/82 (Cooling-fan per EMI-33. Heating) .TR #341554 I-TR #338077 s y 3

h{ BROWNS FERRY NUCLEAR PIANT UNIT 3 ~ ~' a :s MECHANICAL MAINTENANCE

SUMMARY

gy CSSC EQUIPMENT For the Month of Fby 19 82 f. EFFECT ON SAFE ACTION TAKEN s DATE SYSTEM COMPONENT NATURE OF OPERATION OF CAUSE OF RESULTS OF 10 PRECLUDE MAINTENANCE THE REACTOR MALFUNCTION MALFUNCTION RECURRENCE 4-29 LPCI 3DN LPCI MG Suspect Flywhl,None Unknown Low bearing grease Replaced bearing __ Set bearing "D" is grease bad TR# 235035 l 2 5-04 HPCI HPCI Turbine Remove spool None Unknown Unknown Removed aux. steam piece spool pc. 8 installed blind flanges. TR# 311942 7 C I S O4 D/G 3A D/G A Air Air Comp. will None Faulty head Pump not pumping Replaced head gasket; Compressor not pump gaskets high-pressure cylinder TR# 225805 5-03 HPCI HPCI Turbine Install spool None None None Installed aux. steam piece spool piece ~ g TR# 342042 'o 5-03 RCIC RCIC Turbin Install spool None None None Installed aux. steam piece spool piece TR# 342051 4-22 EECW PCV-67-79 Leak None Bolt Broken Bonnet Leak Replaced bolt on bonnet TR# 341509 Unknown 5/8" OD copper line Cleaned & replace $ 4-26 Control Ba rTCV-31-50B Leak None l Heat, Vent leaking tubing. Resweated & A.C. copper line. TR# 342007 .5-24 CRD Module HCV Module. slow to None O' rings bad-needt Scram valve not Replaced O' rings in 55 scram pilot start moving repair kit working scram valve. Install valve during scram repair kits TR#. 342068 timing 5-23 CRD Coggrol Rods Slow to begin None Faulty diaphragm Control rods slow to Replaceddidphragm& 18-07 & 54-47 travel upon O' rings, pilot respond pilog head sub-assem- ' receiving a head assembly & bly & body gaskets & i scram signed body gaskets O' rings ~ ,TR# 341565

e W f ',/ i> c .' r BROWNS FERRY NUCLEAR PIANT UNIT 2 - 4 \\ MECHANICAL MAINTENANCE SUNMARY [': $ CSSC EOUIPMENT / For the Month of May 19 82 - t / ' r W ,t' t EFFECT/ON SAFE ACTION TAKEN DATE SYSTEM CQ1PONENT NATURE OF . OPERATION OF CAUSE OF RESULTS OF 'ID PRECLUDE MAINTENANCE ) THE REACTOR MALFUNCTION MALFUNCTION RECURRENCE 3-31 Fuel Pool 2A FPC Pump Pepp running None Outboard bearings Pump,not operating Replaced outboard. ' ~ Cooling hot bad & packing out properly bearings. Filled with ~ grease & adjusted l of adjustment packing TR# 229930 4-23 IIPCI FE-73-33 Flow element None Worn gaskets Faulty gaskets Replaced gaskets TR# 233340 non-functional 4-24 HPCI IIPCI Gland Faulty Gasket None Top gasket Prevents condensor Changed gasket Seal Condensor blown from functioning TR# 340315, properly 3-19 HPCI HCV-73-587 Broken pin in None Sheared pin in Replaced pin in handwheel handwheel Handwheel inoperable handwheel. TR# 229906 w co 4-20 RilR FCV-23-34 Service water' None Bolts broken Valve not bolted Replaced operator with A Heat Exch. outlet valve securely new bolts needs new TR# 339822 bolts 4-02 Fire Line between Hole in fire None Pin hole in 3" Corrosion contribu-' Welded hole in pipe Protection valves 26-990 protection line ed to water leakage TR# 337818 & 26-984 line 5-7 CRD Module 42-23 Leak None Faulty Valve Valve leaking Replaced valve & y & 0' Ring Gaskets 2 0' ring gaskets HCV-Directional Control Valve TR# 314584 5-20 HPCI Hyd, oil Tank Plug needs None Plug in oil drair Drain valve not Replaced 1" threaded Drain Valve replacing valve missing operating properly plug TR# 311910 5-19 Fire Piping between Pipe leaking None Piping Eroded Water Leak Replaced 20' section Protection Valves 2-26-990 of 3" carbon steel & 2-26-984 pipe / TR# 103388 t e e e

31 o FIrin SERVICES

SUMMARY

May 1982 General The principal Field Services effort during the month of May has been 3C LP turbine reassembly following repairs to the damaged 13th stage (damage occurred during initial turbine roll April 12, 1982 which took place at the completion of the unit 3 cycle 4 refueling / torus outage). The lower half of the modified pressure reducing plate for 3C LP turbine was received May 13, 1982, and turbine reassembly was completed May 17, 1982. Unit 3 startup procedures were then performed and the unti was tied online at 2225 hours on May 20, 1982. This ended a forced turbine outage on unit 3 with a duration of 38 days. The auxiliary boiler modification (P0305) was completed during the report period and the dewatering pump comitment was met. Other general work items include; EPA modifications, LPCI modification, automatic backwash modifications, PASF modification, fabrication of "M" and "N" line MSRV tailpipes as part of P0093 prefabrication, debris screens prefababrication, and preparation of the fabrication shop with stainless steel and welding test work areas. Electrical The major work during the last month has been: 1. Provide plant data from cooling tower gate structures and pumphouse to the environmental data station by the way of the RRRMS computer (PO480) - installation of conduit is in progress. 2. LPCI modifications (L1845) - installation of conduit on unit 2 elevations 621 and 639 is in progress.

ij h BROWNS FERRY NUCLEAR PIANT UNIT 3 ~ $. h CSSC EOUIPMEiiT MECHANICAL MAINTENANCE

SUMMARY

n

j For the Month of May 19 99 L

y EFFECT ON SAFE ACTION TAKEN DkTE SYSTEM COMPONENT NATURE OF OPERATION OF CAUSE OF RESULTS OF 10 PRECLUDE MAINTENANCE Tile REACTOR MALFUNCTION MALFUNCTION RECURRENCE 5-25 CRD Module 18-35 Valve won't None Valve stripped Stem nut on wheel Installed key back on Charging H P isolate handle worked loose. stem & tightened gtem 2 O isolation nut on charging water k valve valve TR# 342061 4-20 RBCCW Sup 1 Valve Broken Valve None Unknown Broken Valve Stem Replaced stem TR# 342001 j I3-5 EECW PCV-67-79 Faulty Valve None Bad diaphragm Worn diaphragm Replaced diaphragm & cleaned valve 3 TR# 311263 4-28 CRD HCV-58-39 Faulty Accumu-None Worn accumulator Accumulator not oper-Changed accumulator ' lator ating properly TR# 342033 5-8 CRD Valve 85-229A Leak None Worn packing Packing leak Replaced packing TR# 311256 4-30 CRD 58-39 Accumu-Faulty Accumu-None Bad accumulator Accumulator non-Rebuilt & replaced lator lator functional o' rings on accumula-tor TR# 307461 4 5-21 HPCI HPCI Turb. Pump Missing bolt None Unknown One bolt & nuts Replacedbolts&}uts Test Line & nuts missing & torqued bolts TR# 339785 5-20 HPCI Ilyd. oil tank Plug missing None Unknown No plug in pipe Plugged line drain valve TR# 339794 5-20 HPCI Valve 73-34 Handwheel None Handwheel missing Valve non-functional Replaced handwheel missing TR# 342031 5-23 CRD Control Rods Slow scram None Faul'ty diaphiagm Control rods slow to Replaced diaphragm 30- 5,22-11 insertion time O' rings, pilot respond & pilot head sub-06 35,34-47 head assembly & assembly and body 50-23,42-31 body gaskets gaskets & 0' rings. 54-27,42-27 TR# 311289 38-31,34-51 '4R-47

33 o FTFLD RFRVICES-

SUMMARY

May 1982 Mechanical (Continued) 3. Fabrication of debris screens (PO428) - two debris screens have been fabricated. 4. Prefabrication of vacuum breakers of the "N" line MSRV tailpipe has started. Sandblasting of pipe is in progress. Torus Unit 2 torus prefabrication and selected external modifications continue in preparation for the upcoming cycle 4 outage. 1. Tie down work has progressed through completion of drilling, cradle extension installation and MK I installation. Weld out of "A" plates was completed May 27, 1982 and grouting has started with three positions complete. 2. Temporary ECCS supports are complete at six locations and old ECCS supports are cut at four locations. Four templates have been sent to the power service shop for prefabrication. TWo new ECCS supports have been received and two others are still outstanding. 3. External ring girder reinforcing installation was locally approved on May 13, 1982 and four locations were completed on May 26, 1982 with partial weld out as authorized. 4. Torus snubbers drilling equipment preparation is complete and final design drawings are expected in June. 5. Quencher end-arms prefabrication is complete on 16 of 26. l

32 o FTFTD SERVICES-

SUMMARY

May 1982 Electrical (Continued) 3. Provide visual indication of upscale and downscale trips to the unit operator for each annunciatin, trip, and CAM unit (P0254/L1997) - l l completed pulling cable, and tcrmination work is in progress - 70 i percent complete. 4. L2052 automatic backwash system for RCW strainers units 1, 2, and 3 - installing brackets, conduit, and junction boxes. Pulling cable on i unit 2. Completion unit 1 equals 34 percent, unit 2 equals 28 percent, and unit 3 equals 10 percent. 5. Update CCTV system (P0287) - pulling cables and continuity testing, cables for the CCTV cameras. 6. Illuminate exterior of the protected area (P0286) - installing junction boxes in manholes for camera feeder cables. Installation of l the diesel generator control wiring is in progress. 7. Other electrical work - assigning ECNs for the unit 2 cycle 4 refueling outage, providing temporary classroom facilities in the hypochlorite building for operations, support work, electrical inspections of cords, tools, and lights and telephone maintenance. Mechanical The major work activities in progress are: l 1. Work plans for the fabrication of the strongbacks for unit 1 and 2 were approved and fabrication is underway on the unit 2 strongback. 2. Installation of piping and a valve from radwaste floor drain to condensate waste phase separator (P0178) is approximately 12 percent complete. Work was often stopped due to operations havini to transfer radioactive waste, which restricted personnel in the area. l -}}