ML20112A097

Monthly Operating Repts for Jan 1985

ML20112A097
Person / Time
Site:	Browns Ferry
Issue date:	01/31/1985
From:	Jones G, Thom T TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8503180159
Download: ML20112A097 (33)

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TENNESSEE VALLEY AU'niORITY DIVISION OF NUCLEAR POWER BROWNS FERRY NUCLEAR FLANT MONTHLY OPERATING REPORT 'ID NRC January 1,1985 - January 31, 1985 DOCKET NUMBERS 50-259, 50-260, AND 50-296 LICENSE NUMBERS DPR-33, DPR-52, AND DPR-68 Submitted by: .

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8503180159 850131 PDR ADOCK 05000259 Ml s"

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TABLE OF CONTENTS Operations Summary. . . . . . . . . . . . . . . . . . . . . . . 1 Refueling Information . . . . . . . . . . . . . . . . . . . . . 3 Significant Operational Instructions. . . . . . . . . . . . . . 5 Average Daily Unit Power Level. . . . . . . . . . . . . . . . . 11 -

Operating Data Reports. . . . . . . . . . . . . . . . . . . . . 14 Unit Shutdowns and Power Reductions . . . . . . . . . . . . . . 17 Plant Maintenance . . . . . . . . . . . . . . . . . . . . . . . 20 Outose Maintenouve & Major Modification . . . . . . . . . . . . 27 1

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. 1 Ooerations %==nry January 1985 i

j f The following sunnary describes the significant operation activities during the reporting period. In support of this sununary, a chronological log of significant events is included in this report. ,

There were four reportable occurrences reported to the NRC during the month of January.

Unit 1 j There was one scram on the unit during the month. On January 16, 1985, the unit scrammed due to a feedwater level control instrument malfunction.

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Unit 2

) The unit was in cold shutdown the entire month for the unit's end-of-cycle 5 refueling outage. -

Unit 'O There was one scram on the unit during the month. On January 7, 1985, the unit was manually scrammed due to a loss of instrument power to RBCCW and i.,

recirclation temperature control valves.

Prepared principally by B. L. Porter. ,

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2 Ooerations Snn=nry (Continued)

Janaury 1985 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 0.00619 0.00492 0.00425 Feedwater nozzle 0.29671 0.21319 0.15906 Closure studs 0.23876 0.17629 0.14225 NOTE: This accumulated monthly information satisfies Technical Specification Sr-ction 6.6.f.17,R(3) repnrting re.;uir-ments.

Cnmmnn System Approximately 1.44E+06 gallons of waste liquids were discharged containing approximately 4.32E-01 curies of activities.

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.:  : 3 Ooerations Snmmarv (Continued)

January 1985 Refueling Information Unit 1 Unit 1 is scheduled for its sixth refueling approximately June 1,1985 with a scheduled restart date of March 31, 1986. This refueling will involve loading 8x8R (retrofit) fuel assemblies into the core, replacing recirculation ,

piping, work on "A" and "B" low-pressure turbine, upgrade hangers and anchors, and environmentally qualify instrumentations.

There are 764 fuel assemblies in the reactor vessel. The spent fuel stor-age pool presently contains 252 EOC-5 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 fuel pool capacity is 3,471 locations.

Unit 2 Unit 2 was shut down for its fifth refueling outage on September 15, 1984 with a scheduled restart date of August 1, 1985. This refueling outage will involve loading additional 8X8R (retrofit) fuel assemblies into the core, finishing torus modification, turbine inspection, piping inspection, TMI-2 modifications; post-accident sampling facility tie-ins, core spray chan'ge-out, and feedwater sparger inspection.

There are no fuel assemblies in the reactor vessel. At month end, there were 273 new fuel assemblies, 764 E0C-5 fuel assemblies, 248 EOC-4 fuel assemblies, 352 E0C-3 fuel assemblies, 156 EOC-2 fuel assemblies, and 132 EOC- '

l 1 fuel assemblies in the spent fuel storage pool. The present available capacity of the spent fuel pool is 77 locations. All old racks have been removed from the pool and new HDR's are being installed.

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Ooerations Sn - rv (Continued)

January 1985 Unit 9 Unit 3 is scheduled for its sixth refueling outage approximately November 30, 1985, with a scheduled restart date of November 10, 1986. This refueling involves loading 8X8R (retrofit) assemblies into the core, and complete reinspection of stainless steel piping.

'Ihere are 764 fuel assemblies presently in the reactor vessel. There are 248 EOC-5 fuel assemblies, 280 EOC-4 fuel assemblies, 124 EOC-3 fuel assemblies,144 EOC-2 fuel assemblies, and 208 EOC-1 fuel assemblies in the spent fuel storage pool. The present available capacity of the spent fuel pool is 914 locations.

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5 Significant Doerational Events Date Time Evenq Unit ;

01/01 0001 Reactor thermal power at 39-percent (%), maximum ficw, rod limited.

1500 Reactor thermal power at 98%, maximum ficw, rod limited.

01/05 1454 Commenced reducing thermal power for SI 4.3.A.2 (Control <

Rod Drive [CRD] Exercise).

1500 Reactor thermal power at 94% for SI 4.3.A.2.

1510 SI 4.3.A.2 complete, commenced power ascension.

1515 Commenced PCIOMR from 95% thermal power.

1615 Reactor thermal power at 975, maximum ficw, rod limited.

01/08 2300 Reactor thermal power at 96%, maximum flow, rod limited.

01/09 2000 Commenced reducing thermal power for controlled shutdown s

due to "C" Residual Heat Removal (RHR) heat exchanger and "A" Diesel Generator (D/G) being inoperable.

2325 Stopped load drop at 95% power.

01/10 0155 SI 4.5.C.3 complete, "C" RHR heat exchanger operable.

- 0230 Commenced power ascension from 95% power.

0300 Reactor thermal power at 965, maximum f1cw, rod limited.

1500 Reactor thermal power at 95%, maximum ficw, rod limited.-

01/11 1130 Commenced reducing thermal power for controlled shutdown due to "A" SLC pump and "C" D/G being inoperable.

1452 Stopped reducing thermal power at 94% thermal power, "A" SLC pump operable. Increasing thermal power.

1500 Reactor thermal power at 95%, maximum flow, r'od limited.

2230 Commenced reducing thermal power for control rod pattern adjustment.

01/12 0020 Reactor thermal power at 62% for control rod pattern adjustment.

Commenced power ascension for control rod pattern 0030 adjustment. '

0230 Reactor thermal power at 69% for control rod pattern adjustment.

0330 Control rod pattern adjustment complete, commenced PCIOMR from 69% thermal power.

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6 Significant Ooerational Events Date Time Event Unit 1 (Continued) 01/13 1500 Reactor thennal power at 100%, maximum ficw, rod limited.

01/16 1440 Reactor Scram No.177 from 100% thermal power on low water level. This was believed to have been caused by c the loss of steam to the reactor feed pump turbine by the level controller LIC-46-5.

01/18 1810 Unit in cold shutdown to repair IRM problem.

01/21 0835 Commenced rod withdrawal for startup.

1203 Reactor Critical No. 200.

1820 Commenced shutting down reactor for drywell entry to investigate excessive unidentified leakage in drywell.

Initial drywell inspection identified the leakage source as a flexible hose on the core spray system. Additional inspection identified a leak on a bonnet vent line (66-509) weld on the "A" recirculation discharge valve 60-3.

01/22 1030 Unit in cold shutdown.

01/24 0110 ' Maintenance on drywell leaks complete. The unit remains offline for another entry into drywell to repair IRM "H."

01/25 0338 Maintenance complete on IRM "H," commenced rod withdrawal for startup.

0637 Reactor Critical No. 201.

2034 Rolled turbine generator (T/G).

2127 Synchronized generator, commenced power ascension.

01/25 0200 Canmenced PCIOMR from 73% thermal power.

01/28 0145 Commenced reducing thermal power from 895 when "B" condensate booster pump tripped on low net positive suction head while placing "A" low-pressure heaters in service.

0150 Reactor power at 66% due to "B" condensate booster pump trip.

0155 Canmenced power ascension. ~

0240 Reactor power at 89%, commenced PCIOMR.

1300 Reactor thermal power at 955, maximum flow, rod limited.

2300 Reactor thermal power at 93%, maximum flow, rod limited.

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. 7 Sinnificant Ooerational Events Date Time Event Unit 1 (Continued)

Commenced reducing thermal power for removal of "A" 01/ 29 1130 Reactor Feedwater Pump (RFWP) from se71ce for repair of oil leak.

1210 Reactor thermal power at 71% for repair of leak on "A" RFWP.

1250 Commenced power ascension for control rod pattern adjustment.

1305 Completed power increase for rod adjustment at 75%

thermal power, decreasing thermal power.

4 1350 Commenced pulling rods for control rod pattern .

! adjustment, reactor power at 71%.

1400 Control rod pattern adjustment complete; reactor power at 71%, holding for "A" RFWP maintenance.

1500 "A" RFWP back in service, commenced power ascension.

1630 Commenced PCIOMR from 79% thermal power.

01/30 0842 Commenced reducing thermal power from 93% due to feedwater control problems.

0900 Peactnr thermal powar at 69% due to feedwater control problems (LIC-46-5).

0935 Water level recovered, Instrument Maintenance replaced LIC-46-5. Commenced rod withdrawal for core shaping.

1020 Commenced power ascension from 71% thermal power.

1100 Commenced PCIOMR from 93% thermal power.

, 01/31 0930 Reactor thermal power at 100%, maximum flow, rod l limited.

2400 Reactor thermal power at 100%, maximum ficw, rod .

limited.

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Sinnificant Ooerational Events Date Tim Event i

4 Unit 2 i

01/01 0001 End-of-cycle 5 refuel outage continues.

01/31 2400 End-of-cycle 5 refuel outage continues.

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.. . 9 Significant Ooerational Events Date Time Event Unit 3 01/01 0001 Reactor thermal power at 98% due to problems with indicating watthour meter.

01/06 0100 Commenced reducing thermal power for SI 4.3.A.2 (CRD Exercise).

0110 Reactor power at 91% for SI 4.3.A.2.

0120 SI 4.3.A.2 complete, commenced power ascension.

0230 Commenced PCIOMR from 93% themal power.

2035 Reactor themal power at 100%, maximum flow, rod limited.

01/0'T 1420 Commenced reducing themal power when "B" recirculation pump tripped as a result of Instrment Maintenance personnel performing maintenance on a temperature transmitter for reactor feedwater line "B" (TT-3-50C located on panel 3-25-182). The IMs had removed the instr ment for maintenance and were reinstalling the instrment when they inadvertently allowed the power cable to short to ground. This caused a breaker supplying power to panel 25-182 (breaker 411, panel 9-9, cabinet 4) from the plant preferred bus to trip. The

. instr ment panels that were affected were 3-25-182, 3-25-184, 3-25-196, 3-25-180, 3-25-181, and 3-25-179 The loss of power to these panels caused the E/P to give a false signal to the temperature controller. This caused the RCW temperature control valves for RBCCW heat exchangers A and B, recirculation MG set A and B oil coolers, RFPT A, B, and C oil coolers, alC fluid coolers, and generator exciter to go full closed. This caused the recirculation MG sets to trip on a high temperature.

01/07 1433 "A" recirculation pump tripped, reducing themal power.

1700 Reactor power at 33% due to the trip of A and B recirculation pumps when power cable to TT-3-50C was shorted. The IMs determined where panel 3-25-182 received power and got the ASE to reset breaker 411 and' all temperature controllers returned to normal. During thistime,thecoolanttemperagurebetweenthedomeand bottom head drain exceeded 145 differential limit. '

This prevented restart of the recirculation pumps.

1730 Reactor manual scram No.115 from 33% thegnal power when the temperature differential limit of 145 between the dome and bottom head drain prevented the restart of the recirculation pumps.

10 Significant Ooerational Events Date Time Event _

Unit 3 (Continued) 01/08 0620 Commenced rod withdrawal for startup.

1150 Reactor Critical No. 132.

1545 Rolled T/G.

1625 Synchronized generator, commenced power ascension.

Startup sis in progress. ,

01/10 0130 Canmenced PCIOMR from 77% thermal power.

01/11 1240 Reactor thermal power at 100%, maximum ficw, rod limited.

2015 Commenced reducing thermal power due to HPCI and RCIC being inoperable.

01/12 0755 RCIC operable, stopped load drop at 91% thermal power.

1215 Canmenced power ascension from 91% thermal power.

1430 Commenced PCIOMR from 96% themal power.

1830 Reactor thennal power at 100%, maximm ficw, rod limited.

01/19 2355 Commenced reducing thermal power for SI 4.3.A.2 (Control Rod Exercise).

01/ 20 0030 Reactor power at 97% for SI 4.3.A.2.

0045 Could not perform SI 4.3. A.2 due to APRM rod block, commenced PCIOMR.

0300 Reactor thermal power 9t 100%, maximum ficw, rod limited.

01/22 1245 Commenced reducing thermal power for SI 4.3. A.2.

1255 Reactor thermal power at 98% for SI 4.3. A.2.

1340 SI 4.3. A.2 complete, commenced power ascension.

1400 Reactor thermal power at 100%, maximum flow, rod limited.

01/ 26 0115 Commenced reducing thermal power for SI 4.3.A.2.

0200 Reactor thermal power at 96% for SI 4.3.A.2.

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

0400 Reactor thennal power at 100%, maximm flow, rod limited.

01/31 2400 Reactor thermal power at 100%, maximum flow, rod -

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• • 11 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-259 UNIT Browns Ferrv One l DATE 2/1/85 COMPLETED BY T. Dom _

] TELEPHONE (205) 729-3834 MONTH January

• DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-NetI (MWe-NetI i 1051 37 -13 2 1048 33 -14 3 1047 39 -13 4 1050 :o -14 5 1027 21 -13 l 6 1038 22 -14 7 1033 23 -14 g 1033 24 -16 9 1025 25 17 10 978 26 616 1003 825 ii 3

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12 843 ,3 974 13 1017 29 910 34 1067 30 926 15 1070 3, 1055 is 652 INSTRUCTIONS

, On this fortnat,hst the average daily unit power level in N!We Net for each day in the reporting inonth.Coinpure to the nearest whole megawati.

(9 /77 )

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AVERAGE DAILY UNIT POWER LEVEL l

DOCKET NO. 50-260 UNIT Browns Ferry 2 DATE 2/1/85 COMPLETED BY T. nom <

TELEPHONE (?ns) 72o-1R34 MONTH January DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL IMWe-Neu (Mwe.Neo l 1

-4 17 -3 2 -3 is

-2 3 -4 19 -3 4 -4 20 -4 5 -4 21 -3

-4 -5 g

7 -4 23 -6 8 -4 34 -6

~4 9 25 -5 ,

10 * -4 26 -5 II

-4 -5 27 12 -4 33 -4 ,

13 -4 29 -5 14

-4 -5 30 I5 -4 3; -5

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I On this format, list the average daily umt power leselin slwe. Net for each day in the reporting month. Compute to the nearest whole megawatt.

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. 13 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-296 IJNIT Browns Ferry 3 DATE 2/1/85 COMPLETED BY T. Thom TELEPHONE (205) 729-3834 MONTH January DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL IMWe Net) (MWe-Net)

I 1056 g7 1091 2 1058 gg 1077 l 3 1061 1081 9

l 1061 4 20 1077 5 1051 2: 1089 6 1051 1076 22 7 682 23 1088 8 69 1090 34 9 637 25 1087 10 . 897 1077 26

g 1047 1084 37 12 1037 gg 1081 13 1070 29 1086 34 1084 1082 30 15 1083 3g 1086 16 1084 INSTRUCTIONS On this format. list the average d.uly umt power lesel m MWe Net for each day in the reporting month. Compute to the nearest whole megawatt.

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14 OPERATING DATA REPORT DOCKET NO. 50-259 DA1E 2/1/85 COMPLETED BY I. Thom_

TELEPIIONE (205) 72J-3834 -

OPERATING STATUS 1

Browns Ferry One b"'" l

1. Unit Name:

2. Reporting Period: January 1985 j -

3. Licensed Thermal Power (MWt1: 3293 i

4. Nameplate Rating (Gross MWel: 1152 i S. Design Electrical Rating (Net MWe): 1065 j

6. Maximum Dependable Capacity (Gross MWel: 1098.4

7. Masimum Dependable Capacity (Net MWe): 1065 ,

8. If Chang:s Occur in Capacity Ratings litems Number 3 Through 71 Since Last Report. Giie Reason -

N/A _

9. Power Lesel To Which Restricted.If Any (Net MWel: N/A

10. Reasons Fnt Restrictions if Any- N/A,, , , , , , _ , _. , , , _

This Month Yr. to.Date Omnuluise

11. lloun in Reporting Period 744 744 _92.144

12. Number Of floor Reactor Was Critical , 542.33 _542.33 .5 8 . 43 5 . 9 3 __ _ ___

13. Reactor Reserse Shutdown flours 201.67 _201.67 _6,686.89, .

14. Iloon Generator On.Line 521.22 .521 22 -_ .iL16.1&__ _

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l$. Unit Re ene Shutdown floun 0 _0

16. Grow therma! Energy Generated 1MWill 1.595 J 97 1.595.297 16_4J36,7/3 3_

17 Gros, tiettrical Energy Generated (MWil) 524.9.50_ ._. .121 950 __ 54,27.0 E 0 _.

h. Net Elettrical Energy Generated IMWlO 508.661 508.661 .5_2.722.48.2

19. Unit Senice Factor 70.1 70.1 62.0

20. Unis Asadability Fattor 70.1 70.1 62.0 _,,_

21. Umt Capacits Factor (Using MDC Net, 64.2 64.2 53.7 . _.

2.' Unit Capadty Factor IUsing DER Nett 64.2 64.2 53.7 ,

23. Unit Fnrced Outage Rate 20.2 .20.2 22.1 _

24. Shutdowns Scheduled Oser Nest 6 Months iI>pe. Date,and Duration of Fatht 25 If Shut flown At End Of Report Period. Estimated liate of Startup:

26. Units in fest Status IPrior to Commercial Operationt forcasi gih cs.d INii hl. CRli tral.liY INiflAL Fl.LCIRlCITY COMM ERrl.gl. Opl:R A IlON __

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.' 15 OPERA TING D ATA REPORT DOCKET NO 50-260__

D\TE Y75785 CO'. PLETED BY L._Ihotet.

TELEPHONE (105). 72L-3834 OPERATING STATUS Notes

1. Unit Name: Browns Ferry 2

2. Reporting Period: January 1985

3. Licensed Thermal Power (MWtp: 3293

4. Nameplate Rating (Gross MWe): 1152

5. Design Electrical Rating (Net MWe): 1065

6. Masimum Dependab!e Capacity (Gross MWe): 1098.4

7. Masimum Dependal.fe Capacity (Net MWe): 1065 8 If Changes Occur in Capacity Ratings tirems Number 3 Through 7) Since Last Report.Give Reasone N/A

9. Power Level To which Restricted. lf Any (Net MWe). N/A

10. Reaums For Restrictions.lf Any: N/A This Month Yr. to Date Lumulaine II. Hours in Reporting Period 744 744 ,87.031

12. Number Of Ilours Resctor Was Crit cal , 0 0 . 55,860.03

13. Reactor Reserve Shutdown Hours 0 0 14,200.44

14. !!ours Generator On l.ine 0 0 ,,MJE)6

!!. Unit Reserve:ihutdown llours 0 0 0 ,

16. Crun Thermal Energy Generated iMWH) 0 0 ,,lR.2_41J 6,_7, _

17 Grow Electrical Energy Generated (MWil) 0 , , , , , , _ _ , ,

0 50.7712 798 IM. Net Electrical Ener;> Generated 1M%H) -3095 -3095 g2R3J1,__

19. Unit Service Factor 0 0 62.4 _

20. !! nit Avadabdity Factor 0 0 62.4 ~

21. Unit Capacity ractor (Using MDC Net, 0 0 53.2

22. Unit Cap 1 city Factor (Uring DER Net) 0 0 53.2 ~

23. Unit Forced Outage Rate 0 0 23.0

24. Shntdowns Schedided Over Nest 6 Monthi tTypc. Ibte.and Duration of Eathl:

25. If Shut Down At End of Report Period. Estimated Date of Startup: -Aunust l'. 1935

26. Units in rest Status IPrior to Commercial Operationi: Forecast Ashwsed INITi\L CRITICALITY INITIAL ELECTRICITY CO%fM ERCIAL OPER A TION t'#/??I

' 16 OPERATING DATA REPORT DOCKET NO. 50-296 4 DATE 2/1/85 COMPLETED BY T- Thnm i TELEPilONE (205) 729-3834 i

CPERATING STATUS

1. Unit Name: Broi.rn a Ferry 1 Notes

2. Reporting Period: January 1985 i 3. Licensed Thermal Power (MWt): 1291

4. Nameplate Rating (Gross MWe): 1152

5. Design Electrical Rating (Net MWe): 1065 l 6. Maximum Dependable Capacity (Gross MWe): -.10,,9,8 . 4

7. Maximum Dependable Capacity (Net MWe): 1065

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

N/A l

(Net MWe): N/A

9. Power Level To Which Restricted,if N Any/A 10, Reasons For Restrictions.lf Any: ,

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This Month Yr..to Date Cumulative I1. Hours In Reporting Period 744 744 60;A96

12. Number Of Hours Reactor Was critical , 725.67

• 7?s_67 44.514.10

13. Reactor Reserve Shutdown Hours 18.33 18.33 4.6so g3

14. Hours Generator On.Line 721.08 721.08 43.418.88

15. Unit Reserve Shutdown Houg, 0 0 0

16. Gross Thermal Energy Generated (MWil) 2.311:R14  ? 111_n1A, 129.532.241 17 Gron Electrical Energy Generated (MWH) 769.900 _,,,

769.900 42.670 690

18. Net Electrical Energy Generated (MWH) 750,876 750.876 _41,416,637

) 19. Unit Service Factor 96.9 96.9 62.5

20. Unit Asailability Factor 96.9 96.9 62.5

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21. Unit Capacity Factor IUsing MDC Nerl 94.8 94.8 36.0 22 Unit Capacity Factor (Using DER Neti 94.8 94.8 56.0 _

23. Unit Forced Ontage Rate 3.1 3.1 17.7 _

24. Shutdowns Scheduled ther Nest ti Months t hpe. Date, and Duration of Fashi 2$. IIshut Down At I nd of Report Period. Estimated Ibte of Startup:

2ti. Units in fest Status il'rior to Commercial 0peration t Forecast hhwsed

{ INiilA L CRillCAi ll Y INillAL LLICTRICITY CO\l%IFRCl41. Orl'R A IlON .

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L' NIT SilUTDOWNS ANDPOhER REDUCTIONS DOCKET NO. 50-259 ,,

UNIT NAM E owns Ferry One DATE 2 1 85 ,

COMPLETED gy T. Thom REPORT MON DI . January TELEPIIONE (205) 729-3834 1

h Date

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'h j $~ l 2iy Licensee [n, E*:, C.suse & C irrectne j --

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2: 4 5f- Rep.nl = z 'w y' Present Resursente e _ v 1 -

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) 306 1-11-85 S H . Derated for control rod pattern adjustment.

307 1-16-85 F 132.22 A 3 Reactor scram due to low water level which caused loss of steam to the fuel pumps. The unit remained down due to IRM problems and to repair a C leak on bonnet vent line (valve 68-509) on "A" recire. '

discharge

valve 68-3.

308 1-29-85 F A Derated for leak on reactor feedwater pump.

309 1-30-85 F A Derated for feedwater control probleme .

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1- : Finced Reasigt . Methixt:

S S,heduled lainbit G - Instiu ti.wi>

A-Equiprnent Failure (Espbuil  ! 41anual for Pseparaison sii Data B41aintenance or Test 241anual Scram. I nin Sheets fin Ii.ensee C-Refuehng .i Aulisin it ic Ss r.in.. 13eni Repi : II I R e I ite s '.t Rt (.-

D-ReFulatory Restriction 4 Othei Il'splaini 01 til I i I 4)perator Tsuning i i nens I unuiut:on F- AJ nunist rair.e 5 G4)pesatiinial I u..a t t apt.i.i r I shibit I - Same %* it..

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UNIT SlitrTDOWNS AND PCWEt REDUCTIONS DOCKET NO. 50-260 UNIT NAME Browns Ferry 2 DATE 2/1/85 REPORI MONTil .Tanuary COMPLETED BY T- Thn=

TELEPHONE (205) 729-3834

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305 1-1-85 S 744 C 4 EOC-5 Refuel Outage (Controlled shutdown 9-15-84)

E I 2 3 4 F: Forced Reamn: hie hod: Eshibit G - Instructions S Scheduled A-Equipment Failure q Esplain) 1 Manual for Prepar.irion of Dar.

• B-RIaintenance or Tes: 2-Manual Sciam. Enity Sheets for 1.ieensee C-Refucimg 3- Automatic Sir.sm. 1: vent Repois e 1.110 File int RI G.

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• 6 0 9

l' NIT SitUIDOWNS ANI) POWE R REDUCTIONS DOCKET NO. 50-296 ,,

UNITNAME Browns Ferry 3 DATE 2/1/RS ,

COMPLETED BY T. Thom REPORT MON DI Jariuary TELEPHONE (205) 729-3834

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Prevent Recurrence i A

151 1-7-85 F 22.92 A 2 Reactor scrammed due to temperature ,

o differential limit of 145 between the done and bottom head drain preventing restart. of the recirculation pumps.

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B-Maintenance c.r Tes 2-M.mual Sesam. Ensi> Sheeis for LLensee C-Refueling 3-Automatie Ssram Eseni Repost t1.1 RI I:ile s' t*lti t..

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BROWNS FERRY NUCLEAR l- UC CN.7 3 CSSC EQUIPMENT MECHANICAL MAIN 1EniME SUPetARY For the Month of lannitry 19 85 EFFECT ON SAFE ACTION TAKEN DATE SYSTEM COMPONENT NATURE OF OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE MATMTEMAMCE THE REACTOR MAI. FUNCTION MAfPUNCTION RECURRFMCE 3 EN LPCI MG Disassemble coupli y. None Grease loss Vibration Old seals replac<

12-4-8 0 74 set check seals ed 1-9-85 74 3-A RHR discharge Tighten bonnet None Normal use Leak Torqued bonnet t<

Pump check valve bolts to attempt stop leak, to stop leak.

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CSSC EQUIPMENT MECHANICAL MAINTENANCE SUfetARY For the Month of January 39 85 j EFFECT ON SAFE ACTION TAKEN 1 DATE SYSTEM COMPONENT NATURE OF OfERATION OF CAUSE OF RESULTS OF TO PRECLUDE l MATNTENANCE TFE REACTOR MAT. FUNCTION MatFUNCTION RECUBBRMCE

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! 1-10-85 67 EECW Pump Troubleshoot: None Normal Use Strainer wouldReplace Gear Box Strainer A3 Strainer not rotat- not rotate Drive with new l

ing and drain valve model f is not opening Repaired shaft a automatically Installed new I bearings & seals i

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9/29/32 .-

For the !!anch of January 19 85 .

, .  ;  ; Cffect ca Safe, . .\ction i.acu .

, j - - a  ?;ature of j Operatio;i of g' Cause .c f Results of l Ta Preclu<!e D it e Srste1

• Cc nanent  ! "aintca.is a ~ l 1985 The Re.ictor ?tilfunctian +

!!al f unc t ion i Recurrence .

1/10 Fire XS-039-Ol9C Perform SI None Defective smoke Detector failed Replaced detector protection aux inst rm 4.11.C.1 & 5 detector sensitivity check '

smoke detector sensivitity MR 320628 test i

1/11 HPCI .

1-FCV-073-OOl6 During perform- HPCI inoperable Limit switch HPCI inoperable During troubleshoot -

ance of SI LS-15 on FCV- ing the HPCI ECM ,

4.5.E.1.d & e 73-16 was out of box and ramp gen-the HPCI failed adjustment erator was replace I flow test on MR 171508. Limi I

switch LS-15 was' found to be out of8

, adjustment on I MR 320590. Adjusted limit switch per EMI 18. w w

LER 296-85003 1/21 Fire pro- IS-039-026E Perform SI None Defective smoke Detector gave false Replaced detector '

j tection control panel 4.11.C.1 & 5 detector alarm j i

9-6 smoke MR 177065 i detector

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BF E**s!I. 30 CSSC EQUIPMr.:.T App ndi;. 3 E*.ECTRIC.U. ?!A *: TIC *A.'.CE SDCt.ULY 9/13/32 For the !buth of January 19 85

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• The Rescror !blfunctian 'bl f unc t ion i Rcoerrence

,1985 8/2 Fire pro- IS-039-67ZR Perform SI None Bad detector Detector failed Replaced smoke tection RR zone Z smoke 4.11.C.1 &.5 l sensitivity check detector detector sensitivity tes-;

MR 320688 r

1/10 Cranes & lRefuelingplat-. Troubleshoot None Bad CP 100 modules Platform would not Replaced module, form hoists refuel plat- move forward or adjust settings

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1/24 Residual BER-074-0005 While perform- Unit in 10 day Stuck cell switch Breaker would not Freed cell switch' '

heat RER pump A ing SI 4.5.B.i. LCD in breaker compt close w I removal breaker b-1. 2A RHR #'

l pump failed to ,

MR 181180 start

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9/23/32 For the !!anth of January 19 85 .

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Cause.of  ! Results cf To Preclude Da

c $vs:c 2 Cc ,cnca: ** t i n t enanc e ' Stal func t ion The Reactor ital f unct ion Recurrence 1935 C/22 Residual FCV-74-0054 Replace and None Broken wire on Full closed (green Replaced & adjusted l heat re- RER system 1 adjust magnetic " closed" magnetic light circuit) does magnetic switch lmoval testable check switch switch not work l valve MR 315505 1/19 Contain-

• FSV-76-0053 oCorrect cable None Cables labeled DR 85-0048 Correct cable tags ,

FSV-76-0054 wrong I ment I' tert- tags in panel in panel 9-4 ing FSV 76-0055 9-54 l 1 FSV 76-0056 MR 062186 l

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, H2 and 02 MR 157631 j analyzer y  :

l sample valves u l e

2/26 Annunciaton XA-55-4A Check false None Power supply card False annunciation Replaced card I

& Sequen- control valve annunciation burned out tial eventa half scram MR 176506 recording annunciation I

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Effect on Safe, +

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. The Reactor Malfunctian !falfunction I Recurrence

/5 Control CHR-31-0007 Troubleshoot B None W3ak overload Control bay chiller Replaced overload bay heat- B control bay control bay r.31ay on A O would not run. Breaker relay, l

ing, vent chiller chiller breaker tripping instantan-ond AC eously MR 156994

/12 Standby  ; RLY-082-000C  ; Performing None Wire shorted out ECR failed to operate Replaced lugs on diesel ' D/G C, engine

• nnual inspec- while performing ECR relay '

generator control relay tion on D/C C scheduled mainte-l nance MR 320632 ,

l f23 High pres- PMP-26-ll8 Adjust and None Louver motors not Building air inlet Adjusted and syn-sure fire diesel driven synchronize synchronized dampers malfunctioning chronized louvers l protection fire pump louvers MR 170165 f24 Fire pro- IS-39-72CE Perform SI None Bad detector Detector failed Replaced smoke i

tection smoke detector 4.11.C.1 & 5 sensitivity check detector {

in cable tunne1 sensitivity test

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• 27 OUTAGE MAINTENANCE & MAJOR MODIFICATION MANAGEMENT January 1985 MAJOR WORK COMPLETED A. Refuel Floor Initial sip of 764 bundles was completed. Fifty suspected leakers were reported. c B. Turbine

1. No. 7 and No. 8 bearings were repaired at Muscle Shoals and arrived onsite on January 9, 1985.

2. Boring of #1 coupling completed on January 21, 1985.

3. Low-pressure "C" 8th stage diaphragms were repaired at Muscle Shoals and arrived onsite on January 23, 1965.

C. Drywell

1. Recirculation pump "A" coupled run was completed satisfactorily on January 23, 1985.

2. Recirculation motor "B" uncoupled run was per formed on January 13, 1985, with a suspect upper guide bearing reported. ,

Bearing reinspection was completed on January 31, 1985.

3. Drywell structural steel inspections by the Office of Engineering were reported complete on January 15, 1985.

4. Induction Heat Stress Improvement (IHSI) of Reactor Water Cleanup in-drywell available welds was completed on January 17, 1985 (10 of 13 welds).

28 i a OUTAGE MAINTENANCE & MAJOR MODIFICATION MANAGEMENT January 1985 MAJOR WORK COMPLETED (Continued) ,

D. Balance-of-Plant

1. All condensers were reported opened on January 2,1985. Probolog 4 of all six waterboxes was completed on January 30, 1985.

2. "D" Residual Heat Renoval (RHR) heat exchanger was returned to service on Janucry 7,1985. "C" RHR heat exchanger was taken out of service. HCV-23-37 was replaced. Valve 23-581 was removed, inspected, cleaned, and reinstalled. Vent line modifications were completed. Probolog was performed. Hydrostatic testing was cc=pleted en Janucry 31, 1985.

t 3 Unit 1/2 "C" diesel generator was taken out of service; annual inspections were performed, probolog and air start valve modifications were completed, and the diesel was returned to

service on January 14, 1985.

4. Unit 1/2 "D" diesel generator was taken out of service for maintenance and modifications on January 30, 1985.

S. The Condenser Circulating Water (CCW) inlet tunnel was pumped

down. Two joints will require repairs.

1

. . . . 29 OUTAGE MAINTENANCE & MAJOR MODIFICATION MANAGEMENT January 1985 MAJOR WORK COMPLETED (Continued)

E. Modifications Sections

1. Valves being worked: 74-68, 74-54, 74-61, 73-23,73-603, both "C" line Main Steam Isolation Valves (MSIV), "C" I/B MSIV, Main Steam Relief Valve vacuum breakers, 64-series valves. Valves completed: 71-580.

2. Nine of 13 MSRVs were lift tested at Wyle labs.

3. Scran Discharge Instrument Volume taak prefabrications lack three 3" welds for completion (ECN P0392? .

4. Recirculation motor generator (MG) rnaintenance was completed on both MG sets.

5. MAI-27 was approved on January 30, 1985, allowing for the start of ECN P0126 conduit installations.

6. ECN P0361 (Torus Attached Piping) - two of 318 hangers are modified.

7. Security Modifications - 46 of 89 barriers were installed as of January 31, 1985. Many lack pull-testing. Both cages are installed. The current projected completion date of these modifications is February 24, 1985.

A

._+p.- - _ -. . . _ . _

30  :.  : .'

OUTAGE MAINTENANCE & MAJOR MODIFICATION MANAGEMENT January 1985 -

MAJOR WORK COMPLETED (Continued)

F. Other

1. Work in Progress

- Work Plan writing Inspection of moisture separator cross under piping

- Reinspection of suspect fuel *

- Training of fuel pool sample contractors

- Rebuild of "old" low-pressure 2A turbine rotor at Muscle Shoals Condenser Cooling Water pump pit "A" maintenance Electro Hydraulic Control system calibrations.

Maintenance on 2A and 2C main transformers Minor torus internals modifications TIP indexer maintenance .

IHSI of "A" loop recirculation pump welds '

1 .

TENNESSEE VALLEY AUTHORITY Browns Ferry Nuclear Plant P. O. Box 2000 Decatur, Alabama 35602 FEB 181985 Nuclear Regulatory Commission Office of Management Information and Program Control Washington, DC 20555 Gentlemen:

Enclosed is the January 1985 Monthly Operating Report to NRC for Browns Ferry Nuclear Plant Units 1, 2, and 3.

Very truly yours, TENNESSEE VALLEY AU'niORITY hbh<lhh

[,nG.T. Jones Plant Manager Enclosures cc: Director, Region II INP0 Records Center Nuclear Regulatory Comraission Institute of Nuclear Power Office of Inspection and Enforcement Suite 1500 101 Marietta Street 1100 Circle 75 Parkway Atlanta, GA 30303 (1 copy) Atlanta, GA 30389 Director, Office of Inspection and Enforcement Nuclear Regulatory Commission Washington, D. C. 20555 (10 copies)

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

$624 An Equal opportunity Employer i