ML20106J683

Monthly Operating Repts for Dec 1984

ML20106J683
Person / Time
Site:	Browns Ferry
Issue date:	12/31/1984
From:	Thom T TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20106J669	List: ML20106J667 ML20106J683 ML20106J699
References
NUDOCS 8502190079
Download: ML20106J683 (32)

Text

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TENNESSEE VALLEY AU1110RITY DIVISION OF NUCLEAR POWER' BROWNS FERRY NUCLEAR PLANT i

MONTHLY OPERATING REPORT TO NRC December 1, 1984 - December 31, 1984 i

DOCKET NUMBERS 50-259, 50-260, AND 50-296 LICENSE NUMBERS DPR-33, DPR-52, AND DPR-68' t

Submitted by:_ -

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TABLE OF CONTENTS Operations Summary. . . . . . . . . . . . . . . . . . . . . . . 1 Refueling Information . . . . . . . . . . . . . . . . . . . . . 3 y Significant Operational Instructions. . . . . . . . . . . . . . 5 Average Daily Unit Power Level. . . . . . . . . . . . . . . . . 13 Operating Data Reports. . . . . . . . . . . . . . . . . . . . . 16 Unit Shutdowns and Power Reductions . . . . . . . . . . . . . . 19 Plant Maintenance . . . . . . . . . . . . . . . . . . . . . . . 22 Outage Maintenance & Major Modification . . . . . . . . . . . . 28 Addenda . . . . . . . . . . . . . . . . . . . . . . . . . . . . 31 e

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'l Ooerations Sn=nar v December 1984 The following summary describes the significant operation activities during the reporting period. In support of this stamary, a chronological log of significant events is included in this report.

There were four reportable occurrences and no revisions to previous reportable occurrences reported to the NRC during the month of December.

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

Unit 2

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

Unit ~4 There was one manual scram on the unit on December 9, 1984, due to a condensate pump motor ground coupled with a breaker trip failure.

Prepared principally by B. L. Porter.

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Doerations %==arv (Continued)

December 1984 Fatinue Usage Ev>1uation The cumulative usage factors for the reactor vessel are as follows:

Location Usane Factor Unit 1 Unit 2 Unit 1 Shell at water line 0.00611 0.00492 0.00421 4

Feedwater nozzle 0.29404 0.21319 0.15791 Closure studs 0.23744 0.17629 0.14159 NOTE: This accumulated monthly information satisfies Technical Specification Section 6.6.A.17.B(3) reporting requirements.

C - n System Approximately 8.68E+05 gallons of waste liquids were discharged containing approximately 4/26E-01 curies of activities.

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Ooerations m rv (Continued) I

.  ; December 1984 Refueline 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 change-out, and feedwater sparger inspection.

1here are no fuel assemblies in the reactor vessel. At month end, there were 273 new fuel assemblies, 764 EOC-5 fuel assemblies, 248 EOC-4 fuel assemblies, 352 EOC-3 fuel assemblies,156 EOC-2 fuel assemblies, and 132 EOC-5 1 fuel assemblies in the spent fuel storage pool. The present available '

capacity of th'e 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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4 Ooerations %"==rv (Continued)

December 1984 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 e

complete reinspection of stainless steel piping.

There are 764 fuel assemblies presently in the reactor vessel. There are 248 E00-5 fuel assemblies, 280 EOC-4 fuel assemblies, .124 EOC-3 fuel

' assemblies,144 E00-2 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' Sinnificant Ooerational Events Date Time Event Unit'1

," '12/01 -0001- Reactor thermal power at 56-percent (%) for. control rod 4

} : 0300 sequence exchange.-

Reactor thermal power at 54% for control rod sequence 4

exchange,-increasing thermal-power for control rod sequence exchange.

1308 Control rod sequence exchange complete, commenced power'

, ascension from 63% thermal pcwer. ~

1356 Commenced PCIOMR from 68% thermal power.

I- 12/03

'.0630 Reactor thennal power at 100%, maximum flow, rod limited.

j 1000 Reactor. thermal power at 995, maximum flow, rod limited.

1300 Reactor thermal power at 985, maximta flow, rod limited.

1350 -Commenced PCIOMR from 98% thermal power.

1600 Reactor thermal power at 100%, maximum flow, rod limited.

2300 Reactor thermal power at.995, maximum flow, rod limited.

12/04 0335 Commenced reducing thermal power for SI 4.3.A.2 (Control Rod Drive Exercise).

0400 Reactor thermal power at 96% for control rod drive exercise.

0515 SI 4.3.A.2 complete, commenced power ascension.

, 0600 Reactor thermal power at 98%, maximum flow, rod limited.

2200 Reactor thermal power at 975,- maximum flow, rod limited.

12/06 2241 Recirculation pump "B" tripped, reducing thennal power. -

12/07 0500 Reactor thermal power at 48% due.to "B" recirculation

pump trip.

0550 commenced increasing power to restart "B". recirculation pump.

i 0615 "B" recirculation pump in service, reactor power at 51%.

i 0650 "B" recirculation pump out-of-service, reducing thermal power from 515.

0700 Reactor thermal power at 48% due to "B" recirculation pump out-of-service'.

0812 "B" recirculation pump in service, commenced power ascension.

1200 Reactor thermal power at 97%, holding due to Xenon

\ transient. .]

1210 "B" recirculation pump tripped, reducing thennal power.

1700 Reactor thermal power at 56%, holding due to "B" recirculation ptup trip.'

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• L L, .6-Significant Ooerational Events Date Time- Event

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Unit 1 (Continued) 112/0rl - 1957 "B" recirculation ptanp'in service, commenced power (Cont.) . ascension.

~2330 Commenced PCIOMR from 715 themal power.

12/09. 1130 Reactor thermal power.at 100%, maximum flow, rod limited.-

1500 #

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

2000 Reactor thermal power at 985, maximum flow, rod limited.-

12/10 0300 ~ Reactor thermal power at 975, maximum flow, rod' limited.

1000 Commenced power ascension from 975 thermal power. -

1400 Commenced PCIOMR from 99% .themal power.

1430 Reactor thermal power. at 100%, maximin flow, rod '{

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limited.

-1500 Reactor themal power at 995, maximum flow, rod limited.

12/11 1632 Reduced themal power to 97% when control rod 22-07 was inserted to position 00 for SI 4.3.B.1.a (Control Rod Coupling Integrity).

12/12 1135 Completed SI 4.3.B.1.a; commenced power ascension from 97% thermal power.

i 1400 Reactor- thermal power at 100%, maximum flow, rod  !

limited. I 2200 Reactor thermal power at 99%, maximum flow, rod limited.

12/13 1041  !!B" recirculation pump tripped, commenced; reducing .

thermal power.

1530 Reactor thermal power at 47%, "B" recirculation pump out-of-service.

1600 Attempted to restart "B" recirculation pump, field breaker failed to close.

1855 Commenced; power ascension from 47% thermal power.c "B"-

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Fecirculation pump still out-of-service;'eu_

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12/14 0530 Commenced reducing thermal power from 62% to adjust margins.on core limits.

0545 Reactoripower- at-58% holding-due .torcore limits.-

1014 "B". recirculation pump in service, commenced power r, - "- y ascension.- "~ - "

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1130 Connenced reducing thermal power from 71% for control -<

rod pattern adjustment.

1500 Reactor power at 67% for control rod pattern adjustment.

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7 Significant Ooerational Events Date Time Event Unit 1 (Continued) 12/14 1745 Control rod pattern adjustment complete, commenced power (Cont.) ascension.

1930 Commenced PCIOMR from 76% thermal power.

12/16 _0230 Reactor thermal power at 98%, maximtra flow, rod limited.

0900 Reactor thermal power at 975, maximum flow, rod limited.

1500 Reactor thennal power at 96%, maximtra flow, rod limited.

1728 Commenced reducing thermal power for control rod pattern adjustment.

1855 Reactor thermal power at 76% for control rod pattern adjustment.

1945 Control rod pattern adjustment complete, commenced power ascension.

2000 Commenced PCIOMR from 78% thermal power.

12/17 1800 Reactor thermal power at 100%, maximum flow, rod limited.

2200 , Reactor thermal power at 99%, maximum flow, rod limited.

12/18 0130 Increased thermal power to 100%, maximum flow, rod limited.

1000 Reactor thermal power at 99%, maximum flow, rod limited.

1630 Increased thermal power to 100%, maximum flow, rod limited.

12/21 1900 Reactor thermal power at 995, maximum flow, rod limited.

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12. 2 2335 Commenced reducing thermal power for SI 4.3.A.2 (Control Rod Drive Exercise).

2400 Reactor thermal power at 95% for SI 4.3.A.2.

12/25 0210 SI 4.3.A.2 complete, commenced power ascension.

0700 Reactor thermal power at 100%, maximum flow, rod limited.

12/29 0347 Commenced reducing thermal power for SI 4.3.A.2 (Control Rod Drive Exercise).

0400 Reactor ^ thermal power at 95% for SI 4.3.A.2.

0540 SI 4.3.A.2 complete, commenced PCIOMR.

1000 q Reactor thermal power at 100%, maximum flow, rod limited. d 12/30 0700 Reactor thermal power at 99%, maximum flow, rod lbnited. \

12/31 2400 Reactor thermal power at 99%, maximum flow, rod limited.

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8 Sinnificant Ooerational Events Date Time Event Unit 2 12/01 0001 End-of-cycle 5 refuel outage continues.

12/31 2400 End-of-cycle 5 refuel outage continues.

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9 Significant Operational Events Date Time Event Unit 3 12/01 0001 Reactor thermal power at 13%, holding for startup and turbine vibration checks.

0555 Increased thermal power from 13%.

0630 Reactor thermal power at 18%, holding for startup and turbine vibration checks.

0800 Reactor thermal power at 17%, holding for startup and ,c turbine checks.

0900 Reactor thermal power at 16%, holding for startup and -

turbine vibration checks.

0932 Rolled main turbine.

1007 Turbine at rated speed, oil trip test complete.

1021 Synchronized generator, commenced power ascension from 15% thermal power.

1430 Turbine offline, from 22% thermal power for backup overspeed test.

1455 Backup overspeed' test complete.

1505 Synchronized generator, commenced power ascension.

1950 , Reactor thermal power at 24%, holding for a TIP set.

2400 Reactor thermal power at 23%, holding for a TIP set.

12/02 0300 Reactor thermal power at 22% for a TIP set.

2125 Commenced power ascension from 22% thermal power.

2150 Reactor thermal power at 24%, holding for a TIP set.

12/03 1410 TIP set complete, holding at 24% power for RTI-13 (Proces Computer).

1810 Canmenced power ascension from 24% thermal . power. -

1820 Stopped power ascension at 25% thermal power, computer out-of-service.

2245 Computer back in service, commenced power ascension.

12/04 0100 Stopped power ascension at 26%,' holding for SI 4.1.B-2 (APRM Gain) and SI 4.1.B.1 (IRM/APRM Overlap).

0230 sis complete, commenced rod withdrawal.

0330 Stopped power ascension at 27% thermal power, computer out-of-service.

1615 Computer back in service, commenced power ascension.

1624 Stopped

• power ascension at 28%, computer out-of-service.

1650 computer back in service, commenced power ascension.

1720 Stopped power ascension at 30% thermal power, computer out-of-service.

1735 Computer back in service, commenced power ascension.

2300 Reactor power at 375, holding for scram timing control \

rods (SI 4.3.C-1 A).

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P 10 Significant Operational Events Date Time Event Unit 3 (Continued) 12/06 1030 SI 4.3.C-1 A complete, holding at 37% power for startup sis.

12/07 1834 Commenced power ascension from 37%, startup sis in progress.

1842 Stopped power ascension at 40% power, holding for _

startup sis.

12/08 0155 Adjusted "B" recirculation pump speed due to vibration alam, reducing thermal power to 39%.

0230 Recirculation pump "B" back to original speed, reactor power at 39%, holding for startup sis.

12/09 0945 Adjusted speed on recirculation pumps to clear vibration alam, reducing thermal power.

1000 Reactor thermal power at 36%, holding due to recircula-tion pump vibration alam.

12/05 , Reactor Manual Scram No.114 from 36% themal power due to 3A unit board tripping and "A" hotwell pump going to ground, with RPS "A" being lost. Unit remained offline to repair leaks on the below seat drain valve for valve 68-33 inside the drywell.

12/10 0415 Reactor in cold shutdown.

12/18 1013 Commenced rod withdrawal for startup.

1150 Reactor Critical No. 131.

12/19 b110 Rolled turbine /generat or.

0223 Synchronized generator, commenced power ascension.

0700 Reactor power at 53% for LPRWAPRM gain adjustments.

1500 Reactor power at 47% for LPRWAPRM gain adjustments.

2300 Reactor. power at- 43% for LPRWAPRM gain adjustments.

7, 12/20 0600 Reactor power at 41% for LPRWAPRM gain adjustments.

2030 Reactor power at 40%, LPRWAPRM gain adjustments

. . . - complete, holding _for TIP run. ., , .

12/22 0455 All TIP runs complete, commenced power ascension. ._

0550 Stopped power ascension at 55% power due to APRMs on rod

? blocks. -

0850 Commenced power ascension from 55% power.

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11 Significant Ooerational Events Date Time Event Unit'3 (Continued) 12/22 1310 Stopped power ascension at 65% for -APRM flow bias (Cont.) testing.

2300 APRM flow bias and functional tests complete, holding at 65% for a TIP run.

12/23 0100 TIP run complete, commenced power ascension. y 0152 Reduced thermal power from 66% to 61% for SI 4.3.A.2.d (Control Rod Accumulator Operability).

0325 SI 4.3.A.2.d complete, commenced power ascension.

0430 Commenced PCIOMR from 64% themal power.

12/24 0830- Stopped PCIOMR at 84% themal power for SI 4.1.B.2 (APRM Gain).

1040 SI 4.1.B.2 complete, reactor power at 82% and decreasing for SI 4.1.B.15 (APRM Flow Bias Adjustments).

12/25 0315 SI 4.1.B.15 complete, commenced power ascension from 79%

themal power.

0320 Commenced reducing thermal power from 81% for control rod pattern adjustment.

0400 Reactor power at 58% and increasing for control rod pattern adjustment.

0830 Control rod pattern adjustment complete, commenced PCIOMR from 70% themal power.

12/26 1545 Stopped PCIOMR at 97% themal power due to condensate demineralizer problems, decreasing thermal power.

2130 Commenced PCIOMR from 95% themal power.

12/27 0330 Stopped PCIOMR at 99% thermal power due to probles with "B" recirculation pump speed control, decreasing thermal power.

. _- 1800 Reactor power at 96% due to "B" recirculation pump speed control problems.

12/28 1500 Reactor thermal power at 93% due to "B" recirculation pump speed control problems.

12/29 0044 Commenced reducing thermal power due to computer problems.  :

0053 Reactor power at 90%, holding due to computer problems.

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0315 Computer back in service, commenced power ascension.

0415 Reactor power at 93%, holding for TIP run. \'

0910 Commenced reducing thermal power for removal of "A" condensate pump from service for maintenance.

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12 Significant ODerational Events Date Time Event Unit 3 (Continued) 12/29 1030 Reactor thermal power at 70%, "A" condensate pump (Cont.) removed from service.

1300 "A" condensate pump back in service, commenced power ascension.

1355 Commenced PCIOMR from 77% themal power.

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12/30 1840 Reactor. thermal power at 99% due to problems with indicating watt hour meter (reading >100% We).

2300 Reactor thermal power at 98%, holding due to problems with indicating watt hour meter (reading >100% We).

12/31 0820 Reduced thermal power to 97% due to problems with indicating watt hour meter (reading >100% We).

1335 Increased themal power to 98%, holding due to problems with indicating watt hour meter (reading >100% We).

2400 Thermal power at 98%, holding due to problems with indicating watt hour meter (reading >100% We).

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AVL!tAGI. 8)AILY llNII POWER LEVEL t54 DOCKET NO. 50-259 WIT' Br 'wns Ferry-One DATE 1/1/85 COMPLETED BY T. Thom TELEPHONE - 205/729-3834 MONT11 December 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL IMWe Net) (MWe Net) 1 656 976.

17 2 ___

895 ig 1058" 3

1050 1072 9

4 1059 20 1073 5 1046 1060 21 _

6 1021 1059 22 7 645 1056 23 8 876 1064 24 9

1032 1072 25

• 1 54 1061 10 _

1043 Ii 27 1069 1037 12 1064. ,

779 1055 13 ,9

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683 1062 14 30 15 940 1056 3

991 INSTRUCTIONS On t!is format, list the average daily umt powen lesel in MWe. Net for cach day in the reporting month. Compute to the neirest whole megawatt.

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14-AVERAGE IJAILY UNIT POWER LEVEL DOCKET NO. __50-260 UNIT Br'wbsFerry-Two o

DATE ~_ I/1/85 .

COMPLETED BY T. Thom TELEPHONE __205/729-3834 MONTH December 1984 DAY AVER ACE DAILY POWER LEVEL DAY (Mwe. Net) AVER AGE DAILY POWER LEVEL ~

I I -3 17 -3 2 -3 ,,,, o!.

Ig -3, "

3 -3 __

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

-4 6 -4 22 -4 7 -4 _

23 -3 8 -4 24 _ -3 9 -3 25 -4 10 - ~4 26 -3 11 -

-4 27 -3 - - - --

12 _

-3 28

~3 -

13 -4 0 --

39 -3 14

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-3 40 15 - .

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-3 INSTRUCTIONS Y ""'I ti r are t [31 ,neg,n P""cf lesel in \lWe Net for each day in the reporting month. Compute to (9/771

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• cf d y.t 15 h4 AYlll\Gl. lull.Y ti.NIII'0WER LEVEL.  !!M, .

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• N DOCKET NO. 50-296

• UNIT Browns Ferry-Three DATE 1/1/85 COMPLElliD BY T. Thom TELEP110NE 205/729-3834 MONTil December 1984 DAY AVERAGE DAILY POWER LEVEL DAY "*

AVER AGE DAILY POWER LEVEL (MWe-Net) (ywe. Net)

I Rf' -12 17 2 176 -12 is 3 194 391 39 258 387 4 _ g 5 342 21 371 6 345 ,, 560 7

387 702 23 s 316 24 841 9 169 yg 778 10

. -16 ,3 966 II -12 27 1011-12 -13 28 995 ,

33 -1d ,9 882 g,; -10 999 39 15 -10 3 1055 [

16 -13

• NOTE: Problems with indicating watt hour meter, o

INSTRUCTIONS I On this format.hst the average daily umt powet lesel m MWe Nel for each day in the reporting month. Compute to b the nearest whole meCawatt.

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OPEItATING DATA ItEPORT DOCKET NO. _50-259 DATE 1/1/85

-COAIPLETED BY L Thom

. TELEPl!ONE .205/.229=3834 OPEllATING STATUS

1. Unit Name: Br3wns Ferry - One Notes

2. Reporting Period: December 1984

3. Licemed Thennal Power (stWr): 3298 4.' Nameplate Rating (Grms alWe): 1152

5. Design E!cctrical Rating (Net SIWE): 1065 <

6. Staximmn Depemlable Capacity (Gross h!We): 1098.4

' 7. Stasinmm Dependable Capacity (Net SlWe): 1065

h. If Clunges ()ccur in Capacity Ratings titems Nmnber 3 'Ibrou.th 7) Since i.ast Report. Give Reasone N/A

9. Power Lesel To Which Restricted. If Any INet \lwel: _ b'[A

!O. Reasom For itestrictium. It Any: ,__, . ,,g /3 Ihis Alonth Yr. to.1).ite Omnulatise ll. linun In Reporting Period 744 8,784 91,400 744 8,067.48 l2. Number of flours Iteactor u.n Critical y __ 57,873.6

11. Iteactor iteserve shnailown linurs _ _0_ _ _

700.20 6,485.22 l a ll..nn c. oi s at.. sin l ine 744 7,,92_2.9'i 56,640.59 is tkns Rivnc shuiilem n II.cns 0 .

,, 0 0 in Crow Ihermal Energy Generated (\lWill 2,286,9 W 24,603,767 ~

163, f61,14F .

17 Grnw I let taithi ! nergy Generated ( Alblo 7.E 190 8.099.860 53.745.480 lb. Net I.lectrical Energy Generated (Sthll) 735,474 7,888,494 52,213,821

19. l? nit Senice Factor _

100 90.2 62.0

20. linit badability Factor 100 90.2 62.0 21.11oit Capacity Factor (thing %IDC Net) 92.8 84.3 53.6 21 l' nit Capacity Factor (U. sing DER Net t 92.8 84.3 53.6 23 Unit Forced r .tjge Rate 0 9.5 22.1

24. Shutdnum Sceduled Oser Nest 6.\lonths I r)pc.Date.and Duration of Eacht:

25. Il Shut linwn \t 1.nd Of Report Perioil. Estimateil llate of Startup:

26. Units in lest Statm iPrior io Commercial Operation 1: Forecast Achiesed INill A L CRillCA tilY INilla L El.ECTRICI TY C0\l\lFitCIA1. OPlIt ATION -

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OPE $ATING DATA REPORT DOCKET NO. 50-260 DATE 1/1/85 _,

COMPLETED 15Y T._ Thora _

TELEPIIONE LOSZ72h1834 OPEltATING STATUS

• N' 1.. Unit Name:

2. Reporting Peiiod: Deceraber 1984

3. Licensed Thermal Power (MWI):

3293

4. Nameplate Rating (Gross MWe)':- 1152

5. Desig, Electrical Rating (Net MWe): 1065 5

6. Maximum Dependable Capacity (Gross MWe): 1098.4

7. Masimum Dependable Capacity (Net MWe): 1065

h. If Changes O. mr in Capacity Ratings (fren.s Number 31hrough 7)Since Last Report.Gise Reasone N/A

9. Power Level In Which Restricted.lf Any(Net MWe): - N/A

10. Reasons For Restrictions,If Any: N/A T his Month Yr..to-Date Cumulatise

11. Ilours in Reporting Period 744 8.784 86,287

12. Number Of Ilours ReEctor Was Critical s, 0 5,895.85 55,860.03

13. Reactor Reserve Shutdown llours 0 300.08- 14,200 M

14. Ilours Gener .r On-Line 0 _5,845.52 54,338.36

15. Unit Rewne Shutdown llours 0 0 0

16. Grow Therma! Energy Generated (MWill 0 13,100,122 153,245,167 .

17 Grow I tectrical Energy Generated (Mull) 0___,, 4,174,510 50,771,798

18. Net Electrical Encrgy Generated (MWil) 0 4,044,370- _49,302,973

19. Unit Senice Factor 0 66.5 62.9

20. Unit Asailabi?y Factor 0 66.5 62.9

21. Unit Capacits Factor IUsing MDC Net) 0 43.2 53.7 21 Unit Capacity I actor IUsing DER Net) 0 43.2 53.7

23. Unit Forced Outa..e Rate O. . _4 .1 23.0 24 Shutdemns Scheduled Oser Nat 6 Months (Type. Date.und Duration of Each):

25. If Shut Down At Eml Of Repoit Peniod. Estimated Date of Startup: ADril 13. 1985

26. Units in ~lest StarudPrior to Commercial OperationL Forecast Achiesed

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COM M FRCl \l. OPl.R A l'lON 19177) b .$

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OPEilATING DATA REPORT

' DbCKET NO. 50-296 -

DATE 1/1/85 COMPLETED BY T- Thnm TELEPflONE 2051729 '1834 OPERATING STATUS

1. Unit Name: Broms Fe m a hee -

Notes .

2. Reporting Period: December 1984

3. Licensed Thermal Power (MWt): 3293

1. Nameplate Rating (Gross MWe): IIS2

5. Desi:n Electrical Rating (Net MWe): 1065

6. Maximum Dependable Capacity (Gross MWe): 1098.4 -~

7. Masimum Dependable Capacity (Net MWe): 1065

h. If Changes occur in Capacity Ratings IItems Number 3 Through 71 Since I.ast Report. Gise Reasone N/A

9. Power Lew! To Which Restricted. if Any (Net MWe): N/A

10. Reaums for Restrictions,if Any: N/A lhis Month Yr..to.Da t e Cnmulatise

11. Iloun hi Reporting Period _

744 8,784 68,712

12. Number Of Ilours Reactor was Critical 32d.25 700.63 7T786.43 iL Reactor Resene Shutdown floun _215J5 763.37 _4.641.50

14. Ilour, Generator On.Line .502.77 504.09 42,697.80

15. Unit Resene Simidown lloun 0 _. .0 0 Iri. Grow thermal Energy Generated IMWlh .1102 716 _ . 910,716 127,218,427

!? Giow Electiieal Energy Generated iMWilj fl03.220 _303,370 _41,900,990 l

h. Net Electrical Energy Generated (MWil, ._290,505 290,505 40,665,761

19. Unit Senice Factor 67.6 5.7 62.1

20. Unit Asadability Factor 67.6 5.7 62.1

21. Unit CapacityFactor (Using MDC Net 1 36.7 3.1 53.6 22 Unit Capacity Factor IUsing DER Net) -36.7 3. ( 33.o

23. Unit Forced'Outagd Rate ' 32.4 66'7 17.'9

24. Shutdowm Schednled Oser Nest 6 MonthsIT)pe.Date,and Duration of Eactil:

25. If Shur I)own ..t End Of Report Period. Estimated Date of Startt.p: '~

26. Units in Test Stalin IPrior io Commercial Operation): Forecast Achiesed 4

INillT L CRillCALil Y INillAL ELECTRICITY - -

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COMM ERCIAl. OP! R A IlON P3/77)

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8 UNIT Slf t'TDOk NS AND POWER REDUCTIONS DOCKET NO. 50-259

. UNIT N AME Browns Ferrv-One-DATE 1/1/85 REPORT MONTil December 1984 COMPLETED BY T. lho=

TELEPif0NE 205/729-3834

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• e Y -5 N. . Date

- :, 1? = 6.=.4 '4 Lice nsee j r, N% Cause & Correceive" i 3g 4 igs Esent u, E- Action in 35 -E 3g= Report = EL E'? Present Recurrence e e v

.6 302 12/1/84 S H '

Derated for control rod sequence  :

(Cont.) exchange. *

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303 12/6/84 F A Derated for "B" recirculation pump I trip. 'e '!

304 12/13/84 F A "B" recirculation. pump Derated for g trip.

I 305 12/16/84 S H Derated for control rod pattern adjustment.

I 2 3 4 F: Forced Rerson: Method:

S: Schedufed Exhibit G. Instructions A-Equipment Failure (Explain) 14fanual for Preparation of Data B. Maintenance of Test 24fanual Seram. Entry Sheets for Licensee C Refueling 3-Automatic Scram. Evens Report (LliRi File E NUREG-D-Regulatory Restriction 4-Other ( E xplain) 01611 l"-Operator Training & License Examination F-Administrative 5 G-Operational Error (Explaini (9/77) Exhibii ! - Same Source II-Other(Explain)

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UNITSIlUTDOWNS tND POWER REDUCTIONS DOCKET NO. 50-260 UNIT NAM E Browns Ferrv-T.o

DATE .1/1/85 COMPLETED 11Y ~T. Thott

[ REPORT MONTil December 1984

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TELEPilONE 205/729-383'.

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5"L i  :, 1: E  ;, 5 4 Licensee g-ro E Cause & Corrective j N"- DJle "

5? d 3s$ Event a'g [- ? Action to 3 $2 5 j[2- Repors = #iv j' Present Recurrence 5

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i 305 12/1/84 S 744 C 4

' EOC-5 Refuel Outage (Controlled shutdown. September 15, 1984)

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I 2 3 4 F: Forced Reason: Method:

S: Scheduled Exliibit G - Instructions A-Equipment Failure (Explain) I-Manual for Preparation of Data B Maintenance of Test 2-Manual Scra m. Entry Sheets for Licensee

'C. Refueling 3 Au'omatic Scram. Event Report tLER FileiNt' REG-

'D Regulator) Restriction 4-Other ( Explain) 0161)

'F-Operator Training & License Esamination F-Adminiit ra t r.e 5

'G-Operational Error (Explain) Ex!iibii ! - Same Source (9/77) 's1 Other (ExplainI

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UNIT S!!ttTDOWNS AND POWER REDUCTIONS DOCKET NO. i 50-296 UNIT NAME Browns Ferrv-Three DATT 1/1/85 REPORT MONTIf December 1984 COMPLETED uy l T. Thon

'TELEPif0NE 205 /729-3834

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N"- Date ff f f ,"n r 4 4 C'"S#A C""edne 55 :E 5 3. =

- g Reporn = $5 .;

55 -, Aaion un Prevent Recurrence c

146 12/1/84 F 10.35 B '

(Cont.) Excessive vibration on main turbine 147 12/1/84 S*

(turbine offline for balancing).

0.58 B Turbine. tripped for backup overspeed test.

148 12/9/84 F 230.3 A 2 g

H Reactor manual scram due to "3A" unit board tripping, "A" hotwell pump going to ground and loss of "A" RPS.

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The. unit remained down for repair of a leak'on the below seat drain valve 149 on valve 68-33 inside drywell.

12/25/84 S H Derated ro control rod pattern adjust-ment.

. 150 12/29/84 F A Derated for maintenance on "A" con- ~

densate pump. .

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F: Forced .3 Reason: 4 S: Schedufed Method:

A Equipment Failure (Explain) t-Manual Exhibit G - Instructions B-Maintenance or Test for Preparation of Data C. Refueling 2-Manual Scram. Entry Sheets for Licensee D Regulatory Restriction 3 Automatic Scram. Event Report iLE RI File tNL REG- '

4 Other (Explain) 01611 E Operator Training & Litense Exanunation F. Administrative G-Operational Error (Explain) 5 19/77) Il-Other (Explain) Exhibit I- Same Source e

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BROWNS FERRY NUCLEAR PLANT UNIT 1 '

CSSC EQUIPMENT MECHANICAL MAlliTENANCE

SUMMARY

For the Month of December 39 1984 EFFECT ON SAFE ACTION TAKEN CATE SYSTEM COMPONENT NATURE OF OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE MAINTENANCE THE REACTOR MALFUNCTION MALFUNCTION RECURRENCE

.2-27-8 '

. 82 . 1B Diesel Gen- Clean coolers for None Routine Mainte- N/A N/A erator probolog nance

.-13-84 82 1B Diesel Gen- Inspect EECW None Preventive Mainto- N/A N/A erator Check valves during nance annual maintenance a

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, a BROWNS FERRY NUCLEAR PLANT UNIT 3 CSSC ECUIPMENT MECHANICAL MAINTENANCE

SUMMARY

For the Month ofDecember 19 84 EFFECT ON SAFE . ACTION TAKEN IA~T SYSTEM COMPONENT NAITJRE OF OPERATION OF CAUSE OF RESULTS OF .TO PRECLUDE _

MAINTENANCE THE REACTOR MALFUNCTION MALFUNCTION RECURRENCE 3 L 74 1" line to 74- Grind cut weld and None Unknown N/A A new piece of 587A replace weld ~

p'ipe between Unit 3 Drywell flange to socket.

access Repaired on MR A-174354

-;7-5L 74 RHR Vent line Repair leak

• None Unknown Repair on Mr l A-156303

_3-5k 74 TLV-74-52 Torque flange bolt  ; None Routine maintena ice N/A .N/A O RHR piping

_;- 5!,

• 68 VLV-68-33 Retack weld on kne 3 None Vibration Jelayed startu ) Repaired on MR-brace between 68-5 35 af unit A-160793 6 536 drain valves 54 23 Pop 23-94 Pull, repair & None Normal use None itebuilt pump re-D3 replace pump ) lacing shaft, impellers, bearing 3tc.

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30 CSSC E0i IPMENT ELECTRICAL MAINTENA'!CE SUS %iRY 9/29/82 ,

For the Msnth of December 19 34 I

Effect on Safe, Nature of 4

Operatica of '

e i Action Taken 5 es:e :

Co nonen:

t l Cause.of l Results of I P 'f a i n t c aance -

T5 t. Reacter  !

Malfunction -

Malfunction l To Pecclude Recurrence Diesel 125 0-CHGB-254-BA Replace voltmete : None Wires shorted out Loss of voltage in- '

V DC Syste? 125VDC battery on battery during performance dication on battery Replacedvo'ltmeter-l charger A for charger of Surveillance charger MR 176095 l DG B Instruction

• I fighpres- 0-STN-26-1505 > Replace limit None Limit switch Strainer not operating; Replaced limit sure fire strainer and ' switch spring broken switch  :

rotection vertical fire pump B -

MR 158017

,Centrol bay CHR-31-0007 Replace thermo- None  ; Normal use Chiller failed to Replaced thermostats teating, & CHW, water work properly

' vent, & AC chiller B l MR 319940 g 1

,C ntrol

• bay 0-CHR-31-0013 Replace control None Control bay chiller

7. eating, & CHW, water relay (Burnedoutcontrol relay Replaced control tripped and would not relay jvent. & AC chiller A restart i MR 156656 f

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._. g- ,r, (v BROWNS FERRY NUCLEAR PLANT l' NIT 1 BF EMSIL 30 CSSC F.WIPMENT ELECTRICAL MAINTENA.';CE SLMtARY # 2 '* 3 9/29/82 For the Month of December 19 84 Effeat on Saie , i Aet ion i cen

';sture of. . 0;'e ra t ic;1 of !

• 5 e s t e--

C - :w :, n Cause.of Results of To Practude

t i n t .*n a n c The Reactor I Malfunction I Malfunction Recurrence j  ! I -

Control rodl1-HS-85-48 Replace spring None Broken spring on Switch will not returr Replaced spring.

'driva [ CRD control hand switch to normal 4

' switch FIR 157111 Annunciatori1-PNL-55-25-31[ Troubleshoot None Bad card False annunciation Replaced card

. & Sequ:ntial backup switch land replace Events jinemergency leard MR 156653 Recording position

Reactor None Annunciators will not

'feedwater I!l-PDA-003-095 Froubleshoot Bad card Replaced card 1-PDA-003-096 jandreplace test 1-PDA-003-097 MR 156686 RFP pucp seal l card i '

n u

jinj water

! pressure low e

00 Replace smoke None Moisture inside False annunciation Replaced smoke

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fire storagejl-XS-39-69YD:Rx bldg El 593l detector detector ,

det ctor lzoneYsmoke l detector MR 169843

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BROW'iS FERRY NUCLEAR PLANT UNIT 2 BF EMSIL A, C53C EX IPM NT -

ELECTRICAL !!AINTENA';CE SDDtARY "

9/29/82  !

For the ."anth of December 19 84 l

, Effect on S t:c , ,

Nature af Action laken

, Ope ra t io;1 of I Cause.of i s e- r --- r - c - - - f :.: e: , e f Results of To Preclude The neactnr I M11 f::nc t ion  ! Malfunction Recurrence i

anuncia tor; 2-PNIe-55-9-5 Check power None Weak inverter S2quentialcontrol room ,.nnunciators appear Replace inverter supply v;nts panel 9-5 to flicker when in accrding alarm state. .

MR 314986 3 i Replace smoke 2 storagej2-XS-39-27E None Circuit defective False annunciation Replaced detector fire gsmokedetectorjdetector I rotection

. ncar Pnis 9-14 l ~'

MR 158425 i ,

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BROW';S FERKi~ NUCLEAR P:. ANT C; 7 t S ..$._.

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CSSC E3*IPME!;T .

ELECTRICAL ?'AINTEN/J;CE SCO'.\RY ' -

9 /29/F.!

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For the P. n:5 of December 19 84 '

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Effect ca Sa f e .

[

!  ! Nature of f Operatica of Action Take:-

~5v4:e= i Cause af Results of To Preclude C.- :ponent Maintenance !

The Reactor ' * -

t Rilfunction Malfunction Recurrence -

t . .

-highpres- 3-RS-73-47A Tighten control None Loose and defectiv:n Handswitch not Tighten handle

, sure cool-, HPCI aux oil

, handle and re- parts operating properly !andreplaceswitch<

aa: place switch

• niec:Lon .

,. q MR 252926 j450Vciesel 3-BKR-219-3EB/ Replace correct None Temporary relay

' aux beards 6E nor fdr to time delay relay Not applicable Replaced time delay 4 installed until relay.

DG 3A exhaust to remove TACF replacement was -

fan B 3-84-193-82 obtaliied MR 190822 .

Resiinal 3-FCV-74-54 Replace magnetic. None bes: re- RHR system I reed switch Insulation break- False valve position.- Replaced switch down.- indication

cal testabic check U vIv ,

e MR 1578'41"

!ain steas 3-ZS-001-51 Replace limit None Connections loose Valve will not stay Replaced limit -

limit switch switch for main steam or defective closed in automatic switch line D inbd isol v1v .I FR 171994 teac::: 3-RLY-3-86B Replace relay None Open reset coil feedwater Relay burned up Replaced relay l interlock relar I

. for bypass viv MR 157952  :

1

tas

dby 3-TS-63-004 Replace thermo- None Differential.too

.iquid pump suction stat SLC pump suction line Replace thermostat' on:rel temp switch

.:c c,n cut-of; trace' heaters not and on working MR 157818 1

1

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l 28 OUTAGE MAINTENANCE & MAJOR MODIFICATION MANAGEMENT December 1984 MAJOR MILESTONES AND EVENTS he revised Standard Practice BF 8.3 procedure was PORC-approved in mid-December, changing the work plan writing and approval scenarios.

Fuel receipt was completed on December 21, 1984. 301 new General Electric fuel bundles were received.

In-service inspections of pipe welds and hangers were completed on December 18, 1984. Seven welds were rejected. They include:

DWRC-2-4; Isolable RWCU suction weld JP-2-1 A&-2-1B; Jet pump instrument line nozzles KR-2-14; A Recirc riser saddle weld KR-2-36; B Recire riser saddle weld KR-2-37; B Recire end cap KR-2-41; B Recire riser saddle weld MINAC was tested with unsuccessful results.

Units 1 and 2 "B" and "A" diesel generator annual maintenance was completed.

The new low pressure (LP) "A" turbine rotor arrived onsite December 12, 1984 The "old" LP "C" spindle was shipped to Muscle Shoals on December 12, 1984.

Main steam relief valves were shipped to Wyle Labs for testing.

Fuel sipping was aborted due to new fuel receipt.

The torus drain was completed on December 17, 1984.

All condensers and waterboxes were opened as of December 21, 1984.

Both recirculation pumps "A" and "B" motor maintenance were completed on l December 10, 1984.

l I

he condenser circulating water inlet tunnel was pumped down. Two seams were reported leaking; one of which had been previously repaired.

4 i .

IHSI of the following number of welds will be required:

RWCU: 16 Core spray: 11 d Recire: 96 RHR: 31 \'

TOTAL: 154 (U-3 total was 148) l l

6

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29 OUTAGE MAINTENANCE & MAJOR HDDIFICATION MANAGEMENT DECEMBER:1984 ,

l MAJOR MILFMTONES AND EVENTS (Continued)

Five inoperative SRMS and IRMs were removed from the vessel.

The tatit was taken out of backfeed for a four-week period to perform maintenance and repairs on generator breakers and 2A main transformers.

Probologs completed during December: W C1, C2, B2 Waterboxes 2A5 Drain Cooler 2B 1, 2, 3, 4, 5 Feedwater Heaters

'2A RHRHX 1 and 2 A and 1 and 2 B Diesel Generators Modifications completed during December:

ECN P0646; diesel generator air start valve installations completed on unit 1/2 "A" and "B" diesels.

CRITICAL PATH WORK ECN P0126 Work plan preparations continued with highest priority assigned to core drilling and conduit installation. The core drill workplan was approved on December 26, 1984, and core drilling started at elevation 593 on December 31, 1984.

OTHER MAJOR WORK IN PR0ragSS Security Modifications - As of December 31,1984, 57 days r'emained for completion of modifications. All sterials required for fabrication of the first (of three) set of 38 barrier have been received at the service shop. Modifications to the stairvells outside the power block personnel accesses were completed.

Work plans for modifications to the control bay doors and for installation of the first set of barriers are in the approval cycle.

IHSI - Preparations to start heats on January 8, 1985, continued. The contractor arrived onsite in mid-December for setup and interference identifications. 54 interferences were identified; five electrical and 49 mechanical. The IHSI support building is set and power hookups are 90 percent complete.

Drywell structural steel inspections by Engineering Design continued with overall inspections approximately 80-percent complete.

\

Major valve work in progress: 74-68,71-580, 73-603, 3-76, "Ba I/B and both "C" main steam isolation valves, removal of 64-series valves.

I ~

_.~._ - _. -- - - - - - - - - --

. (

30 OUTAGE MAINTENANCE & MAJOR MODIFICATION MANAGEMENT DECEMBER 1934 OTHER MAJOR WORK IN PROG.WM (Continued)

Recirculation motor-generator set (MG) maintenance continued through December and lacks stoning rings on both MG sets for completion.

ECN P0392 SDIV tank prefabrications are in progress.

Torus baffle removals are 80-percent complete. Bottom decontamination / sandblast <

was completed. Internal work started on December 18, 1984 ECN P0361 (torus attached piping) work has not started. This work continues to be plagued with unissued drawings.

REMARKS As of December 31, 1984 (outage day 108), the projected completion date is August 2, 1985 (outage day 322). Major slippage has occurred during the month and is attributed primarily to revision of BF Standard Practice 8.3 and engineer training.

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