ML20126K508

Monthly Operating Repts for Apr 1981

ML20126K508
Person / Time
Site:	Browns Ferry
Issue date:	05/01/1981
From:	Abercrombie H, Thom T TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20126K506	List: ML20126K502 ML20126K508
References
NUDOCS 8105150335
Download: ML20126K508 (31)

Text

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TENNESSEE VALLEY AUT110RITY DIVISION OF POWER PRODUCTION BR0h?;S FERRY NUCLEAR PLMIT MONTilLY OPERATING REPORT April 1, 1981 - April 30, 1981 DOC 1'ET NUMBERS 50-259, 50-260, AND 50-296 LICENSE NUMBERS DPR-33, DPR-52, N;D DPR-68 l

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Submitted Byi

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Plant Superintendent 81051"'O3 %

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TABLE OF CONTENTS 1

Operations Summary.

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l Refueling Information i

5 Significant Operational Events..

12

. Average Daily Unit Power Level.

15 f

Operating Data Reports.

Unit Shutdowns and Power Reductions.

18 22 i

Plant Maintenance

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28 Outage Summary...

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i Ooerations Summary April 1981 The following summary describes the significant operational activities during the reporting period.

In support of this summary, a chronological log of significant events is included in this report.

There were four reportable occurrences and six revisions to previous reportable occurrences reported to the NRC during the month of April.

Unit 1 There was one scram on the unit during the month. On April 11, the reactor was manually scrammed for the EOC-4 refueling outage.

Unit 2 There were no scrams on the unit during the month.

Unit 3 There were two scrams on the unit during the month. On April 4, the r

reactor scrammed from a low vacuum turbine trip caused when power was restored to the bus for the 250V DC turbine trip after maintenance to locate and remove f

a low resistance positive side ground in the circuitry. The reactor scrammed on April 23, from a MSIV closure when a transfer of start busses caused a short interruption of plant preferred agd non-preferred power resulting in recirculation pump swing (the MG set scoop tubes failed to lock) which produced a low water level in the reactor from the recirculation flow transient.

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.0perations Summary (Continuel)

April 1981 Fatigue Usage Evaluation The cumulative usage factors for the reactor vessel are as follows:

Location Usage Factor Unit 1 Unit 2 Unitj Shell at water line 0.00503 0.00393 0.00352 Feedwater nozzle 0.24411 0.16963 0.12962 Closure studs 0.19865 0.13694 0.10249 Note:

This accumulated monthly information satisfies technical specification section 6.6.A.17.B(3) reporting requirements.

C_cnnon System e

Approximately 6.21E+05 gallons of waste liquid were discharged containing approximately 6.90E-01 curies of activities.

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-I Operations Summarv (Continued)

April 1981

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I Unit 1 f

Unit 1 began its EOC-4 refueling outage on April 11, with a scheduled restart date of August 2, 1981. This refueling will involve loading additional

~8 X 8 R (retrofit) fuel assemblies into the core, the final fix on the sparger j

modification, power supply on LPCI modification, generator breaker and unit station transformer tie-in (requires Unit 2 to be shutdown), and' torus modifi-I cations if all approvals are received.

I There are 46 fuel assemblies in the reactor vessel. The spent fuel i

storage pool presently contains 718 EOC-4 fuel assemblies, 550 spent 7 X 7 l

fuel assemblies, five 8 X 8 spent fuel assemblies, 260 new 8 X 8 R fuel assemblies, and one spent 8 X 8 R fuel assembly.

Because of mcdification work to increase spent fuel pool capacity to 3471 assemblics, present available capacity is limited to 430 locations.

l Unit 2 1

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Unit 2,13 scheduled for its fourth refueling beginning on or about March 26, 1982, with a scheduled restart date of August 13, 1982. This refueling f

i outage will involve completing relief valve modifications, torus modifications

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if all approvals are received, "A" low pressure turbine inspection, MG set l

installation for LPCI modification, and loading additional 8 X 8 R f uel r

assemblies into the core.

I There are 764 fuel assceblies in the reactor vessel. At the end of the month, there were 132 discharged cycle 1 fuel assemblics, 156 discharged cycle 1

2 fuel assemblies, and 352 discharged cycle 3 fuel assemblies in the spent fuel j

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4 Operations Summary (Continued)

April 1981 Unit 2 (Continued) storage pool. The present availabic capacity of the spent fuel pool is 160 storage locations. With present capacity, the 1979 refueling was the last refueling that could be discharged to the spent fuel pool without exceeding I

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that capacity and maintaining full core discharge capability in the pool.

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However, 949 new high density storage locations have been installed, but i

cannot be used until Special Test 161 is completed.

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Unit 3 Unit 3 is scheduled for its fourth refueling beginning on or about September 25, 1981, with a scheduled restart date of February 7, 1982. This l

I refueling involves loading additional 8 X 8 R (retrofit) assemblies into the l

core, relief valve modification, turbine inspection, generator breaker and l

unit station transformer tie-in, and torus modifications if all approvals f

are roccived.

There are 764 fuel assemblies presently in the reactor vessel. Therc f

are 124 discharged cycle 3 fuel assemblics. 144 discharged cycle 2 fuel assemblies, and 208 discharged cycle 1 fuel assemblies in the spent fuel j

storage pool. The present available storage capacity of the spent fuel i

pool is 1052 locations.

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i Significant Operational Events 1

Unit 1 f

Date Time Event 4/01/81 0001 Reactor thermal powet at 97%, maximum flow, EOC ',

j coastdown (all rods out).

1500 Reactor thermal power at 96%, maximum flow, EOC-4 l

coastdown.

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' ' "4/04/81 0050 Commenced reducing thermal power for turbine control valve tests and SI's, i

0100 Reactor thermal power at 89%, holding for turbine l

control valve tests and SI's.

l 0115 Turbine control valve tests and SI's completed, commenced power ascension, v

0400 Reactor thermal power at 96%, maximum flow, EOC-4 coastdown.

4/06/81 2300 Reactor thermal power at 95%, maximum flow, EOC-4

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constdown.

4/09/81 2300 2eactor thermal power at 94%, maximum flow, EOC-4 coastdown.

i 4/10/81 2120 Commenced reducing thermal power for shutdown to I

accommodate EOC-4 refueling outage.

4/11/31 0049 Reactor manual Scram Ho. 141 from 41% thermal power, to accommodate EOC-4 refuel outage.

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4/18/81 1648 Began fuel unloading from RPV, j

4/30/81 2400 End-of-cycle 4 refueling outage in progress.

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6 Significant Operational Events Unit 2 Date Tima Event l

-4/01/81 0001 Reat. tor thermal power at 99%, maximum flow, rod limited.

4/03/81 2134 Reduced thermal power to 82% for MSIV and turbine control valve tests and SI's.

2303 MSIV test, turbine control valve tests and SI's completed, commenced power ascension.

4/04/81 0001 Commenced PCIOMR from 96% thermal power (sequence "B").

0100 Reactor thermal power at 99%, maximum flow, rod limited.

t 2115 Reduced thermal power to 82% for MSIV tests.

2130 MSIV tests complete, commenced power ascension.

F 2200 Commenced PCIOMR from 96% thermal power.

2300 Reactor thermal power at 99%, maximum flow, rod limited.

4/07/81 2030 started reducing thermal power for MSIV tests.

2100 Reactor thermal power at 81%, holding for MSIV tests.

2115 MSIV tests complete, commenced power ascension.

2300 Commenced PCIOMR from 98% thermal power.

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

4/09/81 0030 Received a fuse failure alarm, primary containment isola-7 tion and refuel ::one isolation, started putting station air into drywell.

0345 Commenced reducing thermal power for shutdown due to i

primary containment and refuel zone isolation.

0445 Reactor thermal power at 89%, all isolated systems are back in service.

0448 Commenced power ascension from 89% thermal power.

0500 Station Mir isolated to drywell j

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

r 2012 Commenced reducing thermal power for MSIV tests.

2100 Reactor thermal power at 96%, MSIV teuts in progress.

2130 MS1V testa completed, commenced power ascensien.

2140 Commenced PCIOMR from 98% thermal power.

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2300 Reactor thermal power at 99',, maximum flow. rod limited.

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Significant Operational Events i

Unit 2 h

Date Time Event j

4/10/81 1656 Reduced thermal power to 70% due to a high water level alarm in the CRD west header.

1710 High water level alarm cleared after 1 minute and 58 seconds, commenced power ascension.

1755 Commenced PCIOMR from 96% thermal power.

2300 Reactor thermal power at 99%, maximum flow, rod limited.

2340 Commenced reducing thermal power for turbine control valve tests and SI's.

4/11/81 0010 Reactor thermal power at 73%, holding for turbine control valve tests and SI's.

0115 Turbine control valve tests and SI's complete, commenced l

power ascension.

0630 Commenced PCIOMR from 96% thermal power.

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0800 Reactor thermal power at 99%, maximum flow, rod limited, f

4/14/81 2150 Commenced reducing thermal power for MSIV tests.

2212 Reactor thermal power at 82%, holding for MSIV tests.

i 2214 MSIV tests complete, commenced power ascension.

2300 Reactor thermal power at 99%, maximum flow, rod limited.

4/17/81 2130 Commenced reducing thermal power for MS1V tests.

2155 Reactor thermal power at 82%, holding for MSIV tests.

2244 MSIV test complete, commenced reducing thermal power for control rod pattern adjuercent.

I 2300 Reactor thermal power at 44%, holding for control rod

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pattern adjustment.

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t 4/18/81 0135 Control rod pattern adjustments complete, holding for SI's.

0315 SI's complete, commenced power ascension, i

0755 Commenced PCIOMR fron 58% thermal power.

4/19/91 1130 Reduced thermal power from 83% to 75% for turbine control

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valve tests.

j 1155 Turbine control valve tests complete, connenced PCICMR.

r 4/20/81 2300 Reactor thermal power at 99%, maximum flow, rod limited.

4/24/81 2140 Reduced thermal power to 90% for turbine control valve tests and MSIV tests, f

2315 Turbine control valve and MSIV tests complete, commenced power ascension.

l 4/25/81 0300 Commenced PCIOMR form 96' thermal power.

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0700 React. thermal power at 992, maximum flow, rod limited.

2125 Reduced thermal power to 90% for MSIV tests, j

2140 MSIV tests completa, commenced power ascension, j

2300 Reactor thermal power at 99%, maximum flow, rod limited.

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Significant Operationni Events Unit 2 f

Date Time Event

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4/27/81 2000-Reduced thermal power to 90% for MSTV rests.

2220 MSiv tests complete, commenced power ascension.

2300 Reactor thermal power at 99%, maximum flow, rod limited.

4/30/81 2400 Reactor thermal power at 99%, maximum flow, rod limited.

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Significant Operational Evenrq l

l Unit 3 Date Time-Event i

f 4/01/81 0001 Reactor thermal power at 99%, maximum flow, rod limited.

4/02/81 1515 Lost "B" SJAE, vacuum decreasing, commenced reducing thermal power.

l 1525 Reactor thermal power at 50%, holding, vacuum increasing i

"B" SJAE being returned to service.

i 1543 Commenced power ascension from 50% thermal power.

2230 Commenced PCIOMR from 94% thermal power, (control cell

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core).

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'4/03/81 0430 Reactor thermal power at 99%, maximum flow, rod limited.

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-4/04/81 0001 Commenced reducing thermal power for turbine control valve tests and SI's.

0100 Reactor thermal power at 89%, holding for turbine control f

valve tests and SI's.

0222 Turbine control valve tu ts and SI's complete, commenced power ascension.

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0330 Commenced PCIOMR from 96% thermal power.

l 0735 Reactorthermalpoweggt99%,maximumflow, rod limited.

1251 Reactor Scram No. 95 from 99% thermal power while performing tests to locate a 250V DC ground fault. The low vacuum turbine trip relay K2D18 operated when the 250V bus was re-energized causing a low vacuum turbine trip.

j 1808 Commenced rod withdrawal for startup.

2034 Reactor Critical No. 107, f

l 4/05/S1 0845 Synchronized generator, commenced power ascension.

l 1500 Commenced PCICMR from 72% thermal power.

i 4/06/81 1830 Reactor thermal power at 99%, maximum flow, rod limited.

4/08/81 2130 Commenced reducing thermal power for control rod pattern I

adjustment.

l 2150 Reactor thermal power at 73%, control rod pattern adjust-l ment in progress.

l 2200 Control rod pattern adjustment complete, concenced power l

ascension.

2230 Commenced PC10MR f rom 91% thermal power.

I 4/09/81 0326 Reduced thermal power from 94% to 92% to maintain margin to core limits - xenon transients.

l 0400 TIP run complete, commenced PCIOMR.

l 0S16 Stopped PCICMR due to Xenon transient, reactor pc.ier at 98%.

1300 Commenced PCIOMR from 9S0 thermal power.

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i Significant Operational Events Unit 3 L

I Date

't ime Event

,4/09/81

'1400, Reactor thermal power at 99%, maximum _ flow, rod limited.

1509 Reduced reactor thermal power to 97% due toL1/2 1 solation-l (MSL "A" low pressure).

I 1950 Commenced power ascension from 97% thermal power.

j 2300 Reactor thermal power at 99%, maximum flow, rod limited.

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. - ev 4/12/81 0126 Commenced reducing thermal power for turbine control valve tests and SI's.

0138 Reactor thermal power at 88%, holding for turbine con-trol valve tests and SI's.

i 0145 Turbine control valve tests and SI's complete, commenced t

power ascension.

0255 Commenced PCIOMR from 95% thermal power.

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

4/14/81 0325 Reduced thermal power to 98% to maintain margin

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to core limits.

l 1510 TIP run complete, commenced power ascension.

j 1535 Reactor thermal power at 99%, maximum flow, rod limited.

i 4/15/81 0716 Reduced reactor thermal power to 08% due to CMFLPD.

f 0730 Reduced reactor thermal power to J7% due to CMFLPD.

j 0800 Commenced power ascension f rom 97% thermal power.

f 0900 Reactor thermal power at 99%, maximum flow, rod limited.

i 4/16/81 0900 Reactor thermal power at >99%, maximum flow, rod limited.

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4/17/81 0615 Commenced reducing thermal power due to erratic behavior of 3C RFW pump.

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1000 Reactor thermal power at 89%, holding for maintenance on 3C RFW pump (change out of function generator).

i 1342 Maintenance complete on 3C RFW pump, commenced power I

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ascension.

l 1430 Commenced PCIOMR from 96% thermal power.

i 1730 Reactor thermal power at 99%, maximum flow, rod limited.

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4/18/81 0035 Mechanical trip valve lock out alarm did not annunciate l

when test button was pushed.

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0303 Reduced thermal power to 90% to replace relay XK55 (oil i'

trip overspeed).

0315 Relay XK53 replaced, holding at 90% for CRD exercise.

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0433 CRD exercise complete, commenced PCIO:!R.

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

2200 Commenced reducing thermal power for control rod scram i

time testing.

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2300 Reactor thermal power at 46%, control rod scram time test-ing in progress.

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Significant Operational Events Unit 3 Date Time Event 4/19/81 0230 Control rod scram time testing complete, commenced power ascension.

1200 Commenced PCIOMR from S2% thermal power.

4/20/81 1500 Reactor thermal power at 99%, maximum flow, rod limited.

-~4/23/81 0531 Reactor Scram No. 96( } from 99% thermal power, when a transfer of start busses caused a short interruption of plant preferred and non-preferred power, which resulted in recirculation pumps runback and a scoop tube failure to lock. After reactor feedpumps backed down the recir-culation pumps increased, resulting in a low water level scram.

0940 The unit remains out of service for testing of the scram f

discharge volume level monitoring system, ST-190, required by NRC Bulletin 80-17.

1845 ST 190 complete, commenced rod withdrawal for startup.

2127 Reactor Critical No. 108.

4/24/81 0150 Rolled T/0.

0217 Synchronized generator, commenced power ascensicn.

0245 Reactor thermal power at 23%, holding for IRM calibration.

0310 IRM c>libration complete, commenced power ascension.

1030 Commenced PCIOMR from 79% thermal power.

4/25/81 0230 Reactor thermal power at 99%, maximum flow, rod limited.

0500 Reactor thermal power at 98%, manimum flow, rod limited.

0600 Reactor thermal power at 97%, maximum flow, rod limited.

0700 Reactor thermal power at 96%, manimum flow, rod limited.

0900 Reactor thermal power at 95%, maximum flow, rod limited.

1100 Reactor tlermal power at 94%, maximum flow, rod limited.

1 4/25/81 1400 Reactor thermal power at 93%, maximum flow, rod limited.

1438 Commenced reducing thermal power due to high river aT.

1500 Reactor thermal power at 74%, holding due to high river AT.

i 1530 Commenced power ascension from 74% thermal power.

1610 Reactor thermal power at 91%, maximum flow, rod limited.

2150 Commenced reducing thermal power for a control rod pattern adjustment.

2220 Reactor thermal power at 73%, holding for control rod pattern adj us tment.

2320 Control rod pattern adjustment complete, co=enced power ascension.

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'4/26/81 0430 Commenced PCICMR frem 33% Lhermal power.

1722 Reactor thermal power at 99l;, maximum flow, rod limited.

1 4/30/81 2400 Reactor thermal power at 99%, maximum flou, rod limited.

(1). Equipment Malfunction (2). Equipment Malfunction Maintenance e

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12

.WER -\\GC D \\ll.Y UNil POh ER I.EVEL 50-259 lH:CKETNO.

t.gg Browns Ferry - 1 May 1, 1981 g g.; g Lo\\iP!.ETLD !!Y 3d Thom 205-729-6846 I El.:.Pl Rn t:

"510NTil April 1981 DAY AVERAGE DAILY POWER LEVEL D.\\Y AVERAGE D \\lLY P0hER LEVEL t lhe Nm

(\\lWe Net)

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1021

-8 7

1020

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$3 1017

-8 3

39 1012

-7 4

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1007

-7 3

g 1004

-8 l

3 998

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,I 1001

-3 3

y 955

-7 o

3 952

-7 10

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-9 6

12

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DOCKL1 No.

50-260 UNlI firotms Ferry - 2 D \\1E

_.5-l-81 COsn'Li f Ep !!Y T I Tl"*

-729-6846 205 l t.1..PI(OM

$10NT11 Agr_1.1_.1$1 D \\Y AVI.R AGE D.\\lLY POh Cil LEVEL DAY AVE}L\\Gl'. D \\lt.Y l'Oh LP. LLVEL 4 \\1We Neti IMWe Neti 1061 1013 2

1067 677 p;

1056 901 3

iy 1061 1029 4

39 1064 1053 3

1052 1053 1050 1050 1070 104M

.10 f. 6 105l gg 1006 1007 3,

10.36 1054 i,

1050 1052 3

1049 1045

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_3!!41 30 l_000 15 Ibh 31 1057 p,

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' WER \\GE IMil Y 151'l l'Oh ER LTVl l.

DGCKE'! NO.

50-296 UNIT Browns Ferry -3 l

5-1-81

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CO\\ta'LETEi) Uy _Ted Then i

205-729-6846 l

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' '"f.ONTil April 190I i

DAY AVER AGE D AILY POWER LEVEL DAY AVER AGE D AILY P0hER LEVEL i\\1he.Neo

(.\\lWe NetI

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1070 1027 i

37 3

1033 is 1027 i

1069 863 3

,9 j

552 990 4

20 438 1058 5

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994 1064 n

7 1056

3 230 1

1057 s

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179, 1027 979 9

y 1084 973 ig 3,

1065 1061 1048 1063

.g 1057 1062 i

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i4 1046 30 1_064 i

1048 i

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.I I in 1067 IN>,TRI t ilONS

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OPER ATING DATA !!EPOR f 1

50-259 DOCKET 50 D.\\ T E 5-1-8I~~

COMPLETED l'y Ted Thon TI LI Pl!ON L _205 _Z29: _684 6 OPrR \\ TING S1'\\TUS T

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1. Unit ;s'ame:

11rotms Ferry 1

Anril 1981

)

3. ileporting Peri >d; 3.Sicensed Thermal Power (atWt): 3293 1152

4. Nameplate Itating (Gross.\\lWe):

1065

5. Dnign Electrical Rating (Net 51We):

1098.4

6. Maximum Dependable Capacity (Gron StWe);

1065

7. $lasimum Dependable Capacity (Net 31We):

8. If Chan;:es occur in capacity Ratin;n iItems humber 3 Through 7)Since Last Report. Gise Reasons:

NA NA

9. Power Lesel To Which Restricted. lf Any (Net Sthe):

NA

10. Reasons For Restrictions. If Any:

This Month Yr. to D He Camuhthe i

719 2.879 59,161 ll iloun in Reportin; Perioil 200*02 2]80*4 37 l90 97

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12. Number Of flours Roetor Was Critic:.1 i

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13. Reactor Retirre Shutdown llour>

0 16.42 5,115.29

14. Iloun Generator on.Line 240.82 2,380.77 36,373.59

15. Unit lteserse Shutdown lluun 0

0 0

16. Grou Thermal Ener;y Generatest t\\t%)l) 745.157 7,4252 95 100.717,556 17 Grow Electrical Energy Generated (siwill 247,330_,,

2,474,200 33.23[49E

18. Net Electrical Ener;;y GeneraicJ t'.thit) 236,651 2,407,849 32,271,666 ~

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19. Unit Senice l' actor 33.5 32.7 61.5

20. Unit Availability factor 3_3.5 82.7 61.5

21. Unit Capae:tv l' actor i t' ing MDC Neti 30.9 78.5 51.2 22.1/ nit Capaaty r:tetor (LMng Of R Ni v) 30,.9

_78,5

_5j_, a

21. Unit forsed Ontare !! ate 0

0,8 j2,3 0 2 3. hhutilow ns Schedulest th er Neu 6 Months il s tic. Dat,'. anJ Uuration io I ad t w +- e --

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$h f ll,

n. If uk in iest Statn, tPoor to C.unnteni I Op6 rationi l'o rc c.nl blueu d INil! \\ L CRll!C \\1.11 Y INI Ii \\ 1. El.f C l it it 11 Y 1

COM\\lERCI \\L OPl it \\l10N t

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16 Ol'EftATING DATA REPORT DOCl;El NO.

50-260 DA1E 5'l-81 _

COMI'Li'TLD By Ted Thom

'l LLt:Pll051: 203 7.2h.6846 OPER tTING ':T.'.Tt]

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1. Unit Name:

Browtui Ferry - 2 j

APE 11 1901

2. Report 5,t Perind; 3.lleensed Thennal Pimer plut):

3293 1152

4. Narneplite Italing (Grost MWe):

1065

5. Design Elec:rical Rating (Net Mbel:

1098.4

6. \\tasimnm Dependable Capacity (Gross.',3 vel.

1065

7. Maximum Dependabic Capacity gNet Moe):

8. If Chan;:e5 Decur in Capacity Ratian iliems Number 3 Tiu >uch 7i Since Last Iteport. Gi c Reasont NA NA

9. Pow er Lesel To b bleh Reitri.:ted. lf Any (Net M%'es:

10. Rea>uns For Restrictions. If Any: -

NA l'hh Monto Yr.,to D.n e C uiaida t h e

11. Ilotn s in !leportin,; h riod 2,879_

54,072

12. Nt'mber Of il"urs Itcactor h:n C ritie.d II9

.__2'HI4 21 33; M7 82 0

64.79

_12.513.27

13. Reactor Resene.5;hurdown liours

14. lionri Generator or Line 719 2,759.94

_32j00.95

15. Unit Reserve Shutdoe.n lloon 0

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16. Gross Thermal Energy Geneiated iMnil) 2,2,8,l,714 8 51.4_,683 Jgl.QQ,)l1 2

17 Gross Electrical Encryy Generated Olhil) 76h430

' 35 L,_ lit 0 3Q,538,rM

13. Net Electrical Energy Generatesi(Mbi!)

743,362 2,77b422

_2S 7_21 729 100 95,9 60.1.

19. Is. nit Senke I. actor 2 t). Unit Ata. lability l' actor 100 95.9

,fg0.1

21. Umt Capicity f actor tUsino \\ll)C Net) 97 d 9 0. 5_ _

,5,1, 6 97.1 90.5 51.6

22. L'ni Capnity ractor iU.mg D) R Net) 2.1 l' nit forced Ootage it.ac 0

4...L

_ll. l. -

?.1, S hutdow n. Sc'iedn'cJ Ose Ne u 6 hihs i 13 pe. Date,.nid Dw ation of f.sch i

!!aintenance May l981 (21 davn) 4 o

26, l'vil, in I ss. Who iPrior in sloinn ctcui Ops intion i I oscou b hiemi i

l INl[l \\ l. ('lIll lf \\ L.ll

ISill \\ l.1 L i'C1 MICl FY C0\\lMI RCl \\ L Gl'I It \\ LION en;?)

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i f

OPER ATING DATA REPO!1T j

r DOC::ET NO. 50-296 r

DATF. 5-1-81 COMPLEI ED SY J'ad Then_.

l TI:LEPHON E 205-729-6846 e

r Ol'E! AT!NG STATUS i

)

. Browns Ferry - 3 Notes l

1. Uidt N.ame:

April 1981

2. Reporting Period:

3. $icensed Thennal Power IMWt):

3293 l

I 115*9

4. Nameplate Rating (Gross MWe):

r 1065 l

5. Design Electrical Rating (Net MWe):

1098.4

[

ti. Masimum Dependable Capacity (Gross MWe):

~

1065

7. Maximum Dependable Capacity (Net MWe):

{

S. If Changes Occur in Capacity Ratine (Items Number 3 Through 7) Since Last Report. Gi'e Reasons:

NA-NA

9. Power Level To which Restricted. lf Any (Net MWe):

NA

10. Reasons For Restrictions. If Any:

t Tl.is Month Yr. t a.Date Cannative

?.

11. Ifours in Reporting Penod 719 2,879 36,527 l

695.35 2,329.46

.8,30"077)

12. Number Of H na3 ;teactor h as Critie.il

13. Reactor Ite:en e Shmdown llaurs 14.57 170.14 1931.03

[

14. Ilours Gen. nder On.Line 678.33 2,252.32 27,642.32 I

15. Unit Resene Si utdown llows 0

0 0

l

-. t.0 0 8, 5_14. _._

l

16. Grnts Thermal Energy Generated (MWili 2,154 845 6.643,486 81 s

17 Gross Electrical Energy Generated iMWil) 716 2,8_0__,

2,228,230 26,767,260 u

1R Net Electric;.! En.:r;y Generated (Mh FI) 695,377 2,161,044 25,985,367 l

19. Unit Senice Factor 94.3 78.2 75.7 94.3 78.2 75.7

20. Unit Amitab.tity Factor

21. Un.1 Capacity factor (Usin;; MDC Neri 9 0. S__

70.5 66.8 90.8 70.5 J6. S

22. Umt Capacity Fietor(Using DEit Net)

>. 7 d.3 9.6

23. Unit Forced Outage Rate 2 3. Shutdow ns Scheth.ird ther Nest n Mmuhs ( f.s pc. D.ue, and Duratient of Eachi t-j 21 it 5.hnt D.c.in s t End ut urp.ni h iinil. E ina.ved D.ue ot surtup:

h Unos in Test Staius t P<,or io Conuncret.210perat;on c ro,ccast

. u i,;es ed i

INill \\ L CRil !C A LITY INIT \\L ELEC1RIC11Y j

cob \\1.RCf \\ L Ul'ER AllON l

I l

5 L'8 /7 7 )

e.

+=

50-259 iOCEET t:0.

UNII SilullMum ann i GwrR REDUCf10NS 15rowns l'erry - 1 UNil N A?.tE I

DATI-May 2, 1981 CO?.tPLETED a f _Ied Tlion April REPoitT.90N 111 TELEPi!ONE 70s-729-6846-1 Acive

[1 h"_',

!7

'h 3, E i Cause A Gersecthe

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a-Ac treti sis L

l bic f,_

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Pieven Returrente

=-

p o

6

______3_._.

172 I 4-11-81 S

478.18 C

2 EOC-4 Refuel. Outage Hco k

i 2

3 4

l

1.... e,i Rc,,..n Alet!nal:

I slat it C - la hustio.ts s 5.1

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.1 1.:pa. :e bdine (1.q!ain t t timaal sin hquotii n vi D si It..: 6. 0, tm e m Ic:.:

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1 MUM-UNIT S!!Ull,GWNS AND POWER MLi)UCTIONS Erowns Ferry -2 j

. UNIT t4A?.f E

?.

pr1E lbv 2.

1981 i

CO!.11*1.ETLD IiY Tsd Thon APIil REitit 510'7 til IELLFitONE 70s 7,ri_cagn

=

=

1

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b Cauw & C orectiu

=

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2?

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=-

=-

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i f

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______1.

+

I.

135 4-10-31 F

D liigh water level alarm in CRD west header i

Turbine control valve tests and SI's l

166 4-10-81

! S B

I i

H w

l 187 4-17-81 S

II Control rod pattern adjustment and SI l

t h

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a l,

i I

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+ Orbertl. w i. min 01911 l

l > l:, 41,6 u, : h t r.n I t i; _ u t.i 1.:... in : A t.u cisw-la.uta u' um 5

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c. ET NO.

50 796 UNII Situ 1 DOWNS 1ND POWER HLDUC1'lONS

-,tJNIT N Ah!E Browns Ferry -3 I)A g E

%- 1 R 1 COMI*l.ETI:D i!Y Ted Thom--

1:1.i'OR I MG' Jill _j}pril

)g.1 EPI G23E --205-729-6846--

57

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Cause & Corte tr.:

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Ior -

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E0 h0 hcsetts Reuntui..e U

5 O

f.

69 4/02/81 F

A "B" steam jet air ejector out of ser.

~

70 4/O'4/81 F

19.90 B

3 While testing to find a 250 V ground fault the low vacuum turbine trip re-lay K2D18 operated at the instant the 250V bus was re-energized causing a w

low vacuum turbine trip.

The reactor o

scrammed on stop volve closure.

71 4/08/61 S

H l

Control rod pattern adjustment.

l 72 4/18/S1

! 5 B

Control rod scrum time testing.

I I

I 4___.._

L_

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P. Ma.I tt N.in.c of l c;l 2 bIJIttiJI Sif atti.

l.IllI}.S!trel> list Ihttn L A Autotiutic Lt.un.

l.sent 1(epo.1 t 1.1.R e hic int :HI (..

l r !!dt.ri....f 1

• Rqi.i.iida l'.c.i ncli.m 3-Othen tlag.iain) 01 til I i Uxta o l e stu ng a lu ne i umni an.i s

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

i 50-296

• OCKETNO.

UNIT S!!U1 DOWNS AND POWEll REDUCTIONS UNil' N AM E Browns Ferry-3 (Cont)

DATE 5-1-R1 1'ed 't hom

}205-729-68 %

CIBIPLETED BY REPOR1 slONIll April IELLI'llONE l

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c

=.;

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$0 Present necurrente j@

di 3d5 Repa:

=

0 6

73 4/23/S1 F

!., i-

-D-Transfer of start busses caused a short interuption of plant preferred and non-preferred pouer which result-ed in a recirculation pump runback and a scoop tube lock failure. After reactor feed pumps backed down, the U

recirculation pumps rapidly increased resulting in a low water level scram.

The unit remained offline for test-i ing the scram discharge volume level monitoring system (ST-190).

74 4/25/81 F

D liigh river AT.

I i

3 4

12 Fo r < c J Renon Method:

I:xlubit G - Inst ruct ams i

S. klaNe 1

-\\ l.pnpment fadure (L. plain)

! %nual for Pieparatron ul Data It%iritetune e er 1 cst

2. Manual Scr arn.

Enu) Sheets for IArmee 3 Antunutic Strain.

ther Rep 4nt (1.1 la Ede tNURI G-O Retuthng D R rulan,r> Res!nction 4 Other (lixplam) 01611 I i spcut.,r leanung & IAense f unnnation 5

I - Ad i t ;11al1I E J f !.C

[shibit 1 Saane Souice G 4 Apce atzonal la ror (L s plain )

C8/77) 110;her (i.xi.un) d yg,eyg,g

.-----a.yge.ee.gq-=

q-m

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pg gw.emy-iw emyos-WMw gg-ge-g*mhv--wepu:.r--gg,wy-W.-ggy-4 M

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9 w-

1;n0'.!-IS FI;ititY IIUCLEA1: PIJ.NT UNIT 1 and Common CSSC EnllII:iENT ELECTRICAL MAIIITENANCE SUIsiARY For the :-ionth of April 19 81 v

Etreet en Saic Action Taken Dr.:e Systea Cetponent Nature of Operation of Cause of Results of To Preclude

hintenance The Rei:ctor Malfunction Malfunction Recurrence i 4/7/81 RilRSW D-3 RIIRSil Motor noise.

None Bad motor bear-Motor noise The motor was re-pump motor

ings, paired Dil 33 arid 64 performed and motor returned to service. TR #102617 I

I 4/10/81 IIPCI IIPCI hotwell Hotwell pump None, llPCI was Bad pump motor, llot well pump inop-Replaced motor, per-punp motor.

would run 10

operable, erable.

formed EMI 71 and 33 j pump operated proper-seconds then trip.

ly.

TR #225598 1

'4/14/81 Fire "B" Fire pump Motor noise None Bad motor bear-Motor noise Replaced bad bearings protection

ings, motor operat,ed properly. TR #220534 le 4/16/81 Fire Fire alarm Bad battery None Bad cell No voltage on Replaced battery, I$

l protection

• panel cell battery cell #3 bank voltage was checked and found to

[

be at proper level.

3 i

TR #188003 l

i lD/GFirepro-Trouble alarm None Breaker tripped Interruption of D.C, Reset breaker.

l4/21/81 Fire I

protection tection panel in panel 25-331 power to all smoke TR #191708 25-331 detectors powered LER #BFRO-50-259/8111:

from panel 25-331

'and auto-initiation of the preaction

{

sprinkler inoper-g able.

[

t m

m r

- ~

m.

~

l,.,

LEGh'NS FERRY NUCLEAI: PLANT UNIT 2

CSSC EOUTIMEliT ELECTRICAL tulNTENANCE SUIEBRY For the Month of April 19 81 i

V Ef rect on Saic

-Action Taken-i Nature of Operation of Cause of Results of To Preclude-Dcte Systcc Cenponent

aintenance The Reactor Malfunction Malfunction Recurrence l

4/9/81

, Primary Relay Replacement The Rx cone vent -Bad relay coil Reactor building Natural end of coil life. Replaced coil,

'contain-16AK61A of relay coil ilation system ventilation relay operated ment isolation was isolated.

l isolation bypassed during properly. TR #208649 j

t relay replace-LER #BFRO-50-260/8117 l

ment.

This resulted in a l

limiting condi-i j

tion for opera-l t

tion.

I i

i 4

(n2 i

l l

t i

i l

I e

i l

l t

y i

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i I

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I J

g

URC'.!NS FERRY UUCLEld' PLANT UNIT 3

• CSSC EOUI1EFMT ELECTRICAL MAltITENANCE SUlftARY For the Month of April 19 81 j

Ettect un Sarc Action Taken I D:te Systen Ccrponent Nature of Operation of Cause of Results of To Preclude

aintenance The Reactor Malfunction Malfunction Recurrence 4/2/81 250 Volt Level switch Ground on U-3 None LS-150A grounded Ground on 250V DC Replaced level switch

'DC system 6-150A in 250V DC bat-at internal 0-system TR #205235 ground cleared.

moisture te ry ring leak.

{

separator room l4/2/81 Fire Smoke detec-Detector None Bad detector -

Inadvertent alarms Replaced smoke i

protection tor XS-39-28C inadvertently detector, performed located in alarms SI 4.ll.C.1 & 5, U-3 control detector operated 3

l room panel properly. TR #205457 9-4

!4/12/81 - RPS MG set K-4 input trip Scheduled None, input trip Bad K-4 relay Erratic timing Replaced relay per l

3A relay maintenance relay is not DfI 23, timed relay and testing critical to RPS per Dil 15, system per D1I 13 operation operated properly per l

l section 5.2 D1I 13.

TR #190186 j

TR #219393 I

t I

I4/13/81 RSCS Relay 3AK-49 Received a None 3AK-49 relay coil Fuse failure alarm Tightened loose coil j

in panel 9-28 fuse failure wire loose.

inoperable, wire, fuse alarm I

alarm, circuit operated l

l properly. TRf223326 i

4/24/81 RBCCW "3A" RBCCW Breaker trip-None Apparent misad-

"3A" RBCCW pump Verified trip pump breaker ped while ustment of trip inoperable.

mechanism checked located in transferring mechanism.

trip amp, breaker.

480V shutdown station racked in properly, bd 3A, panel service.

pump returned to i

j 6B service. TR #223331 1

l 5

i i

1

.,.v.,-,,,, - -... -

-w-.. +, -. - - - - - - - <.. - - -.

,-w--+

-,,.e

.r-.-

c--

.'...e--

4--.

,-w.

.::..i ::ili i.Usi; iiJdit L:i t i 1,2,3, 6 Common IMbLICAL IGINTEtaNCE SUI-2IARY CSSC EQUT PME!:;

For the !!unth of April 19 81 SIIEET 10F 2 SiiEETS l

UNIT 1 ACTION TAKE" EFFECT ON SfSE InTE SYSTE1 C0:1PO:.ENT NATURE OF CPERATICN OF CAUSE OF RESULTS OF 70 PRECLUDE MAINTENANCE THE REACTOR l-fALFt*NCTRW MALFLR!CTION RECURRE::CE l-9-81 D/G IC Air Comp.

Blown llead NA High Pressure Leaking Replaced head gasket TR 203080 Casket UNIT 2 4-18-8 L CRD 2A CRD Pump Change Filters N/A Dirty Filters Unknown Changed filters TR 225469 UNIT 3 3-9-81 Fuel Pool Pump 3B Motor needs NA Out of alignment Pump Vibrating Realigned motor to pump 6 installed Closing realignment rubber rhim under each foot of motor TR 136727 m

v 4-18-81 Secondary Door 510 Door giving ofi Containment false alarm NA Latch bolt had a False Alarm Filed off burr 6 burr on it lubricated lock TR 218267 4-18-81 Secondary Door 651 Ilard to open NA Unknown Door wouldn't open Replaced hinge &

adjusted bolt Containment TR 225460 2-24-81 D/G 3/C D/G Uorn Air Valve NA Dirty filter Unknown Cleaned filters &

replaced air valve Air Brake 1 TR 219229 2-26-81 D/G 3D Actuator to NA Unknown Low Oil Level Drained oil to proper level

=

high TR 219231 1-8-81 secondary Reactor side Wo rn foot bolt NA Worn foot bolt Door comes open when New foot bolt 2

not designated adjusted door closer

ontainment door

& weather seal TR 198986 e

_,.-.-.---4w.

,-y-

,..--,vy,-%_.-+.-_v,,,.--m3

,,---p

,,--.-.y-

3 & Common Li:OMGS Fi. DRY ::UCLEAR l1A';, cu t i IIECllidilCAL IfAlllTEIPJ:CE SUM mRY CSSC EQUIPtfEN7 For the Month of April 19 81 SilEET 2 OF 2 SilEETS i

UNIT 3 ACT10It TAKEN EFFECT UN S M E 11ATC SYS1EI!

CU;1PONENT NATURE OF OPERATIO!! OF CAUSE OF RESULTJ OF TD PREC1.UDE flA l tiTENANCE THE REACTOR MALFUNCTION MAI. FUNCTION RECURRI-NCE 4-7-81 RCIC FCV-71-6B Valve blowing NA Needs new kit in Steam leak Installed new kit steam steam trap in steam trap.

TR 223323 4-7-81 RCIC Valve 11-574 Leak NA Unknown Steam leak S/A TR 205480 4-21-81 Secondary Deer 648 Closer too Containment slow NA Closer out of IIold open by air Adjusted closer adjustment pressure TR 218272 4-20-81 Door inter-Door 800 Door closing NA Slow closing of Not enough air Adjusted air press.

lock &

too slow door pressure TR 218268 o

alarm es 4-23-81 liPCI IICV-73-602 Valve stem NA Unknown Unknown Installed new valve TR 159662 broken 4-22-81 Door inter-Door 654 Jill not close NA Uaknown Closer needed Adjusted closer adjusting TR 218083 lock &

Alarm 4-24-81 IIPCI Gland Seal Blown Gasket HA Pressure Seal Condensor blown Changed gaskets TR 190984 Condensor 4-23-81 H1'CI Gland Seal Blown Gasket NA Pressure Unknown Changed both gaskets Condensor TR 190983 CO?f!ON 3

3-26-81 RilR Service D3 Pump Low Flow Rate NA Bearing & wear Caused low flow rate Replaced column ring worn bushings, wear rings, Llater bottom bushings &

top TR 198827 e

er g e w-y

,ye m--v-3

- + -

• w-sr----g

-r-e--

v

-y--gp--s ws-g

=

, er

,-w-3

--,3 w.

+ea e

=

r e

e--

Bl!OUNS FERRY NUCLI2R PLANT UNIT 1, 2, & 3 INSTRU IENT !!AINTENANCE SUl@!ARY

~

CSSC EQUrl';fi' :T FOi; ' HIE MO H l! OF April 19 81' t

NATURE EFFECT ON SAFE CAUSE ACTION TAKEN DATE SYSTEM COMPOI;ENT OF OPERATION OF OF RESULTS OF TO PRECLUDE MAIUTENAIICE THE REACTOR MALFIR?CTION MALFIINCTION RECURRENCE tjn i _t 1

4-28

c ut roa APIGi-A Repair I:ene Faulty Flow Test Power and Flow None Pot.

Signals Did Not Agree i

hu i t o ring

'4-30 containment Lt-84-11A Calibrate Nene Zero Shift Redundant Indicators None Did Not Agree Air Dilutio:

Unit 2 4-1 i'r ima ry Pd e-M-61 A,C Calibrate None Setpoint Drift Isolation Would Not None Reset Containment U

4-6

. Residual FT-74-56 Repair None Faulty Amplifier Indicator Shifted Gff None Zero ireat Removal 4-29 Control Rod PI-85-68 Rcplace None Gauge Damaged Indicated Low Pressurt None (Loc al)

Drive U.._n_i t3 J. - 6 Reactor l'I S-6 3-2 Replace N one Faulty Switch Switch Uculd Not None Reset Feedwater 4-8 Reactor LI-3-46 A,B Repair None Dirty Bearings, Readings Did Not None Zero Drift Agree Feed wa te r l

?. -2 3 Feeduater FM-46-5C Repair None Faulty Circuit Feedwater Flow None l

Control Component Erratic b

Tv i vo++ttw---

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-r-w o

-w

-r 3

-wr--

w=r,w w

- gas w i-7 wwwm r w w -=m+www e,'w---

=

w

-s w

=sw -

mww n-

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w'-

w -

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i i

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28 l

f f

i OUTAGE

SUMMARY

April 1981

?

n Preparation for the unit 1 cycle 4 refueling outage continued through l

1 reactor shutdown which occurred April lith, at 0049 hours5.671296e-4 days <br />0.0136 hours <br />8.101852e-5 weeks <br />1.86445e-5 months <br />.

Initially the l

critical path work to completion of the outage was reactor pressure vessel

}

1. disassembly through reactor cavity floodup for fuel unloading. This work

?

was completed approximately one day behind schedule. The current critical j

path is the torus and related modification work. At the close of-this re-port period torus modification work had progressed throught the installation of the temporary ventilation system, sandblasting internal surfaces - approx-(

imately 20%_ complete, placement of the first ring girder reinforcement for welding on external surfaces and start of welding of cradle extensions. At t

present only 19 of 35 modifications scheduled to be performed on the torus have final drawings issued. The lack of drawings has severly restricted the I

ability to plan work, order material and establish t oling requirements. Other

)

major work in progress includes:

i 1.

P0214 - generator breaker modification.

f 2.

P0275 - unit 2 station service transformer.

3.

P0262 - union cordova line addition.

4.

Unit 1 fuel unloading in preparation for feedwater sparger

(

modification in-vessel.

l 5.

Eddy current testing of selected heat exchanger tubes.

l 6.

Turbo-generator disassembly, inspection and refurbishment.

i 1

7.

Preparations for unit 2 short outage beginning May 15, 1931.

j i

f h

l I

i n

i

..~

...~.

1 29 5

OUTAGE

SUMMARY

(Corttinued) l 1

April 1981 l

Fuel Sipping Equipment Preparations Fuel sipping equipment is due to arrive on May 7.

Actual fuel sipping i

is due to begin on May 11, and is expected to be completed by May 25.

I

~ Unit 1 "B2" CCW/ Inlet Expansion Joint Corrosion Pitting l

Signs of mild pitting corrosion were discovered on the interior surface

{

of the inlet expansion joint to IB2 waterbox. A note of this condition was j

made and followp inspections will be scheduled for future refueling outages.

The remaining expansion joints will be inspected and repaired as necessary.

{

i f

'The scheduled outege duration at this time is 108 days for an expected i

return to service date of July 28, 1981.

{

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f t

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e - - -

wo-o<r<