ML20027E418

Monthly Operating Repts for Aug 1981

ML20027E418
Person / Time
Site:	Browns Ferry
Issue date:	09/01/1981
From:	Thom T TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20027E417	List: ML20027E416 ML20027E418
References
NUDOCS 8211150204
Download: ML20027E418 (40)

Text

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TENNESSEE VALLEY AUTil0RITY DIVISION OF POWER PRODUCTION BROWNS FERRY NUCLEAR PLMIT MONTllLY OPERATING REPORT August 1, 1981 - august 31, ,1981 DOCKET NUMBERS 50-259, 50-260, AND 50-296 LICENSE NUMBERS DPR-33, DPR-52, AND DPR-68 bl\ (ithdan)

Submitted By:

/ lan't Superintendent T

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8211150204 810910 PDR ADOCK 05000259 R PDR

t TABLE OF CONTENTS Operations Summary . . . . . . . . . . . . . . . . . . . . . . 1 Refueling Information . . . . . . .. . . . . . . . . . . . . 4 Significant Operational Events . . . . . . . . . . . . . . . . 6 Average Daily Unit Power Level . . . . . . . . . .. . . . . . 14 Operating Data Reports . . . . . . .. . . . . . . . . . . . . 17 Unit Shutdowns and Power Reductions. . . . . . . . . . . . . . 20 Plant Maintenance . . . . . . . . . . . . . . . . . . . . . . 23 Outage Summary . . . . . . . . . . .. . . . . . . . . . . . . 35 e

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.e Operations Summary

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August 1981

< The following summary describes the significant operations activities u

during the reporting period. In support of this summary, a chronological l

j log of significatn events is included in this report.

There were 9 reportabic occurrences and three revisions to previous reportable occurrences reported to the NRC during the month of August.

]i; Unit 1

.i i Unit I was in its EOC-4 refueling outage the entire month.

1 Unit 2 ,

There were two scrams on the unit during the month. On August 1, the reactor was manually scrammed after an attempt to place the unit on line re-culted in turbine-generator load rejection. The spare main transformer h'ad been incorrectly connected during recent transformer maintenance following trouble with the 2A main transformer. The reactor scrammed on August 23, during the perf ormance of a surveillance instruction when an APRM was placed e

into the standby condition (half-scram) while another APRM had been inadver-tently left in the standby condition when a faulty knob on the selector switch

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sipped as the operator was attempting to return the APRM to the operate position.

Unit 3 i

l There were three scrams on the unit during the month. On August 12, the .

l reactor was manually scrammed in order to, permit a drywell entry to investigate i

! a low oil l'Oel c alarm on the 3A recirculation pump. The reactor scrammed on I August 22 during the performance of a surveillance instruction when a F$1V's i

not fully open signal was received and an extraneous signal from a FSL high tem-

, perature channel was received while another MSL high temperature channel was in l

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Operations Sumary (Continued)

August 1981 .

test. On August 30, the reactor scramed from a load unbalance and generator trip caused when the 500kV Davidson line was lost while the 500kV Cordova line was out due to a faulty relay operation.

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• 3 Operations Summary (Continued)

August 1981 -

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

Location Usage Factor Unit 1 Unit 2 Unit 3 Shell at water line 0.00503 0.00416 0.00359 Feedwater nozzle 0.24411 0.17784 0.13936 Closure Studs 0.19865 0.14126 0.10649 NOTE: This accumulated nonthly information satisfies technical specification section 6.6.A.17.B(3) reporting requirements.

Common System -

Approximately 1.d6E+06 gallons of waste liquid were discharged containing approximately 1.83E+00 curies of activities.

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e Operations Summary (Continued)

August 1981 -

Refueling Information Unit 1 Unit 1 began its EOC-4 refueling outage on April 11, with a scheduled restart date of September 19, 1981. This refueling will involve loading additional 8 X 8 R (retrofit) fuel assemblies into the core, the final fix on the sparger modification, power supply on LPCI modification, generator breaker and unit station transformer tie-in (requires Unit 2 to be shutdown) and torus modifica-tions.

There are 764 fuel assemblics in the reactor vessel. The spent fuel storage pool presently contains 260 EOC-4 fuel assemblies, 550 spent 7 X 7 fuel assemblies, five spent 8 X 8 R fuel assemblics, and one spent 8 X 8 R fuel assembly.

Because of modification work to increase spent fuel pool capacity to 3471 assemblies, present available capacity is limited to 1148 locations.

Unit 2 Unit 2 is scheduled for its fourth refueling beginning on or about March 26, 1982, with a scheduled restart date of August 13, 1982. This refueling outage will involve completing relief valve modifications, torus modifications, "A" low pressure turbine inspection, MG set installation for LPCI modification, and loading additional 8 X 8 fuel assemblies into the core.

There are 764 fuel assemblies in the reactor vessel. At the end of the ,

month, there were 132 discharged cycle 1 fuel assemblies, 156 discharged cycle 2 fuel assemblies, and 352 discharged cycle 3 fuel assemblies in the spent storage

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Operations Summary August 1981 Refueling Information (Continued)

Unit 2 (Continued) ,

j pool. The present available storage capacity of the spent fuel pool is 160 locations. With present capacity, the 1979 refueling was the last refueling-that could be discharged to the spent fuel pool without exceeding that capacity i

and maintaining full core discharge capability in the pool. However, 949 new i

high density storage locations have been installed.

Unit 3 Unit 3 is scheduled for its fourth refueling beginning on or about October 16, 1981, with a scheduled restart date of February 13, 1982. This refueling involves loading additional 8 X 8 R (retrofit) assemblies into the core, relief valve modification, turbine inspections, generator breaker and

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unit station transformer tie-in, and torus modifications.

There are 764 fuel assemblies presently in the reactor vessel. There are 124 discharged cycle 3 fuel assemblies, 144 discharged cycle 2 fuel assemblies,

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and 208 discharged cycle 1 fuel assemblics in the spent fuel storage pool. The present available storage capacity of the spent fuel pool is 1052 locations.

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Significant Operational Events Unit 1 Date Time Event 8/01/81 0001 End of cycle 4 refuel outage continues.

8/11/81 1840 Fuel reload complete.

8/31/81 2400 End of cycle 4 refuel outage continues.

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. 7 Sie.nificant Operational Events Unit 2 Date Time Event 8/01/81 0001 Reactor thermal power at 14% , holdin;; unit off line due to transformer problens.

2018 Reactor scram nanual No. 124 from 14% thermal power after a turbine generator load rejection from "2A" and "2B" main transformer differential relay opera-tion on July 31 at 2216 hours0.0256 days <br />0.616 hours <br />0.00366 weeks <br />8.43188e-4 months <br />, as it was being tied on line. The spare main transformer had been in-correctly connected during recent transformer nainte-nance following troublewith the "2A" main transformer.

8/15/81 1940 Commenced rod withdrawal for startup.

2102 Reactor Critical No. 137, holding for completien of transfomer replacement.

8/16/81 2300 Reactor thermal power at 9%, holding for transformer wiring inspection during daylight hours.

8/17/81 1000 Rolled T/G.

1044 Tripped turbine (exciter brush replacement).

1100 Rolled T/G.

1129 Synchronized generator, commenced power ascension.

8/18/81 1330 Commenced PC10MR from 60% thermal power (sequence "B").

8/20/81 0100 Reactor thermal power at 97*:, maximum flow, rod limitec.

0700 Reactor themal power at 95%, maximum flow, rod limited.

1500 Reactor thermal power at 93%, maximum flow, rod limited.

8/21/81 0016 Reduced themal power f rom 93% to 81% due to recircula-tion pumps runnin3; back when 4SOV shutdown board "2B" was transferred.

0035 Commenced power ascension.

0222 Commenced PCIOMR from 92% thermal power (sequence "B").

0320 Reactor themal power at 94%, maximtna flow, rod limited.

8/23/81 0010 Reduced themal power to 85% for turbine control valve tests and SI's.

0201 Reactor Scram No. 125 from 857. thermal pouer while .

performing SI 4.2.C.1.A, E-APRM nuitch was in wrone, position - 1/2 scram when removed from hypass uhile performing 1/2 scram on F-APRM.

0540 Commenced rod withdrawal for startup.

0708 Reactor Critical No. 138.

1306 Rolled T/G.

1324 011 tripped turbine.

1340 Synchronized generator.

1352 Tripped turbine from 8% thermal power due to inablJity to hold condenser vacuum when gland stean packing on exhaust fan motors failed.

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Significant Operational Events Unit 2 Date Time Event 8/23/81 2400 Folled T/G.

8/24/81 0034 Synchronized generator, commenced power ascension.

0630 Commenced PCIONR from 70% thermal power (sequence "B").

2200 Reactor thermal power at 77%, maximum flow, rod limited.

8/25/81 0400 Reduced reactor thermal power to 64% for control rod pattern adjustment.

0700 Control rod pattern adjustment completed, commenced PC10MR (sequence "B").

2045 . Stopped PCIOMR at 80% thermal power, computer out of service.

8/26/81 0001 Computer back in service, commenced power ascension.

0700 Reactor thermal pouer at 84%, holding, computer out of service. .

1415 Commenced reudcing thermal power to repair strainer on "2C" RFWP.

1425 Reactor thermal power at 74%, holding for repairs to "2C" RFWP.

2110 "2C" RFWP in service, commenced power ascension.

8/27/81 0140 Commenced PC10MR from 77% thermal power (sequence "B").

1745 Reactor thermal power at 99%, maximum flow, rod limited._

1828 Commenced reducing thermal power to maintain back-pressure when removing "2B" CCW pump from service for cooling tower operation.

1915 "2B" CCW pump out of service, reactor thermal power at 94%.

2145 "2B" CCU pump back in service, commenced power ascension.

8/28/81 0700 Reactor thermal power at 99%, maximum flow, rod limited.

1045 Reduced reactor thermal power to 91% thermal power due to run back of both recirculation pumps while performing SI 4.9.A.l.b diesel generator emergency load acceptance test.

1049 Reset runback, commenced power ascension.

1300 Reactor thermal power at 98%, maximum flow, rod limited.

Commenced reducing thermal power for turbine control 2250 valve tests and SI's.

2330 Reactor thermal power at 85%, holding for turbine con-

- trol valve tests and Sl's.

8/29/81 0010 Turbine control valve tests and SI's completed, commenced power ascension.

0700 Reactor thermal power at 97%, maximum flow, rod limited.

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Significant Operational Events

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Unit 2 Date Time Event 8/30/81 1445 Commenced reducing thermal power due to "C" phace transformer high temperatura (cooling probic::s) .

1515 Reactor thermal power at 92%, holding due to trans-former high teuperature.

1645 Transformer problems resolved, co::ur.caced power as-cension.

1715 Reactor therrnal power at 97%, ma::inum flow, rod limited.

8/31/81 0700 Reactor thermal power at 96%, manicum flou, rod limited.

. 2400 Reactor thermal power at 96%, maxinun flow, red limited.

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Significant Operational Events Unit 3 Date Time Event 8/01/81 0001 Reactor in cold shutdown for maintenance on torus 22 Sa P e valve.

11 0 l 1825 Maintenance complete on H22 0 sample valve, commenced rod withdrawal for startup.

2048 Reactor Critical No. 113.

8/02/81 0700 Reactor thermal power at 7%, holding unit off line for maintenance on FCV-71-3.

2056 Maintenance complete on FCV-71-3, rolled T/G.

2135 Synchronized generator, commenced power ascension.

8/03/81 1230 Commenced PCIOMR from 86% thermal power (control cell core).

8/04/81 0700 Reactor thermal power at 95%, holding due to "A" string high pressure heaters out of service.

1000 Commenced reducing thermal power due to "A" string high pressure heaters out of service.

1830 "A" string high pressure heaters back in service, commenced power ascension from 90% thermal power.

2300 Reactor thermal power at 94%, maximum flow, rod limited.

8/06/81 0015 Commenced reducing thermal pouer for control rod pattern adjustment.

0100 Reactor thermal power at 70%,~ control rod pattern adjustment in progress.

0300 Control rod pattern adjustment complete, commenced PCIOMR (control cell core).

8/07/81 0700 Reactor thermal power at 99%, maximum flow, rod limited.

8/08/81 0115 Reduce thermal power to 89% for turbine control valve tests and SI's.

0126 Turbine control valve tests and SI's complete, com-menced power ascension.

0430 Reactor thermal power at 99%, maximum flow, rod ,

limited.

2352 Reduced thermal power to 95% for SI 4.3.A-2 (control rod exercise).

8/09/81 0030 Control rod exercise complete, commenced power ascension.

0230 Reactor thermal power at 99%, maximum flow, rod limited.

8/11/81 2230 Commenced reducing thermal power for shutdown for inves.tigation of 3A recirculation pump low oil level.

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. Significant Operational Events Unit 3 Date Time Event i

8/12/81 0131 Reactor Scram Manual Scram No. 101 from 35% thermal power to investigate low level'in upper bearing oil reservior on 3A recirculation pump (replaced leaking thermocouple in upper bearing).

8/13/81 2258 Maintenance on "3A" recirculation pump complete, l commenced rod withdrawal for startup.

2358 Reactor Critical No. 114.

- 8/14/81 ~ 0902 Rolled T/G.

i '0935 . Synchronized generator, commenced power ascension.

8/15/81 1300 Commenced PCIOMR from 70% thermal power (control cell core).

8/16/81 0305 Reactor thermal power at 96%, maximum flow, rod limited.

} 1530 Reactor thermal po'wer at 93%, maximum flow, rod limited.

2300 Reactor thermal power at 92%, control rod pattern I adjustment in progress.

8/17/81 0010 Control rod pattern adjustment complete, commenced power ascension.

1100 Reactor _ thermal power at 99%, maximum flow, rod

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limited.

2300 Reactor thermal power at 97%, maximum flow, rod limited, i 8/18/81 0700 Reactor thermal power at 97%, control rod pattern adj ustment in progress.

1000 Control rod pattern adjustment complete, commenced power ascension.

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

limited.

t 8/,20/81 0700 R,eactor thermal power at 98%, maximum flow, rod limited.

8/21/81 2352 Commenced reducing thermal power for turbine control -

valve tests and SI's.

8/22/81 , 0026 Reactor thermal power at 85%, holding for turbine 0124 controlvalvetestsagSI's.

Reactor Scram No. 102 from 85% thermal power while performing SI 4.2.A.8 main steam line high temperature. An extraneous signal from channel "D" resulted in the MSIV's going closed.

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Comme 6ced rod withdrawal for startup.

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• O Significant Operational Events Unit 3 Date Tine Event __

8/22/81 1530 Stopped withdrawing control rods, computer out of service.

1546 Commenced rod withdrawal for startup.

1602 Reactor Critical No. 115.

1833 Rolled T/C.

1845 011 tripped turbine.

1853 Synchronized generator, comenced power ascension.

8/23/81 0400 Commenced PCIOMR from 73% thermal power (control cell core).

8/24/81 1130 Reactor thermal power at 94%, maximum flou, red linited.

8/25/81 0110 Commenced reducing thermal power for com rei rod pattern adjustment.

0120 Reactor thermal power at 79%, holding for control rod pattern adjustment.

8/25/81 0140 Control rod pattern adjustment complete, commenced power ascension.

0330 Commenced PCIOMR from 82% thermal power (control cell core).

2300 Reactor thermal power at 99%, maximum flou, rod ..

limited.

8/27/81 1620 Reduced thermal power to 88% to maintain back-pressure when removing "3C" CCW purrp from service during cooling tower operation.

2140 Unit removed from cooling towers, placed in open mode, reactor thermal power at 88%.

2148 Place "3C" CCW pump in service, connenced power ascension.

2330 Commenced PCIOMR from 96% thermal power (control cell core).

8/28/81 0230 Reactor thermal power at 99%, maximum flow, rod limited. ,

8/29/81 0100 Commenced reducing thermal power for turbine control valve tests and SI's.

OI20 Reactor thermal power at 85%, holding for turbine control valve tests and S1's.

0150 Turbine control valve tests and SI's complete, commenced power ascension.

8/29/81 0500 Reactor thermal power at 97%, maximun flow, red limited.

1250 Commenced reducing thermal power due to high con-denser backpressure.

. 13 Significant Operational Events Unit 3 Date Time Event 8/29/81 1320 Back pressure improving, commenced power ascension from 92% thermal power.

2000 Reactor thermal power at 97%, maximum flow, rod limited.

2205 Commenced reducing thermal power for ST-185 RWP test.

2230 Reactor thermal pouer at 85%, holding for ST-185 RFWP test.

8/30/81 0050 ccmmenced power ascension from 85% thermal power.

ST-185 in progress.

. 0115 Reactor thermal power at 95%, ST-185 in progress.

0205 ST-185 completed,congcedpowerascension.

1349 Reactor Scram No. 103 frcm 97% when faulty relay caused a loss of the Cordova line. When relay reset was attempted, the Davidson line was lost with sub-sequent load unbalance and generator trip.

1917 Commenced rod withdrawal for startup.

2241 Reactor Critical No. 116.

S/31/81 0230 Rolled T/G.

0324 Synchronized generator, commenced power ascension.

1230 Commenced PCIOMR from 85% thermal power (control cell core). . . ,

2400 Reactor thermal power at 93%, PCIOMR in progress.

(1) Maintenance Error (2) Equipment Malfunction

• . r 14 R AGE 93 gly LIMIT POhry LEVEL .

DOCKET NO. 50-259 UNil _ Browns Ferry - 1 D tTE 9-1-81 C0\fPLETED Uy Ted Thom TELEPl10NE _205-729-6846 August 310 NTH DAY AVER AGE DAILY POWER LEVEL DAY AVER AGE DAILY P0hER LLVEL

(\lhe Net) t %!We-Neil

, -7 -6

,7 2 -6 is -8 3

-6 ,9 -10 4 -6 ,o -12 3 -6 ,, -11 o -7 -13 33

- -8 33

-13 x -9 y -12

,, -9 25

-12 _

10 -9 - 26 -13 ii -9 3, -13 12 -9 23 -15 i3 -10 yy -12 14 -9 30 -15 15 -5 3, -13 t u, -6 e

INSTRI:CTIONS f Li ilns lotnut. !ns the .n t.ipe d.nts uint pouce lesci ni \lWe Net f oi cach J.o ni ilie scp.uinig in..n:h. G.:npute in t he ne.itest w in l.. ow e.iu.iii.

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, As'ERAGE DAILY UN! r P0hER I.EVEL ,

DOCKET NOo 50-260 UNI T _.Brnwns_ Ferry - 2 DATE 9-1-81 C041PLETE D isY T. Thom 1ELEPilONE 205-729-6846

\f0NTil August DAY .\VER AGE DAILY POWER LEVEL DAY AVER AGE D \lLY POWER LE\*EL s \1he-Ne:I g,gg we.Se,3 1 -16 17 214 3

-15 ,3 631 1

-15 918 9 _

a -14 997 20 3 -14 986

-12 6  :: 980

- -10 68 33 s -10 24 679 9 -10 756 25 _

10 -10 831 26 II -10 957 27 12 -10 1029

s 1.1 -12 1021 29 14 -13__ yg 1013 is -14 ,q 1028 i t. -15 INSIRUCIlONS ,

ho 0 Ih lIIJ , h%h l[ ,j k [l J 'Eg* e ,e j \ l g,'l 9 { %g egg g* g og a g gg e, e .. , , g II!C llCJf Csl u l!t dC tlk'p.la all, vo -- n

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5 16 AVLI: EE 1) VI.Y l'N11 Puh E tt 1.LVEL .

DO: F. L7 'a j 50-296 U,a,I l Browns Ferry - 3 DuE 9-1-81 _

C0\ ipr. LIED !;Y ___T .__Th om___ _

TELEPliGNI- 205-729-6846

\lON111 Apggs_ ti, InY W1.lt TGl.' D All.Y l'Oh ER LINEl. DAY AVER AC.I' !) AILY POWER LEVI L i\0Vr-Nc:) ( \1We Neti 1 -14 37 1018

, 17 1038

,3

, 800 1041 lo __,

a 976 ,o 1028 969 .

,, 1029 929 ,, 129

, 1038 ,>, 869 s 1050 959 34

., 1024 ,g 966

,o 1043 3 1063 _

,, 1033 1019 3

i, 18 1039 3

It _ _ . _ _ _ . _ T31 29 1010 la 369 39 __

577 1.4 _

813,_ ,

,, 672 1, . 978 IN S l'ItI:( l1()',5 i r. : lies t..r: i s. . : : 8.c .. . . _' a i! . i.:, t ,. .. c in ei : . \pW. N

. , , .!,n s i ! . c . . . . .. . i _ , .f , . te :

• ru sa ;ece al.1 i. ....:.

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i OPERATING DATA REPORT . t DOCKET NO. 50-259 DATE 9-1-81 CO5!PLETED liY Tod Thns

1 ELEPflONE 205-429-6846 OPER tTING STA TUS

l. Uni Name: Browns Ferry -1 N"$

2. iteporting Period: August 1981 3293

3. Licenwd Thennal Power (5thti: _1152

4. Nameplate Ratine IGross alwel:

1065

5. Desien Elcetrical Rating INet AtWel:

4

6. Stasiminn 1)epemt.shie Capacitv IGross alWe):

1098.4 1065 1

7. Stasiinum liependable Capacity (Net 31We):

i . h. If Clunges occur in Capacity Ratinp litems Number 3 Through 71Since Let Report.Gi e Reasons:

NA

' NA

9. Power Lesel To hhich Restricted. lf Anv INet .\lwe): .

Ill Reasons l'or Restrictions. !f Any: M i

This Slonth Yr..to Date Cumulatise i1. Ilours in Reporting Period 744 5831 65,113

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12. Number Of it.mrs Reictor was Critical 0 2,384.4 37,190.97

13. Reactor Resene Shutdown flours 0 16.42 5,115.29

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14. Ilours Generator On.Line 0 2,380.77 36,373.59

. 15. Unit Resene Shutdown llours 0 0 0 l 16. Grow T.hermal Energv (.,enerated ISth.ill 0 7,425,495 100,717,856 i 0 2.474,200 33,237,490 17 (.rnw Electrical Eneiyy Generated (N!Will I 18. Net Liectrical Enerp~ Generated IS1Wil) 0 2,407,849 32,271,666 4

19. Unit S. enice Factor 0 40.8 58.6

20. Unit Asaitahihis ractor 0 40.8 58.6 21 Unit Capacit.s Factor (U3ing \tDC Neil 0 38.8 48.8 2.' Unit Capacity factor IUsing DER Neil 0 38.8 48.8 1 23 Uni !~urced Ontage Rate 0 0.8 28.0

24. Sinitdowns Schednird Oser Nest 6 Stooths iType. Date.and Duration ni l'achi-25 !! Shui llown y 1 nd Of Report Period. Estimated Date of Startup:

26. Units in lest Status it'rior to Connnercial Operaiions. I'orceast \chiesnt INilI \ L CRilICAI II Y 1.NII I \ I. l'LI.ClitICI T Y

( O\l\ll:RCI tl OPI'R AllON _

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OPERATING DATA REPORT .

. DOCKET No. 50-260 i DATE 9-1-81 CO.\!PLETED ltY T. Thom TELEP110NE 205-7 20-Ja 846 OPER ATING STAT US Brotms Ferry -2 Notn i I, Unit Name:

2. Reporting PerioJ: August 1981 3293

3. Licenwd T hermal Power (Stha t; _1152

4. Nameplate Rating (Grow Slwet 1065 1 5. Design Electrical Rating (Net alWeb

6. Alasimum Dependable Capacity (Gross AlWep 1098.4

7. Alasimum Dependabic Capacity (Net $1We): 10M S. If Chan-es Occur in Capacity Ratings (Irems Number 3 Through 7) Since Last Report. Gi.e Reasons:

Nd I

J

9. Power Leul To Which flestricted. lf .\ny INet .\lwey NA .

Ill. Reamns for Restrictions. lf Any: NA i

1 I

i 1 This alonth Yr..to Date Cumulatise

! 11. Ilonts in Reporting Period 744 5831 57,024

. 12. Number Of flemas He actor Was Critical 402.15 4,862.68 35,606.29 -

13. Reactor Resene Shutdown llours 341.85 939.95 13,393.43 26.1/ 4,620.68 34,361.64

14. llours Generator On-Line 1 0 0 0 g g7yg

, 15. Uma Rewne Shutdown flours

16. Gnes, T hermal Energy Generated (SIWill 929,335 14,118,753  ::,2'.,002 17 Grow Electrical Energy Gcnerated (\lWill 299,250 4,702,120 32,439,308 1.s. het Electrical Energy Generated 151 Wig, 2c5,490 4.558.493 31.508 28_0_0_ l

19. Unit Senice Factor 43.8 79.2 60.3

, 20. Unii A .nlability ractor 43.8 79.2 60.3

21. Unit Capacity Factor IUsing 31DC Nett 36.0 73.4 J1. 9 2.' Unit Capacily F ector IU ing DER Net 36.0 73.4 51.9

23. L' nit Forced Ontage Rate 56.2 13.3 30.7

24. Shnidowns Schedol.d ther Nes 6 \lonths Type. Date,and Duration of Each e:

4 .

25. Il Shur Down \t I.ml Of Report l'eriod. latimated Date of St.ortup-28 . L'oits in l es Status Prior Io Commercial Operationi: forceast \chiesed

] INIil \ l. CRi l lC A l.1 IY INIIl \ 1. Ell:C I RICIT Y CO\l\llRCl \ L OPER A TION

, par- t

3

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• - s 19 O."ERATING DA1A REPORT .

k DOCKET NO. _50-296 DATr 9 T281-~

COMPLET Ell i:y T. Thom T: LEPi!ON E _10.52729-6846 Ol*l R \ TING ST A IUS Browns Ferry - 3 I %8^ 8

l. UmtName.  ;

2. stepartmg Perind; August 1981  ;

s 3293 ->

3. Licensed T'unaal Power (Mhti: .

I

4. Nameplaie 1:ating tGrun MWei.

1152 l

5. Desien Electrical Rating INet MWel:

- lTf65 8 ti. 31asimnm Dependable Capaciiv (Grow Mbet 1098.4  !

7. Slasimum Del endahic Capacity (Net MWe):

1 65  ;

t

h. IICh:mpes Onur in Capacity Ratin;:s (!! ems Number 3 Thrmgh 71 Siace La t Rel ort. Gi.e Reasuns:

NA

9. Power Lesel Tu hhich Rest icted. lf Any (Net \1het: NA -

NA t

10. Reasom For Re tricti.ms. If Any.

\

'\

This Month Yr..tu-Dan e ' Cumuh th.:

4

11. Ih.nrs in Repmim.: Period

\ ~ 744 5,831 39,479

12. Nu:nher of 11. urs Re setor % Critical 653.25 '6,054.96 31,026.23 --

13. Reactor Resene Shutdown linu.3

' 93 320.14 + 2131.03 I4. linnrs Generaint On-Line 611.28 4,920.03 30,316 J3

15. Unit Resene Shutdnu n linurs 0 0 0 Iti. Gm Thermal Energy Generated (MWl(I 1,859,647 15,083.239 89,448,267 7 9,'535,330

~

17 G;nw flectiia! l n rgy Generated (MWill 607,830 4,996,300 18 ' et Electrisal 1.ner;3 (;enerated t *dWID SYT,9Tf ~ 478CE(Ri9 18- 667 ;'392-~

19. Lnit senice I:alin, 82.2 84.4 76.8

20. Uni: Aud.ibility I actor F2.7 74-4 76T8' 38.0

~ ~ ~ '

21. Umt Capacity factor tusing MDC Neti 74.2 68.2 2.' Unit Capacity I wint it'smg DI.R Neo 74.2 78.0 68.2 23 Unit fmad Uniipe Raic 17.8 9.0 9.6 /

24. Shuidnu ns L t ednh d Oser Nest to Months (l~s t'g Date.and Durat.on at I ach i Maintenmice OctoAer 19_81 a

- L - -- '

25. It Shut Dow n \t.I'ud Of liep.n Period. latimaied Dai: of Siartup. _

li.. l uits in lest Status a Psior to Conuncreial Operadon e I urecast h hn-si d IN I I I \ 1. Cit i I IC.s 1.1 I Y _ - - _ _

INIIIT I. Fl.i.CI R R'lIY _

CO\ltil'RCl \ L Ol'I'R \ilON E - --

4.n ,

~

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UNIT SIIUTDOWNS AND POWER RFDUCTIONS DOCKET NO. -- 50-259 UNI'l NAME Browns Ferry .1 DALE 9-1-BL August COMPLETED BY T. Thpm REPORT MONTil TELEPilONE 70 % 729-6846

=_ . I u. 5 _ h

, Ic  :

7 5 .; 3.it emce 5 -t., =% (..nne & C ,rrect n e

%. Ibie e- ,p g jgp lseni ;7 yd Atteon to

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jE E e~55 Repost <E C 5' Present itecmreiste c U 6

172 8/01/81 S 744 C 2 EOC-4 Refuel Outage (Continued)

N o

b I 2 .i 4 l l' o.eil l(camn Met hotl: lishibit G - Insirnetions

% A he l'ile.1 .\.l't[nspinent l'ailure (I spimi)  ! .Maniual tiir Picpr.iation el Data it.Manitenance t.r iest 2.M.inual Scra m. I'.ntn Sheets fin 1.ieensee

( L Re t' acting .t. Antoin.itic St r'am. Evesit 1(epin t il 1:R) l'ile ( N18Rl'C-D Repolaton Res: i iion 4 Othev (lapt.nn1 0161)

I 0;'esator Training A 1.itense i sannnation 17.Linnuintiats.c

(, ():'etation.it 1 itos (I splanil I slubit 1 - S.iine Soutee l'8 '7) It Other (I spl.nn)

. i

• i- .

UNir SilUlDOWNS \ND POWER REDUCTIONS DOCKET NO. 50-260 - */

UNIT N AME llraEDs Ferry .2 DA1E 0 1 91 _

August COMPl.ETED BY T. Then

-- REPOR T MONTil TELLPilONE 'i n 'i- 7 ? 4- 6 8 4 6

{? h

'h 5') 1.it t mt e .E -r, Came A rnirect.se s.. D.iie i 5g fE 5 4 iie 35,5 rsein Repor  :

i,

v. U p'

E aanin it, Psevent Recurresite e g V 5

202 8/01/81 F 395.48 H 2 Turbine generator load rejection froE 2A and 2B main transformer differential relay operation on July 31 at 2216 hrs as it was being tied on line. The spare r:iain transformer had been in-correctly connected during recent tranr,-

former maintenance following trouble N with 2A main transformer.

203 8/23/81 F 11.65 G 3 While performing SI 4.2.C.1A, E-APRM switch was in wrong position which gave a 1/2 scram whe. removed from bypass while performing 1/2 scram

! on F-APRM.

204 8/23/81 F 10.65 A 4 Turbine trip due to inability to hold condenser vacuum when gland steam packing on exhaust fan motors failed.

l ) .I I

! l.uco' Iteas in. Met hot!: I:stebit (, . Imii..cin is

's N i nto'e 1 \ iipnp.non ! .nluie il spi..in)  ! M.itural i.n 1 :cp.n.n e.in or t i.it.i lIdl. tint'.* '.ll1CC 41 Test

. 1 Maintial S; sani. 1.nsi s Shec ts ... luenset

( E lb.*! uCI h? t y 5 d' tit $111 elle N. ?!!P1. l seni \{.*}.uti (I l N) file { '.['NI 4'e i1 ReguLt. n Re :i. ii..:: . 0;l.. : 4l'splaini Oldt

• l -1)pt'f aleil ll.eitnif e k l is t'lls.* l N.!!!lt fl..e li st)

I' d(llt14flisi!3 f l.. 5 I e-(l;1 '! .lfle st! II l t is ti { l g(d slit i l's}itht! l N.titt

• h6 Hit J.

so O s li-Oihet ii spi nn e -

. i

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UNil Sill'l DOWNS \ND POh!'.R RI.Dlic110Ns IKK'4ET NO, 50-296 -

U.'.lT N A M E Bros:ns Ferry - 3 DATE 9-1-81 RI PORT MON fil August COMPLETED BY T- Tho

TELLi'llONE ?ns 7?o-AR$6

, 5? 'i j E' ~.; 1.acnsee ~ n. , E ':, came & rorrectne Da te i 3? ( -i5 1: vent  ;?  ?? Atuon ti.

f $ 5 5, - Report 8.L ,5 ' Present Recurrense g a

=

84 8/01/81 F 45.58 B 2 Reactor scram to swap transfo ners and maintenance on torus H22 0 sample valve 85 8/06/81 S Derated for control rod pattern adj.

86 8/12/81 F 56.07 A 2 Reactor scram to investigate low level in upper bearing oil reservior ot. 3A recirc. pump (replaced leaking thermo- y couple in upper bearing).

87 8/22/81 F 17.48 A 3 Reactor scram while performing SI 4.2.A.8 main steam line high temp. on extraneous signal f rom channel "D" re-sulted in the llSIV going closed.

88 8/30/81 F 13.58 A 3 -

Reactor scram when faulty relay opera-tion caused a loss of the Cordova line ,

When relay reset was attempted, the Davidson line was lost with subsequent load unbalance and generator trip.

I i 2 3 4 I l'. es cJ Reas.nt : Method: Eshibit G . instructions

% % I. .l'ile ! -\.l yn:pment F.nlure t i.splaini  ! 41anual for Peepasation of Data Italaintenance or Test 24f anual Serain. Ents) bheets fo 1.ieernee t' Rc!nehne .L Antomatic S. rinn. I'sent Repint ti I R1Ir le i i N,tiRI G.

13 Reentatin3 Restiicinin 4 Othei ti.splain t titel1 1 t )pei.itor i t.nnine A I it en se I s.unni.it n'n l - \ditttfilstl 'll.C 5

( s t );'el,s tl.'t!.l! l r t e n f I spl.llet i 1.sinhit i. bJelle bo' Hie t'I'7) 11 Oil.cr 11 splanin s

. LRUWt S t Liud Ut'CI.hAR )LA;. i unit i6 2 '.

1NSTRUMENT MAINTENANCE

SUMMARY

CSSC EQUIPMENT FOR Tile MONTil 0F August 19 81 --

NATURE EFFECT ON SAFE CAUSE ACTION TA'rEN S TE SYSTEM COtiPONENT OF OPERATION OF OF RESULTS OF TO PRECLUDE MAINTENANCE T11E REACTOR 1RLFUNCTION 1MI FUNCTION . RECURRENCE Jnit 5-5 Fuel Pool LS-7S-1A,lB,1C Calibrate None Instrument Drift Level Switches Did None Not Agree 3-5 Radwaste FQ-77-6 Backfill None Air in Lines Erratic Indication None 3 3-17 Neutron LPRM 4B-32-25 Repair None Bad Flux Card Indicating Low None Monitoring ,

LPRM 2B-24-41 Repair None Bad Conne ctor Indicating Low None 4-18 Core Spray FT-75-21 ite' place None Failed Bellows Indicatbr Showed None 6000 GPM Flow with Pumps Off s 3-18' Standby PI-63-7B

• Repair None Bent Pointer Indicated Low None U Liquid . Pressure Control 3-19 Core Spray PI-75-32,.41 Calibrate None Instrument Shift Indicated 11'igh Nonc

, Pressure TI-64-55A 3-20 Pr imary Calibrate None Instrument Shift Indicated Low None Containmcat . Temperature Primary LI-64-54 A Calibrate None Instrument Shift Indicated One Inch None Containment Low Init 2. .-

3-4 Neutron B LPRM Meter Replace None Broken Broken Glass in None Monitoring Meter 3-10 Rod Positio T Top Half of nepair None Circuit Breaker Loss of 1/2 Core None Information Core Lights- Tripped Indication Lights PSY-6 3-23 Neutron ARPM E Mode Repair None Loose Set Screw Indicator Pointed None Monitoring Switch ,

to h'rong Mode

. i

w bKU%S GRRY NUCLIMH Pl.A?iT UNIT' 26 3 -

I!!STRUMI:NT MAINTENANCE SU:! MARY CSSC EQUIPMENT FOR Tile MONTil 0F August 19 81 '

NATURE EFFECT ON SAFE CAUSE MTE SYSTEM ACTION TAKEN CCMPCNENT OF OPERATION OF OF RESUI.TS OF TO PRECLUDE MAINTENANCE ' DIE RrJ.CTOR MALFUNCTION 1%LFUNCTION 4 RECURRENCE (1 nit 2-26 Neutron LPRM Downscale Repair None Faulty Diode in False Alarm None ,

Monitoring Alarm Flux Amp. Card Unit 1 8-10 Neutron Tip "D" Veeder- . Replace None '

Faulty' Contacts " Counts Out Too liigh" None Monitoring Root Counter Alarm D-6 Feedwater PI-3-207 , Replace None Bin' ding Movement

~

Slow Respcuse None B-13 Neutron

's IRM-D Repair None Dirty Connector Erratic Indication None

. Monitoring y 3-15 Control Rod PX-3A-PS-6 Replace None Faulty Circuit No Control Power on None Drive CRD Select . .

3-25 Primary T I-64-55 A'- Calibrate None Instrument Shift False Temperature None Containment ,

Indication 3-28 Primary LI-64-54A Repair None 310wn Fuse Indicated Downscale None Containment s

t e

e

. i

y i;KO'.G;'; Fi'.;;;' ' ;;;;t.L:./S l'L.de l i.S 1'1 A * ~ ~ " +

' ELECTRICAL ltil;iTEN/J:CE SU!D'ARY .

CSS (; D)U T I'llhu r .

August 81 .',,"

For the Month of 19

' 7frect on safe Action Taken Component liature of Operation of Cause of Results of To Preclude D.-te Systce Malfunction R currence Maintenance The Renctor  !!alfunction l Expansion valve Replaced power hea,

' 8/2/li Fire Cardox tank liigh tank None The expansion inoperable and cleaned expan-i Protectior expansion pressure valve power head was sion valve, unit valve sticking operated properly.

g TR #224998 t

Rod 18-39 None Blown fuse Rod would not half Replaced fuse, CRD

!.8/8/81 CRD CRD (Rod 18- '

scram operated properly.

scrams on I

39) control TR #223259 f circuitry 1; scram .

None Broken stop Required care to bc Replaced stop,

,8/17/81 CRD lland switch IIS 85-48 stop taken while operat- switch operatedw 85-48 broken "

ing switch to avoid properly.

l rotating switch TR #225657 t

I past desired sett-

! ing i _

i Two out of three The relay was

!8/17/81 4kV shut- Under voltage Received a None All four RHR pumps were degraded voltage manually reset ana l down relay 27BDDC gnnunciation boards for degraded started and . relays operated the annunciation j voltage on stopped in causing diesel cleared. The D/G I panel 9-23 rapid secces- start. Annuncia- was returned to I, sion not allow- tion for degraded stand-by ready ing time for voltage on panel TR #236204 the degraded 9-23 remained in l voltage relays because relay i

r to fully reset 27BDDC did not fully ,

{ before the reset '

[ next RilR pump l

i started. .

I

't }  ! ,

i t j ,

I;g. wig Fr.;;.* / ;;;;i.; ;.14 i L.iNI WII 1,_& Cpmmon .

CSSC Ei)till?lE;;r ELECTl:ICAI. MalNTENA!!CC SUICG.RY .

For the Month of August 19 81

' ~

' f.ffect on Sate Action Taken Component  !!ature of Operation of Cause of Results of To Preclude Date Systce Malfunction Recurrence Maintenance The Reactor Halfunction I J>

8/18/81 Air-con-

• Control room Air handling None Auxiliary con- Air han'dling unit Cleaned and lub-ditioning air handling unit 1A tacts in unit lA was inoperable ricated the aux-~

(cooling- unit IB con- would not 1B prevented iliary contacts, heating) trol circui- start unit lA from the air handling

.l g try starting units operated

, properly.

l -

, TR #224946 i

8/27/81 , Core Core spray During per- None Timer 14A-Kl9B Timer operated Perfo,rmed SI 4.2.

spray pump 1D formance of was out of slightly slow B-39 to calibrate

. cooling timer 14A- diesel gener- calibration timer. The timer '

Kl9B ator load calibrated proper-acceptance ly.

l test (SI 4.9. TR #186869 $

I A'.l.b) core TR #225134

! spray 1D i '

timing was

• l found slight-

{ ly out of palibration i

I 8/29/81 RBCCW Drywell Breaker . Nor.e ACB molded Breaker would not- Replaced the

! blower 1B5 would not case operator trip broken ACB opera-

feeder trip was broken tor. The breaker j breaker.,, operated p'roperly.

TR #241686 ,

\ .

6

\ \ 1 .

\ \

l

w P. FA'f'is.

• ks !i ...6.....s.' 4 L.; +1 4 a' A e , , _A_

CSSC EQilIp;;;;;r 1:LECTRICAL 21\1;i1ENA: CE SU:2 ARY

~

August 19 81 ~ -

For the Month of 8 Cffeet on baic Action Taken

!!ature of Operation of Cauce of '.sults of To Freclude Date Systce Component

! Itaintenance The Reactor 11alfunction Malfunction Recurrencc l 0 7/2/81, Reactor RPS MG set MG set motor None Bad motor Motor over heating The motor was protec- 2B motor over heating winding however the motor rewound, re-in-tion was operable stalled 8/7/81.

l The MG set motor operated properly.

, TR #225119 I

l 8/2/81 Primary FCV-64-28C .FCV-64-28C None Bad coil FCV-64-28C was Replaced coil, contain- -

would not inoperable for valve operated

{

l

' ment test from manual operation properly. ,'

hand switch TR #205685 M

l 8/3/81 HPCI Suppression While per- None, the unit Relay 23AK51 Parameter sensor Relays 23AK51 and I chamber high forming SI was in cold timing circui- relay 23AK15 did 23AK15 were I level timing 4.2.B-27, shutdown try possibly not operate on this successfully oper-a i circuitry suppression failed'to oper- one occasion ated several time l ,

chamber high ate on this one and the event

{ level sen- occasion could not be re-

,sor's LS peated. The j 57A and LS- relays will be i 73-57B oper- functionally chec:

I ated time ed once per week I

, delay relay for the next four

, 23AK51 at weeks to verify

,,, correct set- operability.

f point but the TR #241292 l parameter LER#BFRO-50-260/

j sensor relay 1 8142

23AK15 did not operate -

i i g i ,

4

I , i;iM*.GJ.; F ; .. 4 * . . . 6 . .. . .. .; . t u.:.. A . u. . t z ,

csse E0tlii'ttt.!; r . ELECTIIICAL ltalliTENANCE SUID ARY ,

For the Month of August 19 81 . .

i Etfcct on Salc Action Taken liature of Operation of Cause of Results of To Pteclude-l D..tc Sys t cr- Component Malfunction Malfunction Recurrence sintenance The Reactor i

2 .

8/10/8L Unit pre- Unit prefer- Breaker 1001 None Over/under Normal fet<. breaker The bad OVR was ferred red MG set tripped voltage trip 1001 was it . per- replaced, cali-120 volt tie to bat- circuitry card able brated and suc-

' AC system tery board' was bad cessfully tested.

1. 2 (normal TR #182803

, feeder break-i er #1001) ,

i l .

d

. y CD 8

t' I

I '

i i I i

I i

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I l .

't I  ! ,

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E.!:.y.G;3 : i.,;;;i ;r..t. ..,.; a u. .a a t .. A > _

C8SC ::OliT PM;.;;r ELECTEICAT It11IiTDUJ1CC SUlW.RY ,

~

For the Nonth of August 19 81 -

Effect on Salc Action Taken D.. t e S ys tcr- Component flature of Operation of Cauce of Results of To Preclude Maintenance The Reactor Malfunction Malfunction Rescurrence l ,,7- '

8/2/81, RCIC 3-FCV-71-3 During rou - RCIC was inop- Bad valve motor RCIC wa's inoper- The valve moto tine startup, erable. Re- due to an open able was replaced.

RCIC steam dundant systems shunt field The valve was supply isola- were available l timed and proven g . tion valve and operable operable.

, .3-FCV-71-3 '

TR#189772 l ~ could not be , LER#BFRO-50-296/

l' '

'clectrically 8138 l operated .

8/2/81 Air con- 3B control Control bay None Low of freon, The control bay Added f reori, ditioning bay chiller chiller 3B temperature chiller was not changed freon @

(cooling- was not controller was cooling properly filters and re-l heating) cooling not operating placed the temp-i properly properly crature controller i

The chiller oper-i ated properly.

• l l TR #189809

! 8/13/81 Off-gas Condensor huse 22-26A- None Bad relay coil Valve 66-93 inop- Replaced bad rela.:

i drive valve F15 on panel and flow regu- erable coil, IM's re-I 66-93 9-53 contin- lator was out paired flow reg-I ually blowing of calibration ulator, the valve

operated properly.

t

.,' TR 182528 I

t I  : i l .

l ._ . __

iiiay.G..; r ;....i . . . ; . . u . . , .. i u. .. . i c .. . i-cssc n)tillHEu r ELECTRICAL ltAlNTENANCE SU10'A .Y .

For the Month of August 19 81 .

' Etfcct on Sa[c Action *Iaken Component  !!ature of Operati.on of Cause of Results of To Preclude D ..t c Sys tcc-Itaintenance The Reactor Malfunction Malfunction Recurrence

.I ,

8/16/81, ilPCI

• Gland seal Level switch None Bad level llot wel1 low level Replaced level condenser hot 73-15B switch trip circuitry switch. Switch well level inoperable inoperable alarms and pump switch operated properly.73-15B TR 182410 i

! Radiation Radiation ' CAM detector Drywell air Loose connec- Drywell air sampl- Tightened loose l8/26/81 monitor- monitor 90-256

. circuitry sampling tion on ther- ing inoperable connection, relay

,ing . inoperable inoperable mostat not operated properly.

allowing relay TR #240635 '

. operation LER#BFRO-50-296/

8143 w l Q l

I l

i t

I <

a t

r I

i e

B I

i i l ' i j

F

. . . . .. ........s.vs.-... s w .s. . w.,-- .',

CSSC ECUIPi1ENT SS.Cil/JiTCAL 1:AINID:ANCE SUIO!ARY .

19 81 Fc,r the Month of August .-

EFFECT ON SAFE ACT10!i TAKFU DATE SYSTE!! COMPONENT NATURE OF OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE MAINTENANCE Tile RF_\CTOR MALFUNCTION MALFUNCTION PECURRENCE 1-16-81 D/G A Air Compress. Blown licad None Unknown Blown head gasket Replaced head gasket Casket high pressure cylit3de.

TR/t 204469 -

3-18-81 Control Bay 1B Control Room Worn shaft & None Worn & broken Shaft & bearings worn Replaced shaft a llc at , Vent Air llandling bearings parts out, & spider broken bearings, also repair.

& A. C. Unit loose spider TRll 189745 1-23-81' EECW A2 RHRSW pump Broken Valve %ne Air release valve Unknown Replaced air release Vacuum Breaker broken valve TR// 203771 3-22-81 D/C 1A D/G A Air Blown gasket, None Blown head gasket Leaking head gasket Replaced bottom gash

(.ompressor & spacer. Iloned jig fit surface v TR// 236214

. i

. - - - = . .-- - -- - - . _ - - - - .- .-- . - -.. . - . ._ -

- ............w.... . _ . . .

CSSC FOUIPMENT MEQlANICAL PMINTEtMNCE

SUMMARY

For the Month of August 1981 .

},

EFFECT ON SAFE ACTION TAKEN DATE SYSTE!! COMPONENT' NATURE OF OPERATION OF CAUSE OF RESULTS OF 70 PRECLUDE MAINTENANCE THE REACTOR MALFUNCTION MALFUNCTION RECURRENCE D-18-81 CRD 34-43 1-85-40B Faulty Valve None Rod withdraw time Rod withdrawal time Replaced directional would not adjust too fast control valve TR# 223283 .

f E-4-81 RCW A-B-C Chiller Faulty gasket None Strainer was Clogged strainer Itcplaced gasket &

clogged up unclogged drain TR# 235855 F-29-81 CRD CRD 06-31 Valve leak None Valve out of Leak Adjusted valve stem FCV-85-39A adjustment TR# 235849 F . -81 Contr. Bay .

Heating Vent & A.C< lB oil cooler Faulty Valve None Bad valve Unknown Replaced all parts chiller valve body TR# 223465 d 1-21-31 EECW A RHR Pump Broken Valve None Valve broken off. Leak Replaced valve Motor Cooler cooler TR# 235918

@-20-81 CRD Valve 1-85-40B Out of Adjust. None Faulty Valve Valve would not oper- Changed out directic Module 26-39 ate control valve TR# 235913 f-20-81 CRD Module 34-11 Out of Adjust. None Faulty Valve Withdraw time too Rebuilt & replaced fast valve TR# 235912 0-21-81 D/G 1A D/G Air Blown Head None Unknown Bottom head gasket Replaced both top &

Compressor Gasket blown bottom head gaskets TR# 241869

. i

P"' ,

CSSC EQUITMEg MEQlANICAL MAINTEFANCE

SUMMARY

For the Month of August 19 81 ,

EFFECT ON SAFE ACTION TAKEN CATE SYSTEM COMPONENT. NATURE OF OPERATION OF CAUSE OF RESULTS OF 'ID PRECLUDE MAINTENANCE 'IllE REACTOR MALFUNCTION MALFUNCTION RECURRENCE 8-5-81 CRD 85-552 Broken stem None Stem bushings Unknown Replaced stem bushin,85-554 bushings broken with new ones

• (

TR# 205747 ,.

7-31-81 CRD Accumulator Leak None Faulty Accumulator Water Leakage Replaced with new one 50-23 TR0 238988 7-31-81 liigh-Press Valve won't Fire Prot.p FCV-26-74C hold press. None Worn seat gasket Valve not functioning Changed rubber flap properly on check valve TR# 205629 8-4-81 Secondary Equip. Airlock' Broken parts None Closer was broken Door would not operat o Install new closure.

Containment U-2 & latch failure properly repaired lock.

Shined hinges L)

TR0 188225 F-28-8LSecondary Door 241 Door not Containment locking proper ly None Worn Parts Joor not locking Straighten air seal properly & fasten it in place TR# 234643 8-18-81 CRD Module 50-23 Blown piston None Piston blown Unknown Replaced'all o' rings Water accum. & rebuilt TR# 233026 s

4 e

. i

V CSSC EQUITMENT MEQIMIICAL HAINTEt&.WCC SUMMAR

For the Month of August 19 81 ,,-

EFFECT ON SAFE ACTION TAKEN L\TE SYSTEM C:!PONENT UATURE OF OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE l'AINTENANCE IIIE REACTOR  !!ALFUNCTION MALFUNCTION IECURRENCE s-12-81 RCIC IICV-71-570 Lenk None Worn gaskets Leakage at steam trap Installed new gasket TR# 189833 f 1-26-81 IIPCI LS-73-56A raulty level None Bad level switch Float sticking Replaced 1cvel swit:..

switch TR# 240708 t

t e

e

$ 35

' OUTAGE

SUMMARY

~

August 1981 The outage related maintenance and modification activities for the month of August continued to focus principally on the unit 1 cycle 4 refueling / torus modification work that has been in progress since April 1981. Note that some outage attention was diverted to the unscheduled unit 2 shutdown for transformer repairs and, to a lesser degree, the unit 3 unscheduled shutdown. Maj or. emphasis was placed on the following activities with additional' effort toward those items that are prerequisites for integrated leak rate testing:

1. Torus modification - Completed all internal torus modifications necessary for torus fill. Torus fill was completed on August 17, and torus was declare'd operable August 25, 1981.

2. LPCI modification continued - Completed Loop 1 portion of this modification and testing August 22. The two motor generator sets associated with Loop 1 have been released to Operations. _

3. 11 220 analyzer and sample pump all pipe welds, caps and tie-ins to existing systems were completed during August. Electrical work, final hanger installations and post modification testing remain.

4

4. Turbine Floor - Completed all major turbine floor work-scheduled for unit 1 outage.

5. Cencrator Breaker Modification P0214 - Continued this month, post modification testing is in progress at the close of this report period.

6. . Core reload was completed August 11.

7. MS1V final repairs and leak testing complete.

F .,

36 , ,

OUTAGE

SUMMARY

(Continued)

August 1981

8. Degraded voltage relay installation and testing in the 4kV shutdown boards was completed. This is part of ECN P0275 Unit Station Service Transformer modification.

9. Five additional CRD's were identified for replacement this month. Work was completed August 26. The late identification of major work such as this has a disruptive effect on the overall outage schedule. It is recommended tl.at efforts be directed toward earlier identification of all work of this nature including more positive diagnostics.

10. Core shutdown margin checks were performed as a prerequisite to CRD changeout.

11. The malfunctioning spare transformer has been disconnected ,

and moved off its foundation pad. It was replaced with the _

transformer that was formerly in the 1C location. A replace-ment transformer has been received for installation in the

, vacated 1C location and work is presently in progress to i

mount the coolers and associated equipment prior to final j placement of the transformer.

D The unit 1 cycle 4 outage. schedule was reevaluated recently which pfaced the -revised outage duration at 161 days for a return to service .

date of September 19, 1981.

(

~

l i

. i : y 37

. [ ..

OUTAGE

SUMMARY

(Continued)

August 1981 During the performance of RTl-5 follouing CRD maintenance for newly rebuilt ~

CRD's (30-31, 34-47, 42-43, and 50-19) experienced difficulty moving from position 00 to 02. They functioned normally-during the withdrawal from 02 to 48. Three CRD's - (30-35, 26-39 and 34-11) could not be timed to <40 second withdrawal time as required by RTI-5. All seven CRD's were replaced and satisfactorily retested. In-vestigation into these two problems continues.

After Unit 1 Cycle 5 fuel loading, the fuel support casting at core location-26-47 was found improperly seated. The problem was corrected prior to core verifi-cation. Subsequent investigation established that it was seated at the beginning of cycle 4 core verification., The fuel support casting is associated with control rod drive 26-47 removed for maintenance and was probably unscated during the main-tenance activities.

/

f o

O 6