ML20010C868

Forwards Monthly Operating Repts for Jul 1981

ML20010C868
Person / Time
Site:	Browns Ferry
Issue date:	08/10/1981
From:	Abercrombie H TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF MANAGEMENT AND PROGRAM ANALYSIS (MPA)
References
NUDOCS 8108210126
Download: ML20010C868 (1)

Text

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O TENNEscEE VALLEY A U Ti to r T'

Browns Ferry Nuclear Plant P. O. Box 2000 Decatur, Alabama 35602 AUG101981

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Nuclear Regulatorybemraission Of fice of Manager'aent Information I

and Program' Control t.ot1I DC 20555 Centlemen:

Enclosed in the July 1981 Monthly Operating Report for Browns Nuclear Plant Unfts 1, 2, and 3.

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Very truly youre.

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l TENiiESSEE VALLEY AUT110RITY

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11. L. Abercrombie

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Plant Superintendent l

' - l : ;0,"d-3 Enclosure cc: Director, Region 11 Mr. Bill Lavalee Nuclear Regulatory Cotamission Nuclear Safety Analysis Center (NSAC)

Office of Inspection and Enforcement 3412 Ili11sood Avenue 101 FL1rietta Street P. O. Box 1041; l

Suite 3100 Palo Alto, CA 94303 l

Atlanta, CA 30303 (1 copy)

Director, Office of Inspection l

and Enforcement i

Nuclear Regulatory Commission i

Washlagton, DC 20555 (10 copies)

Mr. A. Rubio, Director Electric Power Research Institute P. O. Box 10412 l

Palo Alto, CA 94304 l

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TENNESSEE VALLEY AUTHORITY DIVISICN OF POWER PRODUCTION BROWNS FERRY NUCLEAR PLANT MONTHLY OPERATING REPORT July 1, 1981 - July 31, 1981 30CKET NUMBERS 50-259, 50-260, AND 50-296 LICENSE NUMBERS DPR-33, DPR-52, AND DPR-68 Submitted By:

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Plant Sup'erintendent

TABIE OF CONTENTS Operations Summary...

1 Refueling Information 3

Significant Operational Events.

5 Average Daily Unit Power Level.

11 Operating Data Reports.

14 i

l Unit Shutdowns and Power Reductions.

17 Plant Maintenance 20 1

Outage Summary.

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1 Operations Summary July 1981 l

The following summary describes the significant operational activities l

l during the reporting period.

In support of this summary, a chronological log of significant events is includ'd in this report.

l There were 25 reportabic occurrences and five revisiens to previous l

reportabic occurrences reported to the NRC during the month of July.

l.

Unit 1 i

l Unit I was in its EOC-4 refueling outuge the entire month.

l Unit 2 l

There were three scrams on the unit during the month.

On July 7, the 1

reactor was manually scrammed to repair an EllC oil leak on turbine control valve 2A.

7.c reactor scrammed on July 28 when a turbine trip was initiated by high gas accumulation and sudden pressure on the "A" phase main transformer. On l

l July 30, the reactor was manually scrammed to place the unit on the spare trans-former after the main turbine tripped a, gain on sudden pressure on "A" phase main i

tansformer after maintenance was completed following the July 28 scram.

Unit'3 There was one scram on the unit during the month. On July 30, the reactor was manually scrammed so that a transformer could be spared out to Unit 2 and for maintenance on an inoperative torus 11 0 sample valve.

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2 I

l Operations Summary (Ccatinued)

July 1981 l

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

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Location Usage Factor i

l Unit 1 Unit 2 Unit 3 I

l Shell at water line 0.00503 0.00415 0.00349 Feedwater nozzle 0.24411 0.17675 0.13559 Closure studs 0.19865 0.14092 0.10482 l

NOTE:

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

i Common System Approximately 4.29E+05 gallons of waste liquid were discharged containing anproximately 1.46E-31 curies of activities.

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3 Operations Sitmmary (Continued)

June 1981 Refueling Information Unit 1 Unit 1 began its EOC-4 refueling outage on April 11, with a scheduled restart date of September 6, 1981.

This refueling will involve loading additional 8 X 8 R (retrofit) fuel assemblics into the core, the final fix on the sparger i

modification, power supply on LPCI modification, generator breaker and unit section transformer tie-in (requires Unit 2 to be shutdown) and torus modi-fications.

There are 140 fuel assemblics in the reactor vessel. The spent fuci t

i storage pool presently contains 624 EOC-4 fuel assemblies, 550 spent 7 X 7 fuel assemtlies,fivespent8X8fuS1 assemblies,260new8X8Rfuelassemblies, I

and one spent 8 X 8 R fuel assembly. Because of modification work to increase spent fuel pool capacity to 3471 assembl1~s, present available capacity is limited to 524 locations.

Unit 2

'Jnit 2 is scheduled for its fourth reiueling beginning on or about March 26, 1982, with a scheduled restart date of August 13, 1982.

This refueling l

outage will insolve completing relief valve modifications, torus modifications, i

l "A" low pressure turbine inspection, MG set installation for LPCI modification, and loading additional 8 X 8 fuel assemblics into the core.

There are 764 fuel assemblies in the reactor v-.ssel.

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

4 Operations Summary (Continued)

June 1981 Refueling Information Unit 2 (Continued) l l

pool. The present available storage capacity of the spent fuel pool is 169 l

locations. With present capacity, the 1979 refueling was the last refueling that could be discharged to the spent fuel pool without exceeding that capacity J

l and maintaining full core oischarge capability in the pool.

Ilowever, 949 new l

high density storage locations have been installed.

l Unit 3 i

Unit 3 is scheduled for its fourth refueling begin sing on or about October 16, 1991, with a schedul,ed restart date of February 13, 1982. This refueling involves leading additional 8 X 8 R (retrofit) assemblies into the core, relief valve modification, turbine inspections, generator breaker and unit station transformer tie-in, and torus modifications.

There are 764 fuOl assemblies presently in the rea-tor vessel. Tl'ere are 124 discharged cycle 3 fuel assemblics, 144 discharged cycle 2 fuel assenblics, and 208 discharged cycle 1 fuel assemblies in the spent fuel storage pool. The present available storage capacity of the spent fuel pool is 1052 locations.

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5 Significant Operational Events Unit 1 Date T ime Event 7/01/81 0001 End of Cycle 4, refuel outage continues.

7/28/81 2345 Commenced fuel loading.

7/31/81 2400 Fuel reload continues.

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Significant Operational Events Unit 2 Date Time Event 7/01/81 0001 Reacter thermal power at 99%, maximum flow, rod limited (sequence "B").

1140 Commenced reducing thermal power due to high con-censer back pressure.

1300 Reactor thermal power at 93%, holding due to high condenser back pressure.

1405 Commenced power accensioa from 93% tnermal power.

1500 Reactor thermal power at 97%, holding due to high condenser back pressure (C2 waterbox out of service).

7/02/81 2030 C2 waterbox back in service, commenced power ascension from 97% thermal power.

2100 Reactor thermal power at 99%, maximum tiow, rod limited.

7/03/81 2200 Commenced reducing thermal power to remove "C" KFWP from service for maintenance (leaks).

2235 Reactor thermal power at 73%, holding for maintenance o'n "C" RFWP.

7/04/81 054u "C" RFWP back in service, commenced power ascension from 73% thermal power.

0700 Commenced PC10MR from 97% thermal power (sequence "B")

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

2240 Commenced reducing thermal power for control rod pattern adjustment.

7/05/81 0200 Reactor thermal power at 72%, holding for control rod pattern adjustnrnt.

0230 Control rod pattern adjustment complete, commenced power ascension.

0330 Commenced PCIOMR from 77% thermal power (sequence "B").

7/06/81 0215 Reactor thermal power at 99%, maximum flow, rod lirited.

7/07/81 0110 Commenced reducing thermal power due to Xenon burn up.

1103 Reduced reactor thermal power from 98% to 95% due to high condenser back pressure when unit was placed on cooling towers.

1135 Commenced power ascension from 95% thermal power.

2200 Commenced reducing thermal power from 98% for shutdown for maintenance on EllC system, "iA" control valve leak.

2347 Reactor Scram, Manual, No. 121 from 45% thermal power to accommodate maintenance of FhC "2A" control valve.

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7 Significant Operational Events Unit 2 Date Time Event 7/08/81 0740 EllC maintenance completed, commenced rod withdrawal for startup.

3027 Reactor Critical No. 134.

1558 Rolled T/G.

1632 Synchronized generator, commenced power ascension.

7/09/81 0510 Commenced PCIOMR from 62% thermal power.

7/10/81 2255 Commenced reducing thermal power from 97% for con-trol rod pattern adjustment.

7/11/81 0030 Reactor thermal power at 64%, holding for control rod pattern adjustment.

0145 Control rod pattern c2]ustment completed, commenced power ascension.

2200 Commenced PCIOMR from 86% thermal power (sequence "B").

l 2240 Comme.' ecd reducing thermal power from 87% thermal power to remove "C" RFWP from service for mainten.nce on non-return valve.

7/12/81 0150 Reactor thermal power at 79%, holding for maintenance on "C" RFhT non-re turn valve.

0845 "C" RFWP back in service, commenced power ascension.

1001 Commenced PCIOMR from 94% thermal power (sequence "B").

Reactor t'ermal power at 99%, maximum flow, rod 2200 h

limited.

7/15/81 0100 Cor..menced reducing thermal power for cooling tower operation.

0125 Recctor thermal power at 87%, removed Unit 2 from ccoling towe s.

Oll:9 Commenced power as cension from 87% thermal power.

9400 Reactor thermal power at 99%, maximum flou, rod limited.

7/18/81 2150 Commenced reducing thermal power for control rod pattern adjustment.

2300 Reactor thermal power at 70%, holding for control rod pattern adjustment.

7/19/81 0100 Control r'd' pattern adj ustment complete, commenced power ascension.

0230 Commenced PCIOMR from 83% thermal power (sequence "B").

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

7/20/81 1400 "B"

recircul. tion pump tripped (maintenance error),

reduced thermal power to 59%.

1425 "B" recirculation pump back in service, commenced power ascension.

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8 Significant Operational Events Unit 2 l

Date Time Event 7/20/81 2200 Reactor thermal power at 99%, maximum flow, rod limited 7/25/81 0025 Conunenced reducing thermal power for turbine con-trol valve tests and S1's.

0100 Reactor thermal power at 85%, holding for turbine control valve tests and Sl's.

0135 Turbine control valve tests and SI's complete, commenced power ascension.

0230 Ccemenced PCIO!!R from 95% thermal power (sequence "B").

0500 Reactor thermai power at 99%, maximum flow, rod limued.

l 2300 Reactor thermal power at 987., limited by high con-denser back pressure.

122( } from 98% thermal power due 7/28/81 0326 Reactor Scram No.

to "2a" main transformer sudden hic,h pressure.

1545 Conunenced rod withdrawal for startup.

.1820 Reactor Critical l'o. 135, holding for "2A" transformer maintenance completion (Nshing change out).

7/29/81 0700 Reactor thermal power at 10%, holding for turbine

.nalntenance.

7/30/80 1300 Reactor thermal powcc at 16%, holding for trannformer maintenance.

1715 Rolled T/G.

1801 Synchronized generator.

Main turbine tripped from suddenpressureon"A"maintrgformer.

[

l 2156 Reactor Scram, manual, No. 123 from 16% thermal l

powcr fot maintenance on "2A" main transformer and to l

place the unit on cpare transformer.

i 7/31/81 1232 Commenced rod withdrawal for startup.

l 1330 Reactor Crit ical No. 136.

l 2145 Rolled T/G.

2219 Synchronized generator, turbine tripped, PCB 3244 tripped "2A and 2B" main trannformer differential relays operated. (Reactor thermal power holding al 14%).

2400 Unit remained off lina due to main transformer pro-blems.

(Reactor thermal power at 14%).

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9 Significant Operational Events Unit 3 Date Time Event 7/01/81 0001 Reactor thermal power at 93%, control rod pattern adjustment in progress.

0330 Control rod pattern adjustment complete, commenced power ascension.

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

7/05/81 0248 Commenced reducing thermal power for turbine con-trol valve tests and SI's.

0300 Reactor thermal power at 95%, holding for turbine control valve tests and S1's.

0340 Turbine control valve tests and SI's complete, commenced power ascension.

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

7/07/81 0045 Commenced reducing thermal power for control rod pattern adjustment.

0100 Reactor thermal power at 92%, holding for control rod pattern adjustment.

0230 Control rod pattera adjustment completed, conmenced power ascension.

0706 Reactor thermal power at 99%, maximum flow, rod limited.

7/09/81 0201 Commenced reducing thermal power due to a limiting condition for operation on 3C RHR pump. Apparent low breakdown voltage between phases on pump motors.

0230 Reactor thermal power at 97%, holding due to 3C RllR pump problet:.

0305 Commenced power ascension from 97% thermal power.

0400 Reactor thermal power at 99%, maximum flow, rod limited.

7/15/81 0100 Commenced reducing thermal power when cooling towers number 3 and 4 tripped on high temperature.

0110 Reactor thermmi power at 82%, holding due to cooling tower problems.

0240 Commenced power ascension from 82% thermal power.

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

7/17/81' 2140 Commenced reducing thermal power for control rod pcttern adjustment.

k 2100 Reactor thermal power at 84%, holding for control rod I

pattern adjustment.

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10 Significant Operational Events Unit 3 Date Time Event 7/18/81 0030 Control rod pattern adjustment complete, commenced PCIOMR (control cell core).

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

7/24/81 2340 Commenced reducing thermal power for turbine con-trol valve tests and SI'r..

2400 Reactor thermal power at 857., holding for turbine -

control valve tests and SI's.

7/25/81 0100 Turbine control valve tests and SI's complete, commenced power ascension.

0500 Reactor thermal power at 997. maximum flow, rod limited.

7/30/81 2200 Commence'd reducing thermal power for shutdown to take the unit off of the spare transformer for use on Unit 2.

2350 seactor Scram, Manual, No. 100 from 35% thermal poucr to swap transformers and for maintenance on torus H 0 sample valve.

22 7/31/81 2400 Unit remains down for maintenance to torus H 0 22 sample valve.

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Equipment malfunction 5

r-11 AVER AGE DAILY UNIT POWER LEVEL DOCKET NO.

50-259 UNIT Browns Ferry -

DATE 8-1-81 COMPLETED BY Mike Cha gan TELEPilONE 205-729-6846 MONTil July DAY AVER AGE DAILY POWEll LEVEL DAY AVER AGE DAILY POWFR I.EVEL (M We-Net )

(MWe-Net )

-5

-7 g,

2

-6

-7 g3 3

-6

-7

,9 4

-6

-8 20

-6

-8 5

,g

-6

-8 6

7

-7

-7 s

-8

-7

,4 9

-7

-8 25 10

-7 2 r,

-9 11

-7

-8 2'

12

-7

-10 23 13

-9

-8 39

-8 14 30

-7

-8 IS 3;

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-7 INSTRUCTIONS On this fopnat.!Jt the.nerace Jany unut powei !csel in Mwe. Net for each day in ti.e reporting iniinth. Compute io the nearest whole nyawatt.

(9/77) 4

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12 AVERAGE DAll.Y UNIT POWER I.EVEL DOCKET NO.

50-260 UNIT Browns Ferry 8-1-81 DATE C0\\lPLETED llY Mike Chapman 205-729-6846 TELEP'!ONE 510NTil July DAY AVER AGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(51We-Net) 1031 1032 3

37 1034 g

1021 3

1033 987 39 4

954 1018 20 5

910 1044 yi 1045 7

1048 6

993 1043 7

,3 12.4 1045 s

24 792 1024 l

9 25 l

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10 989 2c, 1032 II 848 1030 27 l.

1, 965

,3 129 13 1038

-15 29 34 1050

-16 30 33 1037

-16 3

1044 33 INSTRUCTIONS On il is forin:n. hst the.ner. ige J.si!> unit powei lev.' in MWe Net foi cach day in the scri iting in.. nth. Coin.ute to the I3rGt whoIC nie[.in.it t.

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13 AVERAGl' DAILY UNil POWER LEVEL DOCKET NO. 50-296 UNIT Browns Ferry - 3 DATE 8-1-81

( )'.1PLETED itY flike Chapman 205-729-6846 TELEPil0NE U"IY S!0N111 DAY AVER AGE DAILY /0WER LEVEL 1)AY AVER AGE DAILY POWER LEVEL (Str e Net)

(31We. Net )

1034 1012

,7 2

1051 1005

3 3

1073 1020 39 10'.5 030 a

20 5

1047 1033

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1052

^ -

1034 6

j 7

1045 1033

,3 g

1049 1035 3

l 1040 1023 9

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10 1038 1029

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11 1033 27 1031 12 1034 1034 33 1036 1020 g3 1032 982 g4 30 15 1011

-13 to 1030 INSTRt'CTIONS Oii this finnut, hst the nerage J.nh urut power lael. i Ntwc.N'et for each J.i> ni the repairin;. ni..nih. Cinnpute io it.c neare>t w hole t ry. nut t.

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r 14 OPERATING DATA ItEPOllT 50-259 DOCK ET NO.

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DATE 8-1-81 C051PLETED IlY Ted Thom TELEPilONE 20bl23:5846 OPEli ATING STATUS

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1. Unit Name:

2. Iteponing Period:

July 1981 3293 3 1.icensed Thermal Power (SIW ):

1152

4. Nameplate Itatini:(Gross SIWE):

1065

5. Desi;n I-tectricalItating(Net htWe):

1098.4

6. Stasimum Dependable Capacity (Gross MWe):

1065

7. Masimmn Dependable Capacity (Net SlWe).

S. If Changes Occur in Capacity itatings (1tems Number 3 Through 7)Since 1.:nt Iteport.Giie Itcasonc NA

9. l'ower Lescl To which itestrictcd,1f Any (Net 51We):

NA NA

10. Itcasons For Itestrictions. lf Any:

This Month Yr.-to 1)a:t Cumulatise

11. !!o:us in Reporting Period 744 5,087 61,369 0

2,384.4 37,190.97

d. Number Of Ilours Ileactor Was Critical 0

16.42 5,115.29

13. Itcactor llesene Shutdown lleurs

11. Ilours Generator On-l.ine 0

2,380.77 36,373.59

15. Unit Itesene Shutdoan llours 0

0 0

0 7,425,495 100,717,856

16. Gross Thermal Energy Genen ted (M%II) 0 2,474,200 33,237,490 17 Grow Electrical Energy Gener.'ted (MWil) 2,407,849 32,271,666 0

18. Net Electrical Ener;;) Generated (MWil) 0 46.8 59.3

19. Unit Senice Factor 0

46.8 59.3

20. Unit Asailability ' actor 0

44.4 49.4

21. Unit Capacity I actor (Using MDC Net) 0 44.4 49.4

22. Unit Capacity Factor (Using 1)ER Net) 0 0.8 28.0

23. Unit Foretd Onta,ce Itate 2 4. Shutdowin Scheduled Over Nest 6 Months (Type. Date, and Duration of I'.ach).

25. If Shut Down At End Of lteport Period. Estimated I) ate of htar"tu;r S.ptember 6, 198l

26. l'nlis in.Tht Statin (Prior to Conuncreial Operation):

l're ceas t Achiesed INi l I \\ 1. Cltll ICAl.1 I Y INI I I \\ I. E1. E01 ItlC11 Y CO'!Ml~llCITI Ol'111 AllON (9/77)

15 OPER AllNG D \\T A RLi'OR I DOOKhrNO. 50-260 l) A IT 1-81 C05tPl.L TED I!Y

_llike Chap:846 tan 200-729'6 1 ELI:PilONE OP1 it \\1ING ST \\ TIN

l. Unit Narne:

llrowns Ferry - 2 N"'"'

d"lY 1981

2. tteportmg Period:

3. Licensed Thermal P..wer (51% 1.

3293

4. Nameplate Rating (Gross 51Wel:

1152

5. Desipi LiectricalItating (Net Slwel:

1065 c.. Stasimum Depend.ible Capacity (Gross :.lWe):

1098.4 1065 7 51.nimum Dependahic Capacity (Net SIWE):

If Changes Occur in Capacity Ratino (items Number 3 lhrough 7) Smee I.ast Iteport. Give Reasons:

8.

NA l

l 9 Power Lest! To Which Restricted. If Any (Net Slwe).

NA j

10. Reaw.a For !!cstrietmns. lf Any :

NA t

. -N 1his Stonth Y r.-t o.Da t e Cunwlatise l

s 1. Ilours in Reporting Period 744 5,037 36,280

12. Namber Of Itoun Reactor hn Cruieal 702.92 4,460.53 35,204.14 l

13. Reactor !!ewne Shutdown iloon

- 41.03 598. J 13,051.58 14 llours Generator Oa Line 634.72 4294.51 34.035.47 15 Unit Revne Shutdown llaun 0

0 0

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16. Grou Ihermal Enero Generated (5 twill 1,966,354 11 13,418 ogry27 ~

j 17 Gros, Eleitrial Ener;> Generated (SIWil) 654,140 4.402,870 32,140,056

!$. Net Electrical Encry,) Genaated (51%ID 631,506 4,273,003 31,223,310 l

19 Unit Senice Fac tor 35.3 84.4' 60.5

20. Unit Asadatnhty Factor 85.3 84.4 60.5 21.1: nit Caiueit3 i actor t Using.\\tDC. Net) 79.7 78.9 52.1 l

22 Unit Capacity l'aetor (tIsieg Di R Net) 79.7 73.9 52.1

23. Unit l'areed Outage Rate 14.7 6.3 30.3 24 Shutdowns Scheduled User Next 6 5tonths (Ty pe. l)ah.aml Duration of I.n h r

25. If Shut Down At I nd Of Report Period, L'timated Date of'St.1rtup..

8-18-81 2e Units hg lest Statm(Prior to Commercial Operationk I'orce.nt Acinesed Ib t llTI. CitillCA LIIY INI T I A 1. El.l?C I R !Cl TY CO\\t\\lERCI \\L OPER ATION

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16 OPERATING DATA REPORT DOCKET NO. 50-296 DATE 8-1-81 COMPLETED llY F.tLke Chapman TELEP!!ONE 705-729-6846 OPElt ATING STN1ITS Notes I

1. Unit Name:

Browns Ferry - 3

2. iteporting Period:

July 1981

3. Licensed Thermal Power (MWt):

3293

4. Nr.meplate Rating (Gross MWe):

1152 1065 l

5. Design Electrical Rating (Net MWe):

1098.4

6. Masimum Dependable Capacity (Gross MWe):

1065

7. Masimum Dependable Capacity (Net MWe):

S. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Lut Itepart, Give licasons:

NA l

NA

9. Power Level To Whieb Restricted,if Any (Net MWe):

NA

10. Reasons For itestrictions. !f Any:

l l

l This Month Yr..to Date Cumulatise 7'4 5,087 38,735 f

i1. !!ours in Itepmting Period 719.83 4401.71 30,372.93 l

12. Number Of Ilours Reactor Was Critical l

13. Reactor Reserve Shutdown llours 24.17 229.39 2040.28 i

14. liours Generator On.Line 719.83 4,308.75 29,698.75 0

0 0

f

15. Unit itesene Shutdown llours

16. Cross lhermal Energy Generated (MWil) 2,352,434 13,223,592 87,588,620 l

17. Gross Electrical Energy L.nerated (MWil) 767,230 4,388,470 28,927,500 IS. Net Electrical Energy Genciated (MWil) 742,482 4,255,097 28,079,420

19. Unit Senice Factor 96.8 84.7 76.7 96.8 84.7 76.7

20. Unit Asailability Factor 93.7 78.5 68.1

21. Unit Capacity Factor (Using MDC Net) l 93.7 78.5 68.1 Unit Capacity Factor (14ing l)Eli Net) 3.2 7.6 9.5 l

23. Unit Forced Outage : tate l

21. Shutdowns Sclieduled Over Nest 6 \\lonths (Type. D.ite, and Duration of Each L l

Maintenance Septeraber 1981 1

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8-2-8I

25. It Shut l>own At I:nd Of Report Period. Estimated 11 ate of $tartup-

26. Cnits in Test Status (Prior io Conuncreial Operation L I:orecast Achies ed 1

IN!ll A L C 111CA LITY INITIAL 1:a NCTit! CITY C0\\l\\lFitCl '.L OPER A110N (4/77 )

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a 50-259 DOCKET NO.

UNIT SliUTDOWNS AND I'OWER REDUCTIONS -

Browns Ferry - 1 UNIT NMIE 9

DATE 8-1-8' COMPLETED BY

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REPORT \\!ONT11 July TEl.Erl!ONE 205-729-68'.6 f

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Prevent Recurrence

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1 il 172 ! 7/01/81 S

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2 EOC-4 Refuel Outage

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f: For ed Reason:

Method:

Exhibit G -Instructions c

S: Schedu'e!

A Equipment Failure (E>p!ain) 1 M:naa!

for Preparation of Data B. Maintenance cf Test 2 %nu:1 Scran Entry Sheets for Licensee C-R:f uehng 3 Autonutic Scram.

Trent Report (1.ER) Fde (NilREG-D-Regulatory Restriction 4 Other (Explam) 0161)

E-Operator Trainin;; & Liecase Exanunation F-AJministrative 5

G-Operational Errur (Explain)

Lxhibit I - Same Sour.e (9/77) i1 Other (Explain)

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UNIT SIIUTitOWNS AND POWER REDUCDONS.

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DATE 8-1-81 COMPLETED By n a rh m-n__.

REPORT MON'ill July TELEPI:ONE 205-729-6846 a

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)Y Cause & Currectise No. -

Date i

3g y,4 jj5 Esent g

{T Action to gE f, 7 Rep.n t =

mV y'

Prevent Recurrence H

?

b 195 7/03/81 F

B Derated for "C" RFWP maintenance (leak j

196 7/04/81 S

l B

Derated for control rod pattern adj.

197 7/07/81 F

16.75 B

Icactor scram to accommodate mainte-nance on "2A" EHC control valve.

~

oc Derated for control rod pattern adj.

l 198 7/18/81 S

B 199 7/20/81 F

G Derated because "B" recirculation pump tripped (maintenance error).

200 7/28/81 F

66.46 A

3 Reactor scram due to "2A" main trans-former high pressure.

201 7/28/81 F

26.07 A

2 Reactor scram for maintenance on "2A" transformer and to place unit on spare transformer. An attempt to start re-sulted in a turbine trin at 2219/7-31m I

2 3

4 F: Forced Reason:

Method:

Exhibit G. Instiuctions S: Scheduled A Equipment Failure (E.splain) 1-Man ual for Preparation of Data B-Maintenance ci Test 2 Manual Scram.

Entry Sheets for Licensee C-Refueling 3 Automatic Scram -

Event Report iLER) File (NUREG-D Regulatory Restriction 4-Other ( E xplain) 0161)

E-Operator Training & Licens: Exan:ination F. Ad minist ra ti.e 5

G-Operational Error (Explam)

Exhibit I - Same Source (9/77)

Il-Ot her (E xplain )

9

Us

-~

~' ~

-~~

a.

J DOCKET NO.

50-296 UNIT FIIUTDOWNS AND FOWER REDUCDONS UNIT N.OIE

,drmms Fer ry -3 DATE R-i R1 COMPLETED BY Mien Chann,n REPORT MONTil Julv TELEPIIONE 9ns_7?o_hRt A W

=

=

Licensee 5 -7, h9, Cause & Correctise

.! O 3

h5'k N. i.

Da te i

5?

?

iy5 Esent

?

5?

Action to E

E I p, =f Repor t EU E'

Present Recurrence

.E l

e v

d 84 7/30/81 F

24.17 B

2 Reactor scram to swap transformers and maintenance on torus H 0 sample 32 valve.

H I

2 3

4 F: Forted Reason:

Method:

Exhibit G. Instructions S: S<!:ed uleti A t'quipment Failure (Explain) 14!anual for Preparation of Data B41aintenance or Test 2-Manual Scram.

Entry Sheets for Licensee C Refuelia; 3-Automatic Scram.

Esent Report (LER) File (Nt Ri G-D-Regulatory Restriction 4 Other (Explain) 0161)

E-Operator Training & Licen,e Examination F-Administrati.c 5

G-Operational Lr ror (Explam)

Exhibit 1 - Same Source

('1/77)

It-Other (E xplain)

m BROUNS FERRY NUCI. EAR PLANT UNIT 1, 2 INSTRUMEtiT l'AINTENANCE SUIffARY

,CEOC EQUIP M.t ROP, T11E MONTII 0F July 19 81 1 ATURE EFFECT 0:1 SAFE CAUNE ACTION TANEN I' ATE SYSTCI CG:00NENT OF OPERATION 07 0F RESULTS CF TO PRECLUDE RECURRENCE l' LFUNCTION l'AINTENANCE TiiE_FKACTOR PALFWCTION A

'rn it 1

'-3 Residual TE-74-W Replace None Faulty RTD Alarm Would Not Clear None lle nt Remova:.

'3 Reactor FT-69~60 Calibrate None Zero Shift False Flow Ind.

None Unter Cleanup

'-7 Control Rod 3A-PS6 Replace None Faulty Power Fuse _ Blew None Drive S'upply i

s

'- 14.

Control Rod PI-85-66A Replace Notte Cage Damaged-Would Not Indicate None w

Correct Preasure Drive

/.

,-14 Rod Positio:t Probe 02-27 Replace None Faulty Reed Incorrect Rod Position None Information 06-23 Switch Indication 18-31

~22-39 26-31 26-39 34-23 34-47 38-27 42-23 46-55 50~5 58-19 Init 2

'-2 Primary PDT-64-138 Calibrate None Zero Shift Did Not Agree with None Redundant Containment I

r

y__

s.

EROW:.S FERRY TR' CLEAR PLANT UNIT 3

INSTRUMENT l'.AINTE!'A* ICE SUM:1\\RY i

CESC Fr!bIPM"I.~f FOR 'nl5 MON 111 OF July 19 81 KATURE EFFECT 05 SAFE CAUSE ACTID:; T!dE::

nTE SYSTEM CCMFONE!.~f OF OPEF.ATION OF CF RESULTS OF TO PPECLU'DE RECT!RRENCE MAINTENANCE TliE EFACTOR

?BI.FUl!CTION P.\\T. Fin'CTIO'?

4 s

-Jnit3

)7-9 Er.o rgen cy FT-67-6B

.teplace None Uater in Trans-False Flow Indication None Zquipr.ent mitter 3

Cooling Water

7-16 Reactor LI-3-58B Replace None Bad Bearings Did Not Agee with None Redundant Feedwater b

e6 4

NW e

0 h

6 a

e

,.o'*'**

0 e

(

a e

t 4

,t

'i.

i I

3-.

w

,e

y, ERC'JNS FERRY NUCLEAlt PIlsNT UNIT Common CCSC EOUIPMENT ICCHisNICAL 1%INTElaNCi.: SU10!ARY Fcr the 1:cnth of July 19 81 I

EFFECT 0;! SAFE ACTICN TAKEU

~

EATE SYSTDi CC :FCNE::T NATL'RE OF OPERATICN Or CAUSE OF KESULTS OF TO PRECLUDE I'AINT". NANCE TiiE REACTOR MALFUNCTION IMLFUNCTION RECURRENCE 6-9-81 EliRSN St 6iner C Leakage None Bad Packing Strainer C Leaking Replaced Packing TRf 137291 7-16-81 Secondary Door 240 Door will not None Head bolt & foot Door will not shut Installed new foot Containnent shut bolt removed bolt assembly & new head bolt. rod.

TR# 218317 7-11-81 Rl!RSW Pump A2 Water leak None Float seat torn Leakage Replaced seat off TR# 234311 7-6-81 Secondary Door 225 Broken head None Head bolt broken Door would not close Replaced head bolt &

Containment bolt off properly receiving keeper.

TR# ?34510 I

7-6-81 Secondary Loor 236 Torn seal need9 None Seal torn up Unknown Replaced rubber sealw Contain=cnt replacing on lock.

TR# 208782 e

i j

e

N.

4 a.

1 EROWNS FERRY NUCLEAR FIANT UNIT CSSC EOUIREUT MECHA'iICAL l'AINTENU!CE SU?efARY For the Month of July 19 81 EFFECT ON SAFE ACTION TAKEN DATE SYSTEM COMFC:EN~'

UATURE OF OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE MAINTEN*.NCE TFE REACTOR MAI FU'!CTION MALFUNCTION RECURRENCE 7-15-81 Recir.

FCV-68-1 Shaft binding None Unknown Binding shaft Oiled and stroked valve.

TR# 187180 7-19-81 Control 1-51--x5 kater Leak

'None Line broken at Watcr' Leakage Solder valve &

Bay Heat joint shortened line.

Vent &

TR# 235863 6-20-81 D/G l-9 Diesel Gen.

Faulty startera None Bad starters Unknown Changed left bank starters TR# 240987 7-7-81 RX Feed-PS-3-204D LIS-Worn valves None Valves worn out Unknown Replaced Valves to water 3-203,A,B,C, 25--

TR# 228377 5-1, 25-6-1

~

7-9-81 Sec. Con-Door 235 Missing '.ock-None No lock on door Door would not lock Installed new lock tainment ing device TR# 232811 7 '-81 CRD CRD-50-31-1-85 Broken wedge None Wedge broken off Unknown Replaced wedge 588 on valve of stem IR# 189967 6-26-31 CRD 1A CRD Pump Leskage None Seal needed Seal was leaking Seal was reset resetting TR# 235946 7-13-81 Sec. Con-Door 635 Door will not None Door would not close Adjusted closer &

tainment close tighten screws &

hinges.

TR# 234512

5-2 8-8

HPCI PL 25-53 Leakage None Flow transmitter Leak on fitting Tighten fitting &

FT-73-33 is bent strengthen tubing.

TR# 225635

e 1

BROWS FERRY NUCLEAR PIANT UNIT

_CSSC ECUIF:!E IT IECHANICAL MAINTElaNCE SUM:'ARY For the Month of July 19 81 l EFFECT CN SAFE-ACTION T!JEN DATE SYSTE:

COMPO: TENT NATL *RE CF OPEPATION OF CAUSE OF RESULTS OF TO PRECLUDE MAINTr?!ANCE THE REACTOR MALFU';CTION R\\LFUNCTIO:!

RECURRENCE 7-20-81 CRD "odule 14-15 Leaking thru

one Faulty Valve Scran outlet valve Changed out scran leaking inlet valve, reflom, seat r'.ng disc.

TR# 233024 7-16-81 CRD HCV-30-31 lValvesneed None Unknown Unknown Replaced directional HCV-34-47 changing flow valves on Modules modules.

TR# 241108 b

s O

e 4

9 m

h e

y, 4.

BROWS FERRY NUCLEAR PIAUT UNIT 2

CSSC EOUIP".iN7 IECHAIIICf L MAINTENANCE SUM'RRY For the Month of July 19,81

~

~

EFFECT ON SAFE l.CTION TAKEN DATE SYSTEM CCMPO::ENT NATURE OF OPERATIO:i OF CAUSE OF RESULTS OF TO PRECLUEE luINTFNANCE TIIE REACTOR MALFU: CTION MALFUNCTION RECURRENCE 7-23-81 CRD 2-85-588 Charging water None Unknown llandwheel missing Replaced handwheel Module i,2-51 Iso.

TR# 239215 I

7-20-81 Sec. Con- ; Door 238 Door out of None Lock on door out Unknown Aligned door & frame tainment alignment with of alignment to lock mechanism latching mech-TR# 188051 anism 7-20-82 IIPCI Condenner Top head seal None Unknown Blown head seal Changed seal on blown top head TR# 233025 7-12-81 Sec. Con-Eqt.ip. Access Lock was stick -None Bent door & lock Prevents interlock Repaired lock adjt.sted tainment Doors TB '. RX ing & door was sticking from working closure & straightened bert door y

TR# 224893 7-2-81 Sec. Con-Door 240 Broken door None Door had been Eroke flush bolts &

Replaced flush bolts &

tainment hit and broke hold open arm repaired hold open arm bolts & hold

& tighten weather open arm.

stripping TR# 218600 m

O e

1 4

u.

BR0hNS FERRY NUCLEAR PLANT UNIT 3

CSEC EOUIPMENT MECILV!ICAL MAINTEt AUCE SUIO!ARY For the Month of July 19 P1 EFFECT ON SAFE ACTION TAIGN DATE SYSTEM COM FO..:..u

.!ATUPE OF OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE MAII TENANCE THE REACTOR IMLFU.:CTION MALFUNCTION _

RECURRENCE 7-22-81 Main Steam Pdis-1-30 D Valve bad None Bad Valve Valve would not close Replace valve off TR# 240885 l

6-15-81 D/G 3D D/G Air Blown head None Unkncwn Blown head gasket Replaced head Compressor gasket gaskets TRJ 205373 7-13-81 D/G 3C D/G Air Leak off air None Check valve needs Leaking through Installed check valve Compressor #1 cylinder replacing TR# 205170 7-14-81 RIIR 3A & 3C RHR Replace air Pump Motors duct None 3C3RHR Pump Motor To facilitate 3C Installed duct Bad Motor Change-out TR# 233071 5-27-81 Rx Bld.

FCV-64-140 Busted seal None Seal busted Leak Replaced bad seal llVAC TR# 205056 7-?-81 EECW 3A RH,N Cooler ' Vent connection None Unknown Unknown Silver soldere1 broken connection TR# 232144

'3-2 6 -111 Control Bay Board room Dampers out of None Unknown 3A running with Adjusted damper HVAC supply fans adj us tt-en t damper closed-3B TR# 235076 3A & 3B not running & damper la open e

m EROWNS FERRY NUCLEAR PLANT UNIT 1 &] Common ELECTRICAL MAINTENANCE

SUMMARY

i CSSC Er)UIPMENT For the Month of July 19 81 Action.Taken Effect on Saic Usture of Operation of Cause of Results of To Preclude

[

Date Systen Ccmponent M.~. int enance The Reactor Malfunction Malfunction Recurrence f

l7/1/81 e

CRD Scram accumu-Panel 25-4 Non-reactor was Wire insulatio:-

Scram accumulator Repacied wire in.su- [

lator low blowing fuses unloaded damaged causing low pressure /high lation replaced e

pressure /high a short circuit level alarm annun-fuses, system retur.L level alarm ciation for CRD set ed to service.

circuitry 1 and set 2 inoper-TR #236s56 I

l able i

7/3/81 Fire pro-Annunciation

'While per-E r.e 3ad inverter Alarm panel XA The inverter conttoi tection circuit on

~Iorming SI card f", panel 9-8 inop-card was tightened.

panel 9-8 4.11.C 3&4 erable' in its slot and the inverter i'

began to operate.

for alram The next day w"...le 4

' panel XA performing SI4.11.C '

8E-became 364 it again became inoperable. The y inoperable'.

control card was l

replaced, success-fully tested and 2

l 6

returned to service.

TR #223407 TR #189950 LFR#BFRO-50-259/813t'

,7/3/81 CRD Rod position Lost indica-None-reactor Broken connec-Partial loss of Replaced connector, indication for tion for rod was unloaded tion at penetra-position indication instrument circuitr; CRD 46-23 46-23 tion connector operated properl.

TR #228381 L

a h

y,--

-i.

ERO'GS FERRY NUCLEAR PLANT UNIT 1 & Common CSSC EQUIPMENT ELECTRICAL MAINTENANCE

SUMMARY

For the Month of July 19 81

~

Action _Taken Effect on Sate 2

D.. t e System Ccmponent Nature of Operation of Cause of Results of To Preclude,

Maintenance The Renctor Malfunction Malfunction Recurrence

• 7/4/31 RCIC FCV-71-2 Broken term-None-reactor Broken terminal FCV-71-2 was inop-Reterminated motof inal block in cold shut-block erabic leads, performed on valve down EMI 58, 81 and 18, valve returned to motor g

service.

g TR #187971 l

l I

'7/9/81 Reactor Pa el 9 -5

' Broken switch None (this Switch operator The switch would Replaced switch concrol reactor scram doesn't make spring b*roken not automatically-

' operator, switch r

bay panels reset switch the switch return to normal operated properly.

inoperable) l TR #223411 j

'7/10/81 Secondary Air lock door Door would,

None Door watch was The door would not Cleaned,'a'djusted5 andlubricatedlatch],

out of adjust-open contain-235 not open prformed EMI 8..

ment ment l

door operated proper 4:

8 ly.

l TR #241280 I

TR-#223297 It TR #235443 fl Adjusted' switch,theli 7/13/81 RHRSW A2-RHRSW pump.

Running None Annunciator Received a running running anaunciator switch was out annunciation when annunciator operated!i annunciator would not of adjustment the pump was off properly.

TR #239056' ope. tor e

9

-.l!

k 1

m o.

LROWNS FERRY UUCLEhil PLANT UNIT I & Common ELECTRICAL MAINTENANCE

SUMMARY

CSsc EOUIPMENT For the Month ofi July 19 81 Action Taken Effect on Saic Cause of Results of To Preclude Nature of Operation of l

, Date Systen Cceponent Maintenance The Renctor l

Malfunctica Malfunction Recurrence i

I'7/14/hl Air con-1B control Chiller None Proportional Control bay chiller Adjusted proportion-ditioning bay chiller would not controller was would not cool al controller per (cooling-cool proper-out of adjust-properly EMI 60, chiller heating) ly ment operated properly.

3 TR #224905 I

l7/17/81 250 volt 250 main Cell 98 None Crack in batter)

Required battery to Jumpered out cell i

DC system battery #1 cracked cell 98 be removed from 98, adjusted battery service in order charger, battery to jumper around returned to service.

cell 93-TR #179952 LER#BER0-50-259/8142 7/18/81 Core spray HOV 75-27 "Open" indi None Limit switch "Open" indicating Adjusted limit I

cooling cating light was out of ad-light was'inoper-switch, indicating l

on panel 9-3 justment able light operated prop-i inoperable erly. TR #189979 l

1 7/26/dl Core spray IB core spray Breaker would None-reactor Jack nut mount-Breaker would not Replaced jack nut cooling pump breaker not rack in was unloaded ing bracket was rack Jn.

1B core mounting bracket, properly bent spray pump inoper-the breaker racked able in properly.

TR #189919

'=.,

e i

v, i,

I;;;.7.G;5 Fr.; 4 / :.::t,LLM PL.?;I UI;IT

__2_,_

CLECTEICAL lill:: TEN /J:CE SU!DI?.RY CSSC E0!!IiE Uf For the Month of fuly 19 81

' Action Taken M a cct on daic Nature of Operation of Cause of Results of To Prtclude Date 5: 7ter Ccmpenent ltaintenance The Reactor

!!al funct ion Malfunction Recurrence I

l l

.,.S

'7/7/81 Fire pro-smoke detector An alarm for None Possible ground Received an inc.d-Rephced smoke tection (XS-39-29A) smoke detec-in smoke detec-vertent alarm deteccor, alran tors in the tar due to a cleared and oper-t relay room pinched wire ated properly.

I war received TR #224880 l

'and would not TR #187159 8

cicar LEF "BFRO-50-260/8136 I

t 17/8/8t 4kV ur.it 4kV unit board While attempt-None

. Breaker "'B" 4kV shutcawn bus The breaker contacts boards a?. ternate ing to trans-finger contacts was lost for a few were cleaned and feeder breaker fer station failed to make seconds the breaker sucess-service back contact fully operated.

v to start bus,,

TR #239172 o

l 4kV -2B unit board failed f

to transtcr f

b

'I;7/9/81

! Associated 250V reactor

..larm actuat-

one Bad coil on Undervoltage alarm Replaced relay, per-l electrical MOV board 2A ed and would relay 27B inoperable lformedEMI23and undervoltage not clea-EMI 15, annuncia-tion operated

• alarm circuitry properly.

I TR #205760 I I TR #236943 l

I f

l

tT -

I>

,q:.74W3 F.::. l.. a. L :...: I'-.J:I 0:11 2

ELECTR IC!. :. It\\l :TENA?;CC SIIIDL*'.RI csse :Qiiim :r For the Manth of July

20_81, ACCIO" IOECU Eticct on Sate I!ature of Operation of Cause of Rest.lts of To Frecludc lD~-*a 5 ste" Ccrpenent

ai::tencnce The Renctor

!!alfunction Malfunction racurrence l

y 1

?

'7/16/81 Air cor.li-Flow switch Received None Bad flow switch Flow switch inop-Replaced flow switch

'tiening for 250V annunciation 31-174 erable, vent fans flow switch operated (cooling-battery board XA-31-174 operated abnormal properly.

i heating) room ventila.-

TR #239224 tion I

l7/26/81 RHR Limit switch Indicating None Loose limit Indicati,g light Tightened switch on HCV 74-11 light circui-switch actuator circuitry to panel.

actuator, indicat-j I

try inoper-9-3 inoperable ing lights operated able properly TR #239205 w

l l

None Water in switch Local push button Cleaned and dried I

i7/27/81 'RHR Local control Local contro1 l

switch switch inop-housing corroded control switch switch and housing, e:able contacts inoperable valve operated g

properly.

4 TR #239073 l

l I

i i

k I

1 I

\\

4i

}

Vi i.

i;nGWi;.7 : r.;.4l ::CLL:.i.:' I'L.?;I E';IT 3_

CLECTRICAL ttal ; TEN /J;CC S!!!:':/.U css (: roiiIP;n ;g t

For t.he :fonth of July 19 81 Action Taken c.f t ec t ca batc

!!ature of Opetation of Cause of Results of To Ptcclude 8

I l D.te Syster Cc=penent

a i n t c an nc e

'I h c Rc.~.c to r Malfunction

talfunction Recurrence y.

1 J

7/1/81 RHRSW Ann nciator A3 RRRSW pump None Circui',ry card Recei<cd a false Replaced card relay, circuitry running annun-relay bad

" running" annuncia-annunciation opera-card ciator was tion ted properly.

l actuated with TR #205600 pump off g

e!

I7 Diesel D/G 70, SFD1 During per-None Relay, timing Relay SDF1 tested SDF1 relay was l/6/81 generator relay formance of was slightly out too long.

recalibrated and redundant

out of toler-successfully tested start test ance SFBI was changed l

(EMI 3) relay out by mistake, SDF1 tested calibrated and M

out too long.

successfully *ested.

TR #183840 l

~

TR #186847 l

BFRO-50-296/8133 I.

l

.I t

i i

i e

t i

i-I

=.,

I I

U.

a.

.r.

1.EW.G;3 Fil U % LL;iJ I d I C II CLI;C ri;iCAL ;;ilI;TENA;;CE SUl!"l.F.Y cssc :01iIl':0 ;;r Fur the Month of July 19 81 Acti Takea PEffect on Sate Nature of Operation of Cause of Results of To Freclude lDr.te Syster Cc~,oncam a

tenance The Renctor Malfunction Malfunction Recurrence l

7/9/81, RHR RHR pump RHR pump Unit in limit-Motor failure.

RIIR hebt exchanger The motor was re-motor 3C 3C tripped ing condition Stator resis-C inoperable placed and success-on ground for operation tance and high fully tested.

overcurrent (TS 3.5.B.3) potential tests TR #204460 l

failed. Cause TR #186901 l'

of failure will TR #190658 be investigated TR #186902 i

(

i upon motor LER#BFRO-50-296/8134 l

repairs I

7/15/81 Annuncia-A D/G Recieving Nor.e Bad annu:. cia-Received a false Replaced relays on tor &

annunciator false tion card 3-A RHRSW pump annunciator cards y

i sequen-panel annunciatiod relays running and D/G for both D/G lubeW l

tial 3A engine lube oil oil and RHRSW pump, trouble annuncia-annunciators I

events I

tion operated properly.

TR #205153 l

l l

TR #205171 I

I I

! 7/23/E1 Contain-FSV-76-67 H0 anali-Placed unit in FSV 76-67 H0 analizer B The solenoid assem-22 22 j

ment zur B inop-

. limited oper-solenoid assem-inoperable bly was replaced j.

atmos-erable ating condition bly was grounded on FSV 76-67 and the H 0 nalizer I

phere 22 monitor-returned to service.

TR #204456' I

ing l

TR #204937 i

TR #204938 TR #129379 BFRO-50-296/8137 I

t 1

l

34 OUTAGE

SUMMARY

July 1981 I

The maintenance and modification activities for the month of July included continuing the Unit 1, Cycle 4 refueling / torus outage with major emphasis concentrated on the following:

1. -Torus internal and external modifications.

2.

LPCI modification.

3.

HU analyz r/ sample pump modification.

22 4.

HP turbine reassembly.

5.

Reactor feedpump turbine maintenance.

6.

Generator breaker modification (P0214).

7.

1B reactor feed pump reassembly. (Complete).

8.

Core reload.

9.

Local leak rate testing on selected valves.

10.

Main steam isolation valve maintenance (repair of 1D damaged stud still required.)~(Complete).

11.

Condenser grating installati;n (P0379).

12.

Control bay fire doors (PO464).

13.

Unit station service transformer modification.

14.

Oil flush on the HP and LP turbines (Completed July 27, 1981).

15.

Recirculation MG set and pump maintenance (Completed July 6,1981).

16.

PCIS modification (P0291).

17.

Condensate short cycle modification (PO434).

18.

CRD cross tie installation (P0353).

1 Th'c duration for the unit 1 cycle 4 refueling outage has been revised to 148 days based on completing torus internal modifications which delays the re-l turn of service date until September 6, 1981.

Fuel reloading was approximately 18 percent completed with 140 of 764 bundles placed in the RPV core at the end of the month.

3

I 35 OUTAGE SL7 MARY (Continued)

July 1981 The only cooling tower modification work done during this month involved the closure of the fan tip seals on cooling tower 1.

This work was not com-pleted as cooling tower 1 was required to be returned to service as a result of weather conditions.

Began ultrasonic examination of the unit 1 offgas system piping. The examination will look for possible cracks caused by acidic compounds 'tesulting from the decomposition of demineralizer resia in the reactor vessel.

p t

,