ML20010C516
| ML20010C516 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 08/01/1981 |
| From: | Chapman M, Thom T TENNESSEE VALLEY AUTHORITY |
| To: | |
| References | |
| NUDOCS 8108200157 | |
| Download: ML20010C516 (36) | |
Text
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. TENNESSEE VALLEY AUTIIORITY DIVISION OF POWER PRODUCTION BROWNS FERRY NUCLEAR PLANT onI' '/,
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MONTHLY OPERATING REPORT July 1, 1981 - July 31, 1981 s
DOCKET NUMBERS 50-259, 50-260, AND 50-296 LICENSE NUMBERS DPR-33, DPR-52, AND DPR-68 Submitted By: /4, 6 a P
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Plant Superintenden't o/r
- 8108200157 810801' PDR ADOCK 05000259 R PDR
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T TABLE OF CONTENTS Operations Summary . . . . . . . . . . . . . . . . . . . . . . 1 Refueling'Information . . . . . . . . . . . . . . . . . . . . 3 Significant Operational Events . . . . . . . . . . . . . . . . 5 Average Daily Unit Power Level . . . . . . . . . . . . . . . . 11 Operating Data Reports . . . . . . . . . . . . . . . . . . . . 14 Unit Shutdowns and Power Reductions. . . . . . . . . . . . . . 17 Plant Maintenance . . . . . . . . . . . . . . . . . . . . . . 20 Outage Summary . . . . . . . . . . . . . . . . . . . . . . . . 34 0
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Operations Summary July 1981 The following summary describes the significant operational activities during the reporting period. In support of this summary, a chronological log of significant events is included in this report.
There were 25 reportable occurrences and five revisions to previous
. reportable occurrences reported to the NRC during the month of July.
Unit 1 Unit 1 was in its EOC-4 refueling outage the_ entire month.
Unit 2 There were three scrams on the unit during the month. On July 7, the I reactor was manually scrammed to repair an EHC oil leak on turbine control valve 2A. The 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
! July 30, the reactor was manually scrammed to place the unit on the spare trans-t former after the main turbine tripped a, gain on sudden pressure on "A" phase main i tansformer after maint 'ance was completed following the July 28 scram.
l Unit 3 There was one scram on the nit during the month. On July 30, the reactor was manually scrammed so that a tt isformer could be spared out to Unit 2 and for maintenance on an inoperative to us H 0 S 22 mPl e valve.
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Operations Summary (Continued)
July 1981 Fatigue Usage Evaluation l
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 0.00415 0.00349 Feedwater nozzle 0.24411 0.17675 0.13559 Closure studs 0.19865 0.14092 0.10482 NOTE: This accumulated monthly information satisfies technical specification section 6.6.A.17.B(3) reporting requirements.
Common System Approximately 4.29E+05 gallons of waste liquid were discharged containing approximately 1.46E-01 curies of activities.
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. . 3 Operations Summary (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 modification, power supply on LPCI modification, generator breaker and unit station transformer tie-in (requires Unit 2 to be shutdown) and torus modi-fications.
There are 140 fuel assemblies in the reactor vessel. The spent fuel storage pool presently contains 624 EOC-4 fuel assemblies, 550 spent 7 X 7 fuel assemblies, five spent 8 X 8 fuS1 assemblies, 260 new 8 X 8 R fuel assemblies, 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 524 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 1
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. Operations Summary.(Continued)
June 1981 Refueling Infci.Jation
[
Unit 2 (Continued)-
pool. - The present available storage capacity of th'e spent fuel pool is 160 locations. With present capacity,'the 1979 refueling was the last refueling i-that-could be discharged to the spent fuel pool without exceeding that capacity and maintaining full core discharge capability in the pool. However, 949 new 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 schedu{ed 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 unit station transformer tie-in, and torus modifications.
There are 764 fuel assemblics presently in the reactor vessel. There are 124 discharged cycle 3 fuel assemblies,-144 discharged cycle 2 fuel'assemblics, 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 Time 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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r Significant Operational Events Unit'2.
' Date Time ! -
Event 7/01/81- 00015 Reactor thermal power at 99%, maximum ' flow,-. rod .
limited (sequence "B"). . .
1140 Commenced reducing' thermal power due to high con-
' censer back. pressure.
fl300 Reactor thermal power at 93%, holding due to high condenser back pressure.
-1405 Commenced power ascension from 93% thermal power.
1500 2eactor 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 flow, rod limited.
. 7/03/81 2200: Commence'd reducing thermal power to remove."C" RFWP from service for maintenance (leaks).
2235 yeactor thermal power at 73%, holding for. maintenance on'"C" RFWP.
7/04/81 0540 "C" RFWP back in service, commenced power ascension from 73% thermal power.
0700 Commenced PCIOMR from 97% thermal power (sequence "B")-
0900 Reactor thermal power ac 99%, maximum flow, rod limited.~
2240 Commenced reducing s'ac el nower for control rod pattern adjustme~
.- 7/05/81 0200. Reactor thermal gow e. s 72%, holding for control. rod pattern adjustmout.
0230 Control rod pattern adjustment complete, commenced power ascension.
l 0330 Commenced PCIOMR from 77% thermal power (sequence "B") .
. 7/06/81 0215 Reactor thermal power at 99%, maximum f;pw, rod limited.
7/07/81 0110 Commented reducing thermal power due to Xenon burn up.:
1108 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
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for maintenance on EllC system, '"2A" control valve leak.
2347 Reactor Scram, Manual, No. 121. from 45% thermal power to accommodate maintenance of. EllC "2A" control valve.
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, . 7 Significant Operational Events Unit 2 Date Time Event 7/08/81 0740 EHC maintenance completed, commenced rod withdrawal for startup.
1027 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 poser from 9'/% for con-trol rod pattern adjustment.
7/11/81 0030 Reactor thermal power at 64%, holding for contr91 rod pattern adjustment.
D145 Contr"' rod pattern adjustment completed, commenced power accension.
2200 Commenced PCIOMR from 86% thermal power (sequence "B").
2240 Commenced reducing thermal power from 87% thermal power to remove "C" RFWP from service for maintenance on non-return valve.
7/12/81 0150 Reactor thermal power at 79%, holding for osintenance on "C" RFWP non-return valve.
0845 "C" RFWP back in servicc, commenced power ascension.
1001 Commenced PCIOMR from 94% thermal power (sequence "B").
2200 Reactor t'hermal power at 99%, maximum flow, rod limited.
7/15/81 0100 Commenced' reducing thermal power for cooling tower
'- operation.
0125 Reactor thermal power at 87%, removed Unit 2 from cooling towers.
0140 Commenced power ascension from 87% thermal power.
0400 Reacrer thermal power at 99%, maximum flow, 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 rod' pattern adjustment complete, commenced power ascension.
0230 Commenced PCIOMR from 83% thermal power (sequence "B").
2045 Reactor thermal power at 99%, maximum flow, rod limited.
7/20/81 1400 "B" recirculation pump tripped (maintenance error),
reduced thermal power to 59%.
1425 "B" recirculation pump back in service, commenced power ascension.
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Significant Operational Events-Unit 2 Date- Time Event 7/20/81 2200 Reactor thermal power at 99%, maximum flow rod limited
'7/25/81 '0025 Commenced reducing thermal power for turbine con-trol valve tests and SI's.
0100 Reactor thermal power at 85%, holding for turbine control valve tests and SI's.
0135 Turbine control valve tests and SI's complete, commenced power ascension.
0230 Commenced PCIOMR from 95% thermal power (sequence "B").
0500 Reactor thermal power at 99%, maximum flow, rod limited.
2300 Reactor thermal power at 98%, limited by high con-denser back pressure.
7/28/81 0328 Reactor Scram No. 122( from 98% thermal power due to "2A" main transformer sudden high pressure.
1545 C.ommenced rod withdrawal for startup.
1820 Reactor Critical No. 135, holding for "2A" transformer maintenance completion (bushing change out) .
7/29/81 0700 Reactor thermal power at 10%, holding for turbine maintenance.
7/30/80 1300 Reactor tiiermal power at 16%, holding for transformer maintenance.
1715 Rolled T/G.
1801 Synchronized generator. Main turbine tripped from suddenpressureon"A"maintrgggformer.
2156 Reactor Scram, manual, No. 123 from 16% thermal power for maintenance on "2A" main transformer and to place the unit on spare transformer.
7/31/81 1232 Commenced rod withdrawal for startup.
1330 Reactor Critical No. 136, 2145 Rolled T/G.
2219 Synchronized generator, turbine tripped, PCB 5244 tripped "2A and 2B" main transformer differential relays operated. (Reactor thermal power holding at 14%).
2400 Unit remained oft line 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 te'ts and SI'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 pattern adjustment completed, commenced power ascet 31on.
0700 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 RllR pump. Apparent low breakdown voltage between phases on pump motors.
0230 Reactor thermal power at 97%, holding due to 3C RilR pump problems.
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 thermal 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 pattern adjustment.
2200 Reactor thermal pcwcr at 84%, holding for control rod pattern adjustment.
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-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's.
2400 Reactor thermal power at 85%, holding for turbino 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 99%, 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 Reactor Scram, Manual, Nc. 100 from 35% thermal power to swap transformers and for maintenance on torus H 0 SamP l e valve.
22 7/31/81 2400 Unit remains down for maintenance to torus H 0 22 sampic valve.
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AVERAGE DAILY UNIT POWER LEVEL :
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DOC'*ET NO. 50-259-
, UNIT. - Browns' Ferry --
DATE 8--l-81 ,
COMPLETED BY Mike Chapman TELEI'llONE 205-729-6846
, MON 111 'Julv DAY . AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net i ' (Mwe. Net)
-I' -5 g7
-7 2 -6 33 -7 3- -6 -7 39 4' -6 20 -8 5
-6 -8 21
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7 -7 23 -7 8 -8 24 -7 9 -7 -8
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15' -7 * -8 3i g g, -7 3 INSTRUCTIONS ,
On this format. list the average daily unit power leselin MWe Net for each tiay in the reporling month. Compute to
.- the nearest whole ineEdwall-
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- AVERAGE DAILY UNITPOWER LEVEL '
DOCKET NO. 50-260~
UNIT ' Browns Ferry,- I-DATE 0-1-01 ~
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CdN1PLETED BY Mike Chapman- -
.TELEPl!ONE .205-729-6846
~ 510NTil July J.
DAY AVERAGE DAILY POWER LEVEL - DAY AVER AGE DAILY POWER LEVEL .
(SIWE NetL- (SlWe Net) g 1031 g7 1032 2 1034 g3 1021 3L 1033 9 987' 4 954 ,
20 1018 '
,e 54 910 21 1044' 6
1048 ... 1045 i 993 1043 7 23
=-
-g 144 24 1045 9- 792 25 1024
-4 10 989 26 1032 II 848 27 1030 h 12 965 23 129 13 1038 '29 -15 34 1050 30 -16
! 3 3 .- 1037 -16 33 16 1044 i
4 INST 11UCTIONS On ilus forittat. list the .ncrage daily unit power lesel in NIWe-Net foi cath day in .the reporting inonth.Gunpute to
. the nearest whole inepwait.
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D'OCKET NO. 50-296 '
b' UNIT Browns Ferry - 3';
D TT . 8-1-81
- l. ' COMPLETND 3Y ~ Mike Chapman TELEPilONE . 205-720-6846 t;
l MONTil July t-DAY AVER AGE DAILY POWER LEVEL - liAY AVERAGE DAILY POWER LEVEL l (M We-Ne!) (Mwe. Net )
e-g- 1034 ,7 1012 2- 1051'- g3 .1005 3 _1073 g9
-1020
-4 1045 >
1030 20 5 1047 1033 21 1052 ^^
6 1034 -7 7 1045 1033 73 g 1049 1035 24 9 _
1040 y. . 1023 10 1038' 26 1029-11 1033 27 1031' I2 1034 10 S4 2S 13 : 1036 1020 9
34
'1032 932
- I5 1011 y, -13 g g, 1030
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j INSTRUCTIONS .
- On this fortuatolist the aserage daily unit pours lesel ni MWe Net for each day in the reporting in unli. Compute to
. the neare>t whole megawatt'.
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OPERATING DATA REPORT DOCKET NO. : 50-259.
DATE 8-1-81 COh!PLETED BY Ted Thom
~ TELEPl!ONE . W -729-6846 J0PERATING STATUS
- Bro m h y - L h es
- 1. Unit Name:
'2. Reporting Perio'd: July 1981--
3293
- 3. Licensed Thermal Power (51Wt):
E L 4. Nameplate Rating (Gross SIWE)i 1152-1065
- 5. Design Electrical Rating (Net SIWE):
6.' 51aximum Dependable Capacity ' (Gross 51We):' 1098.4
- 7. Stasimum Dependable Capacity (Net SlWe):
1065'
. 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report.Gise Reasons:
NA' 9.' Power Level To Which Restricted. lf Any (Net alWe): NA
- 10. Reasons For Restrictions.If Any: NA ,
=.
This 5tonth Yr. to.Date Cumulatis e ,
11; Ilours In Reporting Period' 744 5,087 61,369 !
0 2,384.4 37,190.97
- 12. Number OfIlours Reactor Was Critical
- 13. Reactor Reserve Shutdown llours 0 16.42 5,115.29 -
- 14. linurs Cenerator On.Line 0 2,380.77 36,373.59
- 15. Unit Reserve Shutdown llours 0 0 0-
. 16. Gross Thermal Energy Generated (51Wil) 0 7,425,495 100,717,856
- 17. Gross Electrical Energy Generated (5thil) 0 _ _ _ , , ,
2,474,200 33,237,490
- 18. Net Electrical Energy Generated (SlWil) 0 2,437,849 32,271,666 .
- 19. ' Unit Senice Factor 0 _ 46.8 59.3- -
- 20. Unit Availability Factor 0 46.8 59.3
- 21. Unit Capacity Factor (Using 51DC Net) 0 44.4 49.4
. 22.iUnit Capacity Fact 6r (Using DER Net) 0 44.4 49.4 18.0.
23; Unit Forced Outage Rate ' O 0.8 _
11
- 24. Shut' downs Scheduled over Nest 6 5tonths(Type. Date,and Duration of Eachl:
- 25. If Shur Down At End Of Report l'criod. Estimated Date of Startup: September 6, 1981
- 26. Units in.rht Status (Prior to Commercial Operationl- Es.es git.w INilIT L CRillCA Lil Y INITI A L El.ECTillCITY CO31\lERCI AL OPI'R ATION e
3 p:/77)
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Oi' Ell AllNG DA TA 111.1 Oft i Don:h r NO 50-MO isAIE 8 _l -11__
COMPl.1:I L D liY (:ba pm:m g Etrpigo3g .lills:72F6846 205-OP!'It .\1ING ST VI US
!. Unit Name: Hro m Ferr,y_- 2 N"f"
- 2. Iteptittutg l'eliod.
3.1.is ensed 't hermal Power (Mht i: 3;L93 _
- 1. Nameplate Rating IGrow MWe). 1152
- 5. Ilesign ElectricalItating (Net SIWep 1065
- 6. Masimum Dependable Cagucity IGrow MWen 1098.4 7 Masimum 1)crendable Capacity (Net Mhe): 1065 3
If Changes Occur in Capacity Ratings litems Number 3 Through 7) Smee I.ast Iteport.Gise Reasons:
'J A
- 9. Power Lesel ro hhich Restricted. lf Any (Net MWe): NA
- 10. lirasons For itestrictions. If Any: NA This Month Yr..to Date Cumalatiw II. l!-os in Reporting Period 744 5,037 56,280 '
- 12. Nomher Of Iloon Itcactor was Cruieal 702.92 4,460.53 35,:'04. ] 4
- 13. Reactor llesenc Shutdown floon '4'. 03 __
598.10 13,051.58 14 lloun Generator On.Line 634.72 4294.51 34.035.47 15 linit liesene Shutdown llours 0 0 0 lb. Giow t heim:il Encip Generated IMWill .I,966,354 13,_l8_9,418 07,ggi,327 ~
17 Gloss I !cs t ical 1:ncrg) Generated IMWil) 654,140 4.402,870 12,140,056 1% Net Electricallner;;) Gentiated (Mh t!) b31,506 4,273,003 31,223,310
- 19. IJnit Senice l~attor 3 84.4 60.5 20 l.' nit Asadaluht) I acto, 35.3 84.4 60.5
- 21. Unit Capacity I actor aUsing MI'C Nerl 79 7 78 9
/9.7
_52.I 2.' Unit Capacity f actor Ithing Df R Net) 78.9 52,1
- 23. Unit l'orced Outage Rate 14.7 6.3 30.3
- 24. Shutdowns Schedulsd User Nest 6 Months f l y pc.1) alt, and I)pration of 1.sch t 25 If Shut Down At i nd Of iteport Period. litimatcJ Date of'Stjetop: 8-18-81 26 Units in lest Status ll%r to Commeiei.it Ops ratmnt force.nt Acha wd ISill \ L CitillCAll! Y INill AL Cl.l Citt! CIT Y COM\lERCITI. OPTR AllON .
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OPERATING D' ATA REPORT -
DOCKET NO. 50-296
-DATE'8-1-81 _
COMPLETED IlY. Mike Chapman-TELEPIIONE 70's-729-6846'
- OPERATING STATUS :
Browns Ferry - 3 Notes L 1. Unit Name:
- 2. Reporting Period: July.1981
- 3. Licensed Thennal Power (MWt): 3293
- 4. Nanteplate Rating (Gross MWe): 1152 ,
. S. Design Electrical Rating (Net MWe): 1065-6.: Maximum Dependable Capacity (Gross MWe): 1098.4
- 7.- Maxinuun Dependable Capacity (Net MWe): 1065
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report.Give Reasons:
NA
- 9. Power Level To Which Restricted.lf Any(Net MWe): .' NA
- 10. Reasons For Restrictions,if Any: NA This Month Yr.-to Date 2umulative 744 5,087 38,735 11.^ !!ours in Itepor ting Period .
- 12. Number Of Ilours Reactor Was Critical 719.83 4401.71 30,372.98
- 13. Reactor Reserve Shutdown llours 24.17 229 '9 2040.28 *
- 14. Ilours Generator On Line 719.83 4,308.75 29,698.75 0 0 0
- 15. Unit Resene Shutdown llours
,. 16. Gross Thermal Energy Generated (MWil) 2,352,434 13,223,592 87,588,620
- l
- 17. Grow Electrical Energy Generated (MWil) 767,230 4,388,470 28,927,500
- 18. Net Electrical Energy Generated (MWII) 742,482 4,255,097 28,079,420 .
)
- 19. Ur.it Senice Factor 96.8_ 84.7 76.7
- 20. Unit Availability Fa-:or 96.8 84.7 76.7 -
-21. Unit Capacity Far.or (Using MDC Net) 93.7 78.5 68.1
- 22. Unit Capacity raetor IUsing DER Net) 93.7 78.5 68.l 23; Unit Forced Outage Itate 3.2 7.6 _
9.5
- 24. Shutdowns ' heduled 4,ver Next 6 Months (Type. Date.and Duration of Eachi: .
Maintinance September 1981
~
.25, if Shut Down At i. d Of iteport Perio I, Estimated Date of Startup: 8-2-81 26, Units in Ttst Status IPrior to Conunercial Operationi: Forceast Achiesed INillAL CillTICALITY INITI A L El.ECTitlCITY COMMEllCI \ L OPEll ATION
- - 11 (9/77)
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.t DOCKET NO.
50-259 UNIT SliUTDOWNS AND POWER REDUCTIONS . lircuns Ferry - 1
> UNIT NAME
$ DATE 8-1-81 if July COMPLETED BY Mike Chan-nn REPORT MONT11 205-729-6846 fy TELErl!ONE J
"t
! -, .! ? 3 .5 Licensee ,E-( %
r;.3 Cause & Corrective Action to 1l N' e . Ihte i 33 4 .= i 5 Event 7 l
3E 5 jgg Report EU j' Prevent Recurrence i,m 6
r, 1 172 1 7/01/81 S 744 C 2 EOC-4 Refuel Outage ij g, (Cohtinued)
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F: Forced Reason: Method: Exhibit G -Instructions S: Scheduied A-Equipment Failure (Exp!ain) 1-Manual for Preparation af Data B Maintenance of Test 2 Manual Scram. Entry Sheets for Licensee C-Refueling 3-Automatic Scram. Event Report (LER) File (NUREG-D Regulatory Restriction 4-Other ( Explain) 0161)
E Operator Training & License Examination F-Ad minist ra ti .e 5 G-Operational Er ror (Explain) Exhibit I - Same Suuree
(*)/77) Il-Other (Explain)
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DOCKET NO- 50-260 i UNIT SliUTDOWNS AND POWER REDUCTIONS UNIT NAM E Browns Ferre - 2
.) CATE 8-1-81 1 rh,,-,n July COMPLETED BY sH b REPORT MON 111 P1DNE 205-729-6846 e .
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-, j 'f 3 Y Licensee [=g h., Cause & Corrective No . - D.n e -
3g 4 jjs Esent g7 g? Action to r J :-
y 3 g, =S Report r mO y v
V Pre ent Recurrence
$ 5 195 7/03/81 F B Derated for "C" RFWP maintenance (leak:
i l' 6 3
'/04/81 S B Derated for control rod patter ,.
197 7/07/81 F 16.75 B 2 Reactor scrtm to accommodate mainte-nance on "2A" EHC control valve. r os 198 7/18/51 S B - ,
Derated for control rod pattern adj.
199 7/20/81 F G Derated because "B" recirce.2ation pump tripped (maintenance erro -) .
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 l transformer.
l An attempt sulted in a turbine trio at to start'11 2219/7 re J l 3 J 2 .
F: Forced Reason: Method: Exhibit G-Instructions 5: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B Maintenance of Test 2 Manual Scram- Entry Sheets for Licensee C-Refueling 3-Automatic Scram- Esent Report (LFR) File (NUREG-D Regulatory Pscstriction 4-Ot her (Explain) Ol'I)
E-Operator Trainin;; & License Examination F-Admin: strati.e 5 G-Operational Error (Explain) Exl . bit I - Same Source 19/77.' il-O:her (E xplain) 4 m
r, .. .
I DOCKET NO. 50-296-UNIT SliUTDOWN. 4ND POWER REDUCTIONS Browns Ferry -3 UNIT N A*.!E r DATEM R 1 Ri~ >
COMPLETED BY Mike Chan"'" '
REPORT MONTil Julv ,YLEI'llONE ?ns_7?o AR!16~
g g .
.5? 3 4YIi Licensee 5-tj j%. '
Cause & Corrective -
No. Date
- -- 3g i jqy Event 3' e'? Action to H j5 Report
- mL Prevent Recurrence
- l. E g di, ]' ~
I 6
~
84 7/30/81 F 24.17 B 2 Reactor scram to swap transformers and maintenance on. torus:H22 0 SamPle val ~e ..,
% 4 Af A-
?i d'
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- '; I 2 3 4 ..
Fi forced Reason: Method: .
Exhibit G-Instructions i' S: Scheduled ~ A Equipment Failure (Explain) 1-Manual for Prepiration of Data B-Maintenance or Test . 2-Manual Scram. Entry Sh< cts for Licensee -
C-Refueling L . 3-Automatic Scram. Event Report (LER) File (NUREG- ,
D-Regulatory Restriction . 4 O her(Explain) 0161)
, E-Operator Training & License Examination
- i F-Administrative .
-5 G-Oper:.tional Error (Explain) . Exhibit I Same Source"
[ (9/77) Il Other (Explain) i'
- s
+
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, DROt:NS. FERRY NUCLEAR PLANT UNIT 1, 2 l
' INSIRUm.NT MAINTE!WiCE SUICIARY CSSC E.)UIP:FJT . . FOR . Ti!E MONTil 0F July 19 81 -.
I:ATURE EFFECT 0:i SAFE CAUSE ACTION TAKEN,
- l'. ATE SYSTCI CO
- i?ONEUT OF OPERATION 07 GF RESULTS OF .TO' PRECLUDE PAIRTENANCE THE FF. ACTOR _
MALFUNCTION MALFUNCTION' e RECURRENCE Tnit 1 i'-3 Residual TE-74-95 Replace None Faulty RTD Alarm Would Not Clear None 5
l Heat Remova:. .
g l
l'-3 Reactor FT-69-60 Calibrate None Zero Shift. False Flow Ind. ~None Nater '
Cleanup l '- 7 Control Rod 3A-PS6 Replace None Faulty Power Fuse _ Blew None-
! Drive Supply
- ' Control Rod PI-85-66A Replace None Gage Damaged- Would Not Indicate None '- g--
Drive .. , Correct Pressure 7-16 Rod Position Probe 02-27 Replace None Faulty Reed Incorrect Rod Positior, None Information 06-25 Switch Indication . '
18-31 -
'22-39 26-31 -
26-39 l 34-23 ,
34-47 38-27' 42-23 l 40-55
- 50-35 58-19 <
- Init 2 Primary PDT-64-138 Calibrate None Zero Shift Did Not Agree with None (F-2 '
Redundant-l Containment
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r,ROWNS FERRY IWCLEAR PLAST : . UNIT 3 INSTRU11ENT !!AI:iTENANCE SUl:21ARY CESC TObIP'4E','T FOR TIls MO:nII 0F July 19 81' KA'IU?2 - EFFECT ON SAFE CAUSE . ACTION TAREi MTE SYSTEM Ct41rCGE;T ~
OF OPERATIO'i 0F- CF RESULTS OF TO PPICLUDE.
MAINTENANCE TliE RF. ACTOR MALFUNCTION PAT.FL7:CTION e RECURRENCE
'Jnit 3 7-9 Emergency FT-67-6B Eeplace None Water in Trans- False Flow Indication None ~,.
Equipment mitter ,
Cooling Water.
Replace Bad Bearings Did'Not Agree with None 7-16 Reactor LI-3-58B None Feedwater Redundant
- ,6
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. _ BROWNS FERRY NUCLEAR PLAST UNIT Common CSSC EQUIP'3ENT MECIIANICAL MAINTETANCE SUMIARY , ,
For the Month of July 19 81 EFFECT OU SAFE ACTION TAKEi.~
DATE SYSTDi COMPCNE:;T NATURE OF OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE
!!AIKTE"ANCE ThiE REACTOR MALFUNCTION E\LFlmCTION RECURRENCE 6-9-81 RilRSW Strainer C Leakage None Bad Packing Strainer C Leaking Replaced Packing TR# 137291 f
'7-16-81 Secondary Door 240 Door will not None 11 cad bolt ; foot Door will not shut Installed new foot Containment shut bolt removed bolt assembly & new head bolt. rod.
TR# 218317 7-11-8] R11RSW Pump A2 Water leak None Float seat torn Lcekage Replaced seat off TP# 234311 7-6-81 Secondary Door 225 Broken head None IIcad bolt broken Door would not close Replaced head bolt &
Containment bolt off ,
properly receiving keeper. ,
TR# 234510 7-6-81 Secondary Door 236 Torn seal need s ,None Seal torn up Unknown Replaced rubber sealw Containment replacing ' -
/ on lock.
. TR# 208782 e
b
~ _ _ -
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BROWNS FERRY NUCLEAR PLANT URIT 1 CSSC EOUIPMEiiT PECHANICAL IGINTEKU!CE SUM'RRY ,
For the Month of July 19 81 EFFECT ON SAFE ACTION TAKEN DATE CYSTEM CCMPCHE;iT NATURE OF OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE MAINTENANCE THE REACTOR MALFUNCTION MALFUNCTION RECURRENCE 7-15-81 Recir. FCV-68-1 Shaft binding None Unknown Binding shaft Oiled and stroked valve.
l TR# 187180 i
'7-19-81 Control 1-31-585 Water Leak None Line broken at Water
- Leakage Solder valve &
Bay Heat joint shortened line.
Vent & TR# 235863 Air Con.
6-20-81 D/G l-B Diesel Gen. Faulty starters 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 w water 3-203,A,B,C, 25'-
~ '
TR# 228377 5-1, 25-6-1 . ,
7-9-81 Sec. Con- Door 233 Missing lock- None No lock on door Door would not lock Installed new lock tainment ,
ing device TR# 232811 7-1-81 CRD CRD-50-31-1-85 Broken wedge None Wedge broken off Saknown Replaced wedge 588 on valve of stem TR# 189967 6-26-811 CRD 1A CRD Pump Leakage None Seal needed Seal was leaking Seal was reset resetting TR# 235946 -
7-13-8) Sec. Con- Door 635 Door will not None Door would not close Adjusted closer &
. tainment '
close tighten screws &
hinges.
TR# 234512 6-28-8; HPCI PL 25-63 Leakage Noac Flow transmitter Leak on' fitting Tighten fitting &
FT-73-33 is bent strengthen tubing.
TR# 225635 1
6 i
s.
ER0tR!S FERRY NUCLEAR PLMIT UNIT 1 CSSC ECUIP: g 7 MECHANICAL luINTEmKCE
SUMMARY
For the Month of Julv 19 81 EFFECT ON SAFE- ACTION TAKEN DAIE SYS TE'd COMFO:3NT NATL"tE OF OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE MAINTENANCE THE REACTOR MALFUNCTION MALFUNCTIOil RECURRENCE _
7-20-81 CRD Modu.le 14-15 Leaking thru Sone Faulty Valve Scram outlet valve Changed out scram leaking inlet valve, , t e floa, seat ring disc.
l l TR# 233024 7-16-81 CRD. liCV-30-31 Valves need None Unknown Unknown Replaced directional llCV-34-47 changing flow valves on Modales modules.
TR# 241108 b
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8 #
1 l
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BROWNS FERRY NUCLEAR PIR.iT UNIT
, 2 CSSC EOUIP"gt:7 MECHAl?ICAL MAINTEIRI;CE
SUMMARY
For the Month of July 19 81 EFFECT ON SAFE ACTION TAKEN CATE SYSTEM CCMPONENT NATURE OF OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE 1%It!TEI!ANCE 'I"dE REACTOR MALFUI CTION MALFUNCTION RECURRENCE
'7-22-81 CRD 2-85-588 Charging water None Unknown Handwhccl missing Replaced handwheel Module 42-51 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 7-20-81 HPCI Condenser Top head seal None Unknown Blown head seal Changed seal on blown top head
,, TR# 233025
'7-12-81 Sec. Con- Equip. Access Lock was stick -None Bent door & lock Prevents interlock Repaired lock adjusted tainment Doors TB & P2 ing & door was sticking from working closure & straightened bent
, door 3 TR# 224893
.7-2-81 Sec. Con- Door 240 Broken door None Door had been Broke flush bolts & Replaced flush bolts 5 tainment hit and broke hold open arm repaired hold open arm bolts & hold & tighten weather open arm. stripping TR# 218600 w
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. BROWNS FERRY NUCLEAR PIANT UNIT 3 CSSC EOUIP!'ENT MECHANICAL MAINTENANCE SU1 DIARY ,
For the IIonth of J"lY 19 81 EFFECT ON SAFE ACTION TAKEN DATE SYSTEli COMPONE.u JATURE OF OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE MAINTENANCE THE EEACTOR MALFUNCTION MALFUNCTION RECURRENCE 7-22-81 Main Steam Pdis-1-50 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 Unknown Blown head gasket Replaced head Compressor gasket
- gaskets TR# 205373 7-13-81 D/C 3C D/G Air Leak off air None Check valve needs Leaking through Installed check valve Compressor #1 cylinder replecing TR# 205170' 7-14-81 RHR 3A & 3C RHR Replace air Pump Motors duct None 3C,RHR Pump Motor To facilitate 3C Installed duct Bad Motor Change-out TR# 233071 6-27-8] Rx Bld. FCV-64-140 Busted seal None Seal busted Leak Replaced bad seal HVAC , ; , TR# 205056 7-1-81 EECW 3A RHit Cooler Vent connection None Unknown Unknown Silver soldered broken connection TR# 232144 5-26-81 Control Bay Board room Dampers out of None Unknown 3A running with Adjusted damper HVAC supply fans adjustment damper closed-3B TR# 235076 3A & 3B not running & damper .
is open e
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- - BROWNS FERRY NUCLEAR PLANT UNIT l'&l Common CSSC EOUIPMENT . ELECTRICAL MAINTENANCE SUmfARY July 81 For'the Month of 19 Etfect on Saic .
Action.Taken Nature of Operation of Cause of Results of To Preclude-Date. Systca Cceponent Malfunction-Maintenance The Reactor Malfunction Recurrenec
~
e7/1/81- CRD Scram accumu- Panel 25-4 Non-reactor was Wire insulation Scram accumulator 'Reparied wire.insu--
, lator low blowing fuses unloaded damaged causing low pressure /high lation, replaced nressure/high a short circuit level alarm annun- fuses, system retur:
eel alarm ciation for~CRD set ed to service.
I' ci.euitry 1 and set 2 inoper- TR #236956
~
l able
-t .
'7/3/81- Fire pro- Annunciation 'While per- None Bad inverter Alarm panel XA The inverter control.
tection circuit on forming SI card 8E panel 9-8 inop- card was. tightened panel 9-8 4.ll.C 354 ernble' .in its slot and the inverter ; began to operate.
for alram The next day while-panel XA . performing SI4.11.CJ 8E-became 3&4 it again became inoperable". f inoperable. .The y-
. control card was replaced.. success-l .
fully tested and l
returned toEservice.
l
, TR #223407
! TR #189950 l ,
LER#BFRO-50-259/813i
~ , 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 connect.or operated properly.
TR'#228381'
+
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- EROWNS FERRY NUCLEAR PL!sNT UNIT 1 & Common CSSC EQUID!EUT ELECTRICAL IMINTE?W?CE SUPDfARY For the Month of July 19 81 Eftect on Saic Action.Taken Nature of Operation of Cause vf Results'of To Preclude D-te Systen Cetponent Malfunction Malfunction Recurrence Maintenance The Reactor FCV-71-2 Broken term- None-reactor Broken teruinal FCV-71-2 was inop- Reterminated motor
' 7/4/81 RCIC leads, performed inal block in cold shut- block erable on valve down EM1 58, 81 and 18, motor valve returned to service.
' TR #187971 8
9 Panel 9-5 ' Broken switch None (this Switch operator The switch would Replaced switch 7/9/81 Reactor not automatically operator, switch control reactor scram doesn't make spring broken return'to normal operated properly, bay panels reset switch the switch inoperabic) ,' TR #223411 Secondary Air lock door Door would , None. Door watch was The door would not Cleaned, a'djusted 5 37/10/81 and lubricated latch, contain- 235 not open - / out of adjust- open ment .
ment performed EMI 8,
! - door operated properg 8
ly. :
TR #241280 l; f TR #223297 i TR #235445 'l :
l l
A2-RHRSW pump Running None Annunciator Received a running Adjusted switch, thei-7/13/81 RHRSW annunciator ,eratedI running annunciator switch was out annunciation when
! annunciator would not of adjustment the pump was off properly. i operator TR #239056'
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. - BRO *GS FERirl NUCLEAR PLANT UM1T I & C'o=aon:.
L CSSC EOUIP!'ENT ELECTRICAL MAINTENANCE SLMfARY For Ge Month'of; July 19 81 -
I e Etiect on Sarc ;
Action.Taken Natise of Operation of ' Cause of Results of To Preclude Dnec System Cc=ponent Malfunction Recurrence M..ntenance The Reactor j Malfunction' ;j
- x
- 7/14k1 ' Air con- 1B control . hiller None Proportional Control' bay chillet ' Adjusted proportion ditioning bay chiller would not controller was would not cool' .al: controller.per il (cooling- cool proper- .out'of adjust- properly -EMI 60,' chiller.. -(!
heating) ly cent operatedproperly.-j!
TR #224905 [:;
i, .
t l7/17/81 250 volt 250 main Cell 98 None Crack in oatter; Required battery tc 'Jumpered out cell L
DC system battery #1 cracked cell 98 .be removed from 9S, adjusted battery;'
service in order charger, battery
. to jumper around returned'to service. .
cell'98 .TR #179952 LERfBFRO-50-259/8142, s
g ;;
.- '7/18/81 Core spray HCV 75-27 "Open" indi- None Limit switch "Open" indicating Adjusted' limit .!
cooling -
cating light was out of.ad- ' light was'inoper- . switch, indicating on panel 9-3 justment able' light operated prop-l '
erly. TR #189979 i inoperable
-j. '
i l;7/26/81 Core spray IB core spray Breaker would -N.ce-reactor' Jack nut mount- Breaker would not. Replaced jack nutL cooling pump breaker not rack in .wa3 unloaded ing bracket was rack in. lB core " mounting bracket, properly bent spray pump inoper- the breaker racked able in properly.
, 'TR #189919 .
1- .
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I;RGWii3 Fr.;;.,- ::::':LT.#.. F1,ANI UNIT -
i' -l !
ELECTRICAL lin.'iTEN/J:CE SUID!ARY
- CSsc E0llIIHrJIT '
l
. For the Month of July- .19 81' l
f,ticct on Sate Action'Taken
' Results of. To Preclude l Nature of ' Operation of I Cau:e of '
? Date. Systce 'Cceponent I '11.'finction Malfunction Recurrence- ]
!!aintenance The Reactei l- . => None Possible ground Received an inad-- Replaced ismoke
'7/7/81 Fire pro- smoke detector An alarm for smoke detec- in smoke detec- vertent alarm' : detector,'alram tection (XS-39-29A) tors in the -tor due to a . cleared and oper--~
relay room pinched wire ated properly.
r .
TR'#224880.
was received '
and would not TR #187159- .
l' : clear -LER#BFRO-50-260/8136E
) !
4kV unit board While attempt- None , Breaker "'B" 4kV shutdown bus 'The breaker contacts 7/8/81 4kV unit were cleaned and boards alternate ing to trans- -finger contacts. was lost for a few feeder breaker fer station failed to make seconds the breaker sucess-service back contact . fully operated. w.
TR #239172 o to. start bus,, '
l 4kV-2B unit board failed to transfer 1 s
' Associated 250V reactor Alarm actuat- ,None Bad coil on Undervoltage alarm ' Replaced ~ relay, per-
- l7/9/81
.g relay 27B formed EMI 23 and
-l clectrical MOV board 2A ed and would inoperable EMI 15, annuncia-i '1 undervoltage not clear tion-operated-'
ll - ialarm circuitry I properly.
- l TR #205760--
a* i TR #236943
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DRG'id - FC;;;;." :::;ct.LA!' it.d 7. ildIT - 2 N CSSC EOUTl?C ;;r . EIECTRICAL 11A1 iTENA! CE SUlW.RY July .19~81.
For the Month of Action Taken Ettect on Salc ~Results of To Preclude Nature of Operation of Cause of Dr.t c System ' Cceponent 11alfunction Malfunction' !R1currence.
Maintenance The Reactor 2 . .
_Replacediflow'svltch;-
7/16/81 Air condi- Flow switch Received None Bad flow switch Flow switch inop-
'tioning for 250V annunciation 31-174- erable... vent fans, flow switch operated' (cooling- battery board XA-31-174 operated abnormal properly. ,
heating) room ventila- TR.#239224 i-tion l
l RHR Limit switch Indicating None Loose limit Indicating light -Tightened switch
'l7/26/81 on HCV-74-11 light circui- switch actuator circuitry to panel' actuator, indicat-tiry inoper- 9-3 inoperable ing' lights operated
. able- properly. ,
TR #239205 ,
~
Local push button Cleaned and dried W
l7/27/81'RHR Local control Local control None' Water in switch switch switch inop- housing corroded control switch switch and housing,
- l. erable contacts inoperable valve operated'
- g. . properly.
a TR #239073 l'
l
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I;i:GWi'3 Fr.i'.;;.' :.CLL:./.c l'L.::.'I i.3IT 3_ . t cg s c notirlti: n r CLECTRICAL f ul!! TEN /J CE SU!O').RY ,
For the Month of July 19 81 Action Taken direct ca Saic e
Cause of Results of To Preclude Systce Cceponent !bture of Oncration of Recurrence Tiic Reactor Malfunction :talfunction l Unte ::aintenance A3 RHRSW pump Nore Circuitry card Received a false 7/1/81 . RHRSW Annunciator Replacedcardrelay,(
circuitry running annun- relay bad " running" annuncia- annunciation opera-card ciator was tion ted properly.
.' actuated with TR #205600 pump off s
! SDF1 relay was 1 Diesel D/G 3C, SFD1 During per- None Rel$y, timing Relay SDF1 tested l I
was slightly out too long. recalibrated and l7/6/81 generator relay formance of redundant ;'out of toler- successfully tested-start test ance SFBI was changed (EMI 3) relay out by mistake, SDF1 tested calibreted and d i e out too long.' ,
successfully tested.
TR #183840 l .
I
) .
TR #186847 BFRO-50-296/8133 I.
l J
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CSSC FQti T I':i; ;; r ELECTI:ICAL tiilt;TENA:;CE SU;2:/.RY For the I;onth of July 19 81 Ericct on Sate Action Taken Nature of Operation of Cause of Results of To Proclude Date System Co=penent Malfunction Malfunction Recurrence t Itaintenance The Reactor 7/9/81, RHR RHR pump RHR pump Unit in limit- Motor failure. T.HR heat 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.
8 I
overcurrent (TS 3.5.B.3) potential tests TR #204460 failed. Cause TR #186901 of failure will TR #190658 l be investigated TR #186902 i upon motor LER#BFRO-50-296/8134 repairs l
7/15/81 Annuncia- A D/G Recieving None Bad annur. cia- Received a false Replaced relays on tor 6 annunciator false tion card 3-A RHRSW pump annunciator cards g i sequen- panel annunciatiod , relays running and D/G for both D/G lube w l tial . 3A engine lube oil oil and RHRSW pump, I events . trouble annuncia- annunciators I tion operated properly.
i j 7/23/81 Contain- FSV-76-67 H 22
"" '~ """ ""' '" -
22 analizer E The solenoid assem-ment zer B inop- a limited oper- solenoid assem- inoperable bly was replaced atmos- erable ating condition bly was grounded on FSV 76-67 and I phere the H 0 analizer 22
- monitor- returned to service.
1 ing ..,, TR #204456' l TR #204937 TR #204938 -
TR #129379 BFRO-50-296/8137 e
t
7 n --
34 OUTAGE
SUMMARY
July 1981 The maintenance and modification activities for the month of July included continuing the Unit 1, Cycic 4 refueling / torus outage with major emphasis concentrated on the following:
- 1. Torus internal and external modifications. 4
- 2. LPC1 modification.
- 3. H0 analyzer / sample pump modification.
22
- 4. IIP turbine reassembly.
- 5. Reactor feedpump turbine maintenance.
- o. Generator breaker modification (P0214).
- 7. IB reactor feed pump reassembly. (Complete).
- 8. Core reload.
. 9. Local leak rate testing on selected valves.
- 10. Maln steam isolation valve maintenance (repair of ID l
damaged stud still required.)'(Complete).
- 11. Condenser grating installation (P0379).
- 12. Control bay fire doors (P0464).
i l 13. Unit station service transformer modification.
1
- 14. Oil flush on the llP and LP turbines (Completed July 2,, 1981).
l
- 15. Recirculatior. MG set and pump maintenance (Completed July 6,1981).
L.
- 16. PCIS modification (P0291).
- 17. Condensate short cycle modification (PO434) .
- 18. 'CRD cross tie installation (P0353) l Th'e duration for the unit 1 cycle 4 refueling outage has been revised to 148 days based on completing torus internal modifications which delays the r.--
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.
6 -
-i .
. 35 OUTAGE SUFMARY (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 ur,it 1 offgas system piping. The examination will look for possible cracks caused by acidic compounds resul?ing from the decomposition of domineralizer resin in the reactor vessel.
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