ML20100M054
| ML20100M054 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 10/31/1984 |
| From: | Jones G, Thom T TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| NUDOCS 8412120200 | |
| Download: ML20100M054 (28) | |
Text
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TENNESSEE VALLEY AUDIORITY DIVISION OF NUCLEAR POWER BROWNS FERRY NUCLEAR PLANT MONTHLY OPERATING REPORT 10 NRC October 1, 1984 - October 31, 1984 g$
g DOCKET NUMBERS 50-259, 50-260, AND 50-296 r
rd LICENSE NUMERS DPR-33, DPR-52, AND DPR-68
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TABLE OF CONTENTS s
Operations Sumary......................
1 Refueling Information................... '.
3 Significant Operational Instructions.............
5 Average Daily Unit Power Level................
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Operating Data Reports....................
12 Unit Shutdowns and Power Reductions.............
15 Plant Maintenance......................
18 Outage Maintenance & Major Modification...........
23 p-D Y
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Onerations Summary October 1984 The following sumunary describes the significant operation activities during
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the reporting period.
In support of this stannary, a chronological log of significant events is included in this report.
There were five reportable occurrences and no revisions to previous reportable occurrences reported to the NRC during the month of October.
Unit 1 There were no scrams on the unit' duri'ng the month.
Unit 2 The unit was in cold shutdown the entire month for the unit's end-of-cycle 5 refueling outage.
Unit 'l The unit was in cold shutdown the entire month for the unit's end-of-cycle 35 refueling outage.
Prepared principally by B. L. Porter.
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2 Ooerations %===ry (Continued)
October 1984 5
. Fatinue Usage Evaluation The cumulative usage factors for the reactor vessel are as follows:
Location Usane Factor Unit 1 Unit 2 Unit 1 Shell at water line 0.00611 0.00492 0.00406 Feedwater nozzle 0.29402 0.21319 0.15444 Closure studs 0.23744 0.17229-0.13860 NOTE:
This accumulated monthly information satisfies Technical Specification Section 6.6. A.17.B(3) reporting requirements.
C - n Svglga Approximately 1.35E+06 gallons of waste liquids were discharged containing approximately 6.10E-01 curies of activities.
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Operations m=marv (Continued)
October 1984 Refueling Information Unit 1 Unit 1 is scheduled for its sixth refueling approximately March 22, 1985 with a scheduled restart date of October 8, 1985. This refueling will involve loading 8x8R (retrofit) fuel assemblies into the core, replacing recirculation piping, work on "A" and "B" low-pressure turbine, upgrade hangers and anchors, "
and environmentally qualify instrtmentations.
~
There are 764 fuel assemblies in the reactor vessel'i The spent fue'l stor-age pool presently contains 252 EOC-5 fuel assemblies, 260 EOC-4 fuel assemblies; 232 EOC-3 fuel assemblies; 156 EOC-2 fuel assemblies; and 168 EOC-1 fuel assemblies. The present fuel pool capacity is 3,471 locations.
Unit 2 Unit 2 was shut down for its fifth refueling outage on Septecber 15, 1984 with a scheduled restart date of January 31, 1985. This refueling outage will involve loading additional 8X8R (retrofit) fuel assemblies into the core, finishing torus modification, turbine inspection, piping inspection, TMI-2 modifications; post-accident sampling facility tie-ins, core spray change-out, and feedwater sparger inspection.
There are no fuel assemblies in the reactor vessel. At month end, there were 764 EOC-5 fuel assemblies, 248 E00-4 fuel assemblies, 352 EOC-3 fuel assemblies,156 EOC-2 fuel assemblies, and 132 E0C-1 fuel assemblies in the
- spent fuel storage pool. The present available capacity of the spent fuel pool is 406 locations. All old racks have been removed from the pool and new HDR's are being installed.
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Ooerations S'==arv (Continued)
October 1984 Unit ~4 S._
Unit 3 shutdown for its fifth refueling outage on September 7, 1983, with a scheduled restart date of November 10, 1984. This refueling involves loading 8X8R (retrofit) assemblies into the core, finishing the torus modifications, postaccident sampling facility tie-in, core spray change-out, 1NI-2 modifications, turbine inspection, piping inspections for cracks, and changeout of jet pump hold-down beams.
There are 764 fuel assemblies presently in t'he reactior vessel. There are 248 EOC-5 fuel assemblies, 280 EOC-4 fuel assemblies,124 E0C-3 ftel assemblies, 144 E0C-2 fuel assemblies, and 208 EOC-1 fuel assemblies in the spent fuel storage pool. The present available capacity of the spent fuel pool is 914 locations.
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5 t-Sinnificant Ooerational Events Date Time
- Event Unit 1 10/01 0001 Reactor thermal power at 100-percent- (5), maximum flow, rod limited.
10/02 1400 Comenced reducing thermal power due to condensate demineralizer problems.
1415 Reactor thermal power at 80% due to condensate demineralizer problems.
1420 Comenced power ascension from 80% themal power.
1445 Reactor thermal power at 96%, holding up on PCIOMR until TIP run is complete.
1830 Comenced.PCIOMR from 96% themal power.
1939 Reactor thermal power at 100%, maximum flow, rod limited.
10/06 0004 Comenced reducing thermal power for SI 4.3.A.2 (Control Rod Drive (CRD) Exercise).
0014 Reactor thermal power at 96% for CRD exercise.
0230 Comenced PCIOMR from 96% themal power.
0400 Reactor thermal power at 98% "R" factor out-of-limits'.
2330 Comenced PCIOMR from 98% thermal power.
10/07 0100 Reactor thermal power at 100%, maximum flow, rod limited.
10/13 0145 Comenced reducing thermal power for SI 4.3. A.2 (Control Rod Exercise).
0200 Reactor thermal power at 95% for SI 4.3. A.2.
0320 SI 4 3. A.2 (Control Rod Exercise) complete, comenced-power ascension.
1500 Reactor thermal power at 100% maximum flow, rod limited.
10/19 1955 Comenced reducing thermal power for control rod pattern adjustment.
2400 Reactor thermal power at 625 for control rod pattern adjustment, increasing thermal power.
10/2n 0925 Control rod pattern adjustment complete, comenced power nacension from 775 thermal power.
1030 Comenced PCIOMR from 80% thermal power.
10/21 0630 Reactor thermal power at 100%, maximum flow, rod limited.
1800 Reactor thermal power at 99%, maximta flow, rod limited.
2110 Comenced power ascension from 99% thermal power.-
2200 Reactor thermal power at 100% maximum flow, rod limited.
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i Significant Operational Events Date Time Event Unit 1 (Continued) 10/22 2300 Reactor thermal power at 995 maximu:r flow, rod limited.
10/23 0030 Comenced power ascension from 995 thermal power.
0100 Reactor thermal power at 100%, maximum flow, rod limited.
10/26 2202 Comenced reducing thermal power for SI 4.3.A.2 (CRD Exercise).
2400 Reactor thermal power at 76% thermal power for SI 4.3.A.2.
10/27 0340 SI 4 3.A.2 complete, comenced power ascension.
0430 Comenced PCIOMR from 785 thermal power.
10/28 0800 Reactor thermal power at 100% maximum flow, rod limited.
0830 Reactor thermal power at 995 due to Xenon burn-out.
Comenced PCIOMR.
1000 Reactor thermal power at 100%, maximun flow, rod limited.
10/29 0600 Commenced reducing thermal power for removal of "A" reactor feed water pump (RWP) from service for maintenance.
1002
^ Reactor thermal power at 75%, "A" RWP out-of-service for maintenance.
1300 Reactor thermal power at 69% for maintenance on "A" RWP.
1345 Maintennace complete on "A" RWP, and pump back in service, commenced power ascension.
2200 Reactor thermal power at 100% maximum flow, rod limited.
10/31 2400 Reactor thermal-power at 100% maximum flow, rod limited.
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7 Sinnificant Operational Events Date Time Event Unit 2 10/01 0001 End-of-cycle'5 refuel outage continues.
10/31 2400 End-of-cycle 5 refuel outage continues.
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8 Significant Ooerational Events Date Time Event Unit 3.
10/25 2147 End-of-cycle,5 refuel outage complete. Unit startup on hold due to NRC concerns.
10/31 2400 Unit stariup on hold due to NRC concerns.
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9 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-259 UNIT' s Ferry 1 DATE 11-01-84 COMPLETED BY T. h TELEPHONE f7051 729-3R34 MONT11 October 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILYPOWER LEVEL (MWe-Net)
(Mwe. Net)
I-1052 g7 ins) 2 1051 gg insg 3
1061
'995 39 4
1065 20 R17 5
1050 21 1043 6
1035 22 1060 7
106?
23 1055 8
1062 24 1072 9
1053 25 1051 1068 10 26 1036 11 inso
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27 R93 12 1064 28 1034 13 1048 29 997 14 1053 30 1073 15 1056 3
1061 16 1060
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INSTRUCTIONS On this format. list the average daily unit power level in MWe-Net for each day in the reporting month. Compu the nearest whole megawatt.
(9/77)
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10 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-260 UNIT' Emwns Ferry 2 DATE ^ 11 R4 COMPLETED BY T 'Thern TELEPHONE (205) 729-3834 MONm October 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL
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(MWe-Net)
(MWe-Net)
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-8 17.
-6 2
-8 18
-6
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-8 39
-8 4
-8 20
-7 5
-8 21
-8 6
-R 22
-8 7
-8 23
-8 8
R 24 7
9
-8 25
-8
-8 10 26
-7 II 7
27
-8
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-8 28
-8 13
-R 29
-8 14
-8
-7 30 15
-7 3g
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INSTRUCTIONS i
On this format, list the average daily unit power lesel in MWe Net for each day in the reporting month. Compute to the nearest whole megawatt.
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11 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-2 %
UNIT a Ferrv_3 DATE :11-01-84 COMPLETED BY T. Than TELEPHONE (205) 729-3834 MONTH October DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL
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(MWe-Net)
(MWe-Net)
I
-11 17
-11 2
-12 is
-11 3
-12
_3 g 4
-10 20
-17 5
-10
_g 6
-11 g
_g 7
-11 73
_g 8
-11 24
-13 9
-11 25
-12
-10 10 26
-13 II
-10 27
-12 12
-10
-11 13
-10
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9
-12 I4
-10 30
-11 15
-10 31
-12 16
-11
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INSTRUCTIONS On this format. list the average daily unit power leselin MWe Net for each day in the reporting month. Compu the nearest whole megawatt.
4 (9/77)
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OPERATING DATA REPORT DOCKET NO.
50-259 DATE 11 n1 Ra COMPLETED BY
'P
'Mvun TELEPHONE 9 05) 729-3834 OPERATING STATUS
' l. Unit Name:
ha Fa= Na
- 2. Reporting Period: M h 19R4
- 3. Licensed Thermal Power (MWt):
3293
- 4. Nameplate Rating (Gross MWe):
1152
- 5. Design Electrical Rating (Net MWe): 1%5' W,.. '_'
T. Maximum Dependable Capacity (Gross MWe):
1098.4 6
- 7. Maximum Dtpendable Capacity (Net MWe):
1065
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:
N/A e
(Net MWe):
N/A
- 9. Power Level To Which Restricted. If Any/A
- 10. Reasons For Restrictions,If Any:
N This Month Yr.-to Date Cumulative -
- 11. Hours In Reporting Period
_745 7.320 89.936
- 12. Number Of flours Reactor Was Critical 745 6.603.48
_56,409.6-
- 13. Reactor Reserve Shutdown Hours 0
700.20 6.485.22 l
- 14. Hours Generator On Line
_745
_.6 458.95
._55 176.59-15c Unit Reserve Shutdown flours 0-0
_0
- 16. Gross Thermal Energy Generated (MWH) 2.424.554 19.981.494 158,539,173~
- 17. Gross Electrical Energy Generated (MWH) 794.160. _....
6.575.690
_52.221.310
- 18. Net Electrical Energy Generated (MWH) 773.750 6.401.898 50,727.225 _
- 19. Unit Service Factor 100 88.2 61.4
- 20. Unit Availability Factor 100 88.2 61.4
- 21. Unit Capacity Factor (Using MDC Net) 97.5 82.1 53.0 22.- Unit Capacity Factor (Using DER Net) 97.5 82.1 53.0 l
- 23. Unit Forced Outage Rate 0
11.4 22.5
- 24. Shutdowns Scheduled Oser Next 6 Months (Type.Date.and Duration of Eacht:
l
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- 25. If Shui Down At End Of Report Period. Estimated Date of Startup:
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- 26. Units in Test Status (Prior to Commercial Operation):
Forecast Achiesed INITIAL CRITICALITY INITIAL ELECTRICITY
- ~
COMMERCIAL OPER ATION l
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07/77)
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OPERATING DATA REPORT DOCKET NO. 50-260
- DATE 11-01 A4 COMPLETED BY
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't1vun TELEP110NE (705) 774-3834 OPERATING STATUS
- 1. Unit Name:
E mi.rm h rv h Notes
- 2. Reporting Period: October 1984
- 3. Licensed Thermal Power (MWt): 3293
- 4. Nameplate Rating (Gross MWe): 1152
- 5. Design Electrical Rating (Net MWe):
1069
- 6. Maximum Dependable Capacity (Gross MWe): 1048 4
- 7. Masimum Dependable Capacity (Net MWe):
1065
~+-
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:
N/A
- 9. Power Level To Which Restricted.If Any (Net MWe):
N/A
- 10. Reasons For Restrictions.If Any:
N/A This Month Yr..to Date Cumulatise I1. Ilours In Reporting Period 749 7170
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- 12. Number Of flours Reactor Was Critical 0
5.895.85
_55,860.03
- 13. Reactor Reserve Shutdown ilours O
300.08 14.200.44
- 14. Ilours Generator On Line
-.0 5.Als-s?
54 11A 36
- 15. Unit Reserve Shutdown flours 0
0 0
- 16. Gross Thermal Energy Generated (MWil) 0 11:100.122 153.245.167
- 17. Gross Electrical Energy Generated (MWil)
O 4.174;510 50.771.798
- 18. Net Electrical Energy Generated (MWH)
O 4,044.370 49,302.973
- 19. Unit Service Factor 0
74 9 64_1
- 20. Unit Availabihty Factor O
79.4 64.1
- 21. Unit Capac'ty Factor (Using MDC Net) 0 51.9 54.8
- 22. Unit Capacity Factor (Using DER Net)
O 51.9 54.8
- 23. Unit Forced Outage Rate O
4.1 3.0 2
- 24. Shutdowns Scheduled Over Nest 6 Months (Type. Date.and Deration of Eacht:
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
Anril l'3. 1985
- 26. Units in Test Status IPrior io Commercial Operationi:
Forecast Achiesed INITIAL CRITICALi1Y INITIAL ELECTRICITY COMMERCIAL OPER ATION N/77) p
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OPERATING DATA REPORT DOCKET NO. 50 94A DATE ll Al-M_
COMPLETED BY T 'Tivun TELErilONE (7051 729-3834 OPERATING STATUS
- 1. Unit Name: Browns Ferry '1hree Notn
- 2. Reporting Period:
October 1984
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- 3. Licensed Thermal Power (MWt): 3293
- 4. Nameplate Rating (Gross MWe): 1152
- 5. Design Electrical Rating (Net MWe): 1065
- 6. Maximum Dependable Capacity (Gross MWe): 1098.4
- 7. Maximum Dependable Capacity (Net MWe):
-.1065
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:
N/A
- 9. Power Level To Which Restricted. If Any (Net MWe):
N/A
- 10. Reasons For Restrictions.If Any:
N/A This Month Yr. to Date Cumulatise
- 11. Hours in Reporting Period 745 7 170 67;24R
- 12. Number Of Hours Reactor Was Critical O
O 41,OR7 RO
- 13. Reactor Reserve Shutdown Hours 0
0
- 3.878.13
- 14. Hours Generater On.Line 0
0 42.,19111
- 15. Unit Reserve Shutdown flours 0
0 0
- 16. Gross Thermal Energy Generated (MWH) 0 0
126.307.71.1_,
- 17. Gross Electrical Energy Generated (MWH)
O 0
41:597;620
- 18. Net Electrical Energy Generated (MWH) 0 0
40.375.256
- 19. Unit Sersice Factor 0
0 62.7
- 20. Unit Availability Factor 0
0 62.7
- 21. Unit Capacity Factor (Using MDC Net) 0 0
56.4
- 22. Unit Capacity Factor (Using DER Net) 0 0
56.4
- 23. Unit Forced Outage Rate 100 100 16.7
- 24. Shutdowns Scheduled Oser Next 6 Months (Type, Date,and Duration of Each t:
- 25. If Shut Down At End Of Report Perimi, Estimited Date of Startup: NmmN
- 26. Units in Test Status (Prior to Commercial Operationi:
Forecast Achiesed INITIA L CRITICA LITY INITIAL ELECTRICITY COMMERCIAL OPER ATION (9/77)
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f UNITSHUTDOWNS AND POWER REDUCnONS DOCKET NO. 50-259 UNIT NAME Rvru.m Ferry 1
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DATE 11-nl.m y
REPORTMONTH October 1984 COMPLETED BY T Thewn l
TELEPHONE (705) 779 '4R'46 I1 3
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Date p
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- g Licensee 5%
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Cause & Correcine e ::
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El Action to
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j5j Report =
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295 10-02-84 F
A Derated for condesate denineralizer problens.
2%
10-19-84 S
H Derated for control rod pattern adjustment.
297 10-26-84 S
H Derated for CRD exercise.
298 10-29-84 F
B Derated for "A" RFWB maintenance.
5 1
2 3
4 F: Forced Reason:
Method:
Exhibit G -Instructions S: Scheduled A-Equiprnent Failure (Explain) 14fanual for Preparation of Data B Maintenance of Test 241anual Scram.
Entry Sheets for Licensee C Refueling 3-Automatic Scram.
Event Repori(LER) File (NUREG-D-Regulatory Restriction 4-Other(Explainn ~
01611 E-Operator Training & License Examination F-Adnunistrative 5
G-Operational Error iExplain t Exhibit I - Same Source 19/77) llother (Explain t I
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UNITSIIUTDOWNS AND POWER REDUCTIONS DOCKETNO. 50-260 UNIT NAME Rrrwma Farru ? ~
DATE ll-01-A4 COMPLETED BY T. h l
REPORTMONTH Octnhor 14R4 TELEPHONE (20s) 729 '4834
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jN'S Licensee
,E-r, ye, Cause & Corrective W.
Date i
3=
4 2i5 Event g'?
E'8 Action to i
H jE j ;f, g Reporr a mU j'
Prevent Recurrence d
i 305 10-01-84 S
745 C
4 EOC-5 Refuel outage (Controlled shudown 9-15-84)
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F: Forced Reason:
Method:
Exhibit G-Instructions S: 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.
Event Report (LER File tNUREG-D Regulatory Restriction 40ther (Explain) 0161)
EOperator Training & License Examination F-Administrative 5
Goperational Error (Explain)
Exhibit i Same Source (9/77) llother (Explain) 1
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4
UNITSliUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50 7 %
UNIT NAME Rr e e h,mr '
't DATE 11 -01 M NFPORTMONTNhnhm 14R4 COMPLETED BY T h un TELEPHONE (205) 729 '4R'M d
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, Ei Licensee j-r, he Cause & Corrective No.
Date g
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-8
$ ',E Action to
$5 j di g Report :
rNO EL Prevent Recurrence H
d 140 10-01-84 S
745 C
4 EOC-5 Refuel outage continues.
(Controlled shutdown 9-07-83) 141 10/25/84 F
122.22 D
Unit startup on HdLD due to NRC Concerns.
C I
2 i
3 4
F: Forced Reason:
Afethod:
Exhibit G-Instructions S: 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.
Event Report t LERI File iNUREG.
D Regulatory Restriction 4-Other I Explain) 0161)
E-Operator Training & Ixense Examination F-Administrative 5
G Operational Error IExplain)
Exhibit I-Same Source 19/77)
II-O:her IExplainI h
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+-
BROWNS FERRY NUCLEAR PLANT UNIT CSSC EQUIPMENT MECHANICAL MAINTENANCE
SUMMARY
For the-Month of October 19 84 EFFECT ON SAFE ACTION TAKEN CATE SYSTEM COMPONENT NATURE OF OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE MAINTENANCE THE REACTOR MAfFUNCTION MALFUNCTION RECURRENCE 3A Diesel Repair Unit 3A None Unknown Diesel generator Replaced l/17/84 82 Generator Diesel Engine was inoperabic turbocharger on MR A-260433 e
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CSSC EQUtt' MENT ELECTRICAL MAINTENANCE
SUMMARY
9/29/82 Dr the >' : ' o f October 19 84
-[
Y.iicci e;. Faic 1
A: t lar.. s aen __
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^ ';a ;:re ni O pe r.s : !an i f Cause.o' Ke.vs'ts of
,DWe Sv:.:e :
C,:.;ione:1:
- >'. in t. :.i:te e The Rea.:or Malfunction Malfuncrian R.=ctarrer. e T.i l'rc. '. :ds -
1984 10/5-Standby 1-ANN-82-C Replace power None Shorted power
~
Annunciators will not Replaced. bad PCB 1
. diesel
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l generator supply PCB
, supply PCB test j
MR 318869-g 10/10, Containment; l-IL-76-49-4
! Replace sample None Leaking pump
.1 psi /3 sec Sample pumps leaking Replaced bad pump inerting -
pump 4
MR 252015 10/25 Air-condit-i 1-AHU-31-1A Replaced timer None pirty contacts, Low flow rate Replaced bad recycle ioning system pad timer timer and cleaned l'
contacts l
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I MR 317936 g
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CSSC EQLf!PMENT ELECTRICAL MAINTEL\\NCE.SDetARi' Appendix B 9/29/82 FOr the.. n : S o -
October to 84 l
!:f f eet en Safe Action
..,en
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' Nature of 5.
Operation of Ca.ise.d Re.,.
t.s o f To Prc.-
do y
' ' ~
Jt"r ir st(n Component Maintenance The Esactor M 'functian Malfunctfon Recurre
.e f984 i
If0/4
! Cranes &
Refuel bridge Replace brake None Burnt brake coil Refuel bridge will Replaced brake coil hoists coil not drive MR 064126-LO/9~
Fire pro- [2-ANN-39-000 Replace PCB None^
Bad card tection g Spurious alarms
- Replaced bad PCE
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. o /2 4lP.'
October
.. 84 e :,
ri 0; s. r.
a:
. :., 3
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t -
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.g g, t.,s t- g
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a, 1984
- 3-HS-76-69 lReplacedswitch'None
--h,._ ; r r g. t ' Bad switch
- Key lock bypass jReplaced switch 10/5 iContain-
~ ment lswitchinoperative iMR168938 jinerting system ~ 10/5 lContain-3-PMP-76-A Install pump None . Defective from t Returned to manu-Replaced cotor/pu p ment motor assembly ' l manufacturer facturer , assembly iI nerting 4 4 j
- MR 141115
- system i
10/13 ; Annunciator 3-XA-55-8D Replace cards None Power supply , Annunciator will not jReplaced cards
- & sequen-j
- cards bad itest tial events MR 320548 a
w . recording j 10/15 a48V dc 3-CHRG-251-B i Replaced fuses None Blown fuses and 4 , Voltage dropped to i Replaced fuses ar.d ' power l and contacts fpittedcontacts j46 volts Icontacts " ' system e j MR 319460 10/17 Annuncia-13-ANN-55-3 Replaced None l Bad inverter j Annunciator will not Replaced inverter tor & inverter test . sequential l. MR 319480 events recording - l .i 10/23 Conta$n-l3-IL-076-0049-4 Replaced pump 'None Bad pump i Sample pump not lReplacedpump cent-l l running inerting ! l MR 303506
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[ -l t 10/28 iStandby i3-MTR-82-B l Installed motor l None ,' Bad compressor
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1984 } 8 i g 6 n,- 7/30 l Control l3-HCU-85-22-11 Replace level fNone
- Switch grounded Gives false high Replaced bad level.
rod drive switch n water level alarm switch I l. !MR 314183' l 8/26 Containment; 3-FMP-76-00A (Replace motor Nonc l jBad pump and motorgTo be returned to iReplaced bad pu:;; j
- inerting I
land pump i gmanufacturer for .and motor e irepair l .MR 130689 j l .8/30 jContainment 3-PMP-76-00B. Replace motor None i ad pump and motor,To be returned to . Replaced bad put; B i i nerting and pump ! manufacturer for . and motor i repair eMR 141431 8 .I e 9/27 .RCIC l3-TS-71-23 iReplaced flex None None
- RelocatedinstrumentsjReplacedflex-g conduit e
conduit .i e MR 310974 i e t 5fLowvoltageandlow ' Replaced battery 9/29 Fire pro-3-PNL-039 Replaced battery None iBad rectifier tection 305 charger specific gravity charger n ..e . a,,, -. .)
23 ] OUTAGE MAINTENANCE & MAJOR MODIFICATION MANAGEMENT OCTOBER 1984 I. Unit 3 Work Synoosis By the close of the October report period,- the unit 3 outage had progressed 5 through day number 421. All preparations for startup had been reported complete by October 27, 1984, when the startup was put on hold to resolve procedural questions. II. Unit 3 Si==ary of Maior Activities The following major work activities were completed during the month of October in preparation for startup: A. Diesel generator 3A turbocharger repairs were completed October 21, 1984 B. P5099 HPCI terbperature switch repositioning modification C. P3061 Replace level switches LS-73-56A and 56B D. P3106 Replace flow transmitter FT-84-17 and -20 per NRC Report 79-01B E. P3087 Replace level switches LS-73-57A and 57B F. P533 Torus temperature monitoring system installatiod (worked in conjunction with P0126) G. P0126 Install ECCS ATU inverters (in support of P0533) l H. P0631 Move radiation monitor element in RHRSW tunnel I. P5181 Unistrut supports for drywell instrtmentation tubing J. P0684 Drywell to torus vacuum breakers K. P069164-system valve modification to make flange sides testable L. 257 work plans that were designated as startup prerequisites were dir> positioned this month.
J. 24 OUTAGE MAINTENANCE & MAJOR MODIFICATION MANAGEMENT OCTOBER 1984 III. Unit 2 Work Synoosis The unit 2 outage which began September 15,.1984, progressed through day number 417 by the end of the October report period. ~ 'IV. Unit 2 %===ry of Maior Activities The following is a partial listing of significant work' activities performed in support of the unit 2 cycle 6 outage effort during the October report period. A. Completed unit 2 reactor vessel disassembly for fuel unloe'd (October 1, 1984). In-vessel nozzle flushes were begun. Completed fuel unload (October 13,198k). Preparations for fuel B. sipping have started. C. Low-pressure (LP) "A" turbine spindle was shipped to the TVA Power Service Shop on October 14, 1984. General Electric is to inspect the-LP "C" spindle on site is early November. D. Control blade uncoupling and other preparations for control rod drive changeout work was performed. E. Turbine bearing inspections have been reported complete. F. Flushes were performed on drywell instrtanent, vent and drain line's in an effort to reduce radiation exposure. General improvement was noted. G. Eddy-current inspections of selected unit 2 heat exchangers was begun during the October report period. The 2D RHR heat exchanger has been checked, plugged and returned to available-for-service status. + A w 4 sp e + si Sw6 +1
R 25 OUTAGE MAINTENANCE & MAJOR MODIFICATION MANAGEMENT I ~ OCTOBER 1984 V. Outane Planning and Scheduling With the decline in unit 3 outage planning and scheduling requirements, a portion of the emphasis can be shifted to unit 1 cycle 6 efforts. There is a combined effort in progress that is evaluating multiple options on unit 2 cycle 5 outage work in conjunction with variations to f.he 5-year plan and the resultant effect on unit 1 cycle 6 start date. 9 N 9 9 4 4- ~ b e e
I l 3- .o. TENNESSEE VALLEY AUTHORITY Browns Ferry Nuclear Plant P. O. Box 2000 Decatur, Alabama 35602 1 NOV 161984 Nuclear Regulatory Commission Office of Management Information and Program Control-Washington,'DC 20555 Gentlemen: Enclosed is the October 1984 Monthly Operating Report to NRC for Browns Ferry Nuclear Plant Units 1, 2, and 3 Very truly yours, TENNESSEE VALLEY AU1HORITY h G. T. Jones Plant Manager Enclosures cc: Director, Region II INPO Records Center Nuclear Regulatory Commission Institute of Nuclear Power Office of Inspection and Enforcement Suite 1500 101 Marietta Street 1100 circle 75 Parkway Atlanta, GA 30303 (1 copy) Atlanta, GA 30389 Director, Office of Inspection and Enforcement Nuclear Regulatory Commission Washington, D. C. 20555 (10 copies) Mr. A. Rubio, Director Electric Power Research Institute P. O. Box 10412 Palo Alto, CA 94304 i An Equal Opportunity Emotoyer}}