ML20129G276
| ML20129G276 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 03/31/1985 |
| From: | Thom T TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20129G244 | List: |
| References | |
| NUDOCS 8506070210 | |
| Download: ML20129G276 (31) | |
Text
.
TENNESSEE VALLEY AUTHORITY DIVISION OF NUCLEAR POWER BROWNS FERRY NUCLEAR PLANT MONTHLY OPERATING REPORT TO NRC March 1, 1985 - March 31, 1985 DOCKET NUMBERS 50-259, 50-260, AND 50-296 LICENSE NUMBERS DPR-33, DPR-52, AND DPR-68 Submitted by:
em Pladt Manager
.y 8506070210 850419 PDR ADOCK 05000259 y
R PDR
~
TABLE OF CONTENTS
~
Operations Summary..
1 Refdeling Information.
3 Significant Operational Instructions..........
5 Average Daily Unit Power Level..
10 Operating Data Reports..........
13 Unit Shutdowns and Power Reductions...
16 Plant Maintenance............
19 Outage Maintenance & Major Modification............
27 Addenda.
31 (Corrections to January and February, 1985 Report) m k
1 c -
Operations Summary March 1985 The following summary describes the significant operation activities during the reporting period.
In support of this summary, a chronological log of significant events is included in this report.
There were six reportable occurrences and two revisions to previous occurren'ces reported to the NRC during the month of March.
Unit 1 There was one. scram on the unit during the month.
On March 19, 1985,.the unit was manually scrammed when excessive leakage on the primary contain-ment boundary was identified.
Unit 2 The unit was in cold shutdown the entire month for the unit's end-of-cycle 5 refueling outage.
_ Unit 3 There was one scram on the unit during the month.
On March 9, 1985, the unit was being brought to cold shutdown by controlled shutdown to inspect and repair reactor vessel level instrument lines. The reactor was manually scrammed at less than 0.02 percent thermal power when problems occurred with the rod worth minimizer.
w4 Prepared principally by B. L. Porter.
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- - - - +. -.....,, ~.-
. -. ~. -..
2 Operati'ons Summary (Continued)
March 1985 Fatigue Usage Evaluation The cumulative usage factors for the reactor vessel are as-follows:
Location Usage Factor Unit 1 Unit 2 Unit 3
..Shell at water line 0.00620 0.00492 0.00430 Feedwater nozzle 0.29782 0.21319 0.16133
' Closure studs 0.23910 0.17629 0.14326 NOTE:
This accumulated monthly information satisfies Technical Specification Section 6.6.A.17.B(3) reporting requirements.
, Common System Approximately 1.88E+06 gallons of waste liquids were discharged containing approximately 1.74E-01_curics of activities.
's4 4
9 e
3 Operations Summary (Continued)
March 1985 Refueling Information Unit 1 Unit 1 is scheduled for its sixth refueling approximately June 1, 1985 with a scheduled restart date of March 31, 1986. 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 instrumentations. The unit was shut down on March 19,
'1985, and will remain in cold shutdown until June 1, 1985, because of unfinished modifications to meet environmental concerns.
There are 764 assemblies in the reactor vessel. The spent fuel storage pool presently contains 252 EOC-5 assemblies, 260 EOC-4 assemblies; 232 E0C-3 assemblies; 156 EOC-2 assemblies; and 168 E0C-1 assemblies. The present fuel pool capacity is 3,471 locations.
Unit 2 Unit 2 was shut down for its fif th refueling outage on September 15, 1984 with a scheduled restart date of August 1, 1985. This -efueling outage will involve loading additional 8X8R (retrofit) 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 assemblies in the reactor vessel. At month end, there were 273 new assemblies, 764 EOC-5 assemblies, 248 EOC-4 assemblies, 352 EOC-3 assemblies, 156 EOC-2 assemblies, and 132 EOC-1 assemblies in the spent fuel storage pool. The present available capacity of the spent fuel pool is 77 locations. All old racks have been removed from the pool and new HDR's are being installed.
4 Operations Summary (Continued)
March 1985 Unit 3 Unit 3 is scheduled for its sixth refueling outage approximately November 30, 1985, with a scheduled restart date of November 10, 1986. This refueling involves loading 8X8R (retrofit) assemblies into the core, and complete reinspection of stainless steel piping.
There are 764 assemblies presently in the reactor vessel. There are 248 EOC-5 assemblies, 280 EOC-4 assemblies,124 EOC-3 assemblies,144 EOC-2 assemblies, and 208 EOC-1 assemblies in the spent fuel storage pool. The present available capacity of the spent fuel pool is 914 locations.
t I
l l-4 i
5 Significant Operational Events Date Time Event Unit 1 3/01 0001 Reactor thermal power at 94-percent (5), end-of-cycle 6 coastdown.
3/02 0205 Reduced thermal power to 91% for SI-4.3.A.2, Control Rod Drive (CRD) Exercise.
0220 SI-4.3.A.2 complete, commenced power ascension.
0300 Reactor thermal power at 945, end-of-cycle 6 coastdown.
3/03 1500 Reactor thermal power at 935, end-of-cycle 6 coastdown.
2230 Commenced reducing thermal power for removal of "C"
string high-pressure heater from service for maintenance.
2255 Reactor thermal power at 82% for maintenance on "C"
string high-pressure heater.
2350 "C" string high-pressure heater back in service, commenced power ascension.
3/04 0010 Reactor ther-mal power at 94%, end-of-cycle 6 coastdown.
1230 "C" string high pressure heater isolated on high level, commenced reducing thermal power.
1300 Reactor thermal power at 89%,
"C" string high-pressure heater limited.
3/05 0315 "C" string high-pressure heater back in service, commenced power ascension.
0325 Reactor thermal power at 945, end-of-cycle 6 coastdown.
1500 Reactor thermal power at 935, end-of-cycle 6 coastdown.
3/07 0700 Reactor thermal power at 92%, end-of-cycle 6 coastdown.
3/10 2300 Reactor thermal power at 915, end-of-cycle 6 coastdown.
3/11 1345 During SI-4.1.A-5, control rod 54-39 scrammed, reducing thermal power to 895.
2225 Reducing thermal power for scram testing of control rod
,; 4 54-39 2235 Reactor power at 87% for scram testing control rod 54-39 2300 Scram testing on control rod 54-39 complete, commenced power ascension.
C 9
6 Significant Operational Events Date Time Event Unit 1 (Continued) 3/12 0030 Commenced PCIOMR from 895 thermal power.
-0300 Reactor thermal power at 92%, end-of-cycle 6 coastdown.
2300 Reactor thermal power at 915, end-of-cycle 6 coastdown.
3/13 1500 Reactor thermal power at 90%, end-of-cycle 6 coastdown.
3/16 0010 Reduced thermal power to 87% for CRD Exercise (SI-4.3.A.2).
0145 SI-4.3.A.2 complete, reduced thermal power to 86% for turbine control valve tests and sis.
0530 Turbine control valve tests and sis complete, commenced power ascension.
0700 Commenced PCIOMR from 88% thermal power.
0935 Reactor thermal power at 905, end-of-cycle 6 coastdown.
2200 Commenced reducing thermal power to remove "C" Reactor Feedwater Pump (RFWP) from service for maintenance.
2245 "C"
RFWP out-of-service for maintenance, reactor thermal power at 57% and reducing.
3/17 0200 Reactor thermal power at 53%, holding for "C" RFWP maintenance.
0245 "C" RFWP maintenance continues, commenced power ascension.
0320 "C" RFWP back in service.
0430 Commenced PCIOMR from 81% thermal power.
1520 Reactor thermal power at 92%, end-of-cycle 6 coastdown.
2000 Reactor thermal power at 91%, end-of-cycle 6 coastdown.
i 3/18 0700 Reactor thermal power at 90%, end-of-cycle 6 coastdown.
1500 Reactor thermal power at 89%, end-of-cycle 6 coastdown.
l 2315 Commenced reducing thermal power for shutdown to repair l
and leak test RCIC and HPCI valves 71-14 and 73-23 3/19 0127 React.or manual Scram No. 178 from 44% thermal power for repa'.r and leak test of valve 71-14 and 73-23
-,,; 4 1730 Reactor in cold shutdown.
3/26 0800 Management decided to keep unit 1 in a shutdown condi-tion until the unit undergoes several modifications, including those necessary to bring the unit into compliance with environmental qualifications required under NUREG 0588. The unit was scheduled to begin a 231 l
day refueling and modification outage on June 1, 1985.
p-7 Significant Operational Events Date
. Time Event Unit 1 (Continued) 3/31 2400 Management decided to keep unit 1 in a shutdown condi-tion,until the unit undergoes several modifications, including those necessary.to bring the unit into compliance with environmental qualifications required under NUREG 0588. The unit was scheduled to begin a 231 day refueling and modification outage on June 1,1985.
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8 Significant Operational Events Date Time Event Unit 2 3/01 0001 End-of-cycle 5 refuel outage continues.
3/31 2400 End-of-cycle 5 refuel outage continues.
4 4
9 Significant Operational Events Date Time Event Unit 3-3/01 0001 Reactor thermal power at 100%, maximum flow, rod limited.
3/02 -
0350 Commenced reducing' thermal power for SI-4 3.A.2 (CRD Exercise).
0430 Reactor thermal power at 96% for SI-4.3.A.2.
0600 SI-4.3.A.2 complete, commenced power ascension.
0700 Commenced PCIOMR from 975 thermal power.
1000 Reactor thermal power at 1005, maximum flow, rod limited.
3/09 0200.
Commenced reducing thermal power for turbine control valve test and sis.
0300 Reactor thermal power at 95% for turbine
- control valve test and sis.
0425 Turbine control valve _ test and sis complete, commenced power ascension.
0500 Reactor thermal power at 100%, maximum flow, rod limited.
0745 Commenced reducing thermal power' for shutdown to invest-igate reactor water level concerns.
1935 Main turbine off line.
2142 Reactor manual Scram No.117 from less than 0.02%
thermal power.
- 3/10 1240 Reactor in cold shutdown to repair a leak in the reactor water level reference leg instrument line. This was found to be the root cause of the reactor water level problem.
3/15 1200 The reactor water level reference leg instrument line has been repaired. The unit has been placed on administrative hold until various TVA and NRC concerns are resolved.
3/131 2400 The reactor water level reference leg instrument line has been repaired. The unit has been placed on administrative hold until various TVA and NRC concerns are resolved.
4 4
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10 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-259 UNIT Browns Ferry 1 DATE 4/1/85 T. nom COMPLETED BY TELEMIONE (205) 729-2171 MONTH March 1985 DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL.
(MWe Net) iMWe-Net) 953 870 17 2
999
~
3 998 14 gg 959
-14 4
20 5
984 21
-15 6
981
-13 22
~
7 978
-16 23 8
971 21
-15 9
971 25
-15 973 10 26
-10 947 27
-8 952 12
-8 28 13 958 29
-6 14 956 30
-6
.15 952 Ji
-6 910 16 INSTRUCTIONS On thitformat list the average daily unit power leselin MWe Net for each day in the reporting month. Compute to o
the nearest whole nwgswatt.
(9/77)
W
11 AVER AGE DAILY UNIT POWER LEVEL DOCKET NO. 50-260 UNIT Browns Ferry 2 4/1/85 DATE COMPLETED By T. Thom 729-2171 TELEPHONE March 1985 MONT71 DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe Neti (MWe Net)
I
~3 E7
-2
-3 2
18
-2
-3
'2 3
19
~3
-2 4
20
-3
-2 3
21
-3
-2 6
22
~3 7
I
~
-2 8
24
~
- 3
-2 9
25
-3
-7 10 26
-3
~7 27
-3
-7 12 28 0
-3 13
-6 29
-3
-7 14 30
~2
-8 15 31
-3 16 INSTRUCTTONS I
On thitformatolist the average duty unit power toelin MWe Net for each day in the reporting month. Compute to the nearest whole megswatt.
(9/77)
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12 AVERAGE DAILY UNIT POWER LEVEL 50-296 DOCKET NO.
Browns Ferry 3 WIT DATE 4/1/85 T. Thom COMPLETED BY TELEPHONE (205) 729-2171 MONTH March 1985 DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL IMWe-Net)
(MWe-Net)
I 1079
,7
_10 1076 c 11 2
,3 3
1093 39
_10 4
1080 20
-10 1083
-11 5
21 1085 6
22
-11 7
1084 23
-11 1081
-11 3
24 9
552 25
-11
-13 10 26
-10 lI
~13
-11 27
-12
' _11 12
,g l
13
-11 29
-10 l
l4
-10
-10
.10
~11
~
15 3
I6
-10 INSTRUCTIONS On thi$ format list the average daily unit power leselin MWe Net for each day in the reporting month. Compute to the nea' rest whole rnegawatt.
e (9/771 m
13 OPERATING DATA REPORT DOCKET NO.
50-259 DATE 4-1-85 COMPLETED BY._L Thom TELEPHONE 729-2171 OPERATING STATUS
- 1. Unit Name:
Browns Ferry One N#885 March 1,. 985
- 2. Reporting Period:
- 3. Licensed Thermal Power (MWt): _ 3293 1152
- 4. Nameplate Rating (Gross MWel.
1065
- 5. Design Electrical Rating (Net MWe):
1098.4
- 6. Maximum Dependable Capacity (Gross MWe):
1065
- 7. Maximum Dependable Capacity (Net MWe):
- 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 N/A
- 10. Reasons For Restrictions.lf Any:
This Month Yr..to Date Cumularise 744 2,160 93,560
- 11. Hours in Reporting Period
- 12. Number Of Hours Reactor Was Critical 433.45 1,647.78 59,521.38
- 13. Reactor Reserve Shutdown Hours 310.55 512.22 6,997.44
- 14. Hours Generator On-Line 433.45 1,626.67 58,267.26
- 15. Unit Reserve Shutdown flours 0
0 0
- 16. Gross Thermal Energy Cenerated (MWH) 1.308.962 4.982,981 168,144,427 17 Gross Electrical Energy Generated (MWH) 427,190 1,652,650 55,398,130
- 18. Net Electrical Energy Cencrated (MWH) 412,402 1,603,031 53,816,852
- 19. Unit Senice Factor 58.3 75.3 62.3
- 20. Unit Availability Factor 58.3 75.3 62.3
- 21. U.iit Capacity Factor (Using MDC Net) 52.0 69.7 54.0
- 22. Unit Capacity Factor IUsing DER Net) 52.0 69.7 54.0
- 23. Unit Forced Outage Rate 41.7 24.7 22.2
- 24. Shutdowns Scheduled Over Nest 6 Months IType. Date,and Duration of Each):
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
- 26. Units in Test Status (Prior to Commercial Operation p:
Forecast Achiesed
)
INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPER ATION N
N/77)
14 OPERATING DATA REPORT DOCKET NO. 50-260 DATE 4/1/85 COMPLETED BY T. Thom TELEPHONE (205) 729-2171 OPERATING STATUS
- 1. Unit Name:
Brows Fem Tw Notes March 1985
- 2. Reporting Period:
- 3. Licensed Thennel Power (MWal:
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 N/A
- 9. Power Level To which Restricted.lf Anget MWe):
- 10. Renwns For Restrictions.If Any:
This Month Yr..to Date Cumulative
- 11. Hours in Reporting Period 744 2160 88,447
- 12. Number Of Hours Reactor Was Critical 0
0 55.860.03
- 13. Reactor Rewrve Shutdown Hours 0
0 14.200.44
- 14. Hours Generator On-Line 0
0 54,338.36
- 15. Unit Rewrve Shutdown flours 0
0 0
- 16. Grow Thermal Energy Generated (MWH) 0 0
153,245,167 O
0 50,771,798 17 Grou Electrical Energy Generated (MWHI
- 18. Net Electrical Energy Generated (MWH)
-2,528
-8,232 49,294,741
- 19. Unit Service Factor 0
0 61.4
- 20. Unit Availability Facto, 0
0 61.4
- 21. Unit Capacity Factor (Using MDC Neti 0
0 52.3
- 22. Unit Capacity Factor (Using DER Net) 0 0
52.3
- 23. Unit Forced Outage Rate 0
0 23.0
- 24. Shutdowns Scheduled Over Next 6 Months (Type. Date.and Duration of Eacht:
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
September 1985
- 26. Unism in Test StatuitPrior to Commercial Operationi:
Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPER ATION (4/77)
15 OPERATING DATA REPORT DOCKET NO.
50-296 DATE 4/1/85 COMPLETED BY T. Thom TELEPHONE
(?nsi 7?9-2171 OPERATING STATUS I. Undt Name:
Browns Ferry Thron Notes
- 2. Reporting Period:
March 1985 3 Licensed ThennalPower(MWI):
3293
- 4. Nameplate Rating (Gross MWet:
1152 1055
- 5. Design Electrical Rating (Net MWe):
- 6. Manimum Dependable CapacHy (Gross MWe):
1098.4 1065
- 7. Mazimum Dependable Capacity (Net MWe):
- 8. If Changes Occur in Capacity Ratings (items Number 3 Through 7) Since Last Report. Give Reawns:
N/A
- 9. Power Level To Which Restricted.lf An Net MWe):
N/A A
- 10. Reasons For Restrictions. lf Any:
This Month Yr..to.Date Cumulative i1. Hours in Reporting Period 744 2160 70.872
- 12. Number Of Hours Reactor Was Critical 213.70 1,517.65 45,306.08
- 13. Reactor Reserve Shutdown Hours 396.00 508.05 5,149.55
- 14. Hours Generator On.Lir, 211.58 1496.96 44,194.76
- 15. Unit Reserve Shutdown flours 0
0
- 16. Gross Thermal Energy Generated (MWH)
- 17. Gross Electrical Energy Generated (MWH) 226,850 1,572.770
_ 43.473.760
- 18. Net Electrical Energy Generated (MWH) 215,175 1,526,475 42,192,226
- 19. Unit Sersice Factor 28.4 69.3 62.4
- 20. Unit Availability Factor 28.4 69.3 62.4
- 21. Unit Capacity FactorIUsing MDC Neti 27.2 66.4 55.9
- 22. Unit Capacity Factor (Using DER Net) 27.2 66.4 55.9
- 23. Unit Forced Outage Rate 71.5 30.6 18.4
- 24. Shutdowns Scheduled Over Next 6 Months (Type. Date,and Duration of Eacht:
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
April 15, 1985
- 26. Units in Test Status tPrior to Commercial Operation):
Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATlON (4/77)
50-259 l
UNITSilUTDOWNS AND POWER REDUCTIONS DOCKET NO.
UNIT NAME Browns Ferry 1 DATE 4 /1/R5 COMPLETED BY T. Thom REPORT MONTil March TELEPifONE (205) 729-2171
)
i
.i ?
g f5X Licensee
,Ev, E 't, i
s' Cause & Correceive No.
Date i
3:
(
3g5 Event gy p'?
Auion to j5 5
5 ;% g Report e mu 5
Prevent Recurrence u
O 312 3/16/85
'F A
Derated for "C" RWP Maintenance 313 3/19/85 F
174.55 A
2 Rx scrammed for repair and leak test on valve 71-14 and 73-23.
E 314 3/26/85 F
136.0 D
Unit remains offline for modifications to bring the unit into compliance with environmental qualifications required under NUREG 0588.
l I
2 3
4 F: Forced Reason:
Method:
Exhibit G - Instructions S: Scheduled A-Equipment Failure (Explain)
I-Manual for Preparation of Data B Maintenance of Test 2-Manual Scram.
Entry Sheets for Licensee C Refueling 3-Automatic Scram.
Evens Report tLER) File INtiRLG-D Regulatory Restriction 4-Other ( Explain) 01611 EOperator Training & Litense Examination F-Ad nu mst rai r<e 5
G-Operational Er ror I E splain)
Eshibis 1 Same Source (9/77) li-Other (Explain) g
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UNIT SilUTDOWNS AND POWER REDUCTIONS DOCKETNO. 50-260 UNIT NAME Browns Ferry 2 DATE 4/1/85 COMPLETED BY T. Thom REPORT MONTit Mnech TELEPHONE (20 9 774-2171 n.
E c
jg 3
y.Y 3 Licensee
,Ev, K
Cause & Currectise No.
Date g
3g i;
2s&
Event gg
&T Acta.n su f5 5
H
~ p3 Report :
mV E'
Prevent Recurrence
=
u; f a
v C
305 3/1/85 5
744 C
4 EOC-5 Refuel Outage (Cont)
(Controlled Shutdown 9/15/84)
C I
2 3
4 F: Forced Reason:
Method:
Exhibis G. instructnus 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 Autunutic Scram.
Event Report t LL Ri rile t M'Rt G.
/
D Regulatory Restriction 4-Other (Explain) 0161I EOperator Tsaining & License thanunainin F-Adnunistrative 5
G-Operational Eirur ( Explain)
Estnbit I-Same Source (9/77)
Il-Other (E xplain t
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p UNITSHUTDOWNS ANDPOWER REDUCTIONS DOCKET NO. 50-296 UNIT NAME Browns Ferry 3
~
DATE A /1/M REPORT MONTH March COMPLETED BY T. "Mion TELEPHONE (205) 729-2171 n.
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9 5
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C'"5' A C""' I
I 26 4
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- n. ?"
Action to 5E E
h15j Report =
JEC 0
Prevent Recurrence
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k 155 3/9/85 F
136.42 A
2 Turbine offline to investigate reactor water level concerns.
I 15 6 3/15/85 F
396.0 F
Unit remains down due to being placed on administrative hold until 3
various TVA and NRC concerns are 5
- resolved, l
4 I
2 3
4 F: Forced Reason:
Method:
Exhibit G Instructions S: Scheduled A Equipment Failure (Explain) 1 Manual for Pacparation of Data B-Maintenance of Test 2-Manual Scram.
Entry Sheets for Licensee C-Refueling 3 Autunutic Scram.
Even Report ll.ER File a NU REG-D.Regulasury Restriction 4-Other I Explam i 0161)
Loperator Training & Lisenw I sananation F-Administrative 5
G-Operatomal Leror ll~ splai.il Estubit I Same Source 19/77) llother IExplain) t d
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CSSC EQUIP.'"ENT ELECTRICAI. MAI :TE':ANCE SC?uRY 9/29/82 For the Nath of M. arch 19 1 Eifeet on Safe, Act ion Taken Nature of Operation at Cause,0f Results cf i To Preclude i
- Dat, System Component Maintenance The Reactor Ralfunction I
Malfunctfan
! Recurrence 1985 2/24 480V commori27-215-3/10A-BY DPSO functional None Coil open on relay Lost of undervoltage Replaced undervolt-boards undervoltage testing 480V protection for 480V age auxiliary aux relay 27BY common board 3 common board 3 relay MR 181133 3/1 Radiation TC-90-0044 Check heat None lleat trace defect-- Temperature of line Replaced heat monitoring temperature traces for ive was 74*F. Should be traces controller for proper operatior between 110*F & 150*E heat race on MR 310349 Isokinetic probe 3/8 Standby llTR-065-0060 Troubleshoot None Defective breaker Loss of redundancy Replaced breaker gas treat-SCT relative to determine (BKR-065-0060) due to C train ment humidity con-cause of breaker inoperable MR 171119 trol heater for filter train C 3/14 Eligh pres-KIR-26-0001 Replace defect-None Bad upper bearings Excessive vibration Replaced upper zure fire fire pump A ive bearing in and noise on motor bearing protection motor motor MR 317734 i
3/26 liigh pres-STN-26-1504 Troubleshoot -
None Contacts burned Fire pump A Changed out con-i ture fire fire pump A contacts smok-up on starter strainer motor tacts on starter protection strainer motor ing on motor inoperable
_MR 180518 t
l 1
q i
l 8
ek
.q
!c- " INS t ERT! ND:f.DR PLANT C.;T 1
7 CSSC EQt'IPylNT ELECTRIC.it St\\1NTEN.iSCE StX"iRY 9/29/82 For the Month of March 19 85 Eftect on Safe, Action T.ikeu Nature of Operation of Cause_of t
Results ef
- To Preclude i
sto System Component Maintenance The Reactor Malfunction I
M.n i f unc t ion l Recurrence B5 75 RPS RLY-099-5AK3D Adjust / replace Half Scram on Limit switch 3, on Relay SAK3D dropped Adjusted limit nain steam lino limit switch unit 1 FCV-001-26 which out and gave a half switch 3 on isol viv-per EMI 39 anergizes relay scram when channel B FCV-001-26 closure sensor SAK3D, was out of inboard & outboard relay. Channel adjustment MSIV's were tested HR 321785 m
B2 4
HPCI FCV-73-6A & 6B Performirig HPCI system Arc suppressing HPCI inverter fuse Replace blown fuse-liPCI steam line SI 4.5.E.1.c declared inop -
resistors found blown when valves MR 216545 drain isolation Entered 7-day to be open in were cycled Troubleshoot syster valves LCO both valves MR 171114 Replacement of re-I sistors (later)
MR 171115 & 171116 LER 259/85006 7
480V LPCI MG sets Inspect loose N/A N/A N/A (Interim Repairs) rrctor IDA, IDN, IEA, diode connectico s Diodes tested and MOV bds lEN
& high exciter rotating rectifier field voltage rings tightened.
KR 157548/157549.
KC sets will be sent to Louis-Allis for permanent repair during outage
- 2 Neutron MONT-92-7-41A Correct None Connectors were IRM's A & C were Drywell penetration monitoring MONT-92-7-41A excessive noise not adequate for experiending high connectors were intermediate problem on IRM's the application noise levels taodified to isolate range monitor A&C signal l
,the center shield cables to pre-
]
from the connector
, amp detector f
I body l
l MR 190483 i
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bi.N:S F ri s.
' ; C'.f AM i ' 'o r l ' : :
1
'.' ". f.,,,
..a.t.
CSSC EQl'IP.'?E.NT E!.ECTRIC t!. ?'.\\!!!TE';r:CE St*::;nRY O
9/29/32 for the Month af March I '* 85 l
Effect ca Safe,
~~
i
.iction Takea l
l Sature of l
Operation of Cause.of Re:,ial t s c f
{ Ta Preclude Dat^
Svsten t
Co=ponent Maintenance The Reactor Malfunction ihlfunct ton
! Recurrence L985 s/22 Radwaste FSV-077-0014A Troubleshoot to None Unknown - suspect Fuse 1-20A-F77 Replaced blown fuse drywell equip identify problem moisture present blows each time dry-drain sump with blown fuse in either JB3078 well sump attempts to MR 558105 recire vlv or at the solenoic. recirculate itself causing th(
cables to be grounded 1/24 Main steam 1-FCV-001-026 Replace limit None Missing arm -
Could not check Replaced limit main steam line switch arm on unknown proper operation of switch arm B inbd isol vls LS-2 valve FCV-1-26 MR 321156 m
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CS 9' PU I !"E '-T r!.ECIP.!C.1!. ?tilTTF'!.1?:CE SD"t\\RY 9/29/82 Fer the Mantb eJ _ March I c.
85 1:i t ec t ca Safe,
.ictton Taken j
';ature of Operation of Cause.of R0sults or To Preclude Date i
Svsten Co.m. 'e n en t Maintcaance The Reactor Malfunction Malfunction i Recurrence 985
/6 RPS RLY-99-5AK01C Check circuitry Italf Scram Defective relay Blows fuse SA-FIC Replaced relay A2 west scram for short and give half scram dis vol hi wtr when not bypassed by MR 179929 Iv1 sensor control room switch relay
/8 HPCI FSV-73-006A Check resistor None N/A Resistor found bad Check resistor for HPCI steam line to use as on FSV-73-6A replacement / repair condensate replacement on of unit 1-inboard drain unit 1 FSV-73-6A valve or 6B
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MR 171117.
Replace resistor -
MR 554205 y
714 Cranes and Bridge crane Replace liuit None Worn out cam in Switch for refuel Replaced sensitive hoists refuel floor switch sensitive switch interlock hangs in switch head head the UP position MR 064216 O
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C:M C D WI7'- *.7 FLECIRICAL l'.\\I';TE';,U;CE SC'?'.M i
9/29/52 For the l* ath of March 19 85 i
I Etfcct oa Safe, l
Ae:,ior. Takea
!.ature ef 3
Operation of Cause.cf Kesults cf To-Prcelude Date
- Sv4te, C m onent
?*iinrenance I The Reactor
>!alfunction
!!al func t ion
! Keeurrence 11985 52/28 Control bah CHR-31-19%
Troubleshoot None Evaporator freeze Caused chiller to trip Replaced thermo-heat, vent 352 shutdown chiller tripped protection thermo~ and not start auto-stat
& AC sys bd rm chiller off and will not stat bad matica11y start MR 182831
!3/4 Control bay CHR-31-1976 Troubleshoot.
None Found hole in cap Expansion valve Replaced expansloc l
heat, vent 3B1 shutdown Chiller not tube on expansion freezing up valve
{
cnd AC sys bd rm chiller operating
- valve,
[
- properly MR WM N
w.
B/7 480V reactor LPCI MC sets Inspect loose N/A N/A N/A (Interim repairs) j.,
MOV bd 3DA 3DN.
diode connection:5 j
3EA 3EN
& high exciter Diodes tested and l
field voltage rotating rectifier rings tightened.
MR 157547/157543.
MG sets will be sent to Louis-Alli for permanent repairs during outage Q/11 Neutron MONT-92-7-41D Repair / replace None Broken pin in Connection to detector Replace connector i
monitoring channel D IRM cable connector not made up l
intermediate connector range monitor MR 310415
)/27 Control barCHR-31-1951 Replace thermo None Broken thermo Chiller would not Replaced pilot
'"E' 3B control bay pilot regulator pilot regulator operate properly expansion valve vent & AC l
chiller an pilot expan-on expansion viv i
lon valve MR 554214 1
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EROWNS FERRY NUCLLAR PLANr UNIT l
CSSC EQUIPMENT MEQlANICAL MAINTE!ENCE SUltlARY For the -Month -of March 19 85 j
e EFFECT ON SAFE ACTION TAKEN DNRl SYSTEM COMPONENT NATURE OF OPERATION OF CAUSE OF RESULTS OF
'IO PRECIEDE
{
NAINTENANCE THE REACTOR MALFUNCTION MALFUNCTION RECURRENCE I
3-19-8 71 HCV-71-14 Replace Inner hLoss of Primary Normal wear Failed LLRT Replacedtwogaskys Outer Bonnet Containment MR 308126 i
Gaskets 3-19-85 73 HCV-73-23 Replace inner Loss of primary Ruptured gasket Failed LLRT Replaced gasket
& outer bonnet containment HR 560752 gaskets 2-22-85 74 Duct Hanger Remove hanger None None NA Re-weld duct hangers for ID RHR to replace RHR in ID RHR Room Pump Motor pump motor MR 182425 s
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3 BROWNS FERRY NUCLEAR PIANT UNIT CSSC EQUIPMENT NEGANICAL MAINTENANCE SUNHARY March 19 85
~
For the Month of.
i EFFECT ON SAFE ACTION TAKEN DATE SYSTEM COMPONENT NATURE OF OPERATION OF CAUSE OF RESULTS OF IO PRECLUDE MAINTENANCE
'ITIE REACTOR MALFUNCTION MALFUNCTION RECURRENCE 8 i 74 FCV-74-60 Inspect motor None Preventative NA NA pinion gear maintenance g
arrangements 13-85 74 FCV-74-12 Repair valve None Motor pinion Failed to close during Reoriented motor i
installed S.I. 4.5.B.I.c pinion gear l
Operator
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f 23-85 75 FCV-74-22 Inspect motor None he M
M P nion gear i
g arrangements i
Normal () age & use j
Failed LLRT Replaced gaskets 15-35 71 HCV-71-14 Replace inner Loss of primary
& outer bonnet containment gaskets 5
1 i
1 i
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27 OUTAGE MAINTENANCE & MAJOR MODIFICATION MANAGEMENT March 1985 MAJOR WORK COMPLETED A.
Refuel Floor 1.
Decontamination of unit 1 fuel pool equipment started on March 7, 1985, finished in March.
2.
SRM/IRM dry tube inspections were completed on March 19, 1985 with one suspect tube reported.
B.
Turbine The rebuilt low-pressure "C" turbine was returned from Muscle Shoals and was set on the turbine floor on March 6, 1985. The generator end coupling required boring, which was completed on March 22. The turbine is installed, upper diaphragms are installed and the inner. casing is set but not torqued.
C.
Drywell Instrument lines and tents were set up as of March 31 in vreparation for vessel drain and jet pump instrument line nozzle replacements.
D.
Balance-of-Plant 1.
"B" residual heat removal (RHR) heat exchanger tube plugging was completed.
"B" RHR heat exchanger service water vent line modifications were completed.
- s..r - 4 2.
The Condenser Cooling Water intake tunnel was pumped down on March 1, but joint repairs have been postponed.
E.
Modifications Mechanical 1.
Valve 74-54 work was completed on March 1, 1985.
2.
"B" RHR pump seal heat exchanger and associated RHR and Emergency Equipment Cooling Water piping were changed out on March 18.
J 28 OUTAGE MAINTENANCE & MAJOR MODIFICATION MANAGEMENT March 1985 MAJOR WORK COMPLETED (Continued)
E.
Modifications Mechanical (Continued) 3 Torus heat cure started on March 8.
As of March 31, six of 16 bays
.had been heat cured.
4.
Scram header cuts for changeout of instrument volumes were started on March 25.
5.
Induction heat stress improvement (IHSI) was completed on March 31.
The following system welds were treated:
Recirculation
- 101 Residual Heat Removal - 29 Reactor water Cleanup - 14 Total - 155 Two recirculation system welds (KR-2-37 and KR-2-36) received reheats.
F.
Modifications Electrical 1.
"A" recirculation motor generator (MG) set linkage was inspected as a result of operational problems. The HEIM rod end coupling was repaired and the MG set was turned over to operations on March 7 2.
Instrumentation was removed from the scram discharge header instrument volumes on March 24, 1985.
G.
Major Maintenance J4 1.
2B RHR pump motor was removed to be installed on ID RHR pump. The replacement motor, which was sent from the service shop, was installed on the pump but was removed prior to coupling on March 25 to replace 3D RHR pump motor, which had failed several days earlier. Projected delivery of a rebuilt pump motor is early May.
1 1
~
29 OUTAGE MAINTENANCE & MAJOR MODIFICATION MANAGEMENT March 1985 MAJOR WORK COMPLETED (Continued)
G.
Major Maintenance (Continued) 2.
All turbine building cranes and the reactor building (refuel floor) crane were taken out of service on March 29 following a fatal accident on March 28 associated with *,he unit 2 turbine building crane.
3 During post-IHSI ultrasonic transmitters weld GR-2-15, "A" recirculation riser-to-reducer weld to nozzle N2H, was found to have a 1" through-wall indication.
}p 4.
Control rod drive system maintenance started following rem' oval of the system from service on March 19 5.
Final local leak rate testing started this month.
"B" feedwater header string was tested, with valve 69-579 being the only valve on the string reported failed.
CRITICAL PATH STATUS A.
Work Plan Approvals; Modifications Group March 1 April 1 Change Total Workplans 242 280
+38 Approved Workplans 23 61
+38 Outstanding Workplans 219 219 0
Workplans in Approval Cycle 74 69 N/A B.
ECN P0126; Replace Transmitters with Analog / Trip System Conduit Installation Location March 1 April 1 Auxiliary Instrument Room 55 20%
El. 565' 105 75%
Turbine Building 25%
90%
10%
Spreader Room
F 30 OUTAGE MAINTENANCE & MAJOR MODIFICATION MANAGEMENT March 1985 CRITICAL PATH STATUS (Continued)
C.
ECN P0361; Torus Attached Piping Hanger Modifications Hangers Installed: March 1 - 11 April 1 - 83 Hanger Status by System:
- 17%
i RCIC
- 41%
RHR I
- 43%
RHR II
- 625 CS I 4%
CS II
- 27%
Drywell Torus Purge - 36%
- / k.
t;A RETURN TO SERVICE DATE:
September 21, 1985 w%
MODIFICATIONS IN PROGRESS P0392 - Scram Discharge Header Modifications P0361 - Torus Attached Piping Hangers PO126 - Analog / Trip System Installation P0613/4 - MSIV Mods on "B" I/B and Both "C" Valves P0689/91 - System 64 Valve Overlays P0547 - Replace CRD Supply Water Valves to Recir Pump Seals P0653 - Modify MSRV Vacuum Breakers (Preps)
P0684 - Modify Drywell to Torus Vacuum Breakers l
P0697 - Control Bay HVAC Systems Installation P0555 - Sandblast, Paint, Heat Cure, Torus l
P5187 - Revise Off-gas Piping As-Constructed Drawings P5177 - Revise Valve Marker Tag Tabulation P0533 - Install Improved Torus Temperature Monitor Systems PO415 - Install Reactor Feedwater Header Temperature Monitoring System P0085 - Replace Existing Drywell Sensors L1965 - Replace CRD Scram Pilot Valve Solenoid 0-Rings
- P0692 - Generator Breaker Monorail (TACF)
"P5041 - Remove Leak Rate Test Devices (TACF)
P0586 - Rod Consolidation Demonstration Equipment Installation
' Completed during this month.
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