ML20133H274
| ML20133H274 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 05/31/1985 |
| From: | Jones G, Thom T TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| NUDOCS 8508090270 | |
| Download: ML20133H274 (33) | |
Text
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TENNESSEE VALLEY AUTHORITY DIVISION OF NUCLEAR POWER BROWNS FERRY NUCLEAR PLANT MONTHLY OPERATING REPORT TO NRC May 1, 1985 - May 31, 1985 DOCKET NUMBERS 50-259, 50-260, AND 50-296 LICENSE NUMBERS DPR-33, DPR-52, AND DPR-68 Submitted by:
P1 Manager
-1 850B090270 850531 PDR ADOCK 05000259 i/If R
7 9
TABLE OF CONTENTS Opera tions Sumary......................
1 Refueling Information.....................
3 5
Significant Operational Instructions..
Average Daily Unit Power Level.................
8 Operating Data Reports.....................
11 Unit Shutdowns and Power Reductions..............
14 Plant Maintenance......................
17 Outage Maintenance & Major Modification............
25 Addenda (Corrected Operating Statistics - March / April 1985).
29 l
1 4
(
l 1
Operations Summary May 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 ten reportable occurrences and one revision to previous occurrences reported to the NRC during the month of May.
Unit 1 The unit was in cold shutdown the entire month as it undergoes several modifications including those necessary to bring it into compliance with environmental qualifications required under NUREG 0588.
Unit 2 The unit was in cold shutdown the entire month for the unit's end-of-cycle 5 refueling outage.
Unit 3 The unit was in cold shutdown the entire month on an administrative hold to resolve various TVA and NRC concerns.
Prepared principally by B. L. Porter.
2 t
Operationn Summary (Continued)
May 1985 l
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 1.37E+06 gallons of waste liquids were discharged containing approximately 7 33E-02 curies of activities.
i L
3 Operations Summary (Continued)
May 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 EOC-3 assemblies; 156 EOC-2 assemblies; and 168 EOC-1 assemblies. The present fuel pool capacity is 3,471 locations.
Unit 2 Unit 2 was shut down for its fifth refueling outage on September 15, 1984 with a scheduled restart date of October 20, 1985. This refueling 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.
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4 Operations Summary (Continued)
May 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 ccmplete reinspection of stainless steel piping. The unit was shutdown on March 9, 1985, and will remain in cold shutdown until July 24, 1985, on an administrative hold to resolve various TVA and NRC concerns.
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.
5 Significant Operational Events Date Time Event Unit 1 5/01 0001 The unit remains in a shutdown condition until it undergoes several modifications including those necessary to bring it into compliance with environmental qualifications required under NUREG 0588.
5/31 2400 The unit remains in a shutdown condition until it undergoes several modifications including those necessary to bring it into compliance with environmental qualifications required under NUREG 0588.
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0 Significant Operational Events Date Time Event Unit 2 5/01 0001 End-cf-cycle 5 refuel and modifications outage continues.
5/31 2400 End-of-cycle 5 refuel and modifications outage continues.
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Significant Operational Events 4
Date Time Event Unit 3 5/01 0001 The unit has been placed on administrative hold until various TVA and NRC concerns are resolved.
5/31 2400 The unit has been placed on administrative hold until various TVA and NRC concerns are resolved.
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- - - - - - - -., -, - -~=-- - ---~- -
8 AVERAGE DAILY UNIT POWER LEVEL
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DOCKET NO.
50-2.h UNIT B'rowns]rtyOne DATE 1-85_
COMPLETED BY T~ Thor
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TELEPHONE MONT11 May DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Neti (MWe Net)
-8 37
-9 2
-9
-10""
is 3
19
-10
~
~
20
-10 4
-10
-9 5
21
-9
-10 6
22
-9
~9 7
23 3
-9
-10 24
-10
-9 9
25
-9
~
10 3
11
-10
_9 12
-9
-10 28 13
-6
-10 29 14
-1n 30
- -10 15
-10 3
-10 16
-10 INSTRUCTIONS Ihe neare I wh$1 ge daily unit power leselin MWe Net for each day in the reporting month. Compute u a
e (1/Tl,
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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-260 UNIT Browns Fe n T.co 1-M DATE COMPLETED BY T. Tho'-
TELEPHONE -205/729-2,09 MONTH May DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe.NetI (Mwe. Net) 1
-5 g7
-2 2
-t t8
-2 3
-3 19
-2 4
-3 20
-2 5
-3 21
-2 6
9 22
-7 7
-3 23
-2 3
-3 24
-2
-2 9
-2 25 10
-2 26
-2 11
-2 27
-2 12
-2 28
-2 13
-2 29
-2 14
-2 10
-2 15
-2 33
-2 I6
-2
' INSTRUCTIONS On this. format. list the average daily unit power leselin MWe Net for each day in the reporting month. C the nearest whole megawatt.
(4/77)
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AVER AGE DAILY UNIT POWER LEVEL DOCKET NO.
50-296 UNIT Browns rgry T'.'res DATE ~ A 1 R*
COMPLETED BY _ T. Tho i TELEPHONE 205/729-250i MONTH Mnv DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net)
(MWe-Net)
-10
-9 g7 2
-0 gg
_9 3
-9 gg
_9 4
-9 20
-9 5
-10
-9 21
-9
~9 6
22 7
-9 23
-9 8
-9
-9 28 9
-9 25
-9
-9 10 26
-9 II 27
-9 12
-9 28
-10 13
-9
-10 29
-10
_9 14 15
-9'
._9 3,
16
-9 INSTRUCTIONS On this. format. list the average daily unit power level in MWe Net for each day in the reporting month. Comput
.o the nearest whole rnegawati.
$c m
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OPER ATING DATA REPORT DOCKET NO.
50-28 DATE 6-1-6;_
COMPLETED BY
.T.. T.s en TELEPHONE
.205,
F c OPERATING STATUS
- 1. Unit Name:
Browns Ferry One Nol'5
- 2. Reporting Period:
May 1985 l
- 3. Licensed Thermal Power (MW ):
3293
- 4. Nameplate Rating (Gross MWe):
1152 1065
- 5. Design Electrical Racing (Net MWe):
- 6. Maximum Dependable Capacity (Gross MWe):
1098.4
- 7. Maximum Dependable Capacity (Net MWe):
1065
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
N/A
- 9. Power Level To Which Restricted,1f Ang (N/A Net MWe).
N/A
- 10. Reasons For Restrictions. If Any:
This Month Yr. to Date Cumulair..'
i1. Ilours in Reporting Period 744 3,623 95,023
- 12. Number Of Houri Resetor Was Critical 0
1647.78 59.521.39
- 13. Reactor Reserve Shutdown Hours 0
512.22 6.997.44
- 14. Hours Generator On.Line 0
1,626.67 58,267.hF
- 15. Unit Newrve Shutdown flours U
U U
- 16. Grow Thermal Energy Generated (MWH) 0 4,982,981 168,144,42f 17 Grow Electrical Energy Generated (MWH) 0 1,652,650 55,396,150 ~
- 18. Net Electrical Energy Generated (MWH)
-6.989 1.589.819 5t Rn11 -
- 19. Unit Service Factor 0
- 20. Unis Asailability Factor 0
- 44.9 61.3 44.9 61.3
- 21. Unit Capacity Factor (Using MDC Net) 0 41.2
'~
53.2
- 22. Unit Capacity Factor (Using DER Net) 0 41.2 53.2
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- 23. Unit Forced Outage Rate 100 55.1 23.6
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- 24. Shutdowns Scheduled Oser Nest 6 Months (Type. Date.and Duration of Each t:
June 1, 1985 - Refuel 6utane bhains.
- 25. If Shut l$wn A End Of Reimrt Period, Estimated Date of Startup-
- 26. Units in Test Status IPrior to Commercial Operation):
Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPER ATION 19 7 )
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= = =...u w.- u a OPERATING DATA REPORT DOCKET NO.
50-160 DATE 6 ' L 'b.?
COMPLETED BY _ T, R,.i TELEPHONE 90%.'2.S : 30 )
OPER ATING STATUS
- 1. Unit Name:
Brom s Fe m ho Notes i
- 2. Reporting Period:
Mnv 1985
- 3. Licensed Thermal Power (MWI):
3293
- 4. Nameplate Rating (Grow MWe):
1152
- 5. Design Electrical Rating (Net MWe):
065
- 6. Maximum Dependable Capacity (Gross MWe):
1098.4 l
1065
.7. Maximum Dependable Capacity (Net MWe),
8
- 8. If Changes Occur in Capacity Ratings (items Number 3 Through 7) Since last Report Gi e Rea>ons:
N/A
- 9. Power Lesel To which Restricted,if Any (Net MWe).
N/A
- 10. Reawns For Restrictions,1f Any.
N/A This Month Yr..to-Date Cumulati.
I1. Hours in Reporting Period 744 3623 89,910
- 12. Number Of Hours Reactor Was Critical 0
0 qq_pgn,g3
- 13. Reactor Rearrve Shutdown Hours 0
0 14.200.44
- 14. Hours Generator on.Line 0
0 54,338.36
- 15. Unit Reserve Shutdown Hours 0
0 0
- 16. Gross Thermal Energy Generated (MWH) 0 0
153,245,167 17 Grnu Electrical Energy Generated (MWH) 0 0
50,771,796]
-1575_,_,_,,_,
- 18. Net Electrical Energy Generated (MWH)
-13,687 49,289,2E
- 19. Unit Service Factor 0
0 60.4
- 20. Unit Asailability Facto, 0
0 60.4
- 21. Unit Capacity Factor (Using MDC Net)
_0_ ___
0 51.5
- 22. Unit Capacity Factor IU>ing DER Net) 0 0
51.5
- 23. Unit Forced Outage Rate 0
0 23.0
~ ~ ' '
- 24. Shutdowns Scheduled Oser Nest 6 Months (Type. Date, and Duration of Each t:
=-
- 25. If Shut IM*n At End Of Report Period. Estimated Date of Startup:
September 1985
- 26. Uniti in Test Status (Prior to Commercial Operation):
Forecast Achieved INITIA L CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPER A T10N
._ _ / - - - _.._. a c -
13 OPERATING DATA REPORT DOCKET NO.
5 0-2 5,_
DATE 6-1 "5 COMPLETED BY T.
Then TELEPHONE 9n; /77 c-2509 OPERATING STATUS
- 1. Unit Name:
Browns Ferry Three Notes
- 2. Reporting Period:
May 1985 1
- 3. Licensed Thermal Power IMWI): 1791 l
- 4. Nameplate Rating (Gross Mhe):
1152
- 5. Design Electeical Rating (Net MWe):
1065_
- 6. Maximam Dependable Capacity (Cross MWe): 1098.4
- 7. Madnum Dependable Capacity (Net MWe):
1065
- 8. If Changes Occur in Capacity Ratings (items Numbec 3 Through 7) Since Last Report. Gi+e Reasons:
N/A
- 9. Power Level To Which Restricted. lf Any (Net MWe):
N/A
- 10. Reasons For Restrictions. lf Any:
N/A This Month Yr.-to-Date Cumulative ll. liours in Reporting Period 744 3623 72,335
- 12. Number Of Hours Reactor Was Critical 0
1517.63 43,306.05
- 13. Reactor Reserve Shutdown Hours 0
508.05 5.149.55
- 14. Hours Generator On Line 0
_1,496.96 44,194.76
- 15. Unit Reserve Shutdown flour, 0
0 0
- 16. Cross Thermal Energy Generated (MWH) 0
_4,649,840 131,868,2e.
17 Gross Electrical Energy Generated (MWH) 0 1,572,770
_ 43,473,iJ.
- 18. Net Electrical Energy Generated (MWH)
-6,781 1,512.056 42,177,tdI-~
- 19. Unit Senice Factor 0
41.3 61.1
- 20. Unit Availability Factor 0
41.3 61 1
~
- 21. Unit Capacity Factor IUsing MDC Net) 0 39.2 54.8
~
- 22. Unit Capacity Factor (Using DER Net) 0 19.2
_54.8
- 23. Unit Forced Outage Rate 100
_58.7 20.5
- 24. Shutdowns Scheduled Oier Nest 6 MonthslType. Date.and Duration of Eacht:
November 1985
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
- 26. Units in Test Status IPrior eo Commercial Opecation):
Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCITL OPER ATION 14/77 m
50-259 UNIT SIIUTDOWNS AND POWER REDUCDONS ET NO.
Browns Ferry One DATE 6-1-8s REPORT MONT11 May EPHONE _20572h-2509 e.
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3 4 El Licensee P,
Cause & Corrective No.
Date e-3g
(
1ye Event g
9'E Action to f :,
E 3 ;p, =
Report r mL EL Prevent Recurrence
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C 314 5/1/85 F
744 D
The unit remains in a shutdcun Cont condition until it undergoes several modifications, including those necessary to bring it into compliance with environmental qualifications required under E
I 2
3 4
F: Forced Reason:
Method:
Exhibit G - Inst ructions S: Scheduled A Equiprnent Failure (Explain) 1-Manual for Preparation of Data B-Maintenance of Test 2-Manual Scram.
Entry Sheets for 1.icensee C. Refueling 3 Automatic Scram.
Event ReporI (1.E RI File (NURI.G-D-Regulatory Restriction 4-Other ( Em plain )
0161)
-4 ne.. :. n Tr.iini..g &.2 t o -e ' ven rmn F-A ;m:m a:r.,
5 GGreia!... - l 1
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! si.. bit ! - Ei:nc Soi w
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y UNIT SlibiDOWNS AN) POWER REGUCTIONg DOCKET No. l'U 2,fy UN!i NAME E cnw. s eerre Tco DATE 6 -i -f45 REPORT MONTH May C00&l2TED BY T
Th-TELEPHONE 205/724-2509
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Action to Prevent Recurrence c5 305 5/1/85 5
744 C
4 EOC-5 Refuel Outage Cont (Controlled Shutdown 9/15/84)
G I
2 3
F: Forced Reason:
Method:
Exhibit G - Instructions 4
S: Scheduled A-Equipment Fa !ure(Explain) 1 -Manual for Preparation.of Data B Maintenance of Test 2-Manual Scram.
Entry Sheets for Licensee C-Refueling 3 Automatic Scram.
Event Repost (LERI File (NUREG.
D-Regulatory Restriction 4-Oiher ( Explain) 0161)
E-Operator Training & License Examination F-Administrative 5
G-Operational Le ror I Explam n 49/77) lloiher (Explain)
Eshibit i. Same Source I
1 UNIT SHUTDOWNS AND POWER REDUCTIONS DOCET NO. %-M6 UNIT NAME Browns Ferry Three DATE 6 85 REPORT MONTH May COMPLETED BY T.
Thnm TELEPHONE ?ns/??o ?sno n.=
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Cause & Curreceive E
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E 7s4 Licensee No.
Date i
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- 7 E-?
Action to f5 cE 35=
Repor:
- A0 E'
Preveni Recurrence 1
G 6
i 156 5/1/85 F
744 F
i The unit remains on administrative Cont hold until various TVA and NRC s:
concerns are resolved.
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3 4
F: Forced Reason:
Method:
Exhibit G Instructions S: Scheduled A-Equiprnent Failure (Explain) 1-Manual for Preparation of Data B Maintenance or Test 2-Manual Scram.
Entry Sheets for Licensee C. Refueling
- 3. Automatic St ram.
Evens Repose (1.l:R) File INURI:G-D-R gulatony Rev'iction 4 Other (Expiaml 0?611
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l' O, crator Tsa.r.ing A Lrcene 1%nu:utiori F-t.Inv m e; a.c
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0;s tainre el 1.irus t.xplanO
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I (9/77)
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BROWNS FERRY NUCLEAR PLANT UNIT 0
BF ISIL 30 CSSC EQUIPMENT ELECTRICAL MAINTENANCE SQ01ARY 9/29/82 For the Month of May 19 85 Effect on Safe
.\\etion Taken Nature of Operation of Cause.of Rest.is.s of To Preclude Dat7 System Component Maintenance The Reactor Malfunction Malfunction Recurrence 1985
- 5/3 RHRSW PT-23-0004 Resplice cable Grounded cable Pressure transmitter Respliced cable RHRSW header A Rll8 in J.B.
to PT-23-4 inoperable
. r; pressure 1274 MR 556183 transmitter 5/24 4-kV BKR-211-0C/02'2 Troubleshoot /
Broken secondary Breaker slow to trip Replaced contact shutdown ACB 1718 -
repair breaker connector block block and one boards &
normal supply contact pin busses breaker 4kV shutdown bd C MR 125000 g
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CSSC EQUIPMENT ELECTRICAL MAINTENANCE SD01ARY 9/29/82 For the Month of May 19 85 I
Effect on Safe i
Aetion T.sen Nature of Operation of Cause.of Results of To Preclude
! Dato System Component Maintenance The Reactor Malfunction Malfunction Recurrence 1984
'10/24 CO2 storago BATT-39-0001 Replace battery cell-5 would not Preventative mainte-Replaced battery
& fire fire protec-read on hydro-nance protection tion battery meter. Voltage No. 1 borderline
- MR 320031 1985 4/30 Control CHR-31-0007 Work with Bad proportional Chiller would not Replaced proportional bay heat, control bay -
factory rep controller load up controller vent & ac chiller 1-B on repairs MR 563586 Sf6 RPS FLY-99-5AK13A Monthly inspec-Generic problem Coil very hot
.: Replaced coil w Al neu non tion of RPS HFA with GE type HFA h 553007.
~
non-coincident relays (EMSIL relay coils NRC Inspection &
trip sensor 102.1) relay Enforcement Bulletin 84-02 5/9 4kV shut-27-211-001B Remove and Defective under-Preventative mainte-Replaced relay down bds undervoltage bench check voltage relay nance
& busses relay-4kV relay shutdown bd A
- MR 553055 i
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BROWNS FERRY NUCLEAR PLANT UNIT 3
t BF IL 30 CSSC EQUIPMENT ELECTRICAL MAINTENANCE SDDIARY 9/29/82 For the Month of May 19 85 Effect on Safe Action T:sen Nature of Operation of Cause.of Results of To Preclude
- Dat, System Component Maintenance The Reactor Malfunction Malfunction l
Recurrence 1984 Standby NVR relay d/g Replace NVR Defective no Loss of control room Replaced NVR relay diesel 3D no voltage relay voltage relay in annunciation generator relay 3D d/g engine control cabinet MR 255006 1985 1/2 Standby D/g exhaust Troubleshoot Bad actuator Oil leaking from Replaced actuator diesel fan motor oil leaking actuator on floor generator on floor MR 320560 3/27 Control CHR-31-1943 Troubleshoot Low pressure Chiller tripped on Adjusted setting on
~
bay heat-3A control CB chiller 3A switch out of low suction pressure low pressure switch ing vent bay chiller
& ac adjustment and would not restart
{MR558018 g
4/23 Standby PC-82-FTSND Troubleshoot 3D Bad low level Starts the fuel oil Replaced and adjusted diesel d/g 3D fuel d/g fuel oil start switch transfer pump No. I switch generator oil transfer transfer pump too soon pump controllei Iow level start
@ 521570 switch 5/2 480 volt CEN-268-3EN Replace 3EN Unknown Voltage fluctuation Replaced voltage reactor LPCI mg set LPCI mg set MOV bds 3EN voltage regu-
, regulator from ur LPCI mg set 2EA-lator MR 552290-from LPCi mg set 2DA-MR 591823 5/6 HPCI FCV-73-0027 Perform Wires rolled at Caused valve to cycle Rolled wiring on HPCI suppres-SI 4.5.E.1.c board & motor too fast board & motor sion pool out-to take strobe board suction light readings MR 258678 valve I
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BR6MNS FERRY NUCLEAR PLANT UNIT 3
BF E!!SIL 30 CSSC EQUIPMENT ELECTRICAL MAINTENA'JCE SU)DtARY Appendix B 9/29/82 For the Month of May 19 85 Effect on Safe Action T.eken Nature of Operation of Cause.of Results of To Preclude Dato System Component Maintenance The Reactor Halfunction Malfunction Recurrence 1985 May 6 480V GEN-268-3DN Troubleshoot Unknown Low voltage Replaced voltage reactor LPCI mg set cause of low regulator from LPCI MOV bds 3DN voltage mg set 2DN MR 521634 5/9 Radiation RM-90-0265 Motor not run-Bad pump motor Radiation monitor Replaced motor monitoring of f gas post -
ning - trouble-sample pump 1 will treatment rad shoot not run MR 567150 monitor
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sample pump 1 c$
5/16 Standby PNLA-82-003D Troubleshot Bad diodes in Engine started when Replaced diodes on diesel d/g 3D elect d/g 3D annunciation air compressor No. 1 1, 3, 4,16, and 16A generator control cabinel switch was turned relays from auto to stop MR 557226 I
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BROWNS FERRY NUCLEAR PLANT UNIT 0
CSSC EQUIPMENT MECHANICAL MAINTENANCE SUfMARY For the Month or May 19 85 EFFECT ON SAFE ACTION TAKEN 4
DATE SYSTEM COMPONENT NATURE OF OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE MAINTENANCE THE REACTOR MAf. FUNCTION Maf_ FUNCTION RECURRENCE 5/6/85 23 Al RHRSW Pump MMI-29 and NONE normal use vibration Impeller gap retorqued i
increased adjusted on baseplate bolts MR-A-317765 I
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l BROWNS FERRY NUCLEAR PLANT UNIT 1
CSSC EOUIPMENT MECHANICAL HAINTENANCE
SUMMARY
For the Month of May 85 39 EFFECT ON SAFE ACTION TAKEN DATE SYSTEM COMPONENT NATURE OF OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE MAINTENANCE THE REACTOR MALFUNCTION MALFUNCTION RECURRENCE 4/30/85 78 FPC Replaced Linge NONE worn excessively Leaking valve MR 592543 Pump A Dis-pin fabricated charge Check Valve 78-502 new pin I
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BROWNS FERRY NUCLEAR PLANT UNIT 3
CSSC EQUIPMENT MECHANICAL MAINTENANCE
SUMMARY
For the Month of May 19 85 EFFECT ON SAFE ACTION TAKEN DATE SYSTEM COMPONENT NATURE OF OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE MAINTENANCE THE REACTOR MALFUNCTION MALFUNCTION RECURRENCE 5/10/85 71 Flow Element Repair Flange NONE Flow element NONE Replace gasket 71-36 coflow element leaking
& repaired flange on MR 592634 I
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25 OUTAGE MAINTENANCE & MAJOR MODIFICATION MANAGEMENT May 1985 MAJOR WORK COMPLETED A.
Refuel Floor 1.
The fuel pool cleanup contractors arrived onsite May 6, 1985.
Cut up of unit 3 control rod guide surfaces was completed. The unit 2 and 3 fuel pools were sampled and the contractors left on May 24, 1985.
B.
Turbine No major work completed. The units 1 and 3 cranes were released for lifting. The unit 2 crane has not been released.
C.
Drywell 1.
Vessel drain was completed on May 2, 1985.
2.
J. P. Instrument nozzle replacement:
Cut-outs complete: May'S Weld preps complete: May 7.
Nozzle weld complete: May 15 "B" nozzle and piping complete: May 20 "A" nozzle and piping (rework) complete: May 30 3.
Torus heat cure was completed on May 15.
4 Radiographs were performed on SCRAM discharge headers (ECN P0392),
J. P. Instrument line nozzles and piping, and two Residual Heat Removal (RHR) and one Control Rod Drive (CRD) weld during the weekend of May 17-20.
5.
Weld GR-2-15 seal weld was completed on May 22, 1985. Final overlay still remains to be done.
26 OUTAGE MAINTENANCE & MAJOR MODIFICATION MANAGEMENT May 1985 MAJOR WORK COMPLETED (Continued)
D.
Major Valves 1.
Recirculation pump seal water valve replacement complete: May 8.
2.
Valve 23-582 maintenance complete: May 8 3.
R0 Valve replacements complete: May 8 22 E.
Balance-of-Plant 1.
"C" condenser work, including replacement of an 8" elbow, was completed on May 22, 2.
"2B" RHR pump motor was shipped to Atlanta for rewinding.
F.
Modifications 1.
ECN P0392 (Scram Discharge Header Modification) - tie-ins were complete and welds were accepted. Hanger work'is in progress.
Electrical work is 30% complete.
2.
ECN P0533 (Torus Temperature Monitoring) - panels are set, conduit and cable installation is 50% complete.
3 ECN PO415 (Feedwnter Header Temperature Monitors) - work is in progress, 155 complete.
4.
ECNs P0322 and P0323 (Wide Range Drywell Pressure / Torus Level) - are 20% complete.
5.
ECN P0354 (Effluent High Range Radiation Monitors) - work is 55 complete.
6.
ECN P0085 (Drywell Temperature / Pressure Monitors) - work is 5%
complete.
7.
IE Bulletin 79-01B modifications are 55 complete.
27 t
OUTAGE MAINTENANCE & MAJOR MODIFICATION MANAGEMENT May 1985 MAJOR WORK COMPLETED (Continued)
F.
Modifications 8.
Three Main Steam Isolation Valves will be disassembled due to vendor oversight.
CRITICAL PATH A.
Work Plan Approvals; Modifications Group May 1 June 1 Change Total Workplans 269 277
+8 Approved Workplans 100 118
+18 Outstanding Workplans 169 159
-10 Workplans in Approval Cycle 78 81 N/A B.
ECN P0126; Replace Transmitters with Analog / Trip System Conduit Installation Location May 1 June 1 Auxiliary Instrument Room 60%
90%
Elev. 565' 995 1005 Turbine Building 99%
100%
Spreader Room 90%
1 00%
Elev. 593' 20%
20%
Elev. 541' 20%,
60%
C.
ECN P0361; Torus Attached Piping Hanger Modifications Ranger Status by System:
May 1 June 1 HPCI 41%
44%
RCIC 44%
44%
RHR I 66%
73%
RHR II 64%
64%
CS I 79%
905 CS II 49%
805 Drywell Torus Purge 59%
75%
Total Number of Hangers (of 318) 161 193 RETURN TO SERVICE DATE:
June 1:
October 5,1985 May 1:
September 20, 1985 l
28 i
OUTAGE MAINTENANCE & MAJOR MODIFICATION MANAGEMENT May 1985 REMARKS Slippage of the scheduled end date from September 20 to October 5 (15 day slip in last 30 days) is attributed to increased work scope of ECN P0126 and to lack of priority on unit 2 efforts due to shift in priority to unit 3 work and support.
-g---
a., __..-m.
i wa nan tonio.eu NUCLEAR PLANT OPERATING STATIS, w
- Corrected Browns Ferry huclear 9
)
Plant Period Hours 719 Month April Item 19 35 No.
Unit No.
Unit-1 Unit-2 Unit-3 Plant I
Averace Hourly Gross Load. kW 0
0 0
0 2
Maximum Hour Net Generation. MWh 0
0 0
0
_ 3 Core Thermat Energy Gen, GWD (t)2 0
0 0
0 t
4 Steam Gen. Thermal Energy Gen., GWD (t)2
~~ -
8 5
Gross Electrical Gen., MWh 0
0 0
_0
~~~
5 6
Station Use, MWh 6,223 3.880 7,638 17,741 h
7 Net Electrical Gen., MWh
-6.223
-3.880
-7.638
- - ~ ~
5 8
Station Use, Percent
-17,741_ Y 0
0 0
0 9
Accum. Core Avg. Exposure, MWD / Ton 1 0
0 0
0 t
6 10 CTEG This Month,10 BTU 0
0 0
0 T
~
6 11 SGTEG This Month,10 BTU T_. g_ __~_~
13 Hours Reactor Was Critical 0
0 0
0 l '
~~
u.-.
14 Unit Use, Hours Min.
0 0
0 0
15 Capacity Factor, Percent 0
0 0
0
~ ~ ~ ~ ~
16 Turbine Avail. Factor, Percent 100 0
100 66.7 17 Generator Avail. Factor. Percent 100 0
_100 66.7 L_ _ _
4 O
18 Turbooen. Avail. Factor. Percent 100 0
100 66.7 t
19 Reactor Avait. Factor. Percent 100 0
_100 66.7 i_-~
~-
20 Unit Avail. Factor. Percent 0
0 0
0 1 __. _ _ _
21 Turbine Startuos 0
0 0
0
{__ ___ __
22 Reactor Cold startuos 0
0 0
Q 4
?3 1
24 Gross Heat Rate, Gtu/kWh 0
0 0
0 E
25 Net Heat Rate, Glu/kWh 0
0 0
0 3
26 i
w
?7 L. ~
g 28 Throttle Pressure, psig 0
0 0
0 j
~~~
d 29 Throttle Temperature, "F 0
0 0
0 i
-~
j 30 Exhaust Pressure, inHg Abs.
0 0
0 0
t
,E 31 Intake Water Temp., *F 0
0 0
0
- ~ ~ ~ ~~
H 32 33 Main Feedwater, M lb/hr 0
0 0
0
-~
j - -- -. - - -
o
-- )-
36 l
1 37 Full Povver Capacity, EFPD (3)
(4)
(5) 375
~
38 Accum. Cycle Full Power Days. EFPD (3)
(4)
(5) 70 T
' - ~ ~ - -
s 39 Oil Fired for Generation. Gallons
~ ~
6839 2
40 Oil Heatina Value. 8tu/ Gal.
13Q007(( ]
41 Diesel Generation. MWh
- 42.0 l
i 49 i
Max. Hour Net Gen.
Max. Day Net Gen.
Load
~
MWh Time Date MWh Date Factor, %
~
43 0
l 0
0
'N IFor 8FNP this value is MWD /STU and for SONP and WBNP this value is MWD /M TU.
O Remarks:
5 2(t) indicates Thermal Energy.
~ ~ ~ ~
5 (3)
Information furnished by Reactor Analysis Group, Chatt 3
~ ~ ~
(4) Environmental qualification modifications outage
~ ~ ~
(5) End of cycle-5 refuel outage Data Submitted Date Revisod pw
, ~
m.
.m nera tornou NUCLEAR PLANT OPERATING STATIS a
30
- Corrected Browns Ferry Nuclear Pla nt Period Hours Month March
_ _ _ In 35 Item
~~
1 No.
Unit No.
Unit-1 Unit-2 Unit-3 Plant 2..--
1 Averaae Hourty Gross Load. kW 985.558 0
1,072,171 1,013,963' 2
Maximum Hour Net Generation. MWh 1031 0
1086 2079 3
Core Thermal Energy Gen, GWD (t)2 54.5401 0
26.9945 81.5346
~~
4 Steam Gen. Thermal Energy Gen., GWD (t)2 l
'~
j 5
Gross Electricaf Gen. MWh 427.190 0
226,850 654,040 _
~-- ]
6 Station Use, MWh 14,788 2,528 11,675 28,991 h
7 Net Electrical Gen., MWh 412,402
-2,528 215,175 625,049 1
[$
8 Station Use, Percent 3.46 0
5.15 4.43
['~~_][]
9 Accum. Core Avg. Exposure, MWD / Ton 1 18,401 0
11.012 29,413 j_
6 10 CTEG This Month,10 BTU
- y 33 y 1 0 2.220.739 *6.979.4cM 11 SGTEG This Month,106 BTU
{_, _. _
12 13 Hours Reactor Was Critical 433.45 0
213.70 647.15
(__
14 Unit Use. Hours Min.
433:27 0
_211:35 645:02 L__
l u
e Ava. a Percent 0
Ob 66 7 j
17 Generator Avait. Factor. Percent 100 0
100 66.7 1 _ _,. __
,a t*
18 Turbogen. Avail. Factor Percent 100 0
100 66.7
)
19 Reactor Avail. Factor. Percent 100 0
81.9 60.6
{ _ _' ]~_
C 20 Unit Avait. Factor. Percent 58.3 0
28.4 28.9 v
21 Turbine Startuos 0
0 0
0 f
22 Reactor Cold Startuos 0
0 0
0 i[__ ~]
n 1
3 24 Gross Heat Rate, Btu /kWh
- 1,1.140 0
9.790
- 10.680 l
~
j 25 Net Heat Rate, Stu/kWh 3
26
_*11.540 0
10.320
- 11.170 i _
27 W
a 28 Throttle Pressure, psig 949 0
937 945
' l -.
[
29 Throttle Temperature, *F 538 0
537 538
{_--
] -]-
=a 30 Exhaust Pressure, inHg Abs.
1.22 0
1.25 1.23 E
31 Intake Water Temp., *F 58.8 0
54.6 57.4
, H 32
[
33 Main Feedwater, M lb/hr 11.9 0
12./
12.2 F
[
34 o
8~~
6 36 1
5 37 Full Power Capacity, EFPD (3) 346 (4) 373 38 Accum. Cycle Full Power Days EFPD (3)
(4)
J _ _] ~ "
j 39 Oil Fired for Generation Gallons 25,322
- _ _]
2 40 Oil Heatino Value. Btu / Gal.
140,900 1 41 DieseJ Generation. MWh 21.0
~]
4?
i Max. Hour Net Gen.
Max. Day Net Gen.
Load
~$
MWh Time Date MWh Date Factor, %
f a
43 2079 1300 3/1/85 50,113 3/3/85 40.4
{
O Remarks: IFor BFNP this value is MWD /STU and for SQNP and WBNP this value is MWD /MTU.
~
g 2(t) indicates Thermal Energy.
~~
5 (3)
Information Furnished by Reactor Analysis Group. Chattanooga
~~
0 (4) End of Cycle 5 Refuel Outane Dit] Submitted Date Revised p
TENNESSEE VALLEY AUTHORITY Browns Ferry Nuclear Plant
- Decatur, 1
35602 g
Wc9&O JUN 131985 60-139(,
Nuclear Regulatory Commission Office of Management Information and Program Control Washington, DC 20555 Gentlemen:
Enclosed is the May 1985 Monthly Operating Report to NRC for Browns Ferry Nuclear Plant Units 1, 2, and 3.
Very truly yours, TENNESSEE VALLEY AUTHORITY A1e G.
ones P1 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
[
An Equal Opportumty Employer b