ML20138B939
| ML20138B939 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 09/30/1985 |
| From: | Robert Lewis, Thom T TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| NUDOCS 8512120414 | |
| Download: ML20138B939 (26) | |
Text
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8 WLRAGE D.tlLY UN1I POWER LEVEL 50-259 DOCKET NO.
(JNIT Browns Ferrv 1 10-1-85 D \\TF.
CO\\!PLETED DY T. Thom 205/729-2509 TELEPHONE MONTli.__Septem.ber t
DAY AVER \\GC DAILY POWER LEVEL o.gy A\\,ER AG.. dally PObER LEVEL t
ngw. 3,,,
O!We-Net) 1
_10
,7
_9 2
-11
-12 3
rM la
_12
~11 20
-11
-10
.I
-12 6
-12
- 2 7
-10 23
-12
-11 3
24
-12 9
~
-12 n
-10 10 o
-12 il
-10 27
-12
-11 gs
-11
- g
-0 v3 29
-12 la
-10
.? 0
-12
-10 33 31 I,s
-10 INS TRL'C1 TONS Gn (Si< forrnal.!.st ISc m' ge dails uniit,s esses ks,.! is, yi,ig. g., i ' CJ'I' ddY i!* ll.c 8eP081133 nNn th. Ctiippate t ;
t!.e nearest whole meg ufi, 0"778 8S12120414 850930 PDR ADOCK 05000259 R
PDR t
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Significant Operational Events Unit-3 9/01 0001 The unit has been placed on administrative hold until various TVA and NRC concerns are resolved.
9/30 2400 The unit has been placed on administrative hold until various TVA and NRC concerns ere resolved.
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AVER \\GE D. illy UNIT POhER LEVEL 50-260 DOCKET NO.
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UNIT Browns Ferry 2 10-1-85 DATE C0\\lPLETED BY T. Then 205/729-2509 TELEPil0NE MONni September 1985 DAY AVER ACE D illy. POWER LEYtt
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A\\.ER AGE Dr:LY r0hER LEVEL
, y w,,,.,,,
t?.IWe Ne:)
-0
-6 g7
-6
-7 1.3
-6
-6 3
9
-6
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-6 5
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-6 23
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24
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-6 9
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-5
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-6 23
-5 W
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-5 30
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-6 INS TR Uf.'T!CNS Or, th'< f or:n :. !b: the serage J. n,,n:, p,.g c, r s eg,n 7,p,y,,y,, or ea.h da) in the reporting month. C.emp ;te su e
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4VER AGE DAILY UNIT POWER LEVEL DOCKET NO. 50-296 Brcvns Ferry 3 E'1T DATE 10-1-85 COMPLETED CY T. Thom TELEPHONE 205/729-2509
.i!0NT11 ScPtember 1985 D \\Y AVER AGE D A:LY POWER LE\\ LL I '.Y A\\ ER AGE (>AILY POWE'. LEVEL orw.Neti iMWe Net!
1
-9 17
-10
-9
-11
!3 3
-9 g
4
-9 20
-10 5
-9 2:
-11
-9 4
-11 33
,9
-11 33 3
-9
-9 9
-9 23
-9 9
IO 26
-8 II
-9 3,
-8 l.,
_9
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-9
- 3
-8 3 j
_9 14
_9
.10
~9 i$
11 I$
-9 l'iSiliUr IiGN3 On t!ue !.umet. !c.: !,c.i.ctr.;c dm uisi 6 iin, les,.] jn,ygift"33 g"' CJch day in the re'*ritzung iniinth. C.nr.pt.te so the r.t6tes: whole nyging,,
e 191771.
, r-11 OPERATING DATA REPORT DOCKET NO.
50-259 DATE 10-1-85 CO.\\lPLETED BY
_T.
Thom TEL,EPl!ONE W /729-2509 OPERATING STATUS
- 1. Unit Name:
Browns Ferry One Notes
- 2. Reporting Period:
Sentember 1985
- 3. Licensed Thermal Power (5tht1:
3293 l
- 4. Nameplate Rating tGross \\lhel:
1152 l
l 1065 S. Design Electrical Rating (Net 31We): -_-
- 6. Sinimum Dependable Capacity (Groo $1We):
1098.4 l
- 7. Stasimum Dependable Capacity (Net 31We):
1065 l
- 8. If Changes Occurin Capacity Ratings titems Number 3 Through 7) Since Last Report.Gise Reasons:
N/A 9 Power Lesel To which Restricted,If Any (Net SlWe):
N/A 1
l
- 10. Reascas For llestrictions. If Any:
N /A
)
This hi'onth Yr..to Date Cumut:ris e
!1.11ours in L porting Period 720 6.551
_.9_7 951 2
- 12. Number Of !!ours Reactor Was Critical 0
1,647.78 59,521.38
- 13. Reactor Reserve Shutdown !!ours 0
512.22 6,997.44
- 14. Ilours Generator On.Line 0
1,626.67 58,267.26
- 15. Unit Rewne Shutdown llours 0
0 0
- 16. Gross Thermal Energy Generated (5tWH) 0 4,950,821 168,066,787 17 Gross Electrical Energy Generated 15thil) 0
- 13. Net Electrical Energy Generated 15tWif)
-7,829
_ 1,652,650 55,398,130 1,559,896 53,773,717
- 19. Unit Service Fictor 0
24.8 59.5
- 20. Unit Availabili y Factor 0
24.8 59.5 t
- 21. Unit Capacity Factor IUsing StDC Net 1 0
22.4 51.5
- 22. Unit Capacity Factor iUsing DER Net 1 0
22.4
_51.5
- 23. Unit Forud Outage Rate 0
55.1 23.6
- 24. Shutdowns Seneduled Oser Nest 6 Stonths tType. Date,and Duration of Eacht:
- 25. If Shut Down At End Of Report Period.Esiimated Date of Startup:
9/14/86 2t. Units in Test Status (Prior to Commercial Opa:: tion):
Foreca<t Achiesed INITITI. CRITICALITY INITIAL ELECTRICITY CO\\131ERCI AL OPER ATION I'8/77)
12 OPERATING DATA REPORT DOCKET NO.
50-260 DATE 10-1-85 COMPLETED BY T. Thom TELEPilONE -205/729-2509 OPERATING STATUS
- 1. Unit Name:
Browns Ferrv 2 Notes
- 2. Reporting Period:
September 1985
- 3. Licensed Thermal Power (MW ):
3293
- 4. Nameplate Rating (Grou MWe):
1152 1065
- 5. Desi;;n E!ectrical Rating (Net MWe):
l 1098.4
- 6. Masimum Dependable Capacity (Gross MWe):
- 7. Masimum Dependable Capacity (Net MWe):
1065 S. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Gise Reasons:
N/A l
- 9. Power Lescilo which Restricted.lf Any INet MWe):
N/A
- 10. Reavms For Restrictions. !f Any:
N/A This Month Yr. to.Date Cumulative II. Ilours in Reporting Period 720 6551 92.838
- 12. Number Ofliours Reactor Was Critical 0
0 55.860.03
- 13. Reactor Reserte Shutdown llours 0
0 14,200.44
- 14. Ilours Cencrator On-Line 0
0 54,338.36
- 15. Unit Reserve Shutdown flours 0
0 0
- 16. Gross Thermal Energy Generated (MWil) 0 0
153.245.167 17 Gross Electrical Energy Generated IMWil) 0 0
50,771,798 IS. Net Electrical Energy Generated (MWil)
-4,196
-24,200 49,278.773
- 19. Unit Sersice Factor 0
0 38.5
- 20. Unit Availability Factor 0
0 58.5
- 21. Unit Capacity Factor (Using MDC Net) 0 0
49.8 0
0 49.8
- 22. Unit Capacity Factor ilhing DER Net) 0 0
23.0
- 23. Unit Forced Outage Rate
- 24. Shutdowns Scheduled Over Nest 6 Months (Type. Date.and Duration of Eacht:
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
April 1, 1986
- 26. Units in Test Status (Prior io Commercial Operation):
Forecast Achiesed INITIA L CRITICALITY INITI A L El.ECTRICITY 00\\lMERCI-\\ L OPER ATION 19/77)
--m..rm.-------_...___m 13 OPERATING DATA REPORT DOCKET NO.
50-296 DATE 10-1-85 COMPLETED BY T. Thom TELEPl!ONE 205/720-2309 OPERATING STATUS Browns Ferry 3 Notes gg,,
- 2. Reporting Period:
September 1985
- 3. Licensed Thermal Power (Mht):
3293 119~7
- 4. Namep! ate Rating (Grow S!We):
- 5. Design Electrical Rating (Net MWe):
1065 1098.4
- 6. Stasimum Dependable Capacity (Gross MWel:
1065
- 7. Masimum Dependabic Capacity (Net MWep:
- h. If Changes Occur in Capacity Ratings (Items Number 3 Through 7)Since Unt Report.Give Reasons:
N/A
- 9. Power Lesel To %hich Restricted,!f Any (Net MWe):
N/A
- 10. Reasons For Restrictions If Any:
N/A This Month Yr. to-Date Cumularise
- 11. Iluun in Reportin; Period 720 6551 75,263
- 12. Numi.e-Of floun Reactor Was Critical 0
1,517.65 45,306.08
- 13. Reactor Resene Shutdown ilours 0
508.05 5,149.55
- 14. Ilours Generator On-Line 0
1,496.96 44,194.76
- 15. Unit Resene Shutdown llours 0
0 0
- 16. Grow Thermal Energy Generated (MWil, 0
4,649,840 131,868,267 0
1,572,770 43,473,760 17 Gross Ekcarical Energy Generated (MWil) 11 Net Electrical Energy Generated iMWil)
-6,666 1,485,453 42,151,214
- 19. Unit senice Factor 0
22.9 58.7
- 20. Unit Availability Factor 0
22.9 58.7
- 21. Unit Capacity Factor (Using MDC Net) 0 21.3 52.6 0
21.3 32.6
- 22. Unit Capacity Factor (Using DER Net)
- 23. Unit Forced Outage Rate 100 77.1 24.5
- 24. Shutdowns Scheduled Oser Nest 6 Months (Type, Date.and Duration of Eacht:
i
- 25. If shur Down At End Of Report Period. Estimated Date of Startup:
March 1987
- 26. Units in Test Status (Prior to Commercial Operation):
Forecast Achie.ed INi flA L CRITICALITY INITI \\L ELECTRICITY COMM ERCl \\L OPER A flON o
(0!77 )
UNil Nilt'II; OWNS \\ND POWE:t iti.1;UCT.0?.*S DGCKET NO. 50-259 UNIT N AME _ Browns Ferry _1 j
DATE
.10-1-85__
!!i'i0.~tT MON 114 S.catembitr COMPLETED bY T.
iom IELEPiiONE 72 52509 l'
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UNIT mH "it. OWNS AND TiWEP. R!.DLL UO':S IRX't TNO..5D-191 UI IT N tME. n rovn n Ecr_ry 3 DATI. 10-1 85- - -
!:14. ):t I f.lON111 _Sentembf.I tOMPl.ETED BY _L Thom TLLEP!IONE 205/729-2509 _
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2 The unit remains on administrative (Cont) hold until various TVA and NRC concerns are resolved.
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BROUSS FERRY NUCLEAR P!.A:;T UNIT 0
Appendix B CSSC EQlflPMENT ELECTRICAL MAINTENANCE StaPIARY 9/29/82 For the Manth of September 19 85 Effect on Safe Action laken Nature of Operation of Cause.of Results of To Preclude Date Svstem Component
!!aintenance The Reactor Malfunction Malfunction Recurrence 1985 8/12 Control CilR-31-0013 Troubleshoot None Temperature load Control room, aux Recalibrated terrpora-bay heat, control bay temperature rist controller out of instrument room, and ture load controller vent & AC chiller "A" in control bay calibration computer room heating areas up MR 573175
- - - - ~ ~ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
U/14 Troubleshoot None Bad diaphram Chiller had high Replaced purge unit purge unit on on purge unit discharge pressure chiller "A" MR 584579 I;/16 High pres-PMP-26-0001 Check motor None Motor heaters
!!otor not opera ting Replaced heateru sure fire fire pump moto heater circuit burned out properly protection "A" to continue
!!R 581216 EMI 71
- E 4/19 Radiation MTR-90-152B Troubleshoot None Bad motor Motor had a ground on Pulled motor and se monitoring stack gas circuit &
the circuit to Power Service SI:
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sample pump B2 clear ground for repairs -
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MR 59014'l ie Installed im El stack
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1 pump -
MR 57724e, U
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3
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E CUJ led C
EED C
C 8
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C C
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BROUNS FElillY NUCLEAR PLANT UNIT I
B ' EMSit 30 CSSC EQUIP 1ENT ELECTRICAL ttAINTENANCE SDDIARY Appendix B 9/29/82 For the ?!anth of September 19 85 Effect on Safe Action Taken Nature of Operation of Cause.of Results of To Proclude Date System Component t!aintenance The Reactor Malfunction Malfunction Recurrence 1985 9/16 Cranes &
Refuel plat-Adjust interlocl None Limit switch out Would not operate Adjusted interlock hoists form track limit switch #1 af adjustment when it rolls upon switch #1 the track MR 590040
'9/16 480V shut-BKR-231-A/8C Troubleshoot None Loose bolts in Cear box leaking oil Replaced with spare down board ; 480V SD Bd 1A cause of oil gear box in compartment and breaker from 480V SD emergency
. leaking from on floor Bd 2B -
feeder bkr gear box F!R 5'77244/588105 Repaired 1A breaker -
f MR 587901 E
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N' b IIROITNS FERRY NUCLEAR PLANT UNIT 2
l I-IslL 30 CSSC EQUIPMENT ELECTRICAL MAINTENANCE SDt1ARY E "
9/29/82 For the Month of September 19 85 l
Effect on Safe Action Taken t
Nature of Operation of Cause.of Results of To Preclude Date System Component Maintenance The Reactor Malfunction Ital f unc t ion Recurrence 1985 9/16 Main steam IIS-001-55C Replace contact None Thread stripped llandswitch would not Replaced contact main steam block out on contact operate properly block on handswitch line drain terminal would not valve breaker tighten up
!!R 566955 handswitch 9/25 480V shut-BKR-231-2A/lC Troubleshoot to None Secondary contact Breaker would not Replaced contact pin down bds 2A 480V SD Bd determine why pin #5 bent trip when tested
- 5 normal feeder breaker will not bkr trip MR 644584 e
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BF DIS 1L 30
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Appendix B CSSC EQU1PMENT ELECTRICAL MAINTENANCE SUMIL\\RY l
9/29/82 For the Manth of September 1985 Effect on Safe-Action Taken Nature of Operation of Cause.of Results of To Preclude Date System Component Maintenance The Reactor Malfunction
!!al f unc t ion Recurrence 1985 8/5 Emergency Analog trip Troublenhoot to None Unknown Control room annuncia-MR 519179 core cool-unit (ATU)
Identify tion Electrical Maintenanci ing inverter 3A pr<blem Failure Investigation Div I
- 4791 1/15 Emergency Analog trip Troubleshoot None Unknown Gave control room MR 588754 core cool-unit (ATU) to Identify annunciation Electrical Maintenanci ing inverter 3B problem Failure Investigation Div II
- 4791 L
t 1/29 Standby RPM meter on Troubleshoot None Meter out of Meter not reading Recalibrated meter diesel D/G 3B faul ty meter calibration corre.:t RMP's generator engine control MR 566859 wo cabinet 1/24 Cranes &
Refuel Troubleshoot Bad fuse holders Grapple indicating Replaced fuse holders None hoists-platform
& replace
& fan motor lights not working &
& fan motor on main defective main hoist blower fan hoist components not working MR 581256 I/4 Control bay CHR-31-1951 Replace trans-None Transformer shorted Chiller not operat-Replaced transformer heat, vent 3B control ba3 former out ing
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I BROWNS FERRY NCCLEAR PLANT UNIT 0
CSSC EQUIPMENT IfECRAlllCAL !!AINTENANCE SUlG!ARY
~
For the !!onth of September 19 85 EFFECT ON SAFE ACTION TAKEN DATE SYSTEM COMPONENT HATURE OF OPERATIO'I OF CAUSE OF RESULTS OF TO 1RECLUDE MAINTENAUCE Tile REACTOR MAT. FUNCTION ttALFUNCTTON RECI'ARENCE 8-5-85 84 "B" CAD tank Repair Leaking continuous use MR 176647 repaired valve 84-563 valve valve l
8-5-85 84 "B" CAD tank Repair leaking age and use MR 176648 valve 84-561 valve repaired -
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. BRIE'ES.EERRY JUCLEAR JLANT UNIT 1
CSSC EQUlktmNT MEGANICAL !!AlllTETRUCE SUD!ABX For the Month of September 19 85 EFFECT ON SAFE ACTION TAKEN DP.TE SYSTat COMPONENT NATURE OF OPERATION OF CAUSE OF RESULTS OF TO PRECL1D2 MAINTENANCE TIIE REACTOR MALFUNCTION MAT. FUNCTION RECURREN('
9-19-85 64 damper 1-64-512 Tighten wall NRC concern construction /
MR 571537 e mounting bolt installation erri r to tighten for damper l
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2 CSSC EQUIPMENT HECHA1TICAL MAINTEl%IICE SUIEiRY For the Month of September 19 85 EFFECT 011 SAFE ACTION TAKEN
!WTE SYSTEtt COMPONENT NATURE OF OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE MAINTENANCE Tile REACTOR MAT, FUNCTION ffALFUNCTION RECURRENCE 9-19-85 64 Primary contain-Tighten URC safety FIR 571536 writtentpi ment purge foundation concern tighten bolts filter bolts 9
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TENNESSEE VALLEY AUTHORITY DIVISION OF NUCLEAR POWER BROWNS FERRY NUCLEAR PLANT MONTHLY OPERATING REPORT TO NRC September 1, 1985 - September 30, 1985 DOCKET NUMBERS 50-259, 50-260, AND 50-296 LICENSE NUMBERS DPR-33, DPR-52, AND DPR-68 Submitted by: d. 4. M
[,ActingPlantWanager D
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i TABLE OF CONTENTS Operations Summary.......................
1 Refueling Information...-..................
3 Significant Operational Instructions.............
5
^
Average Daily Unit Power Level.................
8 Operating Data Reports....................
11 Unit Shutdowns and Power Reductions..............
14 Plant Maintenance......................
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Operations Summary September 1985 The following summary describes the significant operation activities during the reporting period.
In support of this summary, a chronological log of s
significant events is included in this report.
There were six reportable occurrences and no revisions to previous occurrences reported to the NRC during the month of September.
Unit 1 The unit was in cold shutdown the entire month for the unit'2 end-of-cycle 6 refueling outage.
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 l
resolve various TVA and NRC concerns.
Prepared principally by B. L. Porter.
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2 Operations Summary (Continued)
Sep.tember 1985 Fatigue Usage Evaluation The cumulative usage factors for the reactor vessel are as follows:
Location Usage Factor Unit 1 Unit 2 Uni M Shell at water line 0.0^620 0.00492 0.00430 Feedwater nozzle 0.29782 0.21319 0.16133 Closure studs 0.24204 0.17629 0.14326 NOTE:
This accumulated monthly information satisfies Technical Specification Section 6.6.A.17.B(3) reporting requirements.
Common System Approximately 1.03E46 gallons of waste liquids were discharged containing approximately 3.88E-02 curies of activities.
1 l
l
3 Operations Sn===nv (Continued)
September 1985 l
Refuelina Tnformation Unit 1 l
Unit 1 was in shutdown for its sixth refueling on June 1,1985, with a scheduled restart date of March 1989 This refueling will involve loading 8x8B (retrofit) fuel assomblies 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 remained in cold shutdown until June 1,1985, because of unfinished modifications to meet environmental concerns.
There are 49 assemblies in the reactor vessel. The spent fuel storage pool presently contains 715 EOC-6 assemblies, 252 E00-5 assemblies, 260 EOC-4 assemblies; 232 E00-3 assemblies; 156 E00-2 assemblies; and 168 EOC-1 assemblies.
The present fuel pool capacity is 3,471 It 'ations.
Unit 2 Unit 2 was shut down for its fif th refueling outage on September 15, 1984, with a scheduled restart date of January 22, 1986. This refueling outage will involve loading additional 8x8R (retrofit) assemblies into the core, finishing torus modification, turbine inspection, piping inspection, THI-2 modifications; post-accident sampling facility tie-ins, core spray change-out, and feedwater i
sparger inspection.
There are no assemblies in the reactor vessel.
At month end, there were 273 new assemblies, 764 E00-5 assemblies, 248 E00-4 assemblies, 352 EOC-3 assemblies,156 E00-2 assemblies, and 132 E00-1 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 HDRs are being installed.
4 Ooerationa Summary (Continued)
September 1985 Refuelina Information Unit "4 Unit 3 is scheduled for its sixth refueling outage approximately 1
November 30, 197;, with a scheduled restart date of March 1987 This refueling involves loading 8x8R (ret.rofit) assemblies into the core, and complete reinspection of stainless steel piping. The unit was shut down on March 9, 1985, and will remain in cold shutdown until November 30,1985, on an j
administrative hold to resolve various TVA and NRC concerns.
There are 764 assemblies presently in the reactor vessel. There are i
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.
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5 Significant Operational Events Unit-1 9/01 0001 End of cycle 6 refuel outage continues.
9/30 2400 End of cycle 6 refuel outage continues.
4
6 Significant Operational Events Unit-2 9/01 0001 End of cycle 5 refuel and modifications outage continues.
9/30 2400 End of cycle 5 refuel and modifications outage continues.
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2.
TENNESSEE VALLEY AUTHORITY Browns Ferry Nuclear Plant Post Office Box 2000 Decatur, Alabama 35602 0CT 211985 Nuclear Regulatory Commission Office of Management Information and Program Control Washington, D.C.
20555 Gentlemen:
Enclosed is the September 1985 Monthly Operating Report to NR,C for Browns Ferry Nuclear Plant Units 1, 2, and 3 Very truly yours, TENNESSEE VALLEY AUTHORITY Y h ull' $
Robert 1. Lewis Acting 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 I
and Enforcement i
Nuclear Regulatory Commission Washington, D.C.
20555'(10 copies) l Mr. A. Rubio, Director Electric Power Research Institute P. O. Box 10412 Palo Alto, CA 94304 i
' I i
An Equal Opportunity Employer
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