ML18025B079
| ML18025B079 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 09/01/1980 |
| From: | Abercrombie H, Green D, Thom T TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML18025B078 | List: |
| References | |
| NUDOCS 8009170277 | |
| Download: ML18025B079 (36) | |
Text
TENNESSEE VALLEY AUTHORITY DIVISION OF POWER PRODUCTION BROWNS FERRY NUCLEAR PLANT MONTHLY OPERAT3$ G REPORT August 1, 1980 August 31, 1980 DOCKET NI2iBERS 50 259 j 50 260>
AND 50 296 LICENSE ~iBERS DPR-33, DPR-52, AND DPR-68
/
Submitted By.
Plant Manager
'277
It
TABLE OF CONTENTS Operations Summary Refueling Information
~
~
~
~
Significant Operational Events Average Daily Unit Power Level Operating Data Reports
~
~
14 Unit Shutdowns and Power Reductions.
17 Plant Maintenance 20 Outage Summary 28
0 erations Summer August 1980 The following summary describes the significant operational activities during the reporting period.
In support of this summary, a chronological log of significant events is included in this report.
There were eleven reportable occurrences reported to the NRC during the month of August.,
Unit 1 There were no scrams on the unit during the month.
Unit 2 There was one scram on the unit during the month.
On August 16, the reactor scrammed from closure of the HSIV's caused by the PCIS not being reset prior to testing the second switch during a surveillance instruction (resulting in a full isolation signal).
Unit 3 There were no scrams on the unit during the month.
2 0 erations Summar (Continued)
August 1980 Fati ue Usa e Evaluation The cumulative usage factors for 'the reactor vessel are as follows:
Location Usa e Factor Unit 1 lJnit 2
Unit 3 Shell at water line Fe'edwater nozzle Closure studs 0.00485 0.00368 0.00308 0.19498 0.12571 0.09060 0.22994 0.15706 0.11326 Note:
This accumulated monthly information satisfies technical specification section 6.6.A.17.B(3) reporting requirements.
Common S stem Approximately 1.38E+05 gallons of waste liquid were discharged containing approximately 7.96E-02 curies of activity.
Refuelin Information
" July 1980 Unit 1 Unit 1 is scheduled for its fourth refueling beginning on or about April 15, 1981, with a scheduled restart date of July 25, 1981.
This re-fueling will involve loading additional 8 x 8 R (retrofit) fuel assemblies into the core, the final fix on the sparger modification, power supply on LPCI modification, and torus modifications if all approvals are received.
There are 764 fuel assemblies in the reactor vessel.
The spent fuel storage pool presently contains 550 spent 7 x 7 fuel assemblies, five 8 x 8 fuel assemblies, and one 8 x 8 R fuel assembly.
Because of modification work to increase spent fuel pool capacity to 3471 assemblies, present capacity is limited,,to 1152 assemblies.
Unit 2 Unit 2 is scheduled for its third refueling beginning on or about September 5, 1980, with a scheduled restart date of October 16, 1980.
Resumption of operation on that date will require a change in technical specifications pertaining to the core thermal limits.
Licensing information in support of these changes will be submitted to the NRC before the outage.
This refueling involves replacing some more 7 x 7 fuel assemblies with 8 x 8 R (retrofit) assemblies, and power supply on LPCI modification.
There are 764 fuel assemblies in the reactor vessel.
At the end of the month, there were 132 discharged cycle 1 fuel assemblies, 268 discharged cycle 2 fuel assemblies, and 240 new p 8 x 8 R assemblies in the spent fuel storage pool.
The present storage capacity of the spent fuel pool is 820 asse'blies.
<i'ith present
- capacity, the 1979 refueling was the last
Refuelin Information (Continued)
July 1980 Unit 2 (Continued) refueling that could be discharged to the spent fuel pool without exceeding that capacity and maintaining full core discharge capability in the pool.
- However, new high density storage racks are being installed prior to the upcoming third refueling of Unit 2.
Unit 3 Unit 3 is scheduled for its third refueling beginning on or about October 17, 1980, with a scheduled restart date of November 25, 1980.
This EOC-3 refueling, involves loading additional 8 x 8 R (retrofit) assemblies into the core, and power supply on LPCI modification.
There are 764 fuel assemblies presently in the reactor vessel.
There are 144 discharged cycle 2 fuel assemblies, 208 discharged cycle 1 fuel assemblies, and 164 new P
8 x 8 R assemblies in the spent fuel storage pool.
The present storage capacity of the spent fuel pool is 1528 assemblies.
With present
- capacity, the 1980 refueling would be the last refueling that could be discharged to the spent fuel pool without exceeding that capacity and maintaining full core discharge capability in the pool.
0 Si nificant 0 erational Events Unit 1 Date Time Bvent 8/01/80 0001 Reactor thermal power at 98%,
maximum flow control rod sequence "A".
8/04/80 0300 0345 0405 0700 1400 1440 1500 Reduced thermal power from 98% to 85% for turbine C. V.
tests and SI's.
Increased thermal power to 90/, holding for control rod exercise SI.
Turbine C. V. tests, SI's, and control rod exercise.
SI completed, commmenced power ascension.
Reactor thermal power at 98%,
maximum flow.
Reduced thermal power from 98%-to 85% due to condenser high back pressure.
Commenced power ascension.
Reactor thermal power at 98%,
maximum flow.
8/09/80 2205 Reduced thermal power from 98% to 52% for removal of "B" recirculation pump MG set from service for brush replacement.
s/ao/so olio 0125 0235 0500 "B" recirculation pump MG set brush replacement completed and pump placed in service, holding at 52% thermal power for removal of "A" recirculation pump MG set from service for brush replacement.
"A" recirculation MG set removed from service for brush replacement.
"A" recirculation pump MG set brush replacement completed and pump placed in service, commenced power ascension.
Commenced PCIOMR from 65% thermal power control rod sequence "A".
8/11/80 1500 8/12/80 0400 0930 1243 Reactor thermal power at
>99%, steady state.
Thermal power reduced from >99% to 95% as a result of loss of preferred power.-
Commenced PCIOMR from 95% thermal power control rod sequence "A".
Reactor thermal power at
>99%, steady state.
8/16/80 0040 0320 0400 1500 Reduced thermal power from >99% to 80% for turbine C. V.
tests and SI's.
Turbine C. V. tests and SI's completed, commenced power ascension.
Commenced PCIOMR from 90% thermal power control rod sequence "A".
Reactor thermal power at
>99%, steady state.
s/as/so 2 oz Reduced thermal power fro~i >99% to 75% for control rod 18-39 solenoid maintenance and control rod pattern adjustment.
Si"nificant 0 erational Events Unit 1 Date Time Event 8/19/80 0210 0530 Control rod 18-39 maintenance and control rod pattern adjustment completed, commenced power ascension.
Reactor thermal power at
>99%, steady state.
8/22/80 2300 8/23/80 0200 0230 Reduced thermal power from >99% to 53% for control rod pattern adjustment, turbine C. V. tests and SI's.
Control rod pattern adjustment, turbine C. V. tests and SI'ompleted, commenced power ascension.
Commenced PCIOMR from 70% thermal power - control rod sequence "A".
8/24/80 2300 8/30/80 0015 0240 0700 Reactor thermal power 99%,
maximum flow.
Reduced thermal power from 99% to 80% for turbine C. V.
tests and SI's.
Turbine C. V. tests and SI's completed, commenced power ascension.
Reactor thermal power at >99%, steady state.
8/31/80 2400 Reactor thermal power at >99%, steady state.
Si nificant 0 erational Events
-Unit 2 Data Time Event 8/01/80 0001 0130 0300 1330 Reactor thermal power at 45% with power ascension in progress.
Reduced thermal power from 60% to 50% for control rod pattern adjustment.
Control rod pattern adjustment completed, commenced power ascension.
Commenced PCIOMR from 68% thermal power control rod sequence "B".
8/03/80 0700 8/04/80 1358 1540 1545 8/05/80 2222 Reactor thermal power at 96%,
maximum flow.
Reduced thermal power from 96% to 75% due to loss of plant preferred power and recirculation pumps run back.
Commenced power ascension.
Reactor thermal power at 95%,
maximum flow.
Reduced thermal power from 95% to 55% for control rod pattern adjustment.
8/06/80 0105 0330 0720 1055 1320 1630 Control rod pattern adjustment completed, commenced power ascension, control rod sequence "B".
Commenced PCIOMR from 70% thermal power.
Reactor thermal power at 75%, holding for removal of "A" reactor feed pump from service for maintenance (replaced vibration pickup).
"A" reactor feed pump maintenance completed and pump placed in service, holding for removal of "B" reactor feed pump from service for maintenance (replaced vibration pickup).
"B" reactor feed pump maintenance completed and pump placed in service, commenced power ascension.
Commenced'CIOM from 78% thermal power.
8/07/80 1800 8/10/80 0205 0320 0700 Reactor thermal power at 98%,
maximum flow.
Reduced thermal power from 98% to 85% for turbine C.V.
tests and SI's.
Turbine C. V. tests and SI's completed, commenced power ascension.
Reactor thermal power at 98%,
maximum flow.
8/ll/SO 2217 "B" recirculation pump ran back, due to 'electrical switching, reducing thermal power from 98% to 93%.
'7') 35 "B" recirculation pump run back reset, commenced PCIO~E from 93% thermal power.
Si nificant 0 erational Events Unit 2 Date Time Event 8/12/80 2320 8/15/80 2340 8/16/80 0155-0539 1322 1625 1933 1955 Reactor thermal power at 97%,
maximum flow.
Reduced thermal po~er from 97% to 80% for turbine C.V.
tests and SI's.
Turbine C. V; tests and SI's completed, commenced power ascension.
Reactor Scram No.
108 from 95% thermal power while performing SI 4.2.A-S (MSL Tunnel High Temperature).
Commenced rod withdrawal.
Reactor Critical No. 118, sequence "B".
Rolled T/G.
Synchronized generator, commenced power ascension.
8/17/80 0704 Commenced PCIOMR from 80% thermal power control rod sequence "B".
8/18/80 0600 8/19/80 0040 0115 1500 Reactor thermal power at 97%,
maximum flow.
Reduced thermal power from 97% to 80% for control rod pattern adjustment.
Control rod pattern adjustment completed, commenced PCIOMR from 80% thermal power, moving toward all rod out condition.
Reactor thermal power at 94%,
maximum flow, EOC 3
8/22/80 1500 8/26/80 2310 8/27/80 0907 1000 Reactor thermal power at 95%,
maximum flow.
Reduced thermal power from 92% to 75% for removal of "C" RFP from service for Special Test No. 185 (vibration checks).
ST 185 (vibration checks) completed and "C" RFP placed in service, commenced power ascension.
Commenced PCIOMR from 81% thermal power, moving toward an all rods out condition.
8/28/80 1050 8/29/80 2300 2342 Reactor thermal power at 94%,
maximum flow.
Reactor thermal power at 92%,
EOC-3 coast down.
Reduced thermal power from 92% to 80% for turbine C. V.
tests and SI's.
8/30/SO 0230 0700 2300 Turbine C. V. tests and SI's completed, commenced power ascension.
Commenced PCIOMR from S5% thermal power.
Reactor thermal power at 92%.
8/31/SO 2400 Reactor thermal power at 92%,
EOC-3 coast down continues.
Si nificant Operational Events Unit 3 Date Time Event 8/01/80 0001 2215 Reactor thermal power at 94%,
maximum core flow rod limited (sequence "B")".
Reduced thermal power from 94% to 51% for removal of "B" recirculation pump MG set from service for brush
'eplacement.
8/02/80 0310 0700 0730 "B" recirculation pump MG set brush replacement completed and pump placed in service, holding for control rod pattern adjustment.
Control rod pattern adjustment completed, commenced power ascension.
Commenced PCIOMR from 66% thermal power control rod sequence "B".
8/03/80 1830 8/04/80 0900 1500 8/09/80 0105 0310 0555 1245 1430 Reactor thermal power at 94%,
maximum flow rod limited.
Corznenced power ascension by withdrawing control rods.
Reactor thermal power at 99%,
maximum flow.
Reduced thermal power from 99% to 47% for control rod sequence exchange from "B" to "A".
Control rod sequence exchange completed, commenced power ascension.
Reactor thermal power at 60%, holding for TIP run.
TIP run completed, commenced power ascension.
Commenced PCIOMR from 77% thermal power - control rod sequence "A".
8/11/80 0310 0505 0535 1207 1905 Reactor thermal power Reduced thermal power feed pump trip on low "A" reactor feed pump ascension.
Commenced PCIOMR from sequence "A".
Reactor thermal power E
at
>99%, steady state.
from >99% to 85% due to "A" reactor oil pressure.
placed in service, commenced power 95% thermal power, control rod at
>99%, steady state.
8/13/80 1500 8/16/SO 2210 Reactor thermal power at 99%,
maximum flow.
Reduced thermal power from 98% to 63% for control rod pattern adjustment.
8/17/SO 0125 0230 Control rod pattern adjustment completed, commenced power ascension.
Commenced PCIOMR from 78% thermal power control rod sequence "A".
10 Si nificant 0 erational Events 0 Unit 3 Date Time Event 8/18/80 0700 8/22/80 2207 Reactor thermal power at 99%,
maximum flow.
Reduced thermal power from 99% to 65% for removal of "B" condensate booster pump from service for maintenance.
8/23/80 0145 0315 1900 "B" condensate booster pump maintenance completed, commenced power ascension.
Commenced PCIOHR from 85% thermal power, control rod sequence "A".
Reactor thermal power at 99%,
maximum flow.
8/30/80 0030 0200 0800 Reduced thermal power from 99% to 80% for turbine C. V.
tests and SI's.
Turbine C. V. tests and SI's completed, commmenced power ascension.
Reactor thermal power at
>99%, steady state.
8/31/80 2400 Reactor thermal power at >99%, steady state.
(1) Personnel error.
P l
I AVERAGE DAILYUNITPOWER LEVEL DOCKET NO.
UNIT DATE COi1PLETED BY 50-259 Browns Ferry 1 9-1-8 Ted Thorn TELEPHONE 205 729 6846 MONTH Au ust 1980
. DAY AVERAGE DAILYPOWER LEVEL IIIWe-Net )
991 DAY AVERAGE DAILYPOWER LEVEL (SIWe Net) 1023 17 10 13 15 16 1013 1011 1013 1032 1016 1019 1010 977 716 971 1021 1017 1026 1030 971 18 19
'lP 21 23
'75 26 27 28 99 30 31 1009 988 1027 1030
'1018 03 1008 1014 1023 1028 1032 1029 1025 1035 INSTRUCTIONS On this tortnat.!1st the as'efa;e daily, unit poa'<.'r Iesel in F15'e.Net I'or each dJy in the fepnflin8 ll'lnnlh. Cnnlpule ln lhe fleafest <<lnlle nlee<ai'Patt.
l~ll771
12 AVERAGE DAILYUNITPOWER LEVEL DOCKET NO 50-260 Browns Perry 2
DATE COMPLETED BY Ted Thotrt TEf PPHONE 205 729 68 MONTH DAY AVERAGE DAILYPOWER LEVEL (MWe-Net I 631 DAY AVERAGE DAILYPOWER LEVEL IMWe.Net) 788 lp l3 IS 886 1005 990 971 755 1026 1016 1019 1 0 997 994 272 IS 19 20 2l 23
'l5 26 27 28
'l9 30 3I 986 955 974 969 964 965 959 950 944 815 972 926 957 INSTRUCTIONS On t!tis iornnt.!!st thc average Gaily unit pnrccr IclcI ln 11'tVC Nct iof chch dly tn thc rcpnrtin tnnnth. Compute tn tile nccrcrl tcllulc tnc3JN'nit.
('tr77)
13 AVERAGE DAlLYUi"IITPOlVER LEVEL COMPLETED GY TELEPHOgE 205 729 6846
'ugust 1980 DAY AVERAGE DAILYPOb'ER LEVEL
{MIVe.<1 et )
731 DAY AVERAGE DAILYPOlVER LEVEL (MlVe.Net )
870'7 1063 999 1056 19 80 1057 1062 10 13 15 16 1065 1061 1040 101 1054 1023 0
1034 1003 13 75 26 28 o9 30 31 1Q38 974 1054 1Q57 1063 1066 1060 1057 1045 1066 INSTRUCTIONS On t'!tilfortnat. hst the underage dulls'nit poaer Ieiel in balll'e Yet for i@eh day in the reporting tnonth. Contpute to tlje tte3 f erat N lto!e ta eeghvut t ~
(it/77 1
14 OPERATl>VG DATAREPORT OPERATING STATUS DOCKET NO.
DATE 9-1-80 COl>IPLETED BY e n TELEPHOVE 6846 iVotes U>i>f N >nie Browns Ferrv - Unit 1 t>n P'rh>d:
Au ttsr 1980
- 3. Licensed Thermal Power'MlVt):
- 4. Na>neplate Rating (Gross!>ItVe):
1152
- 5. Deiign Electrical Rating (Net lilVe):
- 6. ~lamin>u<n Depen<lable Capacity (Gross MWe):
- 7. ~laxi>nu>n De endable Ca acitv Iiiet ~flVe:
1098.4 1065 p
p
.(
)
- 8. IfChan"es Occur in Capacity Ratings (Items >Vumber 3 Through 7) Since Last Report. Give Reasons:
- 9. Pn<ver L<<vcl T<> VVhich Restricted, IfAny (<Vet!>INe):
- 10. Reaioni F<>r Restricti<>ns. IfAny:
This Month Yr.-to-Date 5 855 744
- 11. Hours ln Reporting Period
- 12. >Number Of Hours Reactor IVas Critical
- 13. R<<actor Reserve Shutdown Hours
- 14. Hours Generator On. Line
- 15. Unit Reserve Shutdnivn llours
- 16. Grosi Thermal Energy Generated (MPH)
- 17. Gross Electrical Energy Generated
(~IIIVH)
- 18. Net Electrical Fnergy Generated (ihOVH)
- 19. Unit Service Factor
- 20. Unit Availability Factor
- l. Unit Capacity Factor (Using l>IDC Vet)
- 22. Unit Capacity Factor (Using DER <Vet)
- 23. L'nit Forced Outage Rate
- 24. Sill>ld<>wns Scheduled 0'v<'.f lilext 6 i>Ionths 3,653.13 744 3 524.43 744 0
0 10,254,956 2,362,150 766,580 3,297,780 741;958 3,194,295 60.2 100 60.2 100 51.2 93.6 51.2 93.6 11.2 0
IType. Date. and Duration uf Each I:
Cumulative 53 353 31,930.41 4
31 137.16 0
84,391,449 27,816,240 26,996,263 58.4 58.4 47.5 47.5 31.1 i5. IfShut 1)oivn At End Of Re pnrt Period, Estimated Date of Startup:
'o. Uniti In Teit Status tpri<>r to Con>mercial Operation):
Forecast Achieved INITlAL CRITlCALITY INITIAL ELECTRICITY CO.'>OI ERCIAL OPERATION (9/77)
15 OPERATIi cG DATAREPORT OPERATING STATUS
- l. Unit Name v-nit 2
Reportjnz Period.
Au ust 1980
- 3. Licensed Thermal Power (IIIVt):
- 4. Nameplate Rating (Gross IIWe):
1152
- 5. Design Electrical Rating (Net IIIVe):
- 7. XIaxhnunt Dependable Capacity (Net illWe):
1065 Notes DOCKET NO.
DATE COMPLETED SY Don Green TELEPHONE ~~'~846
- 8. IfChan es Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:
N/A
- 9. Povver Level To Which Restricted, IfAny (Net IIWe);
N/A
- 10. Reasons For Restrictions. IfAny:
This Month Yr..to.Date I I. Hours In Reporting Period 744 5 855
- 12. Number Of Hours Reactor Was Critical 7 33 ~ 23 5,185.33
- 13. Reactor Reserve Shutdown Hours 10.77 648.94 I4. Hours Generator On.Line
'29.73 5 052.32
- 15. Unit Reserve Shutdown Hours 0
0
- 16. Gross Thermal Energy Generated (IIWH) 169 170 1
~ 585
'7. Gross Electrical Energy Generated (MWH) 4,838,890
- 18. Net Electrical Fnergy Generated (NIWH) 6 6 119 4
- 19. Unit Service Factor 98.1 86.3
'0. Unit Availability Factor 98.1 86.3 I. Unit Capacity Factor (Using ~IDC Net) 75.4 2
. Unit Capacity Factor (Using DER Net)
I
'3. Unit Forced Outage Rate 1.9 12.~
'4. Shutdowns Scheduled Over Next 6 ~Ionths(Type. Date.and Dur'ation of Each):
Reruel outage September 5, 1980, 42 days.
Cumulative 48,264 29,669.81 12 423.88 28 716.63 0
80 740 799 26 788,958 26.030 899 59.5 59.5 50.6 50,6 33.6
'5. IfShut l)oivn At End Of Report Period. Estimated Date of Startup:
'6. Units ln Test Status (Prior to Cotnmercial Opemtiun):
Forecast Achieved INITIAL CRITICALITY INITIALELECTRICITY COiDIERCIALOPERATION (o/77)
16 OPERATING DATAREPORT OPERATING STATUS DOCKET NO.
DATE 9-1-80 CO~IPLETED BY Don Gree>
TELEPHONE ~~EM846 Notes I. Unit Name Browns Ferr Unit 3
- 2. Reportinu period:
Au ust 1980
- 3. Licensed Thermal Power (>IWt):
- 4. Nameplate Rating (Gross IIWe):
5.
Design Electrical Rating INet IIWe):
1065 6 ~ >Iaxhnu>n Depentlable Capacity (Gross a>IWe):
- 7. Ilaxin>u>n De >endahle Ca acitv Net hIIVe:
1098.4 1065 p
.(
)
II. IfChan es Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Gimme Reasons:
N/A 9.
Pd>>ver Level Td> Which Restricted, IfAny (iVet II'lVe):
- 10. Reasons Fd>r Restrictions. IfAny:
This 4>Ionth
- 11. Hours ln Reporting Period I
. Number Of Hours Reactor Was Critical
- 13. Reactor Reserve Shutdown Hours 0
- 14. Hours Gvnterator On Line 744 IS. Unit Reserve Shutdo>vn llours"""t
. Gree: El'errieat Ener y Generated >tlttH)
~~~>
4>G IS. Net Electrical Energy Generated (IIWH)
- 19. Unit Service Factor 100
'0. Unit Availability Factor
- l. Unit Capacity Factor (Using MDC Net) 95.2 '
. L'>>it Capacity Factor(Using DER Net)
- 95. 2
'3. Unit Forced Outa e Rate 0
- 24. Shutdovvns Scheduled Over Next 6>>Ionths(Type. Date. and Duration Refuel outage October 1980.
Yr.~to-Date 5,855 5,100.22 101.63 5,003.13 0
5 217 450 5 073 556
- 85. 5 81.4 81.4 14.5 of Each):
Cunt ula It'vc 30,719 24,007.77 1 759.94 23,440.94 0
22 620 030 21,961,329 76.3 76.
67.1 67.1 10.3
- 25. IfShut I)>>wn At End Of Report Period. Estimated Date of Startup:
- o. L'nits In Test Status (Prior to Conlltlercial Operation):
Forecast Achieved IN IT IA L CRITICALITY INITIAL ELECTRICITY CO.'>I!>IERCIAL OPERATION (o/77)
~ ~
~
e e
~
UNITSI IUfl)OWNS ANI)PONtER REI)UGTIONS IICPORThlONTll~<<> <L<C I)0(.hET NO.
UNITNAME I)ATE COhI PI.ETEI) ItY TELI I'IIOIVI!
50-259 Browns Ferr 1
Don Green 205 729 6846 Vlh.
I).It>>
~rh Ir, II n
CI II)
I Iee)lsee Evenl Rcporl -"
CI CI w'G
~ l) o ~
o
( ause i%. ( >>Ifeel>ve Act>on lo I reveal lb.l.uffI,nu.
140 800809 B
Deratcd for recirculation pump HG set brush replacement 141 800818 B
Derated for maintenance to control rod 18-39 142 800822 H
Derated for control rod pattern adjustment Ih' I
J' I
I': Forced S: Scheduled l )/77)
Rcasorl:
A.l'.Iluipmenl Failure (Explain)
B.hlaintcnance or Test C.Refueling I) Retlulalory Restriction I'. Operator Training &. License Exantination E-Administrative
(;.Operational Iilr(>r(Iixplain)
I I.0 Ih c I ( Iixpl a hl )
hlcthod:
I.hlanual 2.hIa nual Sera ln.
3 Anion):IlicScram.
~I.Other (I)xplain)
Exhibit G - Instr<<>>lions for Pf>>paration ot l)ata I'.ntry She>>ls I'or l.ice>)s>>c I:v>>ni Report (I.I!RII'il>> (NURIYI~
016) I I 5
lixhibit I
~ Sa)n>> Soul>>>>
~ ~
UNITSIIUTI)OWNS ANI)POWER REI)UCTIONS REPORT hlON'Ill Au ust l)OCKET NO.
UNITNAhlE l)ATE COhll'I.ETEI) BY TELEI'IIONE 50-260 Browns Ferr 2
Don Green 205 729 6846 N>>.
I)Jle Cr
~ll I.lccosce fervent Rcporl +
t cr cr
'
c.
CI o
Cause
&< ('orrcclivc Acl>oo I>>
I feveol Recurrence 152 800804 H
crated due to loss of plant preferred power 153 800805 H
Derated for control rod pattern adjustment 154 800816 F
14 27 G
Personnel error while performing SI 4.2.A-8 I
I.: I'orced S: Schedule<I
()/77)
Reason:
A.l)<luipmcnt Failure (Explain)
B hlaintcnancc or Test C.Rct'uelh>g I) RegulJlory Rcslr<>>lion I!.Operat<>r Training &: Liccnsc Examination I -Adouo<sl<JI<vc (r'.Operational Error (I!xplain)
I I.Other (L'xplaio) hlethod:
I.hl an u J I 2 hlanual Scra<n.
3-Auto>oalic Scrao>.
4 Other (I)xplalo)
Iixhibit G - instructions I'or Pr>>par:Itioo ol')ata Entry Sl>>>cts tor L<c>>os>>e I veo> Report
( LI!R)I'il>>(NURI!G-0I 6) I )
Exhibil I -Sa<ne S>>uree
VNITSIIV1 l)OWNS ANI)POWER HEI)VCTIOiVS REPORT MONfit~Au us t l)OCyET No.
50-296 Browns Ferr 3
I)AgE 9-1-80
('Ohfp(.ETEI) lty Don Green N>>.
l).>fc ss O
J IY I/)
I.iccoscc Event Rcport >
( ols> 8. ( I>flc.>.tl'LE.
Acti>>n lc>
I fCVCOI Recur lf.'nc>s 139 800801 Derated for oB" recirculation pump brush replacement and control rod pattern adjustment 140 800809 H
Derated for control rod sequence exchange from oB" to oAo 141 800816 Derated for control rod pattern adjustment 142 800822 B
Derated for oBo condensate booster pump maintenance s i
~
~
I': Forced S: Schcdolcd
(')/77)
Reason:
A-Equipmcnt Failure (ExplJin)
Bhiai<<tcnancc oi Test
('efueling 1).Regulatory Rest Iiclion I'..OpcfJlof TIJ)ning &. IJccnsc ExJnllnJIII)n I -Adfnioistrativc (s.Opcratf>n)JI Lrror (I:xpla)n)
I I Other (I:xplaio) 3 Method:
I -hlaoual 2 hlanual Scram.
3.Autofn:Itic Scram.
4.Other (lixplaio)
Exhibit G
~ Instructions fc)r Preparation ot f)ata I:fIffySheets tof l.iccnscc Event Rcpoft (I.ER) I'ilc(N(IREG.
OI 6> I )
(exhibit I - S;>>nc Source
'L ~
E
~
C
t:.",.",(: I;rPII I II!:.III.
llllo'.IIIS 'l!IIIH'IUCtl il, tta;IT UIIXT t I r.!XTI<XCAI. IIAXIITE;IAIICCSu! IIIAIn I'or tlie TIonth of Aiigiist:
19 80 D,".te Sy t c<.".
Component llatu re of Maintenance R
act anna a
Operation of Tha Ra.".eton Cause of Haltunctton Result" of
~nialfunc tion Action Taken To Preclude R"currence 8/10/6')
I'nmary Contain-illell L'Cv-64-5 Refueling zone air supply outboard iso-lation damper-getting open-closed indica-tion (red-gree light) ~
None I,imit swit:ch out of adjustment Incorrect.po'sition indicaLion Adji)sted limir swi t:
I tlits and 1 tmt Ls operating l>roperly cliecl<ed ol'ay.
TI( II178101 8/19/80 CIID CIA Module 18-39 One of the scram solenoid valves on CRD module 18-39 is intermitt-ently dropping out.
None Bad Coil Solenoid valve dropping out.
Replaced coil-c!iecked ol'ay.
Tlt I/178146 l8/19/80 CRD I
1B'RD pump breaker needs adjusting.
None Breaker linkage out of adjustment Breaker was trip-froe Adjusted trip free linkage - works properly now.
'I'R //170696 t 8/ 14 /80 RIIR 1A RIIR pump area cooler 1A RIIR pump area cooler fai was found trip ped on thermal overload.
None verload trip ~
rating was set t:oo low Adjust.ed over I
t:o correct set ing clieck okay.
.I'R l/129327,
- 1706i99, and 181,723 I.I':R No, BI:RO-50-25',t 8061 lA RIIR area cooler.
inoperable causing lA RIIR pump to be considered Nnoperabl per the Teclinical Specifications.
BVOTBV PJ!itVT 'lVCLE/,ll PL~VT VHIT EII'-CTR'ICAI lfAIllTE1fAflCESUHffARY D;.te I 8/24/RD System Primary Contain-ment Component 16A-K20 relay ffat:ure of Haintenance 1<eplaced relay 36A-K20 panel 9-43 drywell FD sump pump breaker inter-lock with valv fP ect on ha e
Of>eration of
'i'he Reactor Hone Cause of Halfunction Coil open Ifesults of ifalfunction Stopped drywell flon (lrain sump pump Action Taken To I'rec iud e Recurrence Replaced cui.l.-
cllecl(e(l ol(ay
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'f'l 81S0427
( Sll(
I:OIJI Pl II IIT EEO!'HS",l;El;Y UUCCEA!: l'LAST Ul!XT EL!'-CTRICAI. HAIII'1'BIAIICESUIIIIARY Jtt I);.tc System Component Nature of Haintenance Effect on Sn n
Operation of The Reactor Cause of Halfunction Results of
~>!alfunction Action Taken To Preclude R"currence 8/30 jf)0 I',IIR 8/25/80 RCIC 3A IGIR Room Hagnetic Pi,ck up for speed signal to EGI!
3A RIIR Room Cooler fan 4xO ACB therma.
overloads trip ping Repair connec-tor for mag-netic pickup None None Bad overload relay Plug pulled off 3A RIIR area Cooler inoperable causing 3A RIIR pump to be considered inoperabl per the Technical
~S ecifications.
No speed signal to EGH @hie)i made RCIC inoperable.
Installed nm~ relay checl'ed okay.
'I'l /I l,78898 I.ER No.
IIFI(0-50-296'034
~
Replaced connect>>r.
Operations to test-checI<ed oltay
'I'l 8148297 LER No.
IIFR0-50-29(>,
8832
C!'~!'C 8 llfr:Ir8:T HECIIAIIICAL HAIN1'ENANCE SU?" fARY For the Noeth of cutout 19 80 DATE 8/6/80 8 8/80 8/21/8(
8/19/8(
SYSTEII RB( CIJ Diesel Generator IIPCI CRD CGHPOa~EI IT Pump lB Diesel Generator D
FCV-1-73-6B CRD Hodule 18-39 NATURE OF HAINTE'll4? ICE Excessive leakage No.
2 air comp.
suction relief lifts contin-uously Leaking valve Scram pilot valve is ex-hausting inter-mittently EFFECT C:I SAFE OPERATION OF TIIE REACTOR None None None None CAUSE OF K'tLFIJNCTION Bad seal Blown head gasket Packing leak Pinhole in diaphr on pressure side of valve PESULTS GF HALFU:ICTIO'I Leakage Blown head gasket Leaking valve gm I.caking valve A:;Ti.o."t i"t!:r.tI
'IQ I'RECLUSE R
(.(fI?RE.h.~E Replaced seal TR 181030 Changed head gasltt!
TR 177910 Tightened packing TR 103499 Replaced both diaphragm solenoid
- base, subassembly all o-rings
-TR 153460
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CSSC FX~UI "lEUT 2
IIECIL'NlCALKKIHTEI ENCE SUYIARY For the Iionth of August 19 80 L"~IE 8/1/80 SYSTEIf CRI)
CGHPONEIIT CRD Nodule 30-51 NATURE OF PAINTElIANCE Leaking valve EFFFCT ON SAI:F.
OI'ERATIGti OI'I" t!F. Rl'.ACTOR None CAUSE OF H:I.FUNCTION Scram outlet valv Ieaking through HESUL1'S OP HALFUIICTION Leaking valve
'IQ I':"J:.,LLZ'.
PECURRF'iCE Lengthened valve stem TR 1534I>8 8/12/80 lll'CI Inboard ruptur Rupture disk is disk leaking None Rupture disk seal is leaking IIPCI isolated Replaced disk TR 103659
~ ~
CS."0 FXlIJII'alii.'T FIECIb',IJICAL HA IN'ANCE SURLY.RY 3
For rbo Hoorh of ~Au uur 1980 D.'~TE SYSTE11 CrJadPO~rer.IIT NATURE OF HAIIITHIIANCE EFFECT 0 I SAFE OPERATIG:x OF TIIE REACTOR CAUSE OF V~LFU:iCTTON RESULTS GF IQLFUNCTIGN AC I. IO.I IQ I:RECLUD;-:
r'.FCURKi!ir.":
8/21/80 lligh Pressure I'Ire Pro-tectioll Drain valve 3-26-87 Leaking valve None Leaking valve Leaking valve Tightened valve TR 170192
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CSSC EQUIP:IEI!T Common I'IECIIANICALI'fAIIi'-ENHANCE SUI'IiARY For tl>e Hontl> of August 19 80 Q
0
~
SYSTElf CGI1POIiEHT NATURE OF E'.IhTENANCE EFFECT Oi'i SAFE OPERATION OF TIIE REACTOR SE OF K'MALFUNCTION RESULTS GF IALFU:!CTXON
'IO i'l!=.0: I.r3.":
RECURRENCE 8/13/8(
RIIRSW Fump Cl Bad leak on bal trap vent None Gasket tom up on baal trap Tom gasket Replaced ball tral gasket TR 170372
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CSSC E, UIPMENT BROGANS FERRY NUCLEAR PIaQlT UNIT INSTRUlKNT MAINTENANCE SUlQfARY FOQ THE MONTH OF August 19 8O DATE SYSTEM Unit 1
COMPONENT NATURE OF MAINTENANCE EFFECT ON SAFE OPERATION OF THE REACTOR CAUSE OF MALFUNCTION RESULTS OF MALFUNCTION ACTION TAKEN TO PRECLUDE RECURRENCE 8-4 Unit 2 8-13 Containment 1>>r rting Primary Containment FT-76-16 PdT-64-138 Calibrate Calibrate None None Zero Drift Zero Drift Indicated Flow with System Off Indication Did Not Agree with Re-dundant Indicator None None Unit 3 8-5 P rimary Cont ainmen t Pdic-64-2 Repair None Pneumatic Motor Leak Reactor Zone Damper Not Functioning Properly None
28 OUTAGE Sl&&fARY August 1980 During the past month preparation for the Unit 2 cycle 3 outage have progressed on schedule.
Numerous pre-outage work items have'been completed.
Work continued on the modification program including the Hypochlorite facility, the LLRW Facility, Outage Fabrication Facility, and the moving of the East Portal.
Work was started on the generator breaker modification and prefab-rication of piping for use during the upcoming outage.
The work schedule for the Unit 2 EOC 3 outage was finalized during this reporting period.
Plant sections have provided their anticipated work schedule which has been included in the 'total outage schedule.