ML18025B122
| ML18025B122 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 10/02/1980 |
| From: | Green D, Thom T TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML18025B120 | List: |
| References | |
| NUDOCS 8010150335 | |
| Download: ML18025B122 (31) | |
Text
TENNESSEE VALLEY AUTHORITY DIVISION OF POWER PRODUCTION BROWNS FERRY NUCLEAR PLANT MONTHLY OPERATING REPORT September 1, 1980 - September 30, 1980 DOCKET NUMBERS 50-259, 50-260, AND 50-296 LICENSE NUMBERS DPR-33, DPR-52, AND DPR-68 Submitted By:
lant Manager
i
~
~
e
TABLE OF CONTENTS Operations Summary Refueling Information Significant Operational Events Average Daily Unit Power Level 10 Operating Data Reports 13 Unit Shutdowns and Power Reductions.
16 Plant Maintenance 19 Outage Summary 25
l
0 erations Summar September 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 twenty-three reportable occurrences, one revision to these occurrences, and two cancelled reportable occurrences, reported to the NRC during the month of September.
Unit 1 There were two scrams on the unit during the month..
On September 1, the reactor scrammed when water from the offgas cooler dripped onto the stator cooling cabinet causing a short in a pressure relay and tripping the turbine.
The reactor scrammed on September 24, when a short circuit occurred in the sudden pressure trip causing the 500 KV circuit breakers to open which caused a generator load reject.
Unit 2 There was one scram on the unit during the month.
On September 5, the reactor was manually scrammed in preparation for the beginning of the EOC-3 refueling outage.
Unit 3 There were two scrams on the unit during the month.
On September 12, the reactor was manually sera'mmed to begin a short maintenance outage on the "B" inboard main steam isolation valve.
The reactor scrammed on September 20, when a
480 V shutdown board failed to transfer from alternate to normal feed producing a loss of a RPS IfG set and the isolation of a SJAE which caused a main condenser low vacuum.
0 erations Summer (Continued)
September 1980 Fati ue Usa e Evaluation The cumulative usage factors for the reactor vessel are as follows:
Location Usa e Factor Unit 1 Unit 2 Unit 3 Shell at water line Feedwater nozzle 0.00487 0.23254 0.15822 0.11570 0.00369 0.00314 Closure studs 0.19566 0.12899 0.09194 Note:
This accumulated monthly information satisfies technical specification section 6.6.A.17.B(3) reporting requirements.
Common S stem Approximately 7.58E+05 gallons of waste liquid were discharged containing approximately 1.36E+00 curies of activity.
Refuelin Information September 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 presently in its EOC-3 refueling outage.
Unit 2 is scheduled for its fourth refueling beginning on or about March 1, 1982, with a scheduled restart date of June 14, 1982.
This refueling outage will involve completing relief valve modifications, torus modifications if all approvals are received, "A" low pressure turbine inspection, and loading additional 8 x 8 R fuel assemblies into the core.
There are 764 fuel assemblies in the reactor vessel.
At the'end of the month, there were 132 discharged cycle 1 fuel assemblies, 156 discharged cycle 2 fuel assemblies, and 352 discharged cycle 3 fuel assemblies in the spent fuel storage pool.
The present storage capacity of the spent fuel pool is 820 assemblies.
With present
- capacity, the 1979 refueling was the last
Refuelin Information (Continued)
September 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 during the third refueling of Unit 2.
Unit 3 Unit 3 is scheduled for its third refueling beginning on or about November 2, 1980, with a scheduled restart date of December ll, 1980.
This EOC-3 refueling, involves loading additional 8 x 8 R (retrofit) assemblies into the core, and power supply on LPCX modification.
Thea'e 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 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.
Si nificant 0 erational Events Unit 1 Date Time 9/01/80 0001 1341 1736 2025 2230 2343 Event Reactor thermal power at,>99%,
steady state control rod sequence "A".
Reactor Scram No.
135 from >99% on turbine stop valves
- closure, due to water causing a short in pressure relay 62-C1, which caused relay KT 303 to trip turbine.
Commenced rod withdrawal.
Reactor Critical No. 156.
Rolled T/G.
Synchronized generator, commenced power ascension.
9/02/80 1500 9/03/80 0040 1939 2030 Commenced PCIOMR from 82% thermal power.
Reactor thermal power at 95%, holding due to "C" string high pressure heaters isolation due to relief valve flange leak.
"C" string high pressure heaters maintenance completed and heaters placed in service.
Resumed PICOMR from 95% thermal power.
9/05/80 1500 Reactor thermal power at 99%,
maximum flow.
9/07/80 0015 0230 0705 0905 9/10/80 1500 Reduced thermal power from 99% to 85% for turbine C. V.
tests and SI's.
Turbine C. V. tests and SI's completed, commenced power ascension.
Commenced PCIOMR from 95% thermal power.
Reactor thermal power at
>99%, steady state.
Reactor thermal power at >99%, steady state.
9/12/80 2100 Reduced thermal power from >99% to 50% for control rod sequence exchange from "A" to "B".
9/13/80 0205 2130 Control rod sequence exchange from "A" to "B" completed, commenced power ascension.
Commenced PCIOMR from 82% thermal power.
9/14/80 2300 9/16/80 1843 1905 2030 2300 Reactor thermal power was
>99%, steady state.
Reduced thermal power from >99% to 90% for removal of "A" circulating water pump to allow stop log 1A1 to be lifted.
"A" circulating water pump placed in service, (mode to cooling towers would not operate due to stuck gate),
commenced power ascension.
Commenced PCIOMR from 95% thermal power.
Reactor thermal power at
>99%,. steady state.
Si nificant 0 erational Events Unit 1 Date Time 9/19/80 2230 Event Reduced thermal power from >99% to 77% for removal of "B" reactor feedwater pump for maintenance (excessive vibration).
9/20/80 0216 0315 jj(
N 1220 1225 2030 Reduced thermal power from 77% to 70% for turbine C. V. tests and SI's.
Turbine C. V. tests and SI's completed, commenced power ascension.
Reduced thermal power from 77% to 50% due to loss of unit preferred
- power, when shutdown board power supply was trans-ferred.
Commenced power ascension.
Commenced PCIOMR from 80% thermal power.
9/21/80 1550 9/24/80 2222 Reactor thermal power at >99%, steady state.
Reactor Scram No.
136 from >99% thermal power on load re-(1) ject trip from negative ground on main transformer sudden pressure relay circuit.
9/25/80 0530 0820 1038
. 1107 2110 Commenced rod withdrawal.
Reactor Critical No. 157, sequence "B".
Rolled T/G.
Synchronized generator, commenced power ascension.
Commenced PCIOMR from 67% thermal power.
~ 9/27/80 0015 0)P5 1500 9/28/80 1500 Reduced thermal power from 99% to 85% for turbine C. V.
tests and SI's.
Turbine C. V. tests and SI's completed, commenced PCIOMR.
Reactor thermal power at >99%, steady state.
Reactor thermal power at
>99%, steady state.
9/29/80 0115 Reduced thermal power from >99% to 85% for backwash and precoat condensate demineralizers.
9/30/80 2400.
Reactor thermal power at 85%, holding for condensate de-mineralizer problems.
Si n'ificant 0 erational Events Unit 2 Date Time Event 9/01/80 0001 1500 Reactor thermal power at 92%,
EOC-3 coastdown control rod sequence "B".
Reactor thermal power at 90%,
EOC-3 coastdown.
9/04/80 1500 9/05/80 2130 2247 Reactor thermal power at 89%,
EOC-3 coastdown.
Commenced reducing thermal power from 89% for refuel shut-down (EOC-3).
Reactor Scram No.
109 (manual) from 35% thermal power to accommodate refueling outage.
9/12/80
,1320 1650 Received permission for fuel movement operation, holding due to communication porblems.
Communications restored, commenced fuel movement operation to accommodate LPRli maintenance.
9/19/80 1000 9/30/80 2400 Commenced core fuel shuffle operations.
Refueling operation in progress.
Si nificant 0 erational Events Unit 3 Date Time Event 9/01/80 0001 1455 1522 2055 2200 Reactor thermal power at
>99%, steady state control rod sequence "A".
Reduced thermal power from >99% to 63% due to "A" recir-culation pump trip from a spurious trip.
Reduced thermal power from 63% to 54% due to "A" recircu-lation pump being out-of-service.
"A" recirculation pump maintenance completed and pump placed in service, commenced power ascension.
Commenced PCIOMR from 75% thermal power.
9/03/80 1500 9/07/80 0230 0330 0430 1500 Reactor thermal power at >99%, steady state.
Reduced thermal power from 99% to 75% for turbine C. V.
tests and SI's.
Reduced thermal power from 75% to 67% due to MSIV-1-26 closing too fast (+1.3 seconds).
Turbine C. V. tests and SI's completed, holding at 67%
due to MSIV 1-26 being left in closed position, awaiting maintenance.
Increased reactor thermal power from 67% to 75%, holding due to closure of MSIV 1-26.
9/10/80 1500 Reactor thermal power at 75%, holding due to MSIV 1-26 being closed.
9/12/80 2245 2355 Commenced reducing thermal power from 75% for shutdown for MSIV 1-26 mainteyy~ce.
Reactor Scram No.
88 (manual) from 35% thermal power to accommodate maintenance to MSIV 1-26.
9/14/80 0525 1009 1706 2233 2243 Maintenance to MSIV 1-26 completed, commenced rod with-drawal.
Reactor Critical No.
98.
Reactor was made subcritical due to a feedwater valve (3-219A) leak.
Repairs to feedwater valve 3-219A completed, commenced rod withdrawal.
Reactor Critical No.
99.
9/15/80 0155 0233 1600 Rolled T/G.
Synchronized generator, commenced power ascension.
Commenced PCIOMR from 76% thermal power.
Si nificant 0 erational Events Unit 3 Date Time Event 9/16/80 2330 Reactor thermal power at 92%,
maximum flow, awaiting rod pattern adjustment load drop.
9/17/80 2300 Reactor thermal power at 91%, maximum flow, awaiting rod pattern adjustment load drop.
9/18/80 0700 9/20/80 1358 2230 Reactor thermal power at 90%,
maximum flow.
Reactor Scram No.
89 from 90% thermal power, on loss (1) of preferred power when "A" 480 volt shutdown board failed to transfer back to normal causing loss of "A" RPS MG set.
Commenced rod withdrawal.
9/21/80 0104 0440 0500 1500 Reactor Critical No. 100.
Rolled T/G.
Synchronized generator, commenced power ascension.
Commenced PCIOMR from 67% thermal power.
9/22/80 2240 9/23/80 2145 2255 2300 Reactor thermal power at 90%,
maximum flow.
Reduced thermal power from 90% to 75% for control rod pattern adjustment.
Control rod pattern adjustment completed, commenced power ascension.
Commenced PCIOMR from 82% thermal power.
9/24/80 0725 2130 Reactor thermal power at 93%, holding due to computer malfunction.
Computer back in service, resumed PCIOMR from 93%
thermal power.
9/25/80 0200 1500 9/27/80 0130 0217 0300 1200 Reactor thermal power at 99%,
maximum flow.
Reactor thermal power at 98%,
maximum flow.
Reduced thermal power from 98% 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.
Reactor thermal power at >99%, steady state.
9/30/80 2400 Reactor thermal power at
>99%, steady state.
Equipment Malfunction (1)
10 0
A VERA(iE DAILYU. /IT POWER LEVLL DOCKET NO.
Uy(T Browns Kerr 1 80 COMPLETED BY Don Green HOHTH ~Se tember 1980 DAY AVERAGE DAILYPOWER LEVEL (MWe-Yet )
I S87 709 973 DAY AVERAGE DAlLYPOWER LEVEL (89(We-Net) 1034 l7 ao4o 1030 IO l3 IS le 1012 1034 1022 978 1009 1026 aoos 1021 976 778 1013 1038 1030
'TO 23 95 37 29 30 3!
860 1022 1039 1031 920 344 883 996 1050 893 900 Ii ISTRUCTIOi(S Ort thrs lorrnct. Itst rlr. nvcrncc d:rile unit viiivcr Icicl tri NI'Nc >Net for caclt day>>t t!tc rcportrntt rniinth. Ci>>nputc to thc nearest wltolc ruche;!i8:ut t, (if17 i )
AVERAGE I)A!LYUNIT POWER LEVEL UNI I DATE COMPLETED DY Browne Perry 2
0-2-80 Ted Thorn TELEPIIO>VE 205 729 6846 ilIONTH ember 1980 DAY AVERAGE DAILYPOWER LEVEL IMWe.>Ve t )
I 938 924
'24 946 824 DAY AVERAGE DAILYPOWER LEVEL
(.">IWe.Vct ]
-2 17 IS 19 1Q 13
-2 IQ
'>5 26 13 15 16 3Q 31 INSTRUCTIONS 0>> this I'>>r>>ut. Ii"I thc:>vcrJ>,c >I:>>ly>>>)it I>i>>cc> Icvcl i>> ~Inc Nct l>>r each rlay>>) the rcl)(>>til>>t >>h>r>th. C>>tt>putc t>>
thc ncarcst <<ln>I>> r>>cl;aiv:>tt.
Irt/77 >
AVER ))GE DAILYUNITPOt~'ER LEVEL DOCKET NO.
UNIT 50-296 Browns Ferry 3
10-2-80 COMPLETED DY Ted Thorn TELEPHONE 205 729 6846 MONTH September 1980 DAY AVERAGE DAILYPOWER LEVEL Ii)IWe. Vcr I 897 1061 DAY"'VERAGEDAILYPO4'ER LEVEL (Mme Net l 949 l7 931 940 lp 1054 1072 1068 763 807 814 797 795 10 13 15 Z6 498 537 916 942 951 1042 1045 1040 l3 IS I6 785
-12
-13 541 906 30 1063 1058 1065 INSTR UCTIO.'IS Oi) this f>>r)))at, list tl)c:)vcrJg<<J)ily>>>>it,>> ).ci fc;cl i>> t ltVcNct I'i)r cacI) JJ>'i) !I)c rcp>>) ti>>g )>>>>i) th. C))))tl)utc to thc!)cares) ivl)>>lc ))).'t.vivat t.
OPERATING DATAREPORT OPERATIVG STATUS I
UiiitName.
BROMNS FERRY 1
- 2. Reporting Period:
p d, Sep'~~ I980
- 3. Licensed Thermal Power (MWt):
- 4. Nameplate Rating (Gross MWe).
1152
- 5. Design Electrical Rating (Nct MWe):
- 6. Maximum Dependable Capacity (Gross MWe):
- 7. Maximum Dependable Capacity (Net MWe):
DOCKET NO.
DATE 10-2-80 COIII'LETCD BY Dort Green TELEPHONE ~~~
6846
- 8. IfChanges Occtir in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:
N A
- 9. Power Level To Which Restricted, lfAny (iVet MWe):
IO. Reasons For Restrictions, lfAny:
This Month Yr.~to Date 6 575 I I. Hours In Reporting Period
- 12. i%imbcr Ot'ours Reactor Was Critical 703.30 4,356.43 l3. Reactor Reserve Shutdown Hours l4. Hours Generator On-Line IS. Unit Reserve Shutdown llours
- 16. Gross Thermal Energy Generated (MWH) 2 175 862 12 430 818 ly. Gross Eleerrieel Energy Genernreri iiirrSS>
ySSri 32(L
.3~997 100 IS. Net Electrical Energy Gcncmted(MWH) 677 843 3 872 138
- 19. Unit Service Factor 96.8 64.2
- 20. Unit Availability Factor 96.8 64.2 "1. Unit Capacity Factor (Usillg syIDC iVct) 88.4 55.3
- 22. Unit Capacity Factor (Using DER Net)
- 88. 4 55.3
- 23. Unit Forced Out:ige Rate 3.2 9.9
- 24. Shutdowns Scheduled Over Next 6 Months (Type. Date. and Duration of Facli):
Cumulative 54 073 32,633.71 S,OX~9 0
86,567,311 28 515 560 27,674,106 58.9 58.9 48.1 48.1 30.
- 25. IfShut Down At End Of Report Period, Estimated I)ate of Startup:
- 26. Units ln Test Status (Prior to Commercial Operation):
Forecast Acliicred liVITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIALOPERATION
(')/77)
14 OPERATlifG D'ATAREPORT OPERATliVG STATUS nit jVa me BR0IWj S F ERRY
- 3. Licensed Thermal Power (MWt):
- 4. Nameplate Rating (Gross i%1We):
- 5. Design Electrical Rating (Net MIVe):
- 6. Maximum Dependable Capacity (Gross MWe):
9
~
- 7. Maximum Dependable Capacity (Nct 411We):
Notes DOCKET NiO.
DATE 10-2-80 CO9112LETFD BY ~~ een TELEPHONE ~~29 6846
- 8. IfChanges Occur in Capacity Ratings (Itcnis Number 3 'fhrou'h 7) Since Last Report. Give Reasons:
N/A
- 9. Power Level To Which Restricted, IfAny (iVet jjIWe):
- 10. Reasons For Restrictions. IfAny'/A N/A This j9jlonth Yr..to.Date 6,575 Cumuh tive 48,984 720
- 11. Ilours ln Reporting Period
- 12. Number Of Hours Reactor Was Critical
- 13. Reactor Reserve Shutdown Hours
- 14. Hours Generator On. Line
- 15. Unit Reserve Shutdown Hours
- 16. Gross Thermal Energy Generated (IjIWH)
- 17. Gross Electrical Energy Generated (AI'IVH)
- 18. Net Electrical Energy Generated (l9IWH)
- 19. Unit Service Factor
- 20. Unit Availability Factor
- 21. Unit Capacity Factor (Using MDC Nct)
- 22. Unit Capacity Factor (Using DFR iVet)
- 3. Unit Forced Outage Rate
- 4. Shutdowns Scheduled Over Next 6 Mojjths 29,788.59 118.78 5,304.11 12,423.88 28,835.41 648.94 0
118.78 5,171.10 0
0 81,084,875 14,929,875
- 344 076 4 952 010 26 902~078 113 120 26,138,717 107 818 4,807,248 78.6 16.5 58.9 58.9 16.5 78.6 68.7 50.1
- 14. 1
- 68. 7
- 14. 1
- 50. 1 12.2 33.5 (Typi.. Date. and Duration of Each):
'5. IfShut Down At End Of Rcport Period. Estimated Date of Startup:
11-2-80
- 26. Units ln Test Status (Prior to Commercial Operation):
Forecast Acilia veil IYITIAL CRI1 ICALI'fY Ii( IT I A L ELEC'fR ICI'fY COII9iIERCIALOPI:.RATIOiV
~
~
~
(j>/77),
15 OPERATING STATUS OPERATINiG DATAREPORT DOCKET NO.
50 296 10-2-80 CO!iIPLETED IIY 3h?s~geen TELEPHO74 C ZE~2~6846 BROGANS FERRY 3 September 19 0
- 2. Reporting Period:
- 3. Licensed Therinal Power (MWt):
- 4. Nameplate Ratir<> (Gross M'iVe):
1152
- 5. Design Electrical Rating (iNet iIWe):
- 6. 46(aximum Dependable Capacity (Gross iiIWe):
1098
~ 4
- 2. Maximum Dcp ndablc Capacity (Nct iiIIVc):
Notes
- 8. IfChanges Occur in Capacity Ratings (Items Number 3 Through 2) Since Last Report. Give Reasons:
N A
- 9. Power Level To Which Restricted, lfAny (i%et MWe):
IO. Reasons For Restrictions, lfAny:
N/A N/A This Month Yr..to.Date 6,575 Cumulative 31,439 I l. Hours in Reporting Period 720 1~. Number Of Hours Reactor Was Critical 669.05 l3. Reactor Reserve Shutdown Hours
- 14. Hours Generator On. Line 654.33
- 15. Unit Reserve Shutdown Hours
- 16. Gross Thermal Energy Generated (iiIWH)
- 12. Gross Electrical Energy Generated (MWII) 625,700 IS. Net Electrical Energy Generated (MWH) 607,023
- 20. Unit AvaihbilityFactor 90.9
- 21. Unit Capacity Factor (Using iiIDCNet) 79.2
- 22. Unit Capacity Factor (Using DFR 4"iet)
- 23. Unit Forced Outage Rate
- 24. Shutdowns Scheduled Over Next 6 4ilonths (Type. Date. and Duration uf Refuel outage October 31, 1980 5 769.27 24 676.'62 1 810.89 24 095.27 1 2.58 5 657.46 0
0 17 411 179 70 519 045 23,245,730 22 568.352 5,843,150 5 680 579 86.0 76.6 86.0 76.6 81.1 67.4 81.1 67.4 14.0 10.2 Fach):
- 25. IfShut Down At End Of Rcport Periiid, Estimated Date iifStartup:
- 6. Units ln Test Status (Prior to Commercial Operation):
Forecast Achieved IN ITIAL CRITICALITY INITIAL ELEC'fRICITY CO!iIMERCIlLOPERATION
~
~I UNITSIIUTDOW)IS AND POWER REDUCTIONS DOCI'.ET NO.
50 259 UNITNAMF Browns Perr 1
CO)!PLEYEO BY MBB~O TELEPHONE 205 729 6846 I)J>e Llccnscc F.vc>>l Report <
'ej
~tlm'G CJ 0
CJuse A. Corrective Acl>of> Il)
Prevent R<<<<urrcnce 143 144 800901 800912 10.03 Turbine trip due to stop valve closur Derated for control rod sequence exchange 145 800919 Dere ted for maintenance to "B" reactor feed pump 146 147 800920 800924
- 12. 75 Derated due to loss of unit preferred power Load re)ect due to negative ground on main transformer sudden pressure relay F: I'j)feed S. S'i>ed>>lcil I')/77 )
I Reason:
A Lllmpmcnt Fa>lure (Expla>f))
II Maintenance or Test
( -Ref Ii lg D.Regula>l)ry Rest>i<<lion I'..Oper Jll)r TfJinin E: IJce>>sc Examination F-Administ >alive G.Operational Lrrljr(I:xpla>n)
II.O>her (Lixplaif>)
Method:
I.h(a>> ual i>!IJ>>ual S<<fa>>l.
>-Ciuti)>>):)tie Ser J>>1 0 Other (Fxplain)
Exhibit G
~ Inst ru<<t io>>s fof Pfei)afJl>!)n of Dal J E>>tr) Sheets ll)> I.iecnsec Event Report (I.I:R I F> e (NIIRI'.G-016I I F xi>>bit I - Sa>>tc Si)>> rci
uNITSIIUTDOWNS AND POWER REDUCnONS I)OCI'ETNO.80-260 l)roar>s Fervor 2 DATE ~<L2JBl COMPLETED I)Y Don&xa en
>eL<>noNL>
l)atc r~.
A
~ V)
LI<.'<.'nscc Eve nl Rcport 2>
Ci Q
G Cl~
C Cause A Corrective Action I<>
Prevent Rccufrcnec 155 800905 S
601.22 C
Refueling I.
I>o>CCJ S. S;heJuleJ I
I Reason:
A Equipment Failure ( Explain)
It.h).lintenance or Test
(.Refueling I) Regu)atnry Restrict<<nl I:.Ol)erator Tratnu>g k I.>cense I>xan>ul:>Iron I"Ailnu Ills lIJ I>vc G.Operational Lrr<>r (Explain)
Il.olhc( (ExpiJln) hletho J:
I.hlanual tilJnua) Scfanl 3-Anton>'Itre Ser Jul.
4.Other (Iixplain)
Exhll>it G
~ Instructions tor preparati<>n of l)ata I:ntr) Sheets tof Licensee Event Report I I.I'.R) I'ile I.)ltRI>G~
0 I 6> I )
Exhibit I
~ S;>Inc Source
UNITSl>>UTDOKNS AND PO'4'ER REI)UCTIONS REPORT h>>ON fl>>
Sep tember DOCYET NO 80-296 UNll NAh(E Br<<ns Early 3 COMPLETED BY QQ1LG<een I)JIc Vl Ia=
A
~ Vi Licensee Event Rcp))rt -"
Cause & Corrective Action lo Prcvcnt Rccurrcn).e 143 144 145 146 147 148 800901 800907 800907 800912 800914 800920 F
41.18 9.45 F
15.04 A
B A
Derated when oA" recirculation pump tripped Derated for turbine control valve tests and SI's Derated when HSIV 1-26 closed too.fast Maintenance on HSIV 1-26 r
Maintenance on feedwater valve (3-219A) leak, reactor was already down Loss of preferred power when "Ao 480V shutdown board failed to transfer bacl to normal causing loss of oAo RFS MG Set F:
Fc)rcc)I S; S'l)c'lute)l I'}II7)
I Reason:
A.Erluipmcn t Failure ( Explain)
B hlaintcnance or Test C.R fueling D Regular))ty Restriction E.Opcfal))f Tra)ntng & l.iccnsc I;xallllnallon I"AI)nun)st rat)ac G.Opcrati)ntal Lrr))r (Lxplatn)
II-Otl)er (lixplain }
hlctl)od:
! hlanual 2-h(anual Scram.
.t.Anton) Itic Sera)n.
4.0lllcI (Lxplaln)
I:xl)ibit G - Instructions I'or Prep;II;Iti))n ol l)ata LI)lipSl)ccts tof Ltccnscc Event Rcport (I.I:R) I'IlcINURI'.().
Ol()l)
}!xltibitI - Sa)nc Sour;c
BPOUiVE PEUliY UUCLELU PLIIiVT U!IIT 1.
ELECTRXCAL IIAINTENANCE SUI'IIIARY For the llonth of 9-. te 9/2/ItO System Neutron Honitorin Component RBH Bypass Switch Nature of Haintenance RBH Bypass Switch on panel 9-5 needs repair-ing E
ect on
'a c Operation of The Reactor HONE Cause of Halfunction RBH Switch Bad Results of Halfunction Switch would not go in bypass
'ction Taken To Preclude Recurrence Replaced RBH switch.
Checked switch for proper operation.
Switch functioned okay.
TRP 179518 9/23/80 RIIR-FCV-74-71 IIIIR valve 1;74-71, won '
run Unit in limiting condition for operation (TS.3.5 '.7)
Hotor burned up Valve inoperable.
Performed EHI 71.
Replaced old motor.
Performed EIII 18.
Valve now functionin properly.
TRII 16575 LER No.
BFRO 50-259/
8072
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CSSC FA>JIFF!r?!T HEC!UiNlCAL KKINT-"'NA?~CE SU%!ARY 3
D;".TE SYSTEH CC'IPONENT i&TUBE OF NXINTEHANCE EFFFCT ON SAFE OPERATXO:i'F 1".iE P,L'ACTOR CAUSE OF K'iLFUJCTIGN PESULTS OF PALFUWCTXGN
~.CTJ.ON TA!'KN TO PFJ:CLUDE PZCU <RE'E 9/17/80 Fuel pool coolin 3A FPC pump Outboard pack-in None Packing leak Packing leak Adjusted packing TR 178817
2 5)EC))ANICAL HAINTENANCE SUZIE~.RY For the llonth of ~Se tember 19 80 BATE 9/22/80 S ST&i RCIC
<G~'POi'EV~
Turbine exhaus rupture disk NATURE OF E'LTHTEHANCE Ruptured disk EFFECT O.'l StZE OPEFCTION OF n)E REACTOR none CAUSE OF Yi'iLFU.'i'CTIOV old disk ruptured PESULTS OF YALFUNCTIQN Ruptured disk ACZ>Oal TA)
N VO PRECLUDE Replaced disk with new one TR l03732
CSSC E UIPHENT BROWNS FERRY NUCLEAR PLANT UNIT INSTRUlfENT MAINTENANCE SlMfARY FOR TllE HONTff OF September 19 80 Unit 1 SYSTEM CO."fPONENT NATURE OF tfAINTENANCE EFFECT ON SAFE OPERATION OF THE REACTOR CAUSE OF MALFUNCTION RESULTS OF MALFUNCTION ACTION TAKEN TO S'RECLUDE RECURRENCE 9-2 Containment H A-76-37 2
Inerting Primary PDT-64-138 Containment Replace Calibrate None None Faulty Heter Zero 'Shift Alarm would not reset Did Not Indicate with Redundant None None 9-24 Unit 2 Reactor Building Closed Cool ing Water TI-70-56 Replace None Broken Indicator Did Not Indicate None 9-23 High Pyess-PS-26-78J ure Fire Protection Calibrate None Instrument Drift Setpoint 'Incorrect None Unit 3 9-25 Emergency Equipment Cooling Water FI-67-9A
-12A Calibrate None Zero Shift Indicated Low Flow None 0;
RHR Service PT-23-11 Water FH-23-42 Bf-23-48 Calibrate Calibrate Calibrate None None None Zero Shift Zero Shift Zero Shift Indicated Low Pressure Indicated Low Flow Indicated Low Flow None None None
OUTAGE Slk&fARY September 1980 The unit two reactor shutdown sequence was conducted in an orderly process on September 5, 1980, for refueling activities and routine maintenance to plant equipment.
The refuel activities involve disassembly of Unit 2 reactor for refueling operation with reactor startup scheduled for October 26, 1980.
The routine maintenance involves inspection and repairs to major components and safety systems within the plant.
The initial containment entry was conducted at 1:05 P.M.
on September 6, 1980.
The planned duration for the Unit 2 cylce 3 refuel outage is 49 days.
The pre-planned schedule shows that turbine inspection and maintenance work sequence as the critical work path, a first at Browns Ferry Nuclear Plant.
In order to prevent the outage duration from exceeding the 49 day
- schedule, non-curcial modifications are being minimized, however, major modifications intended to meet safety requirements are being performed.
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