ML17226A103
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Revision141of3September2001RBSUSARTABLE11.1-1REACTORCOOLANTANDMAINSTEAMRADIONUCLIDECONCENTRATIONSReactorCoolantMainSteamDesignExpectedDesignExpected Isotope (Ci/g)(Ci/g)(Ci/g)(Ci/g)NobleGases (1)Kr-83m 5.5-3 (2)9.1-4 Kr-85m9.7-31.6-3 Kr-853.0-55.0-6 Kr-873.3-25.5-3 Kr-883.3-25.5-3 Kr-892.1-13.4-2 Kr-904.6-17.5-2 Kr-915.5-19.1-2 Kr-925.5-19.1-2 Kr-931.5-12.4-2 Kr-943.6-25.9-3 Kr-953.3-35.5-4 Kr-972.2-53.6-6 Xe-131m2.4-53.9-6 Xe-133m4.6-47.5-5 Xe-1331.3-22.1-3 Xe-135m4.3-27.0-3 Xe-1353.6-26.0-3 Xe-1372.4-13.9-2 Xe-1381.4-12.3-2 Xe-1394.6-17.5-2 Xe-1404.9-18.0-2 Xe-1414.0-16.5-2 Xe-1421.2-11.9-2 Xe-1431.9-23.2-3 Xe-1449.1-41.5-4 Halogens14Br-833.5-25.8-31.4-32.3-4Br-843.5-25.8-31.4-32.2-4 Br-852.2-22.3-38.8-41.0-4 I-1312.1-23.4-39.1-41.5-4 I-1323.1-15.1-21.3-22.1-3 I-1332.8-14.6-21.2-21.9-3 I-1344.9-18.1-22.6-24.3-3 I-1352.7-14.5-21.1-21.9-3 14 Revision142of3September2001RBSUSARTABLE11.1-1(Cont)ReactorCoolantMainSteamDesignExpectedDesignExpected Isotope (Ci/g)(Ci/g)(Ci/g)(Ci/g)CesiumandRubidium Rb-892.3-23.8-32.3-53.8-6 Cs-1341.7-42.7-51.7-72.7-8 Cs-1361.1-41.8-51.1-71.8-8 Cs-1374.4-47.3-54.4-77.3-8 Cs-1382.5-17.8-32.5-47.8-6WaterActivationProducts14 N-137.1-25.0-24.2-24.2-2 N-166.0+16.0+13.0+23.0+2 N-171.3-29.0-32.1-11.2-1 O-191.2+07.0-15.9-11.0-1 F-184.8-24.0-34.0-34.0-3 14Tritium H-31.0-21.0-21.0-21.0-2OtherNuclides Na-249.0-39.0-39.0-69.0-6 P-321.9-41.9-41.9-71.9-7 Cr-515.6-35.6-35.6-65.6-6 Mn-546.5-56.5-56.5-86.5-8 Mn-565.0-24.2-25.0-54.2-5 Fe-559.3-49.3-49.3-79.3-7 Fe-598.0-52.8-58.0-82.8-8 Co-585.0-31.9-45.0-61.9-7 Co-605.0-43.7-45.0-73.7-7 Ni-639.3-79.3-79.3-109.3-10 Ni-653.0-42.5-43.0-72.5-7 Cu-642.7-22.7-22.7-52.7-5 Zn-651.9-41.9-41.9-71.9-7 Zn-69m1.8-31.8-31.8-61.8-6 Sr-893.3-39.3-53.3-69.3-8 Sr-902.5-46.5-64.5-76.5-9 Sr-918.1-23.6-38.1-53.6-6 Sr-921.4-18.4-31.4-48.4-6 Y-912.2-43.7-52.2-73.7-8 Y-923.1-25.1-33.1-55.1-6 Y-932.2-23.6-32.2-53.6-6 Zr-954.5-57.4-64.5-87.4-9 3of3August1987RBSUSARTABLE11.1-1(Cont)ReactorCoolantMainSteamDesignExpectedDesignExpected Isotope (Ci/g)(Ci/g)(Ci/g)(Ci/g)Zr-973.6-55.4-63.6-85.4-9 Nb-954.5-57.4-64.5-87.4-9 Nb-981.9-23.2-31.9-53.2-6 Mo-992.5-21.8-32.5-51.8-6 Tc-99m1.1-11.8-21.1-41.8-5 Tc-1014.3-17.0-24.3-47.0-5 Tc-1043.8-16.2-23.8-46.2-5 Ru-1031.2-41.9-51.2-71.9-8 Ru-1051.0-21.7-31.0-51.7-6 Ru-1061.7-52.8-61.7-82.8-9 Ag-110m6.0-59.3-76.0-89.3-10 Te-129m3.7-43.7-53.7-73.7-8 Te-131m5.5-49.1-55.5-79.1-8 Te-1321.5-29.2-61.5-59.2-9 Ba-1392.0-18.2-32.0-48.2-6 Ba-1409.5-33.7-49.5-63.7-7 Ba-1412.4-17.8-32.4-47.8-6 Ba-1422.3-14.6-32.3-44.6-6 La-1422.5-24.1-32.5-54.1-6 Ce-1411.7-42.8-51.7-72.8-8 Ce-1431.6-42.7-51.6-72.7-8 Ce-1443.8-52.8-63.8-82.8-9 Pr-1432.2-43.7-52.2-73.7-8 Nd-1471.7-52.8-61.7-82.8-9 W-1873.0-32.7-43.0-62.7-7 Np-2392.6-17.4-32.6-47.4-6
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(1)Thedesignandexpectedconcentrationfornoblegasesinreactorcoolantarenegligible (2)5.5-3=5.5x10
-3 RBS USAR TABLE 11.1-2 Revision 17 1 of 1 PARAMETERS USED TO DETERMINE REACTOR COOLANT AND MAIN STEAM RADIONUCLIDE CONCENTRATIONS
- Variable Unit Maximum core thermal power 3,039 MWt 14 Total steam flow rate 1.32 x 10 7 lb/hr Weight of reactor coolant in the reactor vessel, including
recirculation lines 4.49 x 10 5 lb Reactor coolant cleanup system
flow rate 1.24 x 10 5 lb/hr Condensate demineralizer flow
rate 9.65 x 10 6 lb/hr 14*Parameters unchanged for TPO (Appendix K) uprate as other conservatisms in the analyses produce results that bound TPO uprate conditions.
RBSUSARTABLE11.1-3GENERALELECTRICDATANOBLERADIOGASSOURCETERMS
______________________________*Estimatedfromexperimentalobservations1of1August1987SourceTermSourceTerm@t=0@t=30min Isotope Half-Life (µCi/sec)(µCi/sec)Kr-83m1.86hr3.4x10 32.9x10 3 Kr-85m4.4hr6.1x10 35.6x10 3 Kr-8510.74yr10to20*10to20*Kr-8776min2.0x10 41.5x10 4 Kr-882.79hr2.0x10 41.8x10 4 Kr-893.18min1.3x10 51.8x10 2 Kr-9032.3sec2.8x10 5---Kr-918.6sec3.3x10 5---Kr-921.84sec3.3x10 5---Kr-931.29sec9.9x10 4---Kr-941.0sec2.3x10 4---Kr-950.5sec2.1x10 3---Kr-971sec1.4x10 1---Xe-131m11.96day1.5x10 11.5x10 1 Xe-133m2.26day2.9x10 22.8x10 2 Xe-1335.27day8.2x10 38.2x10 3 Xe-135m15.7min2.6x10 46.9x10 3 Xe-1359.16hr2.2x10 42.2x10 4 Xe-1373.82min1.5x10 56.7x10 2 Xe-13814.2min8.9x10 42.1x10 4 Xe-13940sec2.8x10 5---Xe-14013.6sec3.0x10 5---Xe-1411.72sec2.4x10 5---Xe-1421.22sec7.3x10 4---Xe-1430.96sec1.2x10 4---Xe-1449sec5.6x10 2---TOTALS2.5x10 61.0x10 5 RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORTGENERALELECTRICDATAPOWERISOLATIONEVENT-ANTICIPATEDOCCURRENCETABLE11.1-4REVISION 14SEPTEMBER 2001THISTABLEHASBEENDELETED RBSUSARTABLE11.1-5GENERALELECTRICDATAREACTORWATERFISSIONPRODUCTRADIOHALOGENS
______________________________*Basedonnoblegasreleaserateof100,000
µCi/secafter30min1of1August1987 Concentration*
Isotope Half-Life (µCi/g)_____________
Br-832.40hr1.7x10-2 Br-8431.8min3.5x10-2 Br-853.0min2.2x10-2 I-1318.065day1.5x10-2 I-1322.284hr1.5x10-1 I-13320.8hr1.0x10-1 I-13452.3min3.0x10-1 I-1356.7hr1.5x10-1 RBSUSARTABLE11.1-6GENERALELECTRICDATAOTHERFISSIONPRODUCTRADIOISOTOPESINREACTORWATER
______________________________*Basedonnoblegasreleaserateof100,000
µCi/secafter30min1of1August1987 Concentration*
Isotope Half-Life____(µCi/g)_________
Sr-8950.8day3.3x10-3 Sr-9028.9yr2.5x10-4 Sr-919.67hr8.1x10-2 Sr-922.69hr1.4x10-1 Zr-9565.5day4.3x10-5 Zr-9716.8hr3.6x10-5 Nb-9535.1day4.5x10-5 Mo-9966.6hr2.5x10-2 Tc-99m6.007hr9.4x10-2 Tc-10114.2min2.0x10-1 Ru-10339.8day2.1x10-5 Ru-106368day2.8x10-6 Te-129m34.1day3.7x10-4 Te-13278hr1.5x10-2 Cs-1342.06yr1.7x10-4 Cs-13613day1.1x10-4 Cs-13730.2yr2.6x10-4 Cs-13832.3min2.5x10-1 Ba-13983.3min2.0x10-1 Ba-14012.8day9.5x10-3 Ba-14118.3min2.4x10-1 Ba-14210.7min2.3x10-1 Ce-14132.53day4.3x10-5 Ce-14333.0hr3.9x10-5 Ce-144284.4day3.8x10-5 Pr-14313.58day4.1x10-5 Nd-14711.06day1.5x10-5 Np-2392.35day2.6x10-1 RBSUSARRevision141of1September2001TABLE11.1-7GENERALELECTRICDATACOOLANTACTIVATIONPRODUCTSINREACTORWATERANDSTEAM Reactor Steam WaterConcentrationConcentrationIsotopeHalf-Life
___(µCi/g)_____________(µCi/g)__________
N-139.99min1.5x10-37.1x10-2 N-167.13sec5.0x10 13.5x10 1 N-174.14sec3.5x10-21.3x10-2 O-1926.8sec5.9x10-11.2x10 0 F-18109.8min4.4x10-44.8x10-214Note:ThesearetheGEprovidedvaluesforNormalWaterChemistry.
14 RBSUSAR1of1August1987TABLE11.1-8GENERALELECTRICDATANONCOOLANTACTIVATIONPRODUCTSINREACTORWATER Concentration Isotope Half-Life (µCi/g)Na-2415hr2x10-3 P-3214.31day2x10-5 Cr-5127.8day5x10-4 Mn-54313day4x10-5 Mn-562.582hr5x10-2 Co-5871.4day5x10-3 Co-605.258yr5x10-4 Fe-5945day8x10-5 Ni-652.55hr3x10-4 Zn-65243.7day2x10-6 Zn-69m13.7hr3x10-5 Ag-110m253day6x10-5 W-18723.9hr3x10-3 RBSUSARTABLE11.2-1EQUIPMENTDESCRIPTIONLIQUID-RADWASTESYSTEMRevision101of4April1998A.TANKS10CapacityDesignItemNo.EachTempPress1LWS-TKName (gal)(°F)(psig)Material Quantity1A,B,C,DWaste22,633150 (1)Fiberglass 4 collector2A,B,C Floor22,633150 (1)Fiberglass 3 drain3A,BRegenerant22,633150 (1)Fiberglass 2 waste4A,B,C,DRecovery17,200150 (1)Fiberglass 4 sample 106A,B Phase5,600150 (1)Fiberglass 2 separator 7Backwash10,700150 (1)Fiberglass 1 22 Polyelec-200120 (1)Polyethylene1 trolyte RBSUSARTABLE11.2-1(Cont)2of4August1987B.PUMPS DesignItemNo.CapacityTDHPress 1LWS-P Name (gpm)(ft)(psig)Quantity1A,1B Waste1105002502 collector2A,2BFloordrain1105002502 collector 3ARegenerant1102351501
waste 4A,4B, Recovery1653352504 4C,4D sample6A,6B Phase552401502 separator7A,7B Backwash551851502tankpumps8A,BMediafilter350802502
backwash22A, Polyelec-11 (2)NA (3)2503 B,C trolyte RBSUSARTABLE11.2-1(Cont)Revision103of4April199810C.DEMINERALIZER(TREATMENT)VESSELS ItemNo.Capa-Design1LWS-cityVolumeTempPressDEMN(gpm)(ft 3)(°F)(psig)Type Material Quantity1A,B10060150150Regener-Rubber-2ablelinedC.S.
cation2A,B10075150150Regener-Rubber-2ablelinedC.S.
stratified anion3A,B10050150150Regener-Rubber-2ablelinedC.S.mixedbed 10 RBSUSARTABLE11.2-1(Cont)4of4August1987D.FILTERSItemNo.DesignCapa-Flow 1LWS-TempPresscityFluxFLTName (°F)(psig)(gpm)(gpm/ft)Material Quantity1A,BRad-1503501001C.S./2 waste304S.S.E.STRAINERSDesign OperatingItemNo.CapacityTempPressTempPress 1LWS-STR (gpm)(°F)(psig)(°F)(psig)Material Quantity4A,B100150250120230316S.S.26A,B100250150120130316S.S.2
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(1)Tankdesignpressureisliquidstatichead (2)Capacityingallonsperhour (3)Positivedisplacementpump RBSUSARTABLE11.2-2APPLICABLECODESANDSTANDARDSFORLIQUIDSYSTEMS Earth-quake SafetyCodeCri-TornadoQADescriptionClass Code Class teria CriteriaCat.1(1)Polyesteratmosphericstoragetanksarefilament-wound,fiberglass-reinforcedplasticplastictanksdesignedto meettheNationalBureauofStandardsPS15-69andthe SocietyofPlasticsIndustriestentativestandardfor filament-woundtanks.(2)ForverticalturbinetypepumpsofSafetyClassNNSandoperatingabove150psior212
°F,ASMESectionVIII,DivisionI,isusedasaguideincalculatingthewall thicknessforpressure-retainingparts.Forallother pumps,manufacturer'sstandardforintendedpumpservice maybeused.(3)RadwastefiltertoASMEVIII.1of1August1987Tanks(steeloralloy)NNSASME-NoNoNo VIII non-stampedTanks(poly-NNS (1)-NoNoNo ester)Filters NNS (3)-NoNoNoDemineral-NNSASME-NoNoNo izers VIII Pumps NNS (2)-NoNoNo RBSUSARRevision141of1September2001TABLE11.2-3MATERIALANDACTIVITYBALANCE-LIQUIDRADWASTESYSTEM14 AverageFractionof 1-Unit Primary FlowDischargeCoolant Input (GPD)Fraction Activity10Floordrains5,7000.10.001Equipmentdrains Drywell 3,400 0.01 1.00 Containment, auxiliary building,and fuelpool 3,700 0.01 0.10Radwastebldg 1,100 0.01 0.10Turbinebldg 3,000 0.01 0.001Ultrasonicresincleanerbackwash15,000 0.01 0.05Resinrinse 2,500 0.01 0.002Phaseseparator decant 320 0.01 0.002Chemicalwastes (deconandlab
drains)600 0.1 0.02Solidwaste
dewater 4,802 0.1 0.002 1014 RBSUSAR1of2August1987TABLE11.2-4EXPECTEDANNUALLIQUIDRELEASES Activity Released Isotope (uCi/g)(Ci)Na-24 1.2-09*5.0-03 P-32 3.5-11 1.5-04 Cr-51 1.0-09 4.5-03 Mn-54 1.2-11 5.0-05 Mn-56 1.2-09 5.5-03 Fe-55 1.7-10 7.5-04 Fe-59 5.1-12 2.3-05 Co-58 3.5-11 1.6-04 Co-60 6.8-11 3.0-04 Ni-63 1.7-13 7.5-07 Ni-65 7.2-12 3.2-05 Cu-64 3.3-09 1.5-02 Zn-65 3.5-11 1.6-04 Zn-69m 4.1-12 1.8-05 Sr-89 1.7-11 7.5-05 Sr-90 1.2-12 6.0-06 Sr-91 3.8-10 1.7-03 Sr-92 2.7-10 1.2-03 Y-91 7.5-12 3.3-05 Y-92 6.3-10 2.8-03 Y-93 4.0-10 1.8-03 Zr-95 1.4-12 6.0-06 Zr-97 7.2-13 3.2-06 Nb-95 1.4-12 6.0-06 Nb-98 5.6-12 2.5-05 Mo-99 3.1-10 1.4-03 Tc-99m 1.4-09 6.0-03 Tc-101 3.0-14 1.3-07 Tc-104 2.6-13 1.2-06 Ru-103 3.5-12 1.6-05 Ru-105 1.0-10 4.5-04 Ru-106 5.2-13 2.3-06 Ag-110m 1.7-13 7.5-07 Te-129m 6.8-12 3.0-05 Te-131m 1.4-11 6.0-05 Te-132 1.6-12 7.0-06 Ba-139 6.6-11 2.9-04 Ba-140 6.7-11 3.0-04 Ba-141 3.8-14 1.7-07 Ba-142 6.1-17 2.7-10 La-142 4.9-11 2.2-04 RBSUSAR2of2August1987TABLE11.2-4(Cont)
Activity Released Isotope (uCi/g)(Ci)Ce-141 5.1-12 2.3-05 Ce-143 4.2-12 1.9-05 Ce-144 5.2-13 2.3-06 Pr-143 6.8-12 3.0-05 Nd-147 5.1-13 2.2-06 W-187 4.0-11 1.8-04 Np-239 1.2-09 5.5-03 Br-83 1.5-10 6.5-04 Br-84 1.2-12 5.0-06 I-131 6.1-10 2.7-03 I-132 1.2-09 5.5-03 I-133 6.6-09 2.9-02 I-134 1.6-10 7.0-04 I-135 3.8-09 1.7-02 Rb-89 3.5-14 1.5-07 Cs-134 5.9-11 2.6-04 Cs-136 3.8-11 1.7-04 Cs-137 1.6-10 7.0-04 Cs-138 1.8-11 8.0-05 H-3 1.0-05 4.6+01 Grams released 4.4+12____________________
NOTES:11.2-09=1.2x10
-92Isotopereleasesoflessthan1.0-10curies/yraresetto0.0.Anticipatedoperationaloccurrences1.00-01curies/yraddedtorelease.Dilution(blowdown)releaserateis 4.38 x10 12ml/yr.Totalrelease(excludingtritium)is1.1-01curies/yror2.5-08uCi/g.
RBSUSARRevision101of2April1998TABLE11.2-5DESIGNANNUALLIQUIDRELEASES10DesignActivityReleasedECL (3)FractionIsotope(uCi/ml)(Ci/yr)(uCi/ml)ofECL (4)Na-241.2-9 (5)5.0-35.0-52.4-7P-323.5-111.5-49.0-63.9-6Cr-511.0-94.5-35.0-42.0-6Mn-541.2-115.0-53.0-54.0-7Mn-561.4-97.0-37.0-52.0-5Fe-551.7-108.0-41.0-41.7-6Fe-591.5-117.0-51.0-51.5-6Co-589.2-104.1-32.0-54.6-5Co-609.2-114.1-43.0-63.1-5Ni-631.7-131.8-61.0-41.7-9Ni-658.6-123.8-51.0-48.6-8Cu-643.3-91.5-22.0-41.6-5Zn-653.5-111.6-45.0-67.0-6Zn-69m4.1-121.8-56.0-56.8-8Sr-896.0-102.7-38.0-67.5-5Sr-904.6-112.1-25.0-79.2-5Sr-918.6-93.9-22.0-54.3-4Sr-924.5-91.9-24.0-51.1-4Y-914.5-112.0-48.0-65.6-6Y-923.8-91.7-24.0-59.5-5Y-932.4-91.1-22.0-51.2-4Zr-958.5-123.7-52.0-54.2-7Zr-974.8-122.1-59.0-65.3-7Nb-958.5-123.7-53.0-52.8-7Mo-994.3-91.9-22.0-52.2-4Tc-99m8.6-93.7-21.0-38.6-6Ru-1032.2-111.0-43.0-57.3-7Ru-1055.9-102.6-37.0-58.4-6Ru-1063.2-121.4-33.0-61.1-6Ag-110m1.1-114.9-56.0-61.8-6Te-129m6.8-113.0-47.0-69.7-6Te-131m8.5-113.7-48.0-61.1-5Te-1322.6-91.2-29.0-62.9-4Ba-1401.7-97.5-38.0-62.1-4Ce-1413.1-111.4-43.0-51.0-6Ce-1432.5-111.1-42.0-51.2-6Ce-1447.1-123.1-53.0-62.4-6Pr-1434.0-111.8-42.0-52.0-6 10 RBSUSARRevision102of2April1998TABLE11.2-5(Cont)10DesignActivityReleasedECL (3)FractionIsotope(uCi/ml)(Ci/yr)(uCi/ml)ofECL (4)Nd-1473.1-121.4-52.0-51.6-7W-1874.4-102.0-33.0-51.5-5Np-2394.2-82.0-12.0-52.1-3Br-839.1-103.9-39.0-41.0-6I-1313.8-91.7-21.0-63.8-3I-1327.3-93.4-21.0-47.3-5I-1334.0-81.8-17.0-65.7-3I-1349.7-104.3-34.0-42.4-6I-1352.3-81.0-13.0-57.7-4Cs-1343.7-101.6-39.0-74.1-4Cs-1362.3-101.1-36.0-63.8-5Cs-1379.6-104.2-31.0-69.6-4 H-3 (1)1.0-54.6+11.0-31.0-2 Total (2)1.7-77.5-19.2-31.6-2Dilutionreleaserate(blowdown)=4.38x10 12 ml/yr.______________________
(1)TritiumreleaseisinaccordancewithNUREG-0016,Rev1,1/79,page1-8,Section1.5.1.10.
(2)Alltotalsareexcludingtritium.
(3)ECLvaluesarefrom10CFR20,AppB,tableII,Col.2.
(4)FractionofECL=designactivityreleased(uCi/ml)ECL(uCi/ml)
(5)1.2-9=1.2x10
-9 RBSUSARTABLE11.3-1EXPECTEDRADIOACTIVEGASEOUSEFFLUENTFROMALLSOURCES(CI/YR/UNIT)1of2August1987 Mechan-icalContain-AuxTurbRadwasteVacuumOffGasIsotopement (1)Bldg Bldg (2)Bldg Pump SystemKr-83m<1<1<1<1neg4.7(-2)
Kr-85m 135<1neg210 Kr-85<1<1<1<1neg210 Kr-87<1212.2<1neg3.8(-4)
Kr-88 1318.2<1neg25 Kr-89<1211629negnegXe-131m<1<1<1<1neg21Xe-133m<1<1<1<1neg6.6(-2)Xe-1332783302201300900Xe-135m154580530negnegXe-135339466280500negXe-1374513520083negneg Xe-138 262002negnegCr-512.0(-6)9.0(-4)1.8(-4)7.0(-6)negneg Mn-544.0(-6)1.0(-3)1.2(-4)4.0(-5)negneg Fe-599.0(-7)3.0(-4)2.0(-5)3.0(-6)negneg Co-581.0(-6)2.0(-4)2.0(-4)2.0(-6)negneg Co-601.0(-5)4.0(-3)2.0(-4)7.0(-5)negneg Zn-651.0(-5)4.0(-3)1.2(-3)3.0(-6)negneg Sr-893.0(-7)2.0(-5)1.2(-3)negnegneg RBSUSARTABLE11.3-1EXPECTEDRADIOACTIVEGASEOUSEFFLUENTFROMALLSOURCES(CI/YR/UNIT)Revision142of2September2001 Mechan-icalContain-AuxTurbRadwasteVacuumOffGasIsotopement (1)BldgBldg (2)BldgPump SystemSr-903.0(-8)7.0(-6)4.0(-6)negnegnegZr-953.0(-6)7.0(-4)8.0(-6)8.0(-6)negneg Nb-951.0(-5)9.0(-3)1.2(-6)4.0(-8)negneg Mo-996.0(-5)6.0(-2)4.0(-4)3.0(-8)negneg Ru-1032.0(-6)4.0(-3)1.0(-5)1.0(-8)negneg Ag-110m4.0(-9)2.0(-6)negnegnegneg Sb-1242.0(-7)3.0(-5)2.0(-5)7.0(-7)negneg Cs-1347.0(-6)4.0(-3)4.0(-5)2.4(-5)negneg Cs-1361.0(-6)4.0(-4)2.0(-5)negnegneg Cs-1371.0(-5)5.0(-3)2.0(-4)4.0(-5)negneg Ba-1402.0(-5)2.0(-2)2.0(-3)4.0(-8)negneg Ce-1412.0(-6)7.0(-4)2.0(-3)7.0(-8)negneg14I-1312.0(-3)3.9(-2)1.1(-1)2.0(-3)8.1(-3)negI-1332.7(-2)5.3(-1)1.52.8(-2)1.1(-1)neg H-322.8neg22.8negnegneg Ar-4115negnegnegneg121.0C-14<1negnegnegneg9.5 14 (1)Fuelbuildingreleasesareincludedinthecontainmentreleases.
(2)Areductionfactoroffiveisincorporatedintotheturbinebuildingreleasestoaccountforspecialdesignfeaturestocontrolsystemleakage.
RBS USAR Revision 17 1 of 1 TABLE 11.3-2 DATA USED IN CALCULATING ANNUAL RELEASES OF RADIOACTIVE GASEOUS EFFLUENTS
- Parameter Data Maximum core thermal power 3,039 (Mwt) 14 Total steam flow rate 1.32 x 10 7 (lb/hr) Off gas system holdup time ~10 min Off gas charcoal bed holdup times (Kr) 46 hr (Xe) 42 days Plant capacity factor 80% Expected releases source term failed 50,000 Ci/sec fuel basis (after 30 min)
Design releases source term failed 304,000 Ci/sec fuel basis (after 30 min)
Iodine partition factor (carryover)
Normal Water Chemistry 0.015 Hydrogen Water Chemistry 0.04 14Off gas system charcoal mass/train 24,640 lb Dynamic adsorption coefficients (Kr) 105 (cm 3/gm) (Xe) 2,410 (cm 3/gm)Charcoal delay system normal operating 0F temperature Charcoal delay system dew point
<-40F temperature Ventilation systems See Section 9.4 Decontamination factors 90% (4" Deep Charcoal Element) 99% (HEPA Filter) *Data unchanged for TPO (Appendix K) uprate as other conservatisms in the analyses produce results that bound TPO uprate conditions.
RBSUSARTABLE11.3-3OFFGASSYSTEMMAJOREQUIPMENTITEMS1of4August1987OffGasPreheater Quantity 2 MaterialStainlesssteeltubes,carbonsteelshellShell:Designpressure,psig350Designtemperature,°F40/450Tube:Designpressure,psig1,000Designtemperature,°F40/575CatalyticRecombiner Quantity 2 MaterialCarbonsteelcartridge,carbonsteelshell.Catalystcar-tridgecontainingaprecious metalcatalystonmetalbase ofporousnondustingceramic.
Catalystcartridgetobere-placeablewithoutremoving
vessel.Designpressure,psig 350Designtemperature,°F 900OffGasCondenser Quantity 1 MaterialLowalloysteelshell,stain-lesssteeltubesShell:Designpressure,psig350Designtemperature,°F900Tube:Designpressure,psig600Designtemperature,°F150WaterSeparator Quantity 1 MaterialCarbonsteelshell,stainlesssteelwiremeshDesignpressure,psig 350Designtemperature,°F 250 RBS USAR TABLE 11.3-3 (Cont)
Revision 18 2 of 4 Cooler-Condenser Quantity 2 Material Carbon or stainless steel shell, stainless steel tubes Shell: Design pressure, psig 350 Design temperature, °F32/170 (2) Tube: Design pressure, psig 100 Design temperature, °F 150 Moisture Separator (downstream of cooler-condenser)
Quantity 2 Material Carbon steel shell, stainless steel wire mesh Design pressure, psig 350 Design temperature, °F 32/150 Desiccant Dryer Quantity 4 Material Carbon steel shell packed with Linde Mol Sieve or equivalent Design pressure, psig 350 Design temperature, °F 32/500 Desiccant, Regeneration Skid Quantity 2
Dryer Chiller Quantity 2 Material Carbon steel shell, stainless steel tubes Design pressure, psig 50 Design temperature, °F 32/500 Regenerator Blower (1)Quantity 2 Material Cast iron housing Design pressure, psig 50 Design temperature, °F 32/150 (1) Material meets seller's standard.
(2)The cooler condenser shell side has been evaluated for operation up to 180°F (Ref. ER 03-0570)
Revision 19 3 of 4 Dryer Heater Quantity 2 Material Carbon steel vessel Design pressure, psig 50 Design temperature, °F 32/500 Gas Cooler Quantity 2 Material Carbon or stainless steel Tube: Design pressure, psig 1,050 Design temperature, °F -50/150 Glycol Cooler Skid Quantity 1
Glycol Storage Tank Quantity 1 Material Carbon steel 3,000 gal Design pressure Water-filled hydrostatic Design temperature, °F 32 API-650 Glycol Solution Refrigerator and Motor Drive (1) Quantity 3 Material Conventional refrigeration unit Glycol solution exit temperature, °F 35 Glycol Pump and Motor Drive (1) Quantity 3 Material Cast iron, 3-in connections Design temperature, °F 0 Prefilter and After Filter Quantity 2 each Material Carbon steel shell, high-efficiency, moisture-resistant filter element, flanged shell Design pressure, psig 350 Design temperature, °F
-50/250 RBSUSARTABLE11.3-3(Cont)4of4August1987CharcoalAdsorber Quantity8beds MaterialCarbonsteel,approximately4-fto.d.x21-ftvesselseachcontainingapproximately 3tonsofactivatedcarbonDesignpressure,psig 350Designtemperature,°F
-50/250 RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT Revision 10 April 1998 PROCESS DATA FOR THE OFF GAS (RECHAR.) SYSTEM TABLE 11.3-4 (SHEET 1 OF 2)
THIS TABLE HAS BEEN DELETED RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT Revision 10 April 1998 PROCESS DATA FOR THE OFF GAS (RECHAR.) SYSTEM TABLE 11.3-4 (SHEET 2 OF 2)
THIS TABLE HAS BEEN DELETED RBSUSARTABLE11.3-5OFFGASSYSTEMALARMEDPROCESSPARAMETERS1of2August1987_____MainControlRoom Parameters Indicated RecordedAirejectordischargepressure-high XPreheaterdischargetemperature-low XRecombinercatalysttemperature-high/low X XOffgascondenserwaterlevel(dual)-
high/low XOffgascondensergasdischargetemperature-high(LOCAL)
X H 2analysis(offgascondenserdischarge)-dual-high X XOffgascondenserdischargeradiation-
high X XGasflow-high/low X XCooler-condenserdischarge temperature-high/low X XGlycolsolutiontemperature-
high/low X XGlycolsolutionlevel-low(AlarmedOnly)Gasdrierdischargehumidity-high(LOCAL)
XPrefilterdP-high XCharcoaladsorbertemperature-high X XCarbonvaulttemperature-high/low XCarbonvaulttemperature-high/low X X RBSUSARTABLE11.3-5(Cont)2of2August1987_____MainControlRoom Parameters Indicated RecordedCarbontrainflow-high/low X XAfterfilterdP-high XOffgas(carbonbeddischarge)radiation-high X XDilutionsteamflow-low X
RBSUSARTABLE11.3-6EQUIPMENTMALFUNCTIONANALYSIS1of5August1987 Equipment Design Item Malfunction Consequences PrecautionsSteamjetLowflowofWhenthehydrogenandoxygenAlarmprovidedon airmotivehighconcentrationexceed4andsteamforlowsteam pressure5vol%,respectively,theflow.Recombiner steamprocessgasbecomesflammabletemperaturealarm.InadequatesteamflowSteamflowtobecausesoverheatingandde-heldatconstantteriorationofthecatalyst.maximumflowre-gardlesstoplantlevel.Recombiner temperaturealarm.WearofIncreasedsteamflowtore-Lowtemperaturesupplysteamcombiner.Thiswouldreducealarmsonpreheaternozzleofdegreeofrecombinationatexit(recombinerin-ejectorlowpowerlevels.let).Recombiner H 2 analyzers.PreheatersSteamleakWouldfurtherdiluteprocessSparepreheater.offgas.Steamconsumption wouldincrease.LowpressureRecombinerperformancewouldLow-temperaturealarmssteamsupplyfalloffatlowpowerlevel,onpreheaterexitandhydrogencontentofre-(recombinerinlet).combinergasdischargemayRecombineroutletincrease,eventuallytoaHanalyzers.combustiblemixture.RecombinersCatalystTemperatureprofilechangesTemperatureprobes graduallythroughcatalyst.EventuallyinrecombinerHdeactivatesexcessH 2wouldbedetectedanalyzerprovidedbyH 2analyzerorbygassparerecombiner.flowmeter.Eventuallythestrippedgascouldbecome combustible.
RBSUSARTABLE11.3-6EQUIPMENTMALFUNCTIONANALYSIS2of5August1987 Equipment Design Item Malfunction Consequences Precautions Catalyst H 2conversionfallsoffandCondensatedrains,getswetatH 2isdetectedbydownstreamtemperatureprobes startanalyzers.Eventuallytheinrecombiner.Airgascouldbecomecombustible.bleedsystematstartup.Re-combinerthermalblanket,sparere-combinerand heater,hydrogen
analyzer.Offgas CoolingThecoolant(reactorcon-None.condenser waterdensate)wouldleaktothe leakprocessgas(shell)side.
Thiswouldbedetectedif drainwellliquidlevelin-creases.Moderateleakagewouldbeofnoconcernfrom aprocessstandpoint(theprocesscondensatedrainstothehotwell).
LiquidIfbothdrainvalvesfailTwoindependentdrainlevelin-toopen,waterbuildsupsystems,eachpro-strumentsinthecondenserandthevidedwithhigh-and failpressuredropincreases.low-levelalarms.ThehighdeltaP,ifnotdetectedbyinstrumentation,couldcausepressurebuild-upinthemaincondenser andeventuallyinitiateareactorscram.Ifadrainvalvefailstoclose,gas recyclestothemaincon-denser,increasestheloadontheSJAE,andincreases theoperatingpressureof themaincondenser.
WaterCorrosionofHigherquantityofwaterStainlesssteel separatorwiremeshcollectedinholduplinemeshspecified.
elementandroutedtoradwaste.
RBSUSARTABLE11.3-6EQUIPMENTMALFUNCTIONANALYSIS3of5August1987 Equipment Design Item Malfunction Consequences Precautions Holdup CorrosionLeakagetosoilofgaseousOutsideofpipe lineoflineandfissionproducts.dippedandwrapped1/4-incorrosion allowance.
Cooler-CorrosionGlycol-watersolutionwouldStainlesssteel condenersoftubesleakintoprocess(shell)tubesspecified.sideandbedischargedtoLowlevelalarmcleanradwaste.Ifnotde-glycoltanklevel.tectedatradwaste,theSparecoolercon-glycolsolutionwoulddenserprovided.dischargetoreactor condensatesystem.IcingupofShellsideofcoolercouldDesignglycol-H 2 tubesplugupwithice,graduallysolutiontemperaturebuildinguppressuredrop.wellabovefreez-Ifthishappens,thespareingpoint.Spareunitcouldbeactivated.unitprovided.CompleteblockageofbothTemperatureindi-unitswouldincreasedeltacationandlowPandleadtoareactoralarmsonglycol scram.temperatureandpro-cessgastemperature.Glycolre-MechanicalIfbothspareunitsfailTwosparerefrig-frigerationtooperate,theglycoleratorsduring machinessolutiontemperaturerisesnormaloperationareandthedehumidifica-provided.Glycolsol-tionsystemperformanceutiontemperaturedeteriorates.Thisre-alarmsprovided.Gasquiresrapidregenerationmoisturedetectorscyclesforthedesiccantprovideddownstreambedsandmayraisethegasofgasdriers.dewpointasitisdischarged fromthedrier.
RBSUSARTABLE11.3-6EQUIPMENTMALFUNCTIONANALYSIS4of5August1987 Equipment Design Item Malfunction Consequences Precautions Moisture CorrosionIncreasedmoisturewouldbeStainlesssteelmesh separa-wiremeshretainedinprocessgasspecified.Spareunit tors elementroutedtogasdriers.Overprovided.HighdeltaPalongperiod,thedesic-alarmonprefilter.cantdriercycleperiodwoulddeteriorateasre-sultofmoisturepickup.
Pressuredropacrosspre-filtermayincreaseiffiltermediaiswetted.PrefiltersLossofMoreradioactivitywouldde-Spareunitprovided integritypositthedrierdesiccant.inseparatevault.offilterThiswouldincreaseradia-DeltaPinstrumenta-tionlevelinthedriertionprovided.vaultandmakemaintenancemoredifficult,butwould notaffectreleasestothe environment.
Desiccant MoistureMoisturewouldfreezoutinDriercyclesontime.
drierbreakthroughgascoolerwouldresultRedundantgashumidityinincreasedsystempres-analyzersandalarmssuredrop.Gaswithahighsupplied.Redundantdewpointtemperaturedriersystemsupplied.wouldreachcharcoalbed.Gasdrierandfirstcharcoalbedcanbe bypassedthroughal-ternatedriertosecondcharcoalbed.
DesiccantMechanicalInabilitytoregenerateRedundant,shielded regenera-failure desiccant.desiccantbedsand tiondrierequipment equipment supplied.
RBSUSARTABLE11.3-6EQUIPMENTMALFUNCTIONANALYSIS5of5August1987 Equipment Design Item Malfunction Consequences Precautions Charcoal CharcoalCharcoalperformancede-Highlyinstrumented, adsorbersaccumulatesterioratesgraduallyasmechanicallysimple moisturemoisturedeposits,holdupgasdehumidificationtimesforkryptonandxen-systemwithredundantonwoulddecrease,and equipment.plantemissionswouldin-crease.Provisionsmade fordryingcharcoalas requiredduringannual outage.VaultMechanicalIftemperatureexceedsap-Sparerefrigeration refriger-failureproximately0°F,increasedunitprovided.Vault ationemissioncouldoccur.andcharcoaladsorber unitstemperaturealarms
provided.AfterLossofin-Probablyofnorealconse-DeltaPinstrumenta-filtertegrityofquence,thecharcoalmediationprovided.Sparefiltermediaitselfshouldbeagoodunitprovided.filteratthelowairvel-
ocity.System InternalReleaseofradioactivityMainprocessequip-detonationifpressureboundaryfails.mentandpipingaredesignedtocon-tainadetonation.
SystemEarthquakeReleaseofradioactivity.Doseconsequences damagearewithin10CFR20limits.AnalysisisincludedinRefer-ence6.
RBSUSARTABLE11.3-7RADWASTEEQUIPMENTDESIGNCODES1of1August1987 WelderDesignandQualificationInspectionEquipmentFabrication MaterialsandProcedureandTestingPressureASME ASME ASME ASMEvesselsSectionVIIISectionIISectionIXSectionVIIIDiv1Div1 Atmos-ASME (2)ASME ASME ASME (2)phericSectionIIISectionIISectionIXSectionIIIor0-15Class3,APIClass3,API psig 620;650,AWWA 620;650,AWWA tanks D-100 D-100 Heat ASME ASME ASME ASMEexchang-SectionVIIISectionIISectionIXSectionVIII ersDiv1;andDiv1 TEMA PipingANSIB31.1ASTMor ASMEANSIB31.1 and ASMESectionIX valvesSectionII PumpsManufacturer'sASME ASME ASME (1)Standards (1)SectionIISectionIXSectionIII orManufac-(asrequired)Class3;and
turer's Hydraulic Standard Institute (1) Manufacturers standard for the intended service. Hydrotesting should be 1.5 times the design pressure.
(2) ASME Code Stamp and material traceability not required.
RBSUSARTABLE11.3-814Revision141of1September2001DESIGNANNUALRADIOACTIVEGASEOUSRELEASESVSECLContinuousReleaseRadwasteBuilding IntermittentRelease(MVP)ActivityatActivityatActivityat RestrictedFractionRestrictedFractionRestrictedFractionTotalECLValuesAreaBoundary ofAreaBoundary ofAreaBoundary ofFractionUsed Isotope (µCi/cc)ECL (µCi/cc)ECL (µCi/cc)ECLofECL(Ci/cc)Kr-83m 1.9-12 3.9-083.9-085.0-05 Kr-85m 1.4-10 1.4-031.4-031.0-07 Kr-85 1.4-10 1.9-041.9-047.0-07 Kr-87 9.7-12 4.8-044.8-042.0-08 Kr-88 3.0-11 3.3-033.3-039.0-09 Kr-89 7.6-11 7.6-02 3.7-10 3.7-017.6-021.0-09 Xe-131m 1.5-11 7.6-067.6-062.0-06 Xe-133m 2.0-12 3.2-063.2-066.0-07 Xe-133 8.2-10 1.6-03 2.8-09 5.6-03 8.4-091.7-022.4-025.0-07 Xe-135m 8.9-11 2.2-03 6.7-09 1.7-011.7-014.0-08 Xe-135 1.9-10 2.7-03 3.5-09 5.1-02 3.4-094.8-021.0-017.0-08 Xe-137 2.4-10 2.4-01 1.1-09 1.1+002.4-011.0-09 Xe-138 1.3-10 6.6-03 2.5-11 1.3-037.9-032.0-08 Cr-51 1.2-16 3.8-07 1.5-17 4.8-103.8-073.0-08 Mn-54 1.2-16 1.2-07 8.3-17 8.3-082.0-071.0-09 Fe-59 9.6-17 1.9-07 1.8-17 3.6-082.3-075.0-10 Co-58 1.1-15 1.1-07 1.1-16 1.1-072.2-071.0-09 Co-60 5.9-16 1.2-05 2.0-16 3.9-061.6-055.0-11 Zn-65 5.4-16 1.4-06 8.2-18 2.0-081.4-064.0-10 Sr-89 4.5-15 2.2-052.2-052.0-10 Sr-90 4.4-17 7.4-067.4-066.0-12 Zr-95 4.5-16 1.1-06 1.0-16 2.5-071.4-064.0-10 Nb-95 5.7-15 2.9-06 5.1-19 2.5-102.9-062.0-09 Mo-99 8.7-14 4.4-05 8.7-19 4.3-104.4-052.0-09 Ru-103 2.5-15 2.8-06 1.3-19 1.4-102.8-069.0-10 Ag-110m 1.3-18 1.3-081.3-081.0-10 Sb-124 3.2-17 1.1-07 8.8-18 2.9-081.4-073.0-10 Cs-134 2.6-15 1.3-05 3.1-16 1.6-061.5-052.0-10 Cs-136 2.7-16 3.0-073.0-079.0-10 Cs-137 3.3-15 1.7-05 5.1-16 2.5-061.9-052.0-10 Ba-140 5.9-14 3.0-05 2.1-15 1.1-063.1-052.0-09 Ce-141 1.7-15 2.1-06 8.8-19 1.1-092.1-068.0-10 I-131 1.5-13 7.5-04 2.5-14 1.3-04 2.1-141.1-049.8-042.0-10 I-133 2.0-12 2.0-03 3.5-13 3.5-04 2.9-132.9-042.7-031.0-09 H-3 4.8-12 4.8-054.8-051.0-07 Ar-41 1.5-11 1.5-031.5-031.0-08 C-14 1.2-12 3.8-04_______3.8-04
_______3.0-09 TOTALS: 3.3-01 2.3-016.5-026.3-01 14 RBS USAR TABLE 11.3-9 FREQUENCY AND QUANTITY OF STEAM DISCHARGED TO SUPPRESSION POOL Quantity Frequency of Steam Event Category Lb/Event______________________________
(1) Events 1 and 2 based on steam flow rate during test mode according to RCIC System Process Diagram, 762E421A, for 60 and 10 min, respectively.
(2) Event 3 assumes tested SRV opened 30 sec maximum at 300-500 psig vessel pressure.
(3) Event 4 assumes tested SRV opened 30-60 sec at 1,000 psig vessel pressure.
(4) Event 5 based on maximum average SRV leakage rate of 20-lb/hr valve.
(5) Event 6 thru 18 based on event description from Chapter 15.
(6) Event 19 based on vessel depressurized to 100 psia with additional SRV's opened 10 min following scram.
(7) Isolation event. Except for events 15 and 16, it is assumed that SRV actuation is terminated 30 min into the event whereupon the reactor is depressurized at 100F/hr via RHR shutdown cooling mode. For events 15 and 16, it is assumed that loss of plant air preventsnormal SRV opening, vessel depressurized via ADS SRVs.Revision 19 1 of 1 1. RCIC test (1)Moderate 25,200 2. Inadvertent RCIC injection (1) Moderate 4,200 3. SRV test (each valve)
(2) Moderate 3,900 4. SRV flow capacity test (each valve)
(3) Infrequent 15,300 5. Total SRV leakage (16 valves)
(4) Continuous 320/hr 6. Trip of both recirculation pump motors (5) Moderate 30,000 7. Turbine trip (5) Moderate 30,000 8. Generator load rejection (5) Moderate 30,000 9. Pressure regulator failure, open (5) Moderate 834 , 3 00 (7)10. Recirculation controller failure (5) Moderate 30,000 11. Loss of all feedwater flow (5) Moderate 30,000 12. Inadvertent MSIV closure (5) Moderate 834 , 3 00 (7)13. Loss of condenser vacuum (5) Moderate 834 , 3 00 (7)14. Feedwater control failure, maximum demand (5) Moderate 30,000 15. Loss of auxiliary transformer (5) Moderate 777,000 16. Loss of all grid connections (5) Moderate 777,000 17. Turbine trip w/o bypass (5) Infrequent 834 , 3 00 (7)18. Generator load rejection w/o bypass (5) Infrequent 834 , 3 00 (7)19. Stuck open SRV (6) Moderate 592,000
3(1)Processedwastevolume 3x" (2)Basedon365daysoperationperyear (3)4.7-02=4.7x10
-2Revision101of1April1998RBSUSARTABLE11.4-1ANNUALQUANTITIESOFSOLIDIFIEDANDRADIOACTIVEWASTEMATERIAL(1-UnitNormal)
Volume(2)SpecificActivityCurieContentSolidWaste (ft 3/yr)(µCi/cc)_____(Ci/yr)_Stream Expected Design Expected Design Expected DesignRadwastefilter 414(1)828(1)6.94-018.65-018.1 20.3 sludge10Fuelpool/RWCU/
486(1)972(1)53.9 175 743.6 4801.7SPCsludgeRadwaste,SPC&fuelpool1,300(1)2,600(1)6.18 50.6 221 3,718deminspentresin 10Condensatedemin6,800(1)13,600(1)6.77 41.2 1305.6 15,912spentresinCompactibledry 14,63219,3064.8-024.7-029.76 12.8solidwaste Noncompactibledry 6,9429,0627.58 7.62 745 978solidwaste RBSUSARTABLE11.4-2EXPECTEDISOTOPICCOMPOSITIONOFSOLIDIFIEDANDDRYRADIOACTIVEWASTEMATERIAL(1-UnitNormal)10 Radwaste,RadwasteSPCandFuelCondensateFuelPoolFilterPoolDemin DeminFilter/RWCUCompactibleNoncompactibleSludgeSpentResin (2)SpentResinSPCSludge (2)DryWasteDryWaste Isotopes(Ci/cc)(Ci/cc)(Ci/cc)(Ci/cc)(Ci/yr)(Ci/yr)10Revision101of2April1998 BR83--3.84-02---I131-3.21-01 2.06 5.04-01--I132-2.80-01 3.64-01 2.28-03--I133-1.90 2.2 2---I134-1.65-02 2.49-01---I135-4.50-01 8.96-01---SR89-9.76-03 1.15-02 6.47-01--SR90---1.13-01--SR91-6.45-02 6.56-03---SR92-1.62-02----Y90---1.13-01--Y91M-2.80-02----Y91--1.68-02 1.03--Y92-1.16-01----Y 93------ZR95---6.26-02--NB95---9.51-02--MO99-1.44-01 2.29-02---TC99M-4.34-01 6.59-02---RU103---1.04-01--RU105------RU106---4.31-02--RH103M---9.40-02--RH105M------RH106---4.31-02--TE129M---1.68-01--TE129---1.09-01--TE131M------TE131------TE132-7.50-04 1.33-04 8.00-06--CS134---4.42-01 6.44-01 4.92+01 CS136---1.39-02--CS137---1.27 1.18 9.01+01 BA137M---1.21--BA139-4.21-03----BA140-3.71-02 2.07-02 2.54-01--LA140---2.92-01--
RBSUSARTABLE11.4-2EXPECTEDISOTOPICCOMPOSITIONOFSOLIDIFIEDANDDRYRADIOACTIVEWASTEMATERIAL(1-UnitNormal)10 Radwaste,RadwasteSPCandFuelCondensateFuelPoolFilterPoolDemin DeminFilter/RWCUCompactibleNoncompactibleSludgeSpentResin (2)SpentResinSPCSludge (2)DryWasteDryWaste Isotopes(Ci/cc)(Ci/cc)(Ci/cc)(Ci/cc)(Ci/yr)(Ci/yr)10Revision 1022of2April1998 LA141------CE141---1.88-01--CE143------CE144---4.15-02--PR143---3.23-02--PR144---4.15-02--ND147------NA241.13-012.80-01
P32 4.30-03--1.75-01--CR511.25-015.76-01 5.37-01 1.93+01 3.03-01 2.31+01 MN54---9.82-01 1.85-01 1.42+01 MN567.33-027.47-02
FE552.13-029.94-02 1.62-01 1.56+01--FE59 6.38-04--1.75-01--CO584.34-032.02-02 2.61-02 1.71 1.02-01 7.82 CO60 8.45-03--6.32 1.63 1.24+02 CU643.15-017.26-01
ZN65 4.34-03--2.73 7.76-01 5.92+01 ZN69M 2.06-02-----AG110M---1.39-02--AG110---1.81-04--W187-1.28-02----NP239-5.42-01 5.15-02 3.47-04--F18 3.94-03-----Other 1----6.30-02 4.84 Notes5.42-01=5.42x10
-1 (1)Forcompactibleandnoncompactibledrysolidwaste,"other"meansacombinationofFE59,ZB95,andNB95.10 (2)SPCsludgeanddeminresinisotopicactivitycomparabletothesevalues.RefertocalculationG13.18.9.0-005fordetailedisotopicmixturesandconcentrations.
10 3(1)RefertoapplicableCNStopicalreportforadescriptionofthesecomponents.
3Revision31of1August1990RBSUSARTABLE11.4-3SOLIDRADWASTECOMPONENTDESCRIPTION Capacity Design Design Component Quantity (ft 3)PressureTemp(°F)MaterialsWastesludge1 838 Atmos.150 Fiberglass tank DischargePressureCapacity Type (psig)(gpm)Wastesludge1Progressing0-75 0-50Carpenter20 pump cavity stainless steel Contractor
equipmenty(1)
RBSUSARTABLE11.4-4APPLICABLECODESANDSTANDARDSFORSOLIDRADWASTESYSTEMS Quality SafetyCodeEarthquakeTornadoAssuranceDescriptionClass Code Class Criteria CriteriaCategoryI(1)Polyesteratmosphericstoragetanksarefilament-woundfiberglass-reinforcedplastictanksdesignedtomeetNationalBureauofStandardsVoluntaryProductStandardPS15-69andAmericanSocietyforTestingandMaterialsSpecification No.ASTMD3299-74forfilament-woundtanks.(2)Forverticalturbine-typepumpsofSafetyClassNNSandoperatingabove150psior212°F,ASMESectionVIII,DivisionI,isusedasaguideincalculatingthewall thicknessforpressure-retainingparts.Forallotherpumps,themanufacturer's standardforintendedpumpservicemaybeused.(3)Fordetailsconcerningcontractorequipment,refertoapplicableCNStopical report.3 Revision31of1August1990 TanksNNS(1)-No No No (polyester)
PumpsNNS(2)-No No NoContractor-(3)(3)(3)(3)
(3)(3)furnished equipment RBS USAR TABLE 11.4-5
Low Level Radwaste Storage Design 1 Dewatered resin with 1-25 R/hr radiation field 2 Dry active waste compacted and uncompacted with 1-5 mR/hr radiation field 3 Dry active waste incinerated and compacted with 10-200 mR/hr radiation field 4 Condenser tube bundle (compacted), tube sheets, tube support plates and tube reinforcing steel with 10-25 mR/hr radiation field.
Revision 24 1 of 1 Waste Type Container Type Container Volume Maximum No. of Containers Total Volume Resin 1 HIC 205 cu ft 90 18,450 cu ft DAW 2 Drum-55 gl 7.5 cu ft 989 7,395 cu ft DAW 3 Box-E48 45 cu ft 123 5,535 cu ft Other 4 Box-B25 96 cu ft 52 4,992 cu ft
RBS USAR TABLE 11.4-6 Revision 24 1 of 1 Container Type Estimated # of Containers Design # of Containers Activity /
Container (mci/cont)
Estimated Activity in Storage (mc) Design Activity (mci)
Drums 80.00 200.00 1.00 80.00 200.00 Boxes 40.00 150.00 3.00 120.00 450.00 Sealands 40.00 80.00 8.00 320.00 640.00 Liners (HICs) 0.00 32.00 1000.00 0.00 32000.00 Misc. 15.00 50.00 1.00 15.00 50.00 Total 535.00 33340.00 RBS USAR TABLE 11.5-1 PROCESS AND EFFLUENT RADIATION MONITORING SYSTEMS Revision 16 1 of 5 March 2003 16 Nominal Equipment Monitor Monitor Channel Detector Range Number Location Type Type Type (uCi/cc) Isotope Function A. Systems Required for Safety*RE5A Fuel building Gas - Gas (L) Beta 10-7-10-1 Xe133, Kr85 Monitors effluent ventilation extended scintillator (4) releases. Acti- exhaust range Gas (M) CdTe 10 10 2 Xe133, Kr85 vates Cat. I Gas (H) CdTe 10 10 5 Xe133, Kr85 filters. PAM(1). *RE5B Fuel building Gas and Gas Beta 10-7-10-1 Xe133, Kr85 Monitors effluent ventilation particulate scintillator releases and exhaust Particulate Beta 10-11-10-5 I131 airborne radia- scintillator tion. Activates Cat.
I filters. *RE13A, Main control Gas Gas Beta 10-7-10-1 Xe133, Kr85 Monitors incoming 13B room air scintillator control room air. *RE14A, intakes (two Activates Cat. I 14B per intake) filters (13A, 13B). 9*RE21A, Containment Area Area Ion chamber 10 1-10 7 mR/hr NA Activates con- 21B purge isola-tainment purge tion (two) isolation.
98*REN003A, Main steam Online Area Ion chamber 10 0-10 6 mr/hr NA Monitors main C line steam steam lines for (two)(2) fuel damage and carryover to turbine building.
8B. Systems Required for Plant Operation*RE125 Main plant Gas - Gas (L) Beta 10-7-10-1 Xe133, Kr85 Monitors effluent exhaust extended scintillator (4) releases. PAM (1) duct range Gas (M) CdTe 10 10 2 Xe133, Kr85 Gas (H) CdTe 10 10 5 Xe133, Kr85 *RE111 Containment Gas and Gas Beta 10 10-1 Xe133,Kr85 Monitors containment atmosphere particulate scintillator for airborne Particulate Beta 10-11-10-5 I131 radiation. scintillator 16 TABLE 11.5-1 (Cont) 16 Nominal Equipment Monitor Monitor Channel Detector Range Number Location Type Type Type (uCi/cc) Isotope Function Revision 16 2 of 5 March 2003 *RE112 Drywell Gas and Gas Beta 10-7-10-1 Xe133, Kr85 Monitors drywell atmosphere particulate scintillator for airborne Particulate Beta 10-11-10-5 I131 radiation. RCPB scintillator leak detection (3).-RE6A Radwaste Gas - Gas (L) Beta 10-7-10-1 Xe133, Kr85 Monitors effluent building extended scintillator (4) releases. PAM (1) ventilation range Gas (M) CdTe 10 10 2 Xe133, Kr85 exhaust Gas (H) CdTe 10 10 5 Xe133, Kr85 -RE6B Radwaste Gas and Gas Beta 10 10-1 Xe133, Kr85 Monitors effluent building particulate scintillator releases and ventilation Particulate Beta 10-11-10-5 I131 airborne radia- exhaust scintillator tion. -RE126 Main plant Gas and Gas Beta 10-7-10-1 Xe133, Kr85 Monitors effluent exhaust duct particulate scintillator releases. Particulate Beta 10-11-10-5 I131 scintillator *RE11A, Reactor build- Gas Gas Beta 10-7-10-1 Xe133, Kr85 Monitors airborne 11B ing annulus scintillator levels in the ventilation annulus.
(two) Activates SGTS. *RE15A, RHR heat Liquid Liquid Gamma 10-7-10-2 Cs137 Monitors effluent 15B exchanger scintillator from heat ex-service changers for water (two) contamination. 12-RE19A, Fuel pool Liquid Liquid Gamma 10-7-10-2 Cs137 Removed From Service. 19B cooling pumps scintillator Controlled In Accord-discharge (two) ance With ADM-0045.
(5) 12-RE102 Turbine plant Liquid Liquid Gamma 10 10-2 Cs137 Removed from Service, component scintillator Controlled in cooling water Accordance With ADM-0045 (5) 16 TABLE 11.5-1 (Cont) 16 Nominal Equipment Monitor Monitor Channel Detector Range Number Location Type Type Type (uCi/cc) Isotope Function Revision 16 3 of 5 March 2003 -RE103 Standby gas Gas Gas Beta 10 10-1 Xe133, Kr85 Monitors radiation treatment scintillator level in SGTS system effluent.
effluent -RE107 Liquid Liquid Liquid Gamma 10 10-2 Cs137 Monitors radwaste radwaste scintillator effluent discharge effluent to environment. Isolates system at trip level. 12-RE108 Cooling tower Liquid Liquid Gamma 10 10-2 Cs137 Monitors cooling blowdown line scintillator tower blowdown.
12-RE110 Auxiliary Gas and Gas Beta 10 10-1 Xe133, Kr85 Monitors airborne building particulate scintillator radiation levels ventilation Particulate Beta 10-11-10-5 I131 in auxiliary scintillator building exhaust. -RE116 Containment Gas Gas Beta 10 10-1 Xe133, Kr85 Monitors function purge gaseous scintillator of containment exhaust purge filter. Isolates purge. -RE117 Mechanical Gas Gas Beta 10 10-1 Xe133, Kr85 Removed from Service, vacuum pump scintillator Controlled in gaseous dis- Accordance With charge ADM-0045 (5)-RE118 Turbine Gas and Gas Beta 10 10-1 Xe133, Kr85 Monitors airborne building particulate scintillator radiation levels ventilation Particulate Beta 10-11-10-5 I131 in turbine building (including scintillator exhaust.
condensate demineralizer
area) 16 TABLE 11.5-1 (Cont) 16 Nominal Equipment Monitor Monitor Channel Detector Range Number Location Type Type Type (uCi/cc) Isotope Function Revision 16 4 of 5 March 2003 12-RE120 Fuel pool Liquid Liquid Gamma 10-7-10-2 Cs137 Removed From Service. cooling scintillator Controlled In Accord- demineralizer ance With ADM-0045 (5) outlet
-RE121 Reactor plant Liquid Liquid Gamma 10 10-2 Cs137 Monitors RPCCW component scintillator discharge for cooling water detection of radiation inleakage. -RE122 Radwaste Online Steam Gamma 10 10-1 N16 Removed From Service.
reboiler clean steam scintillator Controlled In Accord-steam outlet ance With ADM-0045 (5) -RE123 Seal steam Online Steam Gamma 10 10-1 N16 Removed From Service.
evaporator steam scintillator Controlled In Accord-clean steam ance With ADM-0045 (5) outlet -RE124 Offgas build- Gas and Gas Beta 10 10-1 Xe133, Kr85 Monitors airborne ing ventila- particulate scintillator radiation levels tion Particulate Beta 10-11-10-5 I131 in offgas building scintillator exhaust.
1215(2) Offgas Gas Gas GM tube 10 0-10 6 mr/hr NA Monitors process pretreatment before treatment. (2) Offgas post- Gas Gas GM tube 10 0-10 6 cpm NA Monitors process treatment after treatment. Isolates discharge.
15 16 RBS USAR TABLE 11.5-1 (Cont)
Revision 22 5 of 5 ______________________________
(1) PAM - Post-accident monitor.
(2) Monitors are not part of digital radiation monitoring system. They are supplied separately as part of the process system. (3) Reactor coolant pressure boundary leak detection, in accordance with Regulatory Guide 1.45.
(4) The gaseous effluent monitors used on River Bend are manufactured by the General Atomic Company. The detector model nos. used are RD-52 (beta scintillator) and RD-72 (CdTe). The energy dependence of these monitors is in accordance with the design requirements of Regulatory Guide 1.97 overall system accuracy within a factor of two
under accident conditions. Purge capability is provided on all monitors to allow background determination and
correction. Also, post-accident shielding is provided on applicable monitors to prevent saturation of the
detectors from background radiation. Post-accident particulate and iodine sampling to 10 uCi/cc is provided with
these monitors. Shielding of these filters is provided to satisfy Regulatory Guide 1.97 criteria for maintaining
doses ALARA. Sampling systems are designed in accordance with ANSI 13.1. Each effluent monitor is equipped with
a dedicated display panel and recorder in the main control room. Modifications to the system data base and functional control capabilities are available via the control room panels. L, M, and H refer to low-, medium-,
and high-range gas channels. 12 (5) Procedure ADM-0045, "System Management and Utilization of the DRMS" 12 RBS USAR TABLE 11.5-2 GRAB SAMPLES FOR RADIOLOGICAL ANALYSIS Grab Sample Grab Sample at the Local Grab at the Sample Point Location Sample Station Sample Radiation Monitor Revision 16 1 of 6 March 2003 Reactor Steam Supply System Reactor Water Recirculation System Pump Discharge X - -
Main Steam Line X - - Reactor Water Cleanup System Filter/Demineralizer Influent X - - Filter/Demineralizer Effluent X - - Fuel Pool Cooling and Cleanup System12 Purification Pump Discharge X - - Filter Effluent X - - Demineralizer Effluent X - - 12Reactor Plant Component Cooling Water Cooling Water Sample (Outlet of Each Major Heat Exchanger) X - X Turbine Plant Component Cooling Water16 Cooling Water Sample (Outlet of Each Major Heat Exchanger)
X - - 16 Residual Heat Removal System Heat Exchanger Outlet (Service Water) X - X Control Rod Drive System CRD Supply Inlet Line X - -
RBS USARTABLE 11.5-2 (Cont)GRAB SAMPLES FOR RADIOLOGICAL ANALYSISGrab SampleGrab Sampleat theLocal Grabat theSample Point LocationSample StationSampleRadiation Monitor2 of 6August 1987Radwaste SystemWaste Collector Tank Effluent X--Demineralizer Effluent X--Filtrate Pump Effluent X--Demineralizer Effluent X--Demineralizer (Acid Influent)
-X-Demineralizer (Caustic Influent)
-X-Recovery Sample Tank Effluent X--Floor Drain Collector Tank Effluent X--Final Discharge X-XRadwaste Filter Effluent X--Regenerant Waste Tank Effluent X--Regenerant Evaporator BottomsEffluent X--Phase Separator Tank Pump Discharge
-X-Waste Evaporator Bottoms Effluent X--Waste Evaporator Distillate CoolerEffluent-X-Regenerant Evaporator DistillateCooler Effluent
-X-Radwaste Demineralizer Waste HeaderEffluent X--
RBS USARTABLE 11.5-2 (Cont)GRAB SAMPLES FOR RADIOLOGICAL ANALYSISGrab SampleGrab Sampleat theLocal Grabat theSample Point LocationSample StationSampleRadiation Monitor3 of 6August 1987Water Treating SystemCation Exchanger Unit Influent X--Cation Exchanger Unit Effluent X--Anion Exchanger Unit Influent X--Anion Exchanger Unit Effluent X--Mixed-Bed Exchanger Unit Influent X--Mixed-Bed Exchanger Unit Effluent X--Dilute Acid Effluent
-X-Dilute Caustic Effluent
-X-Wastewater Effluent
-X-Condensate Demineralizer SystemDemineralizer (Train) Influent X--Demineralizer (Train) Effluent X--Resin Hold Tank Effluent X--Demineralizers Effluent X--Ultrasonic Resin CleanerEffluent-X-Resin Mix Tank Effluent X--Cation Regeneration TankEffluent X--Anion Regeneration Tankffluent X--Recovered Acid Tank Effluent
-X-RBS USARTABLE 11.5-2 (Cont)GRAB SAMPLES FOR RADIOLOGICAL ANALYSISGrab SampleGrab Sampleat theLocal Grabat theSample Point LocationSample StationSampleRadiation Monitor4 of 6August 1987Dilute Acid Effluent
-X-Recovered Caustic TankEffluent-X-Dilute Caustic Effluent
-X-Recovered Water Sump Effluent
-X-Condensate Makeup andDrawoff System_______Condensate Transfer Line X--Makeup Water SystemDemineralizer Water Transfer Line X--Wastewater Treatment SystemWaste Neutralizing Tank Effluent
-X-Condensate SystemCondensate Pump Discharge X--Condenser Hotwell
---Heater Drains (Third Point)
X--Reactor Feedwater SystemFeedwater (After Last Heater)
X--Circulating Water SystemEffluent (Blowdown Line)
-X XAuxiliary Steam SystemAuxiliary Boiler (Steam Outlet)
X--Feedwater (Pump Discharge)
X--
RBS USARTABLE 11.5-2 (Cont)GRAB SAMPLES FOR RADIOLOGICAL ANALYSISGrab SampleGrab Sampleat theLocal Grabat theSample Point LocationSample StationSampleRadiation Monitor5 of 6August 1987Auxiliary Boiler (Blowdown)
-X-Sealing Steam SystemSealing Steam Evaporator X--Radwaste Steam SupplyRadwaste Steam Reboiler(Radwaste Auxiliary Steam)
X--Reactor Plant Ventilation SystemReactor Bldg. AnnulusVentilation Exhaust
--XMain Plant Exhaust Duct
--XContainment Atmosphere
--XContainment Purge Exhaust
--XDrywell Ventilation SystemDrywell Atmosphere
--XStandby Gas Treatment SystemStandby Gas Treatment SystemEffluent--XAuxiliary BuildingVentilation SystemAuxiliary Bldg. Ventilation Exhaust
--XFuel Building Ventilation SystemFuel Bldg. Ventilation Exhaust
--X RBS USAR TABLE 11.5-2 (Cont)
GRAB SAMPLES FOR RADIOLOGICAL ANALYSIS Grab Sample Grab Sample at the Local Grab at the Sample Point Location Sample Station Sample Radiation Monitor Revision 16 6 of 6 March 2003 Control Building Ventilation System Main Control Room Intakes - - X Radwaste Building
Ventilation System Radwaste Bldg Ventilation Exhaust - - X Turbine Building
Ventilation System Turbine Bldg. Ventilation Exhaust - - X 16 Mechanical Vacuum Pump Discharge - - - 16Condensate Demineralizer and Off Gas Building Ventilation Exhaust - - X Off Gas Pre-treatment - - X Off Gas Post-treatment - - X 12 Turbine Gland Seal Discharge - - - 12