ML18018A457

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Forwards Source Term Evaluation for Vol Reduction Sys
ML18018A457
Person / Time
Site: Harris  Duke Energy icon.png
Issue date: 02/24/1983
From: ZIMMERMAN S R
CAROLINA POWER & LIGHT CO.
To: DENTON H R
Office of Nuclear Reactor Regulation
References
LAP-83-35, NUDOCS 8303070166
Download: ML18018A457 (15)


Text

REGULIA I'0 Y I VFOR'>>IA I ION O'LSTRI BUT IO>>V<Y STEM (RIDS)ACCESSIOV NBR: 8303070)66, ODCI.OA'TE.:

8'3/02/24.VOT~RIZEO':

NO FACILI:50,400 Shear on Ha'r r i s Vuc1 ear Power P>>lento Jni t 1 r Cat'ol jna.50 401 Shearoni terri sVuc I ear Power Pil ant i U'ni t 2i C'ar olrina Au TH.NARK;AUTHOR AFF a LrI A T ION ZIHHER4IAN

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Dear Mr.Denton:

Carolina Power&Light Company (CP&L)hereby transmits one original and forty copies of the following text, tables, and figure: 1.Source Term Evaluation for the Volume Reduction System (VRS)2.Block Flow Diagram of the Volume Reduction System (VRS)3., Table 1, Filter Sludge Activity Calculations (Normal)4.Table 2, Filter Sludge Activity Calculations (Design)5.Table 3, Feed Streams to the Volume Reduction System 6.Table 4, Annual Release of Radionuclides to the Environment Only item five of the above has been revised since its previous transmittal.

Item six has been included to quantify the negligible impact of the VRS operation towards release of radionuclides to the environment.

Items one and two were transmitted by our letter of February ll, 1983 (LAP-83-18).

Items three and four were transmitted by our letter of February 2, 1983 (LAP-83-04).The re-transmittal of this information was requested by your Mr.Prasad Kadambi.Please contact my staff if you have any questions.

Yours very truly, SRZ/kj r (6232JDK)S.immerman Manager Licensing&Permits Mr.Wells Eddleman Dr.Phyllis Lotchin Ms.Patricia T.Newman Mr.John D.Runkle Dr.Richard D.Wilson Mr.G.0.Bright (ASLB)Dr.J.H.Carpenter (ASLB)Mr.J.L.Kelley (ABLB)cc: Mr.N.Prasad Kadambi (NRC)Mr.G.F.Maxwell (NRC-SHNPP)

Mr.J.P.O'Reilly (NRO-RII)Mr.Travis Payne (KUDZU)Mr.Daniel F.Read (CHANGE/ELP)

Chapel Hill Public Library Wake County Public Library~8303070lbb 830224 PDR ADOCK 05000400 I II'"A---PDR 411 Fayetteville Street o P.0.Box 1551 o Raleigh, N.C.27602 p~g k'3')'fit't&I I IP k L tl P I 1 4'

.SOURCE TEL1"EUALUATION FOR THE VOLPiIE REDUCTION SYSTEM (VRS)Figure 1 presents a simplified block fl d The system will receive radioactive wast ow an mass balance of the VRS.c ive wastes from the following sources: 1.Backwash from flushable filters on 1 d on a,qui waste process streams 2.Waste evaporator bottoms 3.RO concentrate evaporator bottoms 4.Secondary waste evaporator bottoms 5.Bo Boron recovery system evaporator bottoms Tables 1 and 2 r espectively, present the normal and desi n basis activities of the particulate and dissolved r y i ter ac wash.The radionuclide content and volumes of the remaining sources are provided in FSAR Tables'1.4;1-3.

throu h 11.4.1-3.These sources of li u a es'1.4;1-3.

through o iquid waste are hatched and processed Table 3 presents the annual average and desi n to the VRS.Thou h age an esign basis radionuclide input oug some particulate radioactivity will be tra p the prefilter, it is assumed tha i e trapped on assumed that all radioactivity enters the VRS.e eed material is preconcentrated throu h a ve'preconcentrator b f b roug a venturi scrubber and a o e ore eing sent to the fluid bed dr er i.e Water vapor exiting the preconcentrator is Drain System.Non-condensed gases from the o the Floor owever, a small portion mav be exhausted, e ollowing sections'present an evaluation o radionuclides which may be event ll d h these sources.eventua y ischar ed event h g to the environment from Source Term Analysis In order to perform the source term analysisfrom the'RS e , it was distinction between particulate and dissolved radioactivity entering the system.The radio e ra ioactivity present in p ra or ottoms is dissolved and is assumed to pass directl throu the feed tank prefilter and enter the VRS.Th the etch aisk filters res e.e filter backwash from ais i ters present a more complex situation.

A total of 17 types or" etch disk filters (see Table 1)prov'd pre'er.fil provi e input to.the Feed Tank These filters are located in process streams throughout the plant and collect p-" W 9$:~particulate material from these streams.When the pressure drop across these filters exceeds a preset value, the filters are backwashed by N2 purge to the filter backwash storage tank.The dissolved radioactivity in the backwash storage tank.The dissolved radioactivity in the backwash is the activity in the etch disk filter at the time of purge.For example, the dissolved radionuclide content of the backflush water of the spent resin sluice filter is assumed to be that of the primaiy coolant.The average dissolved'adionuclide content of the water in the filter backwash storage tank is a weighted average of the dissolved radionuclide concentration in each of the etch disk filters.The filter backwash storage tank which contains particulate and dissolved radioactivity is passed through a single 44*gallon etch disk filter which collects particulate material above 10M.The carrying water along with its dissolved solids, is passed to the waste holdup tank.After processing by the Equipment Drain System, a portion of this water may be discharged.

When the pressure across the single etch disk filter exceeds a preset value, it is backwashed to the 1000 gallon particulate concentrate tank via N2 purge.The activity entering the filter particulate concentrate tank includes the dissolved radionuclides.

The sections which follow describe the mathematical models and assumptions used to calculate these potential sources of liquid and gaseous radioactive effluent.1.Liquid Effluent It has been empirically determined by Aero)et that for feed material with a dissolved solids content above 10%by weight, the dissolved solids content (including radionuclides) in the condenser overflow will be 200 ppm.Since the weighted average dissolved solids content of the feed material is expected to be 110,000 ppm**, the dissolved radionuclide concentration in the condenser overflow will be 1.8 x 10 of that in the feed material.*Calculation of number of backwashes is based on 50 gal to account for 6 gal contained in interconnecting piping.**The PCP will ensure that the feed material is always above 10%.

With this radionuclide concentration, the condenser overflow of 4.24 x 10 Eg/yr will be routed to the Floor Drain System.This system 5 provides for treatment via a reverse osmosis unti followed by a cation demineralizer.

The following decontamination factors were assumed: Cs RO 10-Demin.10 Total 100 10 10 Others 10 10 100 It was further assumed that 90%of the processed waste is recycled and 10%is discharged to the circulating waste discharge.

Figure 1 indicates that 7.80 x 10@/yr of water is processed through the 5 etch disk filter and sent to the waste hold tank for treatment through the equipment drain treatment system.This system provides for treatment via an evaporator.

The following decontamination factors for the evaporator were assumed: Cs Evap.'10 I 10 Others 104'After'processing,'t is assumed chat 10%is discharged.

2.-.Gaseous Effluent As indicated in Figure 1, about 2.4(4)Fg/yr of water vapor will come off the condenser and be recycled to the dryer.Th'is represents 4%of'he feed material.A small portion of the recycled gas will be routed to the VRS air cleaning unit prior to processing through the HEPA and charcoal filter before discharge.

Radionuclides releases can be obtained by applying the following decontamination factors: Iodines-A DF of 100 was applied between the feed material to the VRS and the input to the VRS air cleaning unit.-A DF of 10 was applied between the input to the VRS air 4 cleaning, unit and discharge to the environment at.the plant stack.Others-A DF of 10 was applied between the feed material to the 4 VRS and the input to the VRS air cleaning unit.-A DF of 10 was applied between the input to the VRS air cleaning unit and discharge to the environment at the plant stack.These relationships are based on empirical data.****Topical Report Fluid Bed Dryer Aerojet Solidification System Report No.AECC-1 February 1975.

F I(DOBE I BLOCK FLOW DIACIRAM OF VRS (2 UNIT OPERATION SA(KWASH FROM K TCH t DISK FILlERSP~(~>>TO YIA&TE'n IIOLDT)P TANII~FOR PROCESSINCI TO SOLIDS PACKAGING FII.TER Q>>BACKTIASH JTORA6K TANK 2000 C>AI E.TCH DISK FILTE.IC/,9+ClAL F ILTK RPART ICUL A T 8 CONCKNTRATK ri.IOOO Catha VIASTE EVAPORATOR BOTTOMS R/o COIICEIITRATE.

EVAPORATOR BOT TO 7.47 4)KQTR 9.C I (3)K/V R 1L9(h K/Wa FEED TANK'AE-F ILTER: L.ISO'VRS FEED$TANK~000 GAL Q TANKS)/$32 IS)K6/TR VENTIIRI SCRUBBER.CHAS/SOLID SEPARATOR scRUBBER PRE(ONCEHTRATE FLUID BED DR'f Eg CKAS HEATER OYEILFLOW TO FI,OOR DRAIN TREATIhENT S'fSTEIA (I.ISfh)e,/

I COIIDENSE'TO PLANT I STACK/II(PA/

CHARCOAL HE PhJ CHARCOAL FILTERS SEC WASTE.EVAPORATOR BOTTOMS I3RS EVAPORATOR SOT TOMS 3I K VR 3 I h K TO SOLIDS PACKACIINCI

'.S I<)CCTg/ICII.('ll)PEIIOTES I0 QP TANK IIAS SAMPLING CAPABII ILI TY hgZ D*n~Z AtthOZID htV I C.DATC T>>Z APFhOVID CA Q~lY 2.1.T5 1 55 KOA8CO SKRVICK8 INCORPORATKO AtPAOZK>>~CAKE CN>>AT>>IT.30 8 2 G R-CI/Io IT.CAROLWR POWQ.IL II LICTH T 5IIEqR~HARR>S H P P BLOCk FLOW DWCTRAM OF VRS Fic>uf FILTER SLUDGE ACTI VITT CAISULATIONS (NQRIIAL)TABI.E I tilter 8ystea 1-131 tarticulat

~Activity uCI/cc~1-l3 Co-36 C-60 Ca-336 Cr-333 1-131 Dissolved Activity uCI/cc 1>>133 Co-58 Co-60 Cs-134 NBA j of Cs-137~Lf III~ILCS Spent Resin Sluice tilter 1.26(0)2.06(-l)6.53(-I)2.7S(-l)1.83(0)1.49(0)2 86(I)F 18(-l)1.68(-2)2.10(-3)'.63(-2)1.90(-2)3.179(7)tuel tool Skissacr Filter Refueling Mater tilter Masts Evaporator Condensata Filter Seal Mater Retllrn tilter Seal Mater In]ection tilter Recycle Evaporator 1.14(2)I'eed Filter Recycl~Evaporator 3.86(-4)Condenaats Filter 6.58(-5)2.16(1)2.74 (0)6.99(0)8.90(-l)1.33(-2)2.35(-3)2.60(2)3.40(1)1.90(2)2.54(I)5.80(-2)2.86(-l)4.18(-l)1.68(-2)2.10(-3)2.63(-2)1.90(-2)4.533(6)2.86(-2)4.18(-2)1.68(-3)2.10(-4)2.63(-3)1,90(-3)1.276(6)1.059(6)'.90(-5) 2.70(-5)1.10(-6)1.40(-1)1.10(-6)1.20(-6)9.536(7)1.90(-5)2.70(-5)1.10(-6)1.460 (-7)I.70(-6)1.20(-6)1.590(8)6.73(-5)3.29(-7)1.34(-6)2.08(-7)2.57(-6)4.92(-7)1.059(6)2.86 (-I)4.18(-1)1.68(-2)2.10(-3)2.63(-2)1.90(-2)6.352(6)Recycle Evaporator 8~48(Q)Concentrate filter 3.02(0)9 68(-I)7~IO(-I)6.62(-I)6 61(-I)6.39(-2)4.68(-2)7.953(6)boric Acid Fll tar 2,55(0)I~81(Q)Caa Decay Tarl6 Filter 3.08(-I)3.41(-I)6.62(-I)6.61(-1)3.99(-I)6.39(-2)4.68(-2)6.357(1)1.953(6)Reactor Coolan t Pl I ter 6.71(1)8.40(0)2.86(-I)4.18(-I)1.68(-2)2.10(-3)2.63(-2)1.90(-2)6.357(7)Fuel Pool Filter 2.45(-l)Secondary Mas:e Filter I 43(-7)I.14(-4)I.79(-l)1.46 3(-S)1.27(-2)" 99(3)1,9Q(5)2.70(-5)1610(-6)1.40(-7)1670(-6)1.20(-6)2.43(-6)3.I8(-6)1.42(-1)I~77(-8)2~23(-7)I 61(7)1.574(8)6.357(7)Masts Evapotnt or Filter Iw63nllry 4 llot Shover Filter 4.03(l)9.32(0)9.46(-3)2.19(-2)9.I 7(-7)6.30(-6)1.45(-5)2~IO(-5)3 86(-6)6.73(-2)1.08(-2)1.34(-2)2.08(-3)2.57(-2)1.90(-2)1.059(7)3.179(7)tloor Drain Filter I~59(0)2.20(-I)8.97(-3)I~66(-3)1.06(-3)I 46(-4)I~82(-3)I~33(-3)1.589(8)

FILTER SlUDGE ACTIVITY CAI.CllIATIPKS (DES IGK)TABI.E 2 Filter Systea I-131 Particulate Activity uCf/cc 1-133 Co<<58 Co-60 Cs-134 Dissolved Activity uCL/cc Cs-137 1-131 1-133 Co-58 Co-60 Ce-134 Haas of C-137~Ll 1~l Spent Resin Slufcs 1.26(1)tilter~"{0)3.54{-1)1.49{-1)7.79(0)6-33(p)2.90(p)4.30(p)1.5(2)I 9p(3)2 30(0)I 50(0)Fuel Fool Skfieaar Flit ar Refueling Mat t r Filter Mast~Evaporator.

Conden~ate Pfltet'eal Mater Return Filter Seal Water In]action Filter Recycle Evaporator Peed Pflter 1.16(-1)2.01(1)2.45(0)6.53(0)7.95 (-I)I.18(-2)2.13(-3)2.32(Z)3.07(l)L.70(2)2.30(L)5.07(0)1.90(-4)2.80(-4)1.00(-6)1.30(-6)I Sp(4)1.00(-3)9.536(7)L.90("4)2.80(-4)1.00(-6)I~30(-6)L.SO("4)L.OP(-3)1.590(8)6.82(-4)1.11(-4)I~19(-6)1.88(-7)2'5(-4)I 50(-4)1.059(6)2.90(0)4.30(0)1.50(-2)1.90(-3)2.30(0)1.50(0)6.352(6)2.90(0)4.30(0)1.50(-2)1.90(-3)2.30(0)L.50(0)4.533(6)2.90(-I)4.30(-I)1.50(-3)1.90(-4)2.30(-1)1.50(-l)L.276(6)'ecycle Evaporator 3.91(-3)6,78{-4)Condensata Pfltar Recycle Evaporator 8,58(I)Concentrate Ff ltsr 3.10(1)boric Acid Pil ter 2.SB(1)2.03(1)'Caa Decay Tank Filter 8.48(1)5.62(I)6.70(0)6.80(0)2,69(L)2'9(L)6'0(0)6.80{0)3.48(1)1.059(6)5.60(0)3.70{0)6.357(7)7.953(6)5.60(0)3.70(0)7.953(6)Reactor Coolu>t Filter 6.00(1)7.63(0)2.90(0)4.30(0)1.50(-2)1+90(-3)2.30(0)I.SO(0)6.357(7)Pusl Pool Pfltar 2.45(0)3.35(D)Secondaty Masts Filter 1.33(-Z)1.02(-4)I.A I (-3)1.29(-5)I.11(0)7.37(-1)1.90(-4)2.80(-4)1.00(-6)1.30(-6)1.50(-4)1.00(-3)1.574(8)2.47(-5)3.28(-5)1.27(-7)1.61(-8)1.9S{"5)1.27(-5)6.357{7)Mast~Evaporator Filter Laundry 4 Kot Shuuer Filter Floor Drain F liter 3.64(1)8.44(0)2.47(-2)5.65(-2)1.42(0)2.00(-I)6.82(-1)2.39(-6)1.I I (-I)1.19 (-2)1.88(-3)2.25(0)L.50(0)1.059(7)3.179(7)9.09(-2)1.71(-2)9.44 (-4)1.32 (-4)1.59(-I)1.71(-2)1.589(8)1.65("5)3.78(-5)5.48(-5)1.01(-4)

TABLE 3 FEED STREAMS TO THE VOLUME REDUCTION SYSTEM (2 UNIT OPERATION)

Mass (Kg/yr)Filter BkWash 7.47 (+4)Waste Evap 9.67(+3)RO Evap 7.29(+4)SW Evap 3.18(+5)BRS Evap 5.81(+4)Radionuclide (Ci/yr)Co-58 Co-60 I-131 I-133 Cs-134 Cs-137 13.0 (4)1.41(3)3.16(2)1.54(2)7.89(1}7.10(1)NORMAL OP ERAT ION 9.67 (-1)1.51(-1)4.87(+1)7.80(+0)l.87 (+1)1.37 (+1)5.24 (-1)7.95 (-2)4.33(+1)6.70(+0)9.12(+0)6.76(+0)6.64(-1).8.33(-2)1.09(+1)1.14(+1)1.05(+0)7.53(-1)0.0 0.0 3.89(+1)-3.95(+1)3.25(+1)2.15(+1)Co-58 Co-60 I-131 I-133 Cs-134 Cs-137 9.64(3)1.27(3)3.18(3}2.21(3}3.15(3)2.51(3)DESIGN BASIS 8.64 (-1)1.36 (-1)4.94(+2)8.02(+1)1.63(+3)1.08(+3)4.73(-1)8.54 (-2)4.39 (+2)6.92(+1)7.88(+2)5.18(+2)1.19 (+0)1.51 (-1)2.21(+2)2.35(+2)1.83(+2)1.19(+2)0.0 0.0 3.89(+2)3.95(+2)3.25(+2)2.15(+2)

TABLE 4 ANNUAL RELEASE OF RADIONUCLIDES TO THE ENVIRONHENT (Ci/yr per Unit)LI UID RELEASES NUCLIDE DESIGN BASISA'ODAL OPERATION+

FSAR TABLE 11.2.3-1 Co-58 Co-60 I-131 I-133 Cs-134 Cs-137 1.87 (-6)2.66(-7)1.16(-2)6.25(-3)3.34(-3)1.42(-3)1.75(-6)2.30(-7)1.07(-3)5.35(-4)4.45(-5)3.10(-5)2.3(-3)5.9(-4)1.8 (-1)2.5 (-2)4.6 (-3)3.9(-3)*Releases due to operation of the VRS.

TABLE 4 (cont'd)GASEOUS RELEASES NUCLIDE DESIGN BASISA NORMAL OPERATI0%FSAR TABLE 11.3.3-1 Co-58 Co-60 I-131 I-133 Cs-134 Cs-137 1.30 (-8)1.85 (-9)8.10(-4)4.34 (-4)2.32(-5)9.85(-6)1.20(-8)1.60(-9)7.45(-5)3.70(-5)3.10(-7)2.15(-7)1.6 (-2)7.6 (-3)4.6 (-2)6.0 (-2)4.9 (-3)8.2 (-3)Peleases due to operation of the VRS.

4.-4%I