ML20008D785

Chapter 11 to Midland 1 & 2 PSAR, Radwastes. Includes Revisions 1-36

ML20008D785
Person / Time
Site:	Midland
Issue date:	01/13/1969
From:	CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
References
NUDOCS 8007300694
Download: ML20008D785 (14)

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i TABLE OF COICENTS Section Page 11 RADI0 ACTIVE WASTES 11-1 i f 11.1 DESIGN BASES 11-1 11.1.1 ?ERF0P24AFFE OBJECTIVES 11-1 j 11.1.2 RADI0 ACTIVE WASTE QUARTITIES 11-1 l 11.1 3 WASTE ACTIVITY 11-1

, ll.1.L MEDIODS OF DISPOSAL 11-6

, 11.2 SYSTD4 DESCRIPTION AND OPERATION u-6 1

11.2.1 LIQUID WASTES 4

f 11-6 11.2.2 GASEOUS WASTES 11-7 j 11.2 3 SOLID WASTES u-8 11 3 DESIGN EVALUATION u-8 11.h TEST AND INSPECTIONS n-8 u.5 Pa uEnCES u-8 i

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Table Uc. Title Page 11-1 Padicactive Waste R2antities (Fer ?s Units) 11-2 1

l 11-2 Escape Pate Coefficients for Fission Product .

Eelease 11 L I I

l 11-3 Reacter Coolant Activity 11-5 >

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11-1 Clean Liquid Radvaste Syste= (High Tritiu=) Block Dia s u:

i 11-2 Miscellaneous Liquid Radvaste System (Lov Tritiu=)  :

and Waste Gas System Block Diagra= l 11-3 Flow Diagram Waste Gas System l i

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s11-111 Amendment No. 21 00M? l

11 RADIOACTIVE WASTES 11.1 DESIGN BASES 11.1.1 PERFOP.v.ANCE OBJECTIVES The liquid radioactive vaste treatment system is designed to collect, process and reuse all the liquid vaste, except for laundry vaste, generated during normal operation of the plant. This concept is essentially the same as that to be installed in the Palisades Nuclear Plant.

The gaseous vaste treatment syste= is designed to per=it holdup of the radioactive gases for at least 30 days during nor=al plant operation to permit the removal of the relatively short-lived radioactive gases by radioacti ' decay. After holdup, the gases vill be monitored and exhausted throu6h the stack.

The solid radioactive vastes produced in the plant vill be packaged and 1

shipped of f-site for disposal.

The systems are, for the most part, shared by the two nuclear units; however, it includes so=e equirent in duplicate which is not shared.

11.1.2 RADIOACTIVE WASTE QUANTITIES The estimated volumes of radioactive vastes generated from both units during normal plant geration are listed in Table 11-1.

O 11.1 3 WASTE ACTIVITY Activity accumulation in the reactor coolant system and associa:ed vaste handling equipment has been determined on the bases of fission product leakage through clad defects in one percent of the fuel. The activity level was calculated for an ugtimate reactor core power of 2,552 MWt and a coolant volume of 11,800 ft . One percent of the fuel was assumed to fail at the beginning of the third cycle with the fuel leaking fission products for the full 310 days,respectively, with no defective fuel during the first two cycles. An average of 67 percent of the power was assumed to be produced by fission of U-235 and 33 percent by Pu-239 during the operating period.

Fission products are removed from the coolant only by decay, the purification system, and bleed.

Continuous reactor coolant purification at a rate of one reactor syste=

volume per day was used with no re= oval for tritiu=, Er, Xe, Cs , Mo and Y, and a 99 percent re= oval efficiency for all other nuclides. All levels are relatively insensitive to s=all changes in de=ineralizer efficiencies, '

eg, use of 90 percent instead of 99 percent would result in only about a 10 percent increase in the coolant activity.

The coolant bleed for boron removal is processed through radvaste decineral-izers and, therefore, removal efficiencies consistent with the above have been assumed except that a removal efficiency of 99 percent for Cs , Mo, Y, and essentially 100 percent for the gases has been assumed.

11-1 Amendment No. 20 000 q

_- -- - . _ - . .._._-, -- - . = _ _ -- _.. = . . - _ __

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The quantity of fission products released to the reactor coolant during .

g steady-state operation is based on the use of " escape rate coefficients" (see"*)

as deter =ined fro: experi=ents involving purposely defected fuel ele =ents.

See Reference 1 L. Values of the escape rate coefficients used in the cal- [

culations are sh en in Tabic 11-2.

The calculation of the activity reletsed fro: the fuel was perfor=ed with a i digital co=puter code which solves the differential equatien for a five-= ember radioactive chain for buildup in the fuel, release to the coolant, re= oval fro: the coolant by purification and leakage, and collection en a resin or in a holdup tank. The activity levels in the reacter coolant fer a nuclear unit containing one percent d2fective fuel during full (ulti=ata) power operation at thr. end of the third core cycle are shown in Table 11-3.

Reactor coolant bleed is taken fro: the downstrea= side of the purification de=ineralizers. It is assu=ed to have the sa=e activity concentration as the reactor coolant reduced by the deconta=1 nation facter of the purification de=ineralizers.

Gaseous activity is generated by the evolution of radicactive gases frc= the liquids as they are prccersed through the degassifiers and to a lesser extent as they are stored in teaks throughcut the plant. i.he degassifiers and these tanks are vented to tr gaseous radvaste syste=. The activity of the gases

is dependent on the liquid activity.

.s Table 11-1 Radioactive Waste Quantities (Both Units) '

Waste Source Quantity ver year Assunctions and Co==ents Liquid Waste Reacter Coolant Syste:

Start-up Expansic 192,000 gal L cold start-ups (each unit)

Start-up Dilution 298,000 gal 2 cold start-ups at begin-j ning of life, and 1 cold start-up (each unit) at 100 and 200 full (ulti= ate) power days, respectively lL7,000 gal 2 hot start-ups (each unit) at peak xenon at 100 and 200 full power days, respectively Shi= Sleed (1 Cycle) 53L,000 gal Dilution frc= 1,150 to 17 pp=

Syste= Drain (Refueling) 61,k00 gal Drain to level of outlet I

no::les Syste: Drain (Maintenance) Sk,000 gal Drain 1 stem: generator per 4

.G uni.o 11-2 A=end=ent No. 20

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N Table 11-1 (Contd)

Waste Source Quantity ner year Assu=stions and Co==ents Sa=pling and Laboratory L5,000 gal 2k ss=ples per week at 5 gal Drains per sample Demineralizer Sluice 6,000 gal 2 ft 3f fg 3 resin Area Washdowns 220,000 gal 5 gp: hose, 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> per day Miscellaneous Syste Leakage 90,000 gal 10 gph leakage Showers and Laundry 155,000 gal 10 shcvers per day at 30 gal per shower. 120 gpd laundry

Gaseous Waste l Off-Gas from Reactor Cociant 7,650 ft 3 Degas at k0 ccH 2 P'# 1it'#

Syste= concentration C -Gas fro = Liquid Sa=pling 2h0 ft 3 Degas at ko ecH 2 P'# 'it*#

concentration Off-Gas fro Makeup Tank 1,800 ft 3 Vent once per year f

Q Off-Gas fro = Pressurizer 120 ft 3

Vent once per year Solid Waste l

De=ineralizer Resin h00 ft 3 Resin replacement once per year Miscellaneous (Filter 1,200 ft 3 1-1/255-gagdru=perweek Ele =ents, Clothing, Rags, plus 300 ft per refueling etc.. ) period

(*) Wastes processed through surge tanks.

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'J 11-3 Amendment No. 20 00990

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i Table 11-2 Escape Rate C0effielents for Fission Prodt:et Fielease i j

Escape Rate Coefficient, Element see-1 Xe 1.0 x 10'I Tr 1.0 x 10 ~7 I

2.0 x 10' Br 2.0 x 10' Cs 2.0 x 10' Rb 2.0 x 10'9 MO h.0 x 10'9 Te k.0 x 10~9 Sr 2.0 x 10 -10 Ba 2.0 x 10 -10 Zr 1.0 x 10' Ce and Other Pare Earths 1.0 x 10' 11-L

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Reacter Coolant Activity t (Reactor Cociant Activity rcr tne T=ird Ccre Cycle, [

!, Based on 1% Defective Pael Ele =ents)  :

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4 t i (ue/=1) i Ti=e, Pall Power Days 100 400 200 coa e93 300 310 ~

4 Isotope P

l Kr 85 = 15 ------------------------ 15 i i Kr 85 9.8 97 6.3 L.5 33 2.1 1.1

{ gr 87 .8L ----------------------- - .84 l j

K: 88 27 ----------------------- -

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sr 89 .0L1 .041 .0LO .0LO .039 .038 .038 ,

sr 93 .0029 .0033 .0034 .0034 .003L .0034 .0033 sr 91 .0L6 .0L6 .0L6 .0L6 .0L6 .0L5 .0L5 sr 92 .017 ----------------------- - .017 Xe 131= 2.0 19 17 15 1.4 1.1 92 i i Xe 133= 27 27 2.6 25 2.4 23 2.1 i

Xe 133 243 238 227 211 205 17 3 15L 3

Xe 135= 94 94 9L 9L 93 92 92 Xe 135 5.6 5.6 5.6 55 55 54 53  :

1 Xe 138 51 - - - - - - - ,,- - - - - - - - . . 51 9 I113 --

34 3. e-34 32 3 1---.0 3 30 ,

i I 132 L.7 L.7 L.6 L.h L.2 39 3.6 I 133 38 38 38 38 37 36 3.6 I 13L 50 ----------------------- -

50 1

I 1 35 2.7 27 27 27 2.6 2.6 2.6 Cs 136 76 73 .66 58 51 .k2 3L ,

4 Cs 137 26 36 29 22 18 12 6.9 i Cs 138 74 ----------------------- -

7L

Mo 99 54 53 52 50 L.8 L.L L.1 ,

l 3a 139 .081 ----------------------- -

.081 l 3a 150 .065 .065 .065 .06L .063 .062 .061 ,

l La ILO .021 .021 .021 .021 .020 .020 .019  ;

i Y 90 .26 57 75 .82 .84 .85 .85 l l Y 91 .18 .19 .15 .12 .10 .072 .0L9  !

i Ce ILL .0027 .0027 .0027 .0027 .00P7 .0027 .0026 h

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11.1.h METHODS OF DISPOSAL Four =ethods are defined in the treatment of the radioactive vastes:

a. The clean liquid vastes consist of liquids such as reactor coolant and fuel pool coolant, which are relatively lov in chemical i= purities and suspended solids content. Processing consists cf vacuu: degassing, storinc, filtering, de=ineralizing and evaporating. The end products, concentrated beric acid and de=ineralized water are nor= ally stored for later reuse in the reactor cycle.

b. The dirty liquid vastes censist of liquids of largely varying types and origins such as radioactive labcratory drains, building su=ps , and deconta=ination drains. These liquids are relatively high in che=ical i= purities and suspended solids content but lov in radioactivity. Normal processing includes storage, filtration, de=inerali:ation and evaperation.

The condensate is then recycled back to the lov tritiated

=ake-up storage tank. The concentrate (boric acid and other solids) is recycled back to the beric acid addition tank or sent to the solid vaste handling facility for dr"-~4ng and off-site disposal.

c. The gaseous vastes consist of the discharges fro: all potentia.lly radioactive syste=s. Processing consists of high efficiency filtration and, if necessary, radioactive decay through high-pressure, long-tem storage. The gaseous end products are 3 discharged to the at=osphere through the plant stacks.

d. The solid vastes consist cf all potentially radioactive solid vastes such as de=ineralizer resins, spent filter ele =ents, clothing and rags. Processing consists of stora6e and packaging, as appropriate, for later off-site disposal.

11.2 SYS T DESCRIPTION AND OPERATION 11.2.1 LIQUID WASTES The radioactive liquid vaste system is shown sche =atically on Figures 11-1 and 11-2.

a. Clean Liquid Wastes. The vastes enter the radvaste syste=

through the degassifiers where they are stripped of their centent of dissolved gases. The gases exhausted by the vacuu=

pu=p are discharged into the vaste gas surge tanks. The liquid vastes extracted by the degassifier pu=p are discharged into the heldup tanks.

These tanks provide for the storage capacity required to acco==odate large a=ounts of liquid vastes released fro: the reactor syste=s during so=e shcrt-ter= cperations, such as:

reactor coolant syste= drain for maintenance, er reactor start-up fro: cold shutdown condition near h) the end of core life.

11-6 A=end=ent No. 20 009W L .- - .. . . . ..- - . - . -- -

Frc= these tanks, the clean liquid vastes are removed by the 1 holdup tank pu=pa. Two parallel inlet and outlet headers s service the tanks so that the following two processes can be acco==odated simultaneously recirculation of the contents of one tank for the purpose of thorough mixing and extrrsetien of representative samples ,

extraction of vastes contained in any other tank and feeding to the clean vaste processing facilities.

Upon leaving the holdup tanks the vastes are pu= ped through filters and mixed bed ion exchangers into monitor tanks. In this process radioactive co=ponents are re=oved whether suspended solids or diss '1ved elements. Sa=pling and recirculation through the ion exchanger can be performed as required to =onitor this process and effect further re= oval of dissolved solids. Frc=

these =onitor tanks the vastes are routed according to their boron content:

low boron vastes can be fed to the deborating ion exchanger for later reuse of the water ,

high boron vastes are fed to the evaporators whtre they are separated into their two reusable con-stituents: demineralized water and concentrated boric acid. Prior to storage these constituents can be further decontaminated by ion exchange, if necess ary.

( b. Dirty Liquid Wastes. The vastes enter the radvaste syste=

through filters. The flow from the filters is then passed through a dirty vaste evaporator where the de=ineralized water is separated off and recycled. The re=aining solids may be reusable as borie acid, and as such recycled, or they

=ay be sent to the solid radvaste processing system for dru==ing and eventual off-site disposal.

11.2.2 GASEQUS WASTES The vaste gas syste= is shovn sche =atically on Figure 11-3. Lov activity vastes are vented to the stack through an absolute filter.

Potentially high activity vastes are collected in the vaste gas surge tank vnere their activity is =enitored. Usually, their activity is lov enough that they =ay riov directly through high efficiency filters , to the stacks and be released to the atmosphere. Ecvever, the system provides for the capability of co= pressing and holdup of these gases and allows for their decay in high-pressure vaste gas decay tanks; this capability provides for the unlikely co=bination of high activity gas vastes in the plant plus adverse at=cspheric conditions which =ight prevent direct release.

Gases vill be held up for decay in the gas decay tanks as long as is practicable. A storage capacity is provided to allow at least 30-day hold-up.

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11-7 Amendment No. 20 00908

11 2.3 SOLID WASTES Two facilities are provided for processing solid vastes:

A collection piping syste= and storage tank received spent resins from the plant ion exchangers. These resins are transferred fro =

the storage tank into transportable containers for off-site disposal.

A =iscellaneous solid vaste station receives all contaminated ite=s such as spent filter ele =ents, rags, clothing, parts and =aterials.

These vastes are co=pacted into a for= suitable for off-site disposal.

The shipment and off-site disposed of all radioactive vastes is perfor=ed by AEC licensed contractors.

11.3 DESIGN EVALUATION The possibility of an accidental uncontrolled release of activity from the radvaste syste= is =inimized by reuse of all of the liquid vastes under normal operating conditions. Liquid and stored gaseous vastes art sa= pled prior to discharge to the environ =ent.

Radiation monitoring equip =ent and process flow controls auto =atically alar =

and terr.inate liquid and potentially high activity gaseous discharges to the environ =ent, if the gross activities of the respective discharge stres=s exceed values which would result in release concentrations in excess of 10 CFR 20 li=its.

V Off-site disposal of vastes is acco=plished by AEC licensed contractors.

11.h TEST AND INSPECTIONS All syste= components t.re tested prior to plant start-up. Operation of the syste= and equipment in the course of routine processing tasks de=enstrates the integrity of those portions of the system. That equitment not nor= ally operated or operated infrequently will be tested periodically.

11.5 REFEFE CES Frank, P. W. , et al, Radiochemistry of Third PWR Fuel Material Test -

I-X-1 Loop NRX Reactor, WAPD "Ji-29, F ebruary 1957.

Eichenberg, J. D. , et al, Effects of Irradiation on Eulk UO , W2 PD-183 October 1957 (3)Allison, G. M. and Robertson, R. F. S. , The Behavior of Fission Products in Pressurized-Water Syste=s. A Review of Defect Tests on UO Fuel 2

Elements at Chalk River, AECL-1338, 1961.

(h)Allison, G. M. and Roe, H. K. , The Release of Fission Gases & Iodines From Defected UO Fuel Elements of Different Lengths, AECL-2206, June 1965 2

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