ML20125B905

Forwards Radwaste Section for Environ Statement

ML20125B905
Person / Time
Site:	Monticello
Issue date:	05/12/1972
From:	Benaroya V US ATOMIC ENERGY COMMISSION (AEC)
To:	Harold Denton US ATOMIC ENERGY COMMISSION (AEC)
References
NUDOCS 9212100208
Download: ML20125B905 (18)

Text

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, k GAY 12 1972 ENVIRON, FILE (NEPA)

Docket No. 50-263

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kmid R. Denton, Assistant Dimotor for Site Safety, E hrw mobert L. hasseo, Assistant Dimetor fler Costa t Safety, E RADWASTE SWf3DN 70R N STMBtMT POR MMFICEt2D REEBAR GWBATING PEANT

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. . 1. .

In neponse to your aquest, we haw yewpand and attached is this memo the Radwaste Section for Monticello Bucimar Plant. he numerical source tems were tansmitted to you infomally on April 12, 1972.

he source terms were papand by J. T. Collins fem omta supplied by ORNL. The principal assumptions used an doemented in the writeup, other assumptions an .those tunsmitted to you ty my memo of April 2k,1979. .

Tne glossy prints showing the liquid and pseous waste tmatament systems

, von transmittea to you infomally on April 28,19T2 and umy 3,1972, mapectively.

ertrinal tiemed victer s n,r y by Victor Benamya, Chief 9212100208 720512 Effluent Trektment Systems Bmnch PDR ADOCK 05000263 Dim etonte of Licensing D PDR

Attachment:

As stated above cc: F. Schroeder A. Giambusso AD's/L CS B m nch Chiefs D. h11er R.-Boyd

v. htler ~ - 4 '

O. Ehistrton u G. Ovalar *

3. Youn@3aed .

J. Eastner C. Ommertsfelder T. Bow, %)

DISTRIR7fION l S. Kari G.)

i ETS Branch

. "; ict file (5 263) f omcAL . Reading ,fil,e,,, ETS ETSB/pL,f),, ,_AD/p/pL ,

! ETiB Reading filw y1 p h,B/DL G:pv VENAROYA RT CO su m mOG Readin6 fila - i --- - - - - - - - - - - - - - - - - - - - - - - - - - - - -

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Form AIC d8)ev. 9-53) AECM 0240 . r u s noviewt %t m% w, ona t .7 5 4 e 4e .

pf UNITED STATES  ;

- i' /U ATOMIC ENERGY COMMISSION

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WASHINGTON. D C. 20545 6# May 12, 1972 ,

Docket No. 50-263

Harold R. Danton, Assictant Director for q afety, DL Thru

Robert L. Todesco, Assistant Dirqnor for Containment Safety, DL P

RAWASTE SECTION FOR ENIRON!NIAL SWmE' FOR MONTICELLO NUCLEAR 3

GENERATING PLANT {

J In responce to your request, we have prepared and attached to this memo 4 the Radwaste Section for Monticello Nuclear Plant. The numerical source

' terms vere transmitted to you inforrally on April 12, 1972.

t The source terms were prepared by J. T. Collins from data supplied by ORNL. The principal assumptions used are documented in the writeup, other assumptions are those transmitted to you by my memo of April 24, 1972.

The glossy prints showing the liquid and gaseous vaste treatment systems

. vere transmitted to you infornally on April 28, 1972 and May 3, 1972, respectively.

( ---

Victor Benaroya, Chief Effluent Treatment Systems Branch

, Directorate of Licensin6

Attachment:

! As stated above cc: F. Schroeder

A. Giambusso AD's/L CS Branch Chiefs D. Muller R. Boyd W. Butler G. Kni6hton G. Ovsley B. Youngblood J. Kastner C. Gamertsfelder T. Rov,(HIL)

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WASTE TREATMENT SECTION FOR ENVIRONMENTAL STATDIENT MONTICELLO NUCLEAR PLANT

2. Radioactive Wastes During the operation of the Monticello Nuclear Generating Plant,

. radioactive material will be produced by fission and by neutron

) activation reactions in metals and other materials in the reactor i system. Small amounts of gaseous and liquid radioactive wastes will enter the wastes streams, which are monitored and processed within the plant to minimin the amount of-radioactive nuclides

, that will ultimately be released to the atmosphere and to the Mississippi River. The radioactivity that may be released during operation of the plant will be in accordance with the Commission's

regulations, as set forth in 10 CFR Part 20 and 10 CFR Part 50, 4

The vaste handling and treatment systems installed at'the plant

, are discussed in the Final Safety Analysis Report of October 17, 3 1968, and in the applicant's Environmental Report dated November 5,

. 1971. The waste treatment systems described in these reports and

, in the fellowing paragraphs are designed to collect and process- .

the gaseous, liquid and solid waste which may contain radioactive materials,

a. Caseous Wastes-During power operation of the plant, radioactive materials that may be released to the atmosphere in gaseous effluents include fission-product noble gases (krypton and xenon) and halogens (mostly iodine); activated argon, oxygen and nitrogen; tritium contained in water vapor; and particulate material-including both fission products and activated corrosion products. Fission products are released to the primary coolant and carried to the turbine by

, the steam.

i The major source of gaseous radioactive waste during normal plant operation will be the offgas from the main steam condenser air ejectors. In the present system, offgases from the main condenser consist of approximately 200 cfm of hydrogen and oxygen from de-composition of water and 20 cfm of air from inleakage plus trace concentrations of radioactive xenon and krypton. The noncondensible gases are delayed for a minimum of thirty minutes in a holdup pipe to allow for the decay of short-lived fission product noble gases and activation gases, filtered through high efficiency particulate filters, and released to the atmosphere through the main stack with l dilution air. The radioactive materials released through this system represent greater than 90% of the activity available from gaseous

effluents. In our evaluation we assumed that 90% of the radio-l iodine which may be present in the offgas from the air ejectors will be removed in the steam jet condenser.

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Other sources of gaseous waste include the main steam turbine gland seal system; offgases from the mechanical vacuum pump used during startup; ventilation air released from the radwaste, reactor and j l turbine building exhaust systems; and purging of the drywell and ,

l suppression chamber. The systems for the processing of radioactive l gaseous waste and ventilation paths are shown schematically in J

-Figure III-5.

The turbine gland seal system which provides a seal on the turbine l packing gland is being operated with primary steam and therefore

, expected to be a contributing source of airborne activity. The steam air exhaust from this system passes through a gland seal con-denser where the steam is condensed and non-condensibles exhausted i to the gland seal holdup line. Radioactive gases' released by way of this system are delayed for about 2 minutes to allow decay of the major activation gases (N-16 and 0-19) and released without additional treatment through the 328 ft stack. The mechanical i vacuum pump, used during startup, exhausts air and radioactive gases 2

f rom the main steam condenser. Offgases from this system are dis-charged to the gland seal holdup line before being released to the main stack. In our evaluation we assumed that the mechanical vacuum pump will be operated approximately 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> per year with an estimated release of 1040 curies of noble gases. The isotopic i mixture will vary depending on the decay time in the condenser, The turbine building, reactor building and radwaste building ventilation systems are once-through ventilation with air passing

. from relatively clean areas to those with higher radioactivity

potential. Normally the ventilation air in the reactor building is discharged to the building vent without treatment; however, in the event of abnormal air activity levels, this air will be routed through the standby gas treatment system (HEPA and charcoal

adsorbers in series) prior to being released through the main stack.

i Potentially contaminated areas of the radwaste building are exhausted through prefilters and HEPA filters and released through the plant vent.-

Release of radioactivity from the upper area of the turbine building through a roof mounted exhaust fan-is not' anticipated. The-purpose of this system is to maintain desired ambient conditions 4 above the operating floor utilizing once-through ventilation. -The ventilation air;from equipment areas and lower levels of_the turbine building is. exhausted to the main plenum and released through the '

plant vent without treatment.

The primary containment (drywell) is normally a scaled volume. How-ever, during periods of refueling or maintenance it may be necessary i

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to purge the drywell and suppression chamber and, when this i occurs, the potential exists for the release of airborne radio-activity to the environment. The. system is arranged such that the purge exhaust can be directed to the standby gas treatment systea in the event of abnormal air activity levels. Releases through this system are not expected to be a contributing source of radio-activity. ,

d Estimated annual releases of radioactive materials in gaseous j effluent from the plant during normal operation, including expected a operational occurrences, are shown in Table III-1. Esticated releases from primary and secondary sources are summarized in Table III-2. The estimated releases were based on a minimum hold-up time of 30 minutes for gaseous effluent released from the main 4

condenser air ejectors. Conditions and principal assumptions con-

< sidered in our evaluation of the waste treatment systems are given in Table III-3.

. During the first year of operation of the plant (March 1971) , re-leases of radioactivity have been lower than expected. From the values shown in Table III-1, a release rate of 44,000 pCi/sec is expected; however, the level of release during the startup and shakedown period at full power operation has been approximately 10,000 pCi/sec as shown in Table III-7.

4 To reduce the quantities of radio ctive gaseous effluents released to the atmosphere, Northern States. Power Company has undertaken a plant modification to install additional holdup equipment, in the modification, expected to be completed by December 1972 (see Figure III-5); offgases f rom the main condenser will be processed through a catalytic recombiner where the hydrogen and oxygen .will be reacted to form water, thereby reducing by tenfold the volume

- of gases which must be treated. The water will be removed by the offgas condenser and moisture separator and discharged to the liquid waste system for further treatment. The noncondensible gases will be delayed for a minimum of five hours in the present holdup pipe, filtered through charcoal adsorbers and HEPA filters, com-pressed to 300 psig and stored in one of five (1250 f t 3) holdup tanks. Prior to discharge through the main stack, the offgases will again be filtered through charcoal adsorbers and HEPA filters. The system will provide at least 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> additional decay time. In our evaluation we assumed that nearly all of the radiciodine which may be present in the offgas from the main condenser will be re-moved in either the recombiner condenser or by the double treatment through the charcoal adsorbers. The calculated annual releases of gaseous vaste after the modification has been completed are shown in Table III-4. Based on our evaluation, the calculated annual

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TABLE III-1

! ESTIMATED RELEASES OF RADIOACTIVE MATERIALS IN GASEOUS EFFLUENT FROM MONTICELLO NUCLEAR GENERATING PLANT 4 CURIES PER YEAR Main Condenser Gland Seal Air Ejector Reactor Turbine 2 min. 30 Min.

Nuclide Building Building Holpp,,. Holdup Total Kr-83m ------ 15 42 35,500 35,600 Kr-85m ----- 25 70 65,000 65,170 i

Kr-85 ------ 0.1 0.4 364 365 Kr-87 ------ 75 207 160,500 160,800 Kr-88 ------ 81 226 201,300 201,600 Kr-89 - - - - - - 280 517 1,150- 1,950 Xe-131m ------ 0.1 0.3 320 320 Xe-133m ----- 1.6 4.5 4,430 4,440 Xc-133 - - - - - 44 125 124,600 124,800 Xe-135m - - - - - 129 333 96,800 97,300 Xe-135 ------ 127 357 344,200 344,700 Xe-137 ------ 484 953 5,900 7,340

.Xc-138 ------ 406 1055 336,300 337,800 Total 1670 3890 1,376,000 1,382,000 1-131 0.009 0.57 0.16 8.0 8.7 I-133 0.03 2.8 0.8 39. 42.6 l

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4 TABLE III-2 1

GASEOUS EFFLUENTS SLTIARY 1

C1/yr Present System Noble Gas I-131 Main Condenser Air Ejector 1.38 x 10 6 8.0

-1 Turbine Building 1.67 x 10 3 5.7 x 10 Reactor Building --- 9 x 10 ~3' f

Mechanical' Vacuum Pump 1.04 x 10 3

-1

. Gland Seal -

'3.89 x 10 3 1.6 x 10 1.38 x 10 6 8.77 C1/yr Augmented System Noble Ccs I-131

~3 Main Condenser Air Ejector 1.06 x 10 $ 7 x 10

~1 Turbine Building 1.67 x 10 3 5.7 x 10 Reactor Building ---

9 x 10 ~3 3

Mechanical Vacuum Pump _1.04 x 10 Gland Seal 3.89 x 10 3 -1 1.6 x 10

~1 1.12 x 10 5 7.5 x 10 e

4 TABLE III-3 CONDITIONS USED IN DETERMINING RELEASES OF RADI0 ACTIVITY IN EFFLUENTS FROM MONTICELLO NUCLEAR GENERATING FLA'iT Thermal Fower 1670 Megawatts Total Steam Flow - 6,770,000 lb/hr Plant Factor 0.8 Cicanup Demineralizer Flow -

80,000 lb/hr 3

Failed Fuel equivalent to 100,000 pCi/sec with 30 min. holdup

~

Leaks Reactor Bldg. 480 lb/hr - liquid Turbine Bldg. 2,400 lb/hr - steam Condenser Air Inicakage 20 cfm - air Turbine Gland Seal Steam 0.1% of steam flow

. Dartition Coefficients (Iodine)

Steam / Liquid in reactor 0.012 Reactor Bldg. liquid leak 0.001 Turbine Bldg. seam leak 1.0-Gland Seal 0.1 Air Ejector 0.005 Holdup Times Gland Seal Gas 2 minutes Air Ejector Gas 30 minutes

, Modified System 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> Clean Waste System - liquids 1 day Dirty Waste System - liquids 1 day Chemical Was te Sys tem - liquids 1 day.

Flow Rate Clean Waste Sys tem 21,000 gpd Dirty Waste System 8,200 gpd Chemical Waste 500 gpd Decontamination Factors Fewder filter /demineralizers 10 (except Y, Mo and 3) H Mixed bed demineralizer 100 except: Cs and Rb 10 Y, Mo and 3H 1-Removal factors to account for plateout Mo and Tc - 99m 100 Y 10 Dilution Flow 280,000 g7m 1

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i TABLE III-3 (cont'd) i Number and Capacity of Collector Tanks No. Name Capacity (gals.)

1 1 Waste Surge Tank 35,000 2 Waste Sample Tanks 10,000 each 1 Condensate Backwash Receiving Tank 8,500 1 Waste Collector Tank 10,000 1

1 2 Condensate Phase I

Separator Tanks 12,000 each 2 Condensate Storage Tank 220,000 each ,

1 Waste Sludge Tank '7,500 2 Clean-up Phase Separator Tanks 3,000 each 2 Laundry Drain Tanks 1,000 each 4

1 Floor Drain Collector Tank 10,000 i 1 Floor Drain Sacple Tank 10,000 i 1 Chemical Waste Tank 4,000 4

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TABLE III-4 CALCULATED CURIE RELEASES OF RADIOACTIVE MATERIALS IN GASEOUS EFFLUENT FROM MONTICELLO NUCLEAR GENERATING PLAST AUGMENTED SYSTEM *

. Main Condenser

! Gland Seal Air Ejector Turbine 2 Min. 50 Er.

Reactor Nuclide Building Building Holdup Holdup Total Kr-83m ------ 15 42 ------

57 Kr-85m ------ 25 70 27 120 i Kr-85 - - - - - 0.1 0.4 364 365

Kr-87 ------ 75 207 ------ 282 I

Kr-88 ------ 81 226 0.9 308

. Kr-89 ------ 280 517 ------

798 Xe-131m ------

0.1 0.3 280 280 Xe-133m - - - - - 1.6 4.5 2,360 2,366 ,

Xe-133 ------ 44 125 95,000 95,170

Xe-135m ------ 129 333 ------ 460 Xe-135 ------ 127 357 8,300 8,790 Xe-137 - ---- 484 953 ------ 1,440 j Xe-138 ------ 405 1,005 ------ 1,460 Total 1,670 3,890 106,340 111,900 i I-131 0.009 0.57 0.16- .007_1 0.75 I-133 0.03 2.8 0.8 .007 3.64 i

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• To be installed by the end of calendar year 1972.

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release rate of 44,000 pCi/sec of noble gases from the 30-minute j holdup pipe will be reduced to about 3600 pCi/sce after the modification which consists of a 50-hour holdup. The total lodine and particulate releases have been calculated at about 0.75 curie per year as I-131.

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b. Liquid Waste i

i Radioactive and potentially radioactive liquid wastes are. collected, monitored, processed, stored and prepared for disposal by the rad-waste treatment system. These wastes are classified, collected and

, treated as high purity, low purity, chemical, laundry and sludge or concentrated wastes. The system is designed to handle these wastes separately or on a combined basis. Cross connections between the j subsystems provide flexibility- for processing by alternate methods.

High purity wastes (low-conductivity) consist of liquids collected by equipment drains from the drywell and the reactor turbine and e

radwaste buildings and the decantate from the centrifugation of backwashed resins and sludges. Low-purity wastes (high conductivity) are collected by floor drains from the drywell and the reactor tur-

, bine and radwaste buildings. Miscellaneous chemical wastes are j collected'from the laboratory and from the-laundry and decontam-ination areas.

The applicant plans to recycle water as a fundamental plant process.

) Both the condensate powdex filter and the reactor water powdex filter are designed to assure requisite purity and activity levels to permit recycling of most of the water processed by the liquid radwaste system. In addition, nearly all of the high purity and low purity, along with some porticas of the miscellaneous chemical wastes and laundry rinses, are combined, processed and reused in the reactor. The sources of liquid waste and the systems for pro-cessing these wastes are shown in Figure III-6.

To carry out this program of combined treatment, the liquids in 'he t vaste collector tank and floor drain collector tank are blended and continuously recirculated through a powdex filter and sent back to the waste collector tank with occasional input from the chemical waste co11cetor tank. These latter wastes are.normally mixed with cement to aid in solidification of sludges as solid wastes. The combined wastes are recycled through the filter system until the collector tank is filled, at which time the waste is processed through a fresh powdex filter and mixed-bed domineralizer and collected in one of two waste sample tanks.- The design of the system is such that one of the fuel-pool storage filter-demineralizers can be used as a backup for the radwaste filter-demineralizers. After the batch has~been sampled ar.d analyzed, g

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l' the vastes are normally returned to the condensate storage tanks for reuse in the reactor. A recycle line is provided to return off-standard water either to the waste collector or the vaste surge tanks for reprocessing. Presently, all liquid wastes generated during normal operation are being returned to the plant for reuse. In our evaluation, considering expected operational occurrences and equipment availability, we assumed that 10 percent

of the water processed through the mixed-bed domineralizer will be released from the plant each year.

. Liquid waste from the plant can only be released by one pathway, i

1.e., from the floor drain sample tanks in the radwaste treatment i system. If after sampling and analysis the radioactivity is below i a prescribed level, it will be discharged and monitored. Should the 5 liquid waste require further processing, it will be routed back to

{ the waste collector tank.

. Chemical vastes, including laundry rinses, are collected in the chemical waste tank where they are sampled and analyzed. If found suitable for combining with the lower conductivity wastes, they are sent.to the floor drain collector tank for further processing. The chemical wastes and filtered laundry wastes, which would require

too much processing to render the water suitable for eventual-rcuse

- as coolant, are used as a wetting agent for the cement in the solid

! waste packaging. system. For purposes of this analysis, it was assumed that 10 percent of the chemical and laundry wastes are released after filtration through a precoated filter unit to the discharge canal.

, Phase separator tanks receive sludges and spent resins from the reactor cleanup system and the condensate demineralizer system.

The backwash liquid decantate is returned to the waste collector.

tank and recovered for reuse. The waste filter sludge, the fuel

pool filter /demineralizer sludge, and the floor drain filter sludge are collected in the waste sludge tank and eventually dewatered and solidified with cement in 55-gallon drums.

Based on our evaluation of the liquid waste treatment, it appears that the system as installed is capable of reducing the amount of radioactivity in liquid effluents during normal operation ~ to well vithin the limits specified in 10 CFR Part 20. This is particularly true if the treatment system is operated as it presently is, through combining of waste streams coupled with continuous recirculation through filters and polishing with a mixed-bed demineralizer. Based on the first year of operation, releases have been a fraction of those values-shown in Table III-5. However, to compensate for process

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TABLE III-5 a

CALCULATED ANNUAL RELEASE OF RADIOACTIVE MATERIAL

IN LIQUID EFFLUENTS FROM MONTICELLO KUCLEAR STATION (100% Power)

Nuclides Ci/yr Nuclides Ci/yr Rb-86 0.00040 Rh-103m 0.0017 Sr-89 0.26 Rh-105 0.0018 Sr-90 0.015 Rh-106 0.00050

, Sr-91 0.17 Sn-125 0.000016 i

Y-90 0.053 Sb-125 0.0000077 i

, Y-91m 0.12 Sb-127 0.00013 Y-91 0.18 Te-125m 0.000071 Y-93 0.22 Te-127m 0.00046 Zr-95 0.0028 Te-127 0.0013 Zr-97 0.0019 Te-129m 0.0045 Nb-95 0.0025 Te-129 0.0029 Nb-97m- 0.0019 Te-131m 0.0059 Nb-97 0.0019 Te-131 0.0010 1

Mo-99 0.47 Te-132 0.060 Tc-99 0.44 I-130 0.0021 4 Ru-103 0.0017 I-131 0.36 l

Ru-106 0.00050 I-132 0.060 1

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TABLE III-5 (cont'd)-

Nuclides Ci/yr Nuclides C1/yr i 1-133 0.74 Pm-149 0.00093 I-135 0.10 Sm-153 0.00042 i

Cs-134 0.20 Na-24 0.012 Cs-136 0.076 P-32 0.000076' ,

Cs-137 0.19 Cr-51' O.017 Ba-137m 0.18 Mn-54 0.0031 Ba-140 0.43 Fe-55 0.075 La-140 0.23 Fe-59 0.024' Ce-141 0.0093 Co-58 0.17 Ce-143 0.0075 Co-60 0.017 Ce-144 0.0017 Cu-64 0.019 Pr-143 0.0029 Zn-65 0.00077 Pr-144 0.0017~ Zn-69m 0.00016 Nd-147 0.00095 W-187 0.019 Pm-147 0.00023 TOTAL N 5 C1 H-3 N 20 Ci

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equipment malfunction and downtime and expected operational occur-rcnces, the values have been normalized to 5 curies. The calculated releases of tritium shown in Table 111-5 are based on operating experience.

c. Operational Experience During the course of operating the Monticello reactor under. normal conditions and at an annual average full load factor of 80%, the amount of radioactivity released to the environment is anticipated

. to be greater than that shown for the first year of operation. The applicant expects the total annual release of radioactive materials in ifquid effluents will be about 3 curies including tritium and that the annual average gaacoua radioactivity release rate with the existing 30-minute offgas holdup system will be about 25,000 pCi/sec.

The actual releases of radioactivity for the first year of operation (approximately 49% plant capacity factor) are shown in Tables 111-6 Snd 111-7.

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d. Solid Wastes -

Solid wastes are generated from the operation and maintenance of waste process systcms, reactor systems, and plant support systems.

The solid waste processing and handling operations are carried out remotely in ventilated areas. -

Filter sludges from the reactor clean-up, fuel-pool, condensate-filter /demineralizers, radwaste filters and spent resins from the mixed-bed demineralizer make up the largest volume of solid waste.

The sludges and resins are dewatered by centrifugation after storage in phase separator tanks. The dewatered material is mixed with cement, and placed in a 55-gallon drum. The drum is sealed remotely, decontaminated, and placed in an appropriately shielded area.

Bulk wastes from the reactor system, such as control rod blade:

fuel channels, and in-core-ton chambers are stored in be spent-fuel storage pool before being removed from the plant wa approved shipping containers. Compactible dry wastes are collected in drums at the source locations, transferred to the radwaste building, and compressed by a hydraulic press-baling machine.

Certain chemical vastes that are not suitable for reuse are mixed with cement during drumming operations or are placed directly in 55-gallon drums previously filled with an absorbent and removed from the plant as solid waste.

Based on present operating conditions, it is est!. mated that approximately 33,000 ft3 of solid waste per year containing

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TABLE III-6

HONTICELLO MUCLEAR GENERATING PLANT LIQUID RELEASES - 1971 Ci/ Month Ci/ Month Vol. of Liquid 1971 Cross Activity Tritium (Liters) ,

f January 3 x 10'I 1 x 10~3 2 x 10 5 1.4 x 10 ~3

~

I February 6 x 10 9.2 x 10 5 ,

March 4 x 10-6 4 x 10 7.8 x 10 j April 1 x 10-5 4 x 10~3 4.9 x 10'

~0 ~

May 4 x 10 8 x 10 ' 8.6 x 10' June 6 x 10~' 6 x 10~3 1.4 x 10 5 July 7 x 10~3 9 x 10 ~3 7.9 x 10 0

August 1.5 x 10~' 4 x 10~ 1.9 x 10' September 6 x 10 ~3 2.5 x 10~1 1.4 x 10 5 l October 1 x 10 ~I 3.2 x 10 1.6 x 10' 3.2 x 10 ~1

~

November 2 x 10 ' 2 x 10 5 December 8 x 10-5 1 x 10 ~3 8.8 x 10' l 70TAL 0.014 0.6 1.2 x 10 6 l

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TABLE III-7 +

i MONTICELLO NUCLEAR CENERATING PLANT CASE 0VS RELEASES - 1971

., l l Ci/ Month ' Ci/ Month 1

1971 Eobic cases Iodine VCi/sec.

j i January. ------ ------ ------

February ------ ------ ------

March 12 0.000006 159 April 58 0.000026 900 May 710 -

0.00032 1,875 j June 550 0.00025 900

July 1,283 0.0017 11,250 August 16,700 0.0017 14,250 ,

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, September 21,100 0.015- -15,000

October 26,300 0.0082 14,250

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, November 9,140 0.0046 11',500 December ------

0.00044 :11

' TOTAL 76,000 0.032 f

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l 53 curies will be shipped offsite for disposal. In addition, approximately 80 barrels of compacted wastes will be shipped

! offsite annually. All solid waste will be packaged and shipped in accordance with AEC and DOT Regulations.

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