ML20198F824

Forwards Radwaste Section for Environ Statement.Source Terms Informally Transmitted to Radiological Assessment Branch on 720706

ML20198F824
Person / Time
Site:	Columbia
Issue date:	07/28/1972
From:	Tedesco R US ATOMIC ENERGY COMMISSION (AEC)
To:	Muller D US ATOMIC ENERGY COMMISSION (AEC)
References
CON-WNP-0912, CON-WNP-912 NUDOCS 8605290107
Download: ML20198F824 (15)

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Docket File auus an Dock.t no. 50-397 -

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DOCKET NUMBER: 50-397 RESPONSIBLE BRANCH: Envireemental Projoete Braneh No. 2 FROJRCT LEADER: M. Grotenhuis REQUESTED COMPLETION DATE: September 20, 1972 DE8CRIPTION OF RESPONSE: Radweste Sectfon for Envirvemental Statement REVIEW STATUS: Completed In response to your request, we have prepared and attached to this memo the radweste section for the Envirommental Statement for Easford 2 Nuclear Power Station. The writeup and soures terms were prepared by R. Smith with input from ORNL.

The source terms were informally transmitted to the Radiological Assese-ment Braneh en July 6, 1972. The Sl essy prints of the liquid and gaseous waste treatment system have been provided to your staff.

Original signed byf Ro/bert, .

(Tedesco, u Director for Centainment sty Direeterate of Licensing

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Waste Treatment Section for Environmental Statement Hanford-2 Nuclear Fower Station 3.5 Radioactive Waste Systems During the operation of Hanford-2 Nuclear Power Station, radio-active material is produced by fission and by neutron activation reactions of metals and other material in the reactor coolant system.

Small amounts of gaseous and liquid radioactive wastes will enter the effluent streams and then be processed within the station to minimize the radioactive nuclides that will ultimately be released to the atmo-sphere and into the Columbia River under controlled and monitored conditions. The radioactivity that may be released during operation of the station will be in accordance with the Commission's regulations, as set forth in 10 CFR Part 20 and 10 CFR Part 50.

The waste handling and treatment systems to be installed at the station are discussed in the Preliminary Safety Analysis Report and in the Applicant's Environmental Report, both dated August 1971.

3.5.1 Liquid Waste

, Liquid wastes which may be subject to possible radioactive con-l l tamination will be collected in the liquid radwaste system where they will be monitored, stored, and processed for re-use or for discharge ~

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f to the cooling tower blowdown stream. The liquid radwaste system will be divided into several subsystems so that the liquid wastes from various sources can be kept segregated and processed separately. Cross connections between these subsystems will provide additional flexibil-ity for processing of wastes by alternate methods. The interrelation-ships of these systems and their interaction with other components'are shown in Figure 3.5.1. The liquid radwastes wil) be classified, col-lected and treated as high purity, low purity, chemical, detergent, sludges or concentrated wastes. The terms "high purity" and " low purity" refer to the conductivity and not radioactivity. Table 3.5.1 lists the principal assumptions used in evaluating the waste treatment systems.

m High purity (low conductivity) liquid wastes will be collected in the waste collector tank, principally from the coolant piping and equipment drains, and processed through a filter and a mixed-bed demineralizer. Af ter processing, the waste will be collected in a vaste sample tank. Normally, it will be transferred from the sample tank to the condensate storage tank for re-use. However, on infrequent occa- g sions a portion of this waste will be processed through a vaste con-centrator (10 gpm) and discharged to the cooling tower blowdown line.

In our evaluation, we assumed that 10% of the annual volume would be evaporated and released and the remaining 90% would be recycled.

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Low purity (high conductivity) liquid wastes will be collected in the floor drain collector tank, principally from the various floor drain sumps. From the floor drain tank the wastes will be processed through a precoat type filter and a mixed-bed demineralizer and col-lected in a sample tank. Normally, these wastes will be routed to the condensate storage tanks for reuse. However, some of wastes may be routed to the chemical waste tanks for processing through the waste concentrator before discharge.

Our analysis considered a daily input into the low purity system of 8,390 gallons at an activity equivalent to 35% of primary coolant and tha~ 15% of this waste will be evaporated prior to being released to the circulating water discharge canal. The remaining 85% of this waste was assumed to be recycled.

Radioactive high conductivity chemical wastes from sampling, laboratory drains, and chemical decontamination solutions will be collected in the chemical waste tanks. taese chemical westes are of such high conductivity as to preclude treatment by ion exchange and will be neutralized and processed through the waste concentrator.

The condensate will be routed to distillate tanks where it will be released to the circulating water discharge canal.

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i Our analysis considered a daily input to this system of 4,300 gallons, including 10% of the equipment drain and 15% of the floor .

drain waste volume. and that 100% of the condensate will be released to the circulating water discharge canal.

Liquid wastes containing detergents or similar cleaning agegts from fuel cask claaning and personnel decontamination will be col-lected in a detergest drain tank. Processing will consist of passing .

the waste through the detergent drain filter to remove solids and concentrating it in one of the two waste concentrators. In our evaluation, we considered the potential effluents from the detergent system to be a small fraction of the waste from the other systems and did not analyze them separately.

Annual releases of fission product radionuclides from Hanford-2 were calculated based on reactor operation at 3458 MWt (maximum power) for 292 full power days. Corrosion product activities were based on operating experience with boiling water reactors. The applicant expects the normal cooling tower blowdown flow to be 4000 gpm. We accepted this dilution flow estimate and, therefore, rather than total curies released, the annual average concentration of radioactive material in the liquid effluents prior to dilution will be the limiting constraint for the annual liquid waste discharges. Based on the assumptions shown in Table 3.5.3, the annual releases of radioactive materials in the

liquid waste were calculated to be a fraction of those values shown in Table 3.5.1 (excluding tritium). To compensate for treatment equipment downtime and expected operational occurrences, the values have been normalized to 0.25 Ci/yr, which limits the annual concentration in the

-8 discharge canal to less than 4 x 10 pCi/ml. Based on our evaluation, we estimate that about 10 Ci/yr of tritium will be released to the '

environment. The applicant estimates that 0.16 Ci/yr of mixed isotopes and 16 Ci/yr of tritium will be released to the environment in the liquid effluent.

3.5.2 Gaseous Waste During power operation cf the plant, radioactive materials released to the atmosphere in gaseous effluents include low concentra-tions of fission product noble gases (krypton and xenon), halogens (mostly iodines), tritium contained in water vapor, and particulate material including both fission products and activated corrosion products.

The major source of gaseous waste activity during normal plant operation will be the offgas from the main steam condenser air ejector. Other sources of gaseous waste include turbine gland seal steam exhaust, of fgases f rom the mechanical vacuum pump, ventilation air released from the radwaste, reactor, and turbine building exhaust

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systems, and purging of the drywell and suppression chamber. A schematic flow diagram of the gaseous waste treatment system is shown in Figure 3.5.2.

Offgas from the main condenser air ejector will flow through one of two catalytic recombiners where the hydrogen and oxygen ,

recombine to form steam which is condensed and returned for use in the plant. The waste gas stream will be sent to a holdup pipe which will be designed to delay the full volume of vaste gases for a -

period of at least 10 minutes to permit the decay of short-lived activity. From the holdup pipe the gases will flow through charcoal beds, after having the gas humidity reduced by moisture separators

! and desiccant dryers. Xenon and krypton activities will be j selectively held up on the charcoal beds. In addition, the charcoal j

will also retain radioactive iodine, and long lived radioicotopes in the particulate form, such as strontium-89, strontium-90, and cesium-137. The applicant estimated 42 days xenon and 46 hours5.324074e-4 days <br />0.0128 hours <br />7.60582e-5 weeks <br />1.7503e-5 months <br /> krypton holdup with 30 scfm air inleakage. In our analysis we assumed that the xenon radioisotopes are delayed 18 days and that the krypton isotopes are delayed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on the charcoal beds with 40 scfm air inleakage into the three-shell condenser. The charcoal ,

delay system will consist of 8 beds, each bed containing about 3 tons of charcoal and will be operated at O'F.

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The steam air exhaust from the turbine gland seal system will pass through a gland seal condenser where the steam will be condensed  !

and the noncondensibles exhausted to the gland seal holdup line.

Steam for the turbine gland seal will be generated using effluent from the condensate demineralizer. Based on using this relatively clean steam for turbine gland seal, no radioisotopic discharges were calculated to be released through this route. .

The mechanical vacuum pump, used during startup, exhausts air.

and radioactive gases from the main steam condenser. Offgases from this system will be discharged to the environment without treatment.

The primary containment (drywell) is normally a sealed volume. .

However, during periods of refueling or' maintenance it may be neces-sary to purge the drywell and suppression chamber and when this occurs, the potential exists for the release of airborne radioactivity to the environment. Normally, the purge releases will not be treated before release to the environment, however, the system will be designed auch that the purge exhaust can be directed to the standby gas treatment system in the event of abnormal air activity levels. In our evaluation, we assumed no treatment before release to the environment. The annual releases from this source is not expected to be a contributing source of activity.

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i Ventilation air flow will be provided to the reactor building, turbine building, and the radwaste building. Most of the ventilation systems will utilize 100% outside air with no recirculation. Exhaust air from the non-contaminated areas of the reactor building, the rad-waste building, and the turbine building will be exhausted through the roof vent of the buildings without treatment. The potentia 11y' contaminated areas of the reactor building, turbine building, and radwaste building will be filtered through HEPA filters before being discharged to the atmosphere. The annual releases from these sources are not expected to be a contributing source of activity.

Table 3.5.2 shows the anticipated annual release of radio-

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active materials in the gaseous effluent calculated in our evaluation based upon the conditions listed in Table 3.5.3 The applicant esti-mated that between 300 and 580 curies per year of noble gases and no iodine will be released to the environment in the gaseous effluent.

3.5.3 Solid Waste Four types of solid wastes will be packaged for offsite disposal. Dry wastes will be compacted in 55-gallon drums. Spent filter cartridges will be packaged in shielded drums. Evaporator wastes will be accumulated in phase separators and sludge tanks and

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then pumped into a solidification mixture contained in drums. Resins from the spent resin tank will be discharged to a shielded shipping ,

container.

All solid waste will be packaged and shipped to a licensed burial site in accordance with AEC and DOT regulations. Based on a plants presently in operation, it is expected that approximately 900 drums of spent resin filters, flocculation wastes and evaporator bottoms will be generated per year. We estimate that each drum will contain about 2.9 curies after 180 days decay. In addition, it is expected that 600 drums /yr of dry waste containing less than 5 Ci/yr will also be generated.

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. l Table 3.5.1 Calculated Annual Release of Radionuclides in the Liquid Effluent from Hanford-2 ,

Nuclide Curies Nuclide Curies Rb-86 0.000045 I-133 0.0 15 Sr-89 0.0087 I-135 0.000044 Sr-90 0.00057 Cs-134 .0.028 Sr-91 0.000031 Cs-136 0.0064 Y-90 0.00081 Co-137 0.019 Y-91m 0.00002 Ba-137m 0.018 Y-91 0.016 Ba-140 0.012 Er-95 0.0001 La-140 0.012 Nb-95 0.000096 Co-141 0.00027 No-99 0.0014 Ce-143 0.000037 Tc-99m 0.0013 Ce-144 0.000063 Ru-103 0.000068 Pr-143 0.00011 Ru-106 0.000024 Pr-144 0.000063 Rh-103a 0.000068 Nd-147 0.000028 Rh-106 0.000024 Cr-51 0.0017 Te-127m 0.00002 Mn-54 0.00013 ,

Te-127 0.000022 Fe-55 0.0067 Te-129s 0.00018 Fe-59 0.00027 Te-129 0.00011 Co-58 - 0.017 Te-131a 0.000028 Co-60 0.0017 Te-132 0.00095 P-32 0.000033 1-130 0.000019 W-187 0.000079 I-131 . 0 .0 84 U-237 0.00002 1-132 0.00098 Np-239 0.00048 Total (Excluding tritium)  % 0.25 Curie Tritium N 10 ci/yr

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TABLE 3.5.2 CALCULATED RADIOACTIVE RELEASES IN GASEOUS EFFLUENTS FROM HANFORD NO. 2 REACTOR IN CURIES PER YEAR Turbine and Mechanical Main Total for Reactor Vacuum Condenser Reactor Radionuclide Buildings Pump Air Ejector Unit Kr-83m 2 11 13 Kr-85m -

3.240 3,240 Kr-85 -

760 760 Kr-87 , 10 1 11 Kr-88 10 1,190 1,200 Kr-89 34 -

34 Xe-131m -

230 230 Xe-133m -

40 40 Xe-133 - 1,500 24,700 26,200 '

Xe-135m 17 -

17 Xe-135 15, 215 - 230 Xe-137 60 - 60 Xe-138 50 -

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TABLE 3.5.3 PRINCIPAL ASSUMPTIONS USED IN EVALUATION HANFORD No. 2 REACTOR

1. Thermal power 3458 Mw(t)

2. Plant factor 0.8

3. Failed fuel Equivalent to 100,000 pCi/sec noble gas mixture after 30 min holdup decay for a 3400 MWt reactor

4. Reactor Building Leak Rate 480 lb/hr - liquid

5. Turbine Building Leak Rate 480 lb/hr - steam

6. Condenser air inleakage 40 cfm - air

7. Partition coefficients (for iodine):

Steam / liquid in reactor vessel 0.012 Reactor Building liquid leak 0.001 Turbine Building steam leak 1.0 Air ejector - 0.005 .

Recombiner system 0.1 Charcoal bed ,

0.000001

8. Holdup Times Air ejector gas 10 min -

Xenon lactopes - delay on charcoal beds 17.9 days Krypton isotopes - delay on charcoal beds 24.4 hrs

9. Decontamination Factors: Anton Ca.Rb Others Mixed-bed dominera11:er 100 10 100 Evaporator 1000 10,000 10,000

10. Removal factors ,

Mo & TC 100 Y 10

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