ML20214G799
| ML20214G799 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 08/23/1972 |
| From: | Tedesco R US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Boyd R US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| CON-WNP-0106, CON-WNP-106 NUDOCS 8605220519 | |
| Download: ML20214G799 (11) | |
Text
7 N
oc et rite necket no. 50-397 d 2 31972 Roger S. Boyd, Assistant Director for Boiling Water Baaetore, L SAFETY ETALUATION ' REPORT - MANYORD 2 Plant Name: Ranford No. 2 Licensing Stage: CP Docket Number: 50-397 Responsible Armach: Gas Cooled Kaseter6 Branch Project Leader:
S. Minor l
Requested Completien Date: August 18, 1972 Review Status: Corplete We have reviewed the information provided by the applicant ca the proccan radiation monitorinF and radioactive vaste control cystems ar.d conclude that these systes's are acceptable. Attached is the basic f or our avaltie-tion for inclusion in the ACR$ - S&fety Evalwation Report.
f fi+ rti si 'ted by t
bctar Senareys Kobert L. Tadeaco, Aset.ata:::t Di.ree: tor e
for Containment Safety Directorata of Licaesing
Enclosure:
Safety Evaluation Report cc: v/o enclosure DISTRIBUTION:
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7.11 Process Radiation 5'onitoring Five process conitoring systers are provided to deternine the radiation levels in all normal and potential licuid and crseous release paths during normal operatien, and anticinated operational occurrences. The off-gas vent radiation ronitoring system and the process lionid radiation monitors centinousiv record the quantities of radioactive material being released to the environnent. The off-gas vent radiation monitoring systen has the capability to periodically perform isotopic analyses on iodine and particulate releases.
We conclude that the station will be suitably ecuinted to measure the radiation levels in the station's effluents.
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9.0 _ Radioactive Uaste Control Systers 9,1 Sunnary Description
~ The applicant's desien objectives for the licuid radwaste syster are to naintain the dose due to tadioactive raterial dischareed during norral operation to less than 1 percent of 10 CFR Part 2n linits and to retain as much of the water in the plant as possible.
The design objective of the gasecus radwaste system vill be to reduce doses fron radioactive caterial discharged durine nernal operation to as lov as practicable as defined by the proposed Appendix I to 10 CFR Part 50. The design objective of the solid radwaste systen is to packace radioactive solid vastes in accordance with applicable Federal and State reeulations.
9.2 Liquid Radwaste Systen High purity (low conductivity) liould wastes will be collected in the 20,000 gallon vaste collector tank, principallv from the ecolant piping and euuipnent drains, and processed throueh a filter and a mixed-bed demineralizer. After processing, the waste will be collected in a 20,000 gallen vaste sample tank. Normally, it will be trar.sferred fron the sanple tank to the condensate storaee tank (400,000 gallons) for re-use. However, on infrequent occasions a portion of this waste vill be processed throuth a vaste concen-trator (10 gpm) and discharged to the cooling tower blowdown line.
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In our evaluation, we assumed that 10% of the annual volune would be evaporated and released and the reraining 00% would he recycled.
The applicant assures that 100% of these wastes uould reeveled. ue calculate that.06 Ci/vr of hirh purity vas tes will he released.
Lew purity (hich conductivity) licuid wastes will be collected in the 20,000 gallen floor drain co11cetor tank, nrincipallv f ror the various floor drain sumps. From the floor drain tank the wastes will be processed through a precoat type filter and a nixed-bed denineralizer and collected in a 20,000 Pallon sarple tank.
Normally, these wastes will be routed to the condensate storace tanks for reuse. However, sene of thes e wastes ray be routed to the chemical waste tanks for processing through the waste concen-trator before discharge.
Our analysis considered a daily input into the low purity sys ten of 8,300 gallons ac an activity cauivalent to 357, of prirarv coolant and that 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. The applicant also assuned 15" of this waste would be discharged and 85% reeveled; however, the applicant assumed that oniv ibout 6,200 gallons /dav would be collected at a lower activitv. We calculate that 0.1 Ci/yr of Icw purity wastes will be released.
f Radioactive high conductivity chenical wastes from sampling, j
laboratory drains, and daenical decontanination solutions will be collected in the 13,000 gallon chemical waste tanks. These chemical wastes are of such high conductivity as to preclude treat-nent by ion exchange and will be neutralized and processed through the 8.5 gpn waste concentrator. The condens tate will be rotated to one of two 13,000 gallon distillate tanks where it will be released to the circulating water discharee canal.
Our analysis considered a daily input to this sys ten of 4,300 gallons, including 10% of.he eauipeent drain and 15% of the floor drain waste volume, and that 100% of the condensate will be released to the circulating uater discharge canal. The applicant, however, estimated that 625 to 1625 gallons per day of this waste would be collected and that none would be recycled. We calculate that 0.9 Ci/yr of dienical wastes will be released.
Liquid wastes containing detergents or sinilar cleaning agents fron fuel cask cleaning and personnel decontamination will be collected in a detergent drain tank. Processing will consist of passing the waste through t,he detergent drain filter to remove solids and concentrating it in one of the two waste concentrators. In our evaluation, we considered the potential effluents fron the deter-gent system to be a small fraction of the waste fron the other systens and did not anclyze then separatelv.
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The applicant expects the nornal cooling tot'er blottdown flor to be
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4000 gpn and that 2 x 10 pCi/ml, excludine tritiun, will be released annually from the licuid raduaste svs ten based on 190,000 pCi/see at design basis fuel leakace conditions. This flow will be used to dilute liould radwaste discharges. We accented this dilution flow esticate as reasonable for this plant. Due to the low dilution floti, the annual average concentration of radioactive naterial in the liquid effluents prier to dilution will be the lirdting constraint for the annual linuid waste discharges rather than the total curies release. The annual averaec releaaes fron the primary scurces for normal operation were calculated to be less than 4 x 10-pCi/nl, excluding tritium, which results in 0.25 Ci of liquid radwaste release annually. Therefore, as the basis of our evaluation we conclude that the liould radwaste treate.ent systen proposed for Hanford No. 2 should be caoable of providina effluents which can be considered as low as practicable as proposed in 10 CFR 50.34(a) and therefore conclude that the desi-n of the liquid radwaste system is acceptable.
9.3 Gaseous Radwaste System Offgas consisting of hydrogen and oxygen and other gaseous materials from the main condenser air ejector will pass through oce of two catalytic recombiners where the hydrogen and oxygen recom-bine. The steam that is formed is condensed and returned for use i
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in the plant. The reduced volume of ras stream will be sent to a holdup pipe which will be designed to delay the waste gases for a period of at 1 cast 10 minutes to pernit the decay of short-lived activi ty. From the holdup pipe the gases will fler throuah charcoal beds, af ter having the gas hunidity reduced hv rois ture separators and dryers. Xenon and krypton activities will be selectively held up on the charcoal beds. The applicant es ticated 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 39 scfn air inle akage. In our analysis we assumed that xenon is delaved 18 days and that the krypton is 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 inleakace 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.
Steam for the turbine seal will be generated usine effluent fron the condensate decineralizer. The steam air exhaust fron the turbine gland seal system will pass through a gland seal condenser where the steam will be condensed and the noncondensibles exhausted 1
to the gland seal holdup line. Based on using this relativelv I
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 fron the main steam condenser. Offgases fron
r-I this system will be discharged to the environnent without tre at ment. A nonitor will autonatically s top the vacuun punp if the radioactivity released is too hich.
The primary containment (drywell) is norna11v a sealed volune.
However, during periods of refueling or naintenance it nav be necessary to purge the drywell and suporession chanber and when this occurs, the potential exists for the release of airborne radioactivity to the environment. The apolicant states that normally the purge releases will not be treated before release to the environtxnt. However, the system will be desiened such that the purge eWhaust can be directed to the standby gas treatment system in the event of abnormal air activity levels. In our evaluation, we assumed that the drywell will be purr.ed once per year with no treatment before release to the environment. Based on these assumptions, we calculated that.01 Ci/yr of I-131 and no noble gases would be released. The annual release from this source is not expected to be a contributing source of activity.
Ventilation air flow will be provided to the reactor building, turbine building, and the radwaste buildine. Most of the ventila-tion systens will utilize 100% outside air from the non-contaminated areas of the reactor building, the radwaste building, and the turbine building and will be exhausted through the roof
vent of the buildings without treatrent. The notentially con-tar.inated areas of the reactor building and radwaste buildine will be filtered through HEPA filters before heine dischareed to the atnos ph ere. The annual releases from these sources are not expected to be a contributing source of activity.
Based on our expected annual I-131 releases of 0.13 Ci/yr, we calculate doses to the thyroid to be less than 5 mrem at the boundary of the Hanford Reservation. The applicant clairs that no iodines will be released annually from the gaseous raduaste system.
The expected normal discharges of noble gases and iodines will result in an annual average exposure rate at any location on the boundary of the Hanford Reservation of less than 5 mrens to the whole body. Therefore, we conclude that the provisions proposed to control gases released fran the plant are sufficient to neet the requirements of 10 CFR Parts 20 and 50. The applicant assumes that 303-583 Ci/yr of noble gases will be released annually from the gaseous radwaste system based on 190,000 uCi/sec at design basis fuel leakage conditions.
These systems will be designed and f abricated in accordance with 1
acceptable codes and standards. The equipment in the liquid rad-waste system will not be designed to withstand the design basis
ea rthou ake. Houever, the eouiprent will be located within a structure that will be designed to withstand desien basis earth-quake, so that all licuid radwaste vould be contained foll&<ine a design basis earthouake. The of fras sys ten will not be desf rned for a design basis earthouake or contained within a structure that will withstand a design basis earthquake. H&iever, our analysis shous that rupture of the charcoal tanks will result in doses at the plant boundary less than 10 CFR 20 We therefore conclude that the design of the offgas systen is accentable.
9.4 Solid Radwaste Systen Four types of solid wastes will be packaged for offsite disposal.
Dry wastes will be cor.pacted in 55-gallen druns. Spent filter cartridges will be packaged in shielded drums. Evaporator wastes will be accumulated in phase separators and sludge tanks and then pumped into a solidification mixture contained in drums. Res ins from the spent resin tank will be discharged to a shielded shipping container.
All solid waste will be packaged and shipped to a licensed b Yial site in accordance with AEC and DOT regulations. Based on plants presently in operation, it is expected that approxinately 900 druns of spent resin filters, flocculation wastes and evaporator bottons will be generated per year. We estimate that each drum will
contain about 2.9 curies after 180 days decay. In addi tion, it is expected that 600 druns/yr of dry waste containine less than 5 C1/yr will alsc be generated. The applicant es tinates that about 700 druns per yest of solid waste will be renerated which will contain about 3500 curies.
Design and operation of the solid radwaste systen do not involve any unusual safety problers not alread.y considered on other "WR applications, and therefore, this system is acceptable.
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