ML19221A851
| ML19221A851 | |
| Person / Time | |
|---|---|
| Issue date: | 06/30/1974 |
| From: | NRC OFFICE OF STANDARDS DEVELOPMENT |
| To: | |
| References | |
| REGGD-01.021, REGGD-1.021, NUDOCS 7907100104 | |
| Download: ML19221A851 (21) | |
Text
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Revision 1 7gg A
Lt.S. ATOMIC ENERGY COMMISSION Md R EGU :_ ATO RV G U D D E V
DIRECTORATE OF REGULATORY STANDARDS REGULATORY GUIDE 1.21 5
MEASURING, EVALUATING, AND REPORTING RADIOACTIVITY IN SOLID WASTES AND RELEASES OF RADIOACTIVE MATERIALS IN LIQUID AND GASEOUS EFFLUENTS FROM LIGHT WATER COOLED NUCLEAR POWER PLANTS A. INTRODUCTION day s after January I and July I of cach year which specifies the quantity of each of the prindpal General Design Criterion (0, " Control of releases radionochdes released to unrestncted areasin hquid and of radien t ne matenals to the e nu ro nme nt,' of in gaseous ef fluents dunng the previous 6 months of AppenJ n A. " General Design Criteria for Nuclear ope rat io n, and such other information as may be Pow e r Pla nt sl to 10 CFR hrt 50, "lacensmg of requued by the Commission to estimate maximum Produstion and Utihzation Facihties," requires that tne potential annual radiation doses to the pubhc resulting nuclear power plant design melude means to control from efnuent releases.
the relem of radimet!ve materials in gaseous and hquid etfiuents and to handle radioactne sohd wastes Paragraph (c) o 20.I, " Purpose," of 10 CFR Part r
produced during normal react ( r operation, including 20 states that every reasonable effort should be made by anticipated operational occurrer ces.
AEC licensees to main tain radiation exposure, and releases of radioactive matet tals in efiluents to General Design C rit eno n 64, " Monitoring unrestncted areas, as far below the hmits specified in raduactivity rele ases," requires that nuclear pow er Part' 10 as precticable, i.e., as low as is practicably plant designs proude means f or monitonng efnuent achievable, taking into account the state of technology, discharge paths for radioactmty that may be released and the economics of improvements in relation to from normal o pe r a tions, including anticipated benefits to the pubhc health and safety and in relation operational occurrences, and from postulated accidents.
to the utilizanon of atomic energy in the public interest.
Section 20.106, " Concentrations in ef0uents to This guide describes programs acceptable to the unrestneted areas /' of 10 CFR Part 20, " Standards for Regulatory staff for measuring, reporting.and evaluating Protection Against Radiation," provides that a hcensee releases of radioactive matenals in hquid and gaseous shall not release to an unrestricted area, radioactive ef0uents and guidelmes for. classifying and reporting the marerials in concentrations which exceed hmits categones and' curie content of solid wastes, Otha e
specified in 10 CFR Part 20 or as otherwise authorized programs for the reporting of operating information, in a hcense issued by the Commission. Section 20.201, including abnormal occurrences, are presented in
" Surveys," of 10 CFR Part 20 further requires that a Regulatory Guide 1.16, " Reporting of Operating licensee conduct surveys of concentrations of In fo rmat io n.'
in some cases specific programs should radioactive mate rials as necessary to demonstrate be supplemented because of individual plant design comphance with AEC regulations.
features or other factors. The need for supplemental or moJified programs will be determined on _a case by-case Pa r a g ra ph ( a )( 2 ) of 5 0.36a, " Technical ba sis.
speci0 cations on efnuents from nuclear power reactors /
of 10 CFR Part 50 provides that techmcal specifications The Advisory Committee on Reactor Safeguards has for each hcense will include a requirement that the been consulted concerning this guide and has concurred heensce submit a report to the Commission within 60 in the regulatory position.
}
e USAEC REGULATORY GUIDES cop ei of put:i. hed e des emv tie obte. ied bv reauest.ad.mtg the d'e om desaed to t he US A oi%ec E nsegy Comm assoa. Wesseagtoa. D r. 2%46, Reevia'ory G uedes he.esued to deso.be end erwho sweaieme to om putwec A ttens en Director of Roguetory sienderen Comtreats ord squest.oas f as methods semptab,e to the At C Reperory staff of serweement'ng specif.c pets of mero=orrones in etwee are encouraged ered steved be sont to the Serrotary ou Commiss on a rogue'es to <se..aee, techaiques used by the staff en of the Coram es.oa. U.
Atomic E ae sv Commes.on weshirqsoa. O f. 2C645, eiesuettag SpecM proNea's o* postwieled acc edsats, os to provde guidance to A ftMtion Chee8, PutAC Proceedngs $teff epDetr.Ba tt R*gulatory Gwedes ese not sybst+1stes f or 'egulatsomt and corvipheam er'th toeri9 as not FerJ uer ed Methods and gelutecas d ffereal from those set one en IPW psodes ere estued ta ttie tohoweq tea twood gyiseoal the pedet sw41 De SemD'ahle of they prowese a bases for the Istdengs requestie lo the ses6ance ofm nt enuance of 4 pef ra+t or the+tte by the Cornmsteoa f
Po*** Reactort 6 ProescT5 2 Reteerch and Test Reectors 7 T r eaucorlee son 3 F weet ered Meter we F ecehties 8 Occ sietfonet t4eetth e
3 Pe'shed Pdes
- 'll be rew.ted per.oeMeliv. Os Opptrot4'e 'o acco*Tsmodate 4 { aceommeesel said Setsig 9 Antettwat Revepue co'T58Ttraft and to f 9410(1 rate afitor f'uteoa or esperience 5 M6 eer.ees and Pieae Protect oa 10 Geneens 7907100 TOT '
B. DISCUSSION Batcit rdcases-discontmuws release of gaseous or hquid efnuent which takes piace over a finite pened of time, Informatian on the identity and quantity of usua'.!) hours or days.
radionuchdes in hquid and gtseous ef0uents and sohd wastes from ight water coc'ed nuclear power plants, Continuous release-release ef gaseous or liquid efnuent together with metecrological data representaine of which is essentially urunterrupted for extended periods pnneipal release pomts, are needed:
danng normal creration of the fa;dia.
1.
For esaluation by the brensee and tne Regulatory De t ermined (or a det ermination)- a quantitative
/
st a ff of the ennronmental impact of radioactive evaluatian of the release or presence of radioactne matenals m efnuents and sohd wastes, includmg mat enal under a specific set of condinons. A esumates of the potential annual radiation doses to the determmation may be made by dueet or indirect measurements. In some cases it may not be practical to pubhc; 2.
To ascertain whether AEC regulatory requirements make direct measurements of speafic radionuchdes in and hmitmg conditions of operation have been met and efnuent or waste; e.g, the concentranons may be too whether concentraticns of radioactise materialsin hquid low for measurement in a reasonablc or pracucal volume and gaseous ef0uents have been kept as low as of sample, certain nuchdes may be masked by other practicable; radionuchdes in the sample, or as m the case of sohd or 3.
For esaluarton by the hcensee and the Regulatory concentrated wastes, it may be difncult to obtain a representative samf e. Under these cucumstances,it may l
staf f of the adequacy and performance of containment, waste treatment methods, and effluent controls, be more appropnate to calculate releases usmg prenously estabbshed ratios with those nuclides which are readdy measurable. Such a procedure would it is essential to have a degree of uniformity in the constitute a de:ermination.
methods used for measunt.g evaluating, recording, and reporting data ort radioactive material in efnuents and Elewited release point 'he point of release of gaseous sohd w ast es. The rnuhods described in this guide waste for whrh credit w as given as such in the pronde a uniform basis for companson of data from determmahon of the tech ucal specification limit for different sources and permit the preparation of that release point.
consistent summaries of data for use by the Regulatory staff as bases for the assessment of a licensee's efnuent Ground-lesel release point-t he point of release for controls and the potential environmental impact of Fasecus w aste w hich is treated in the technical iedioactive materials in effluents and solid wastes.
speciGcations as havmg zero heght.
This guide, w hich it a reused and rew ntten v.rsion This guide outhnes general guidelines for monitoring o' Regulatory Guide 1.21 (issued as Safety Guide 21 and reporting programs. Detailed specifications for December 29,1971), describes acceptable programs for samphng and analysis of ef0uents are not included since m e a su ring, evaluat m3, and report mg release of they need to be tadored to the requnements of each radioacthe matenal in hquid and gaseous efnuents and specinc plant. Standardized methods for monitonng, solid wastes from nuclear power plants. It also provides samphng, and analysis should be used to the extent guidelines for calculating potential annual radiation practicable. The followmg is an example of a standard doses to mdividuals and populations using appropriate wtuch is appropnate for these purposes models and parameters and pertinent recorded ef0uent and meteorological data. Sigmficant changes from the The Amen;an Nanonai Standards Institute (ANSI) previous version are identined below :
has developed a standard' which inc'udes general prin-There has been a mamr change m the format of this ciples and guidance for sampling airborne radioacWe guide. The more detaded recommend:tions concernmg m tenah radionuchde measurements are presented in Appendn A and the reportmg resommenda' ions are indicated m To assure uniformity of interpretanon, the Appendix B.
followmg definitons of terrns used in this guide are 2.
In many cases the cotena for senutmt> of ef nuent provided measurements base been modified to redett as law as practicabic dose conuJerations m the of fsite enurons; Abnormal releases unplanned or uncontrolled release of i.e., the sensitmt> of et0uent measurements should be radioactive matenal from the site boundary.
sufGcient to detect concentrations w h:ch. when dispersed in the onsite enwrons, would result in a d< se a small fra tion of natural background to individuals of ANSI N I 31 19M. " Guide to Sarnpimg Mrborne Radio-r a d ia tio n.
e werwis on Nuacu l mhoec 0.pm may te obtunal 3.
Some changes hm been made m the frequency of im, i hc A mer na t Nahanal Standads Insm ute. Inu 143o anah us for certam r3damus hdes m sescral catepones of thJ e ay. New Y or k. N. Y. 10o14 dbp hh
})E 1.21 2 J
.~
4 Proustons f or morutormg and reporting of sohd o pe r a '.
Judu p.u.t m pt d ops saoonal occu:re nces, 9
wastes and for r e po r ting of meteorological shoulJ be nomtored. Measurements of efl'oent vulume, measurements, categones not considered in the earher rates of relece, and specific radm nuchdes should be guide, have been included made, msotar n practiuble, at the punt (s) whhh would 5.
Provisions for app!>irg the measmed meteorolosncal proude data thit are the most uprescntatne of efnuent acceptable dme models ' I m
releases to the plant enurons. f or t hose ef n ue nt and efnuent data to calculating potential doses to ind md uals and discharge piutts whhh hae input from two or more populations, and for reportmg of these dose est; mates contnbutmg sources within the plant, momtonrg of the h.ne been included.
nujor contnhuting sources should also be considered from the st andpo mt of more effective process and C. REGULATORY POSITION etnuent control in many cases, monitonng of each of the major contributing sources may be a preferable or more sensit ne alt e rn at tW to mon toring the total 1.
Metcomlogy elduent releJsc when dilution w it h other less A knowledge of meteorological conditions in the concen: rated einuent streams makes the resultant vaimty of the nuclear plant is essential to make vahd effluent c o n c e n t rations too iow for accurate estimates of maumum potential annual radiation doses measurements.
resulting from radioactive materials released in gaseous ef0uents. Meteorological measurements should be made 3.
Type of Monitoring m accordance with the guidance set forth in Regulatory Guide 1.23 (Safety Guide 23), "Onsite Meteorological The i > pe of monitonng selected, mcludmg the Programs." A summary report of the n'eteorological frequena, duration, and methods of measurement, measurements taken during each calendar quarter in the depenJs to a large degree on the obiettnes of the 6-mo nt h pe nod should be submitted with the monnoneg program. I10uent momformg h required to sen.iannual Efnuent and Waste Disposal Report as jomt (a) demonstrate comphance with technical speci0 cation frequency distnbutions of wind direction and wind and/or 10 CFR Part 20 e f 0 uent hmit s, (b) allow speed by atmospheric stability class in the format etaluation of the performance of contamment, waste presented in Table 4A of Appendix B to this guide.
treatment; and efnuent con t rols, and (c) perm ti ev luanon M emnmental imp et and estimation of Hourly meteorological dita for batch releases the potential annual radiation doses to the pubhc.
should be recorded for the peru e of actual,elease, and Because r a d iation dose is dependent on the quarterly summanes snould be rep.rted separately. from radionuchde(s) to wtuch the mdmdual is exposed, the summaries of all observations taken during each monitoring programs shoulJ provide accurate quarter. The batch release uati and the quarterly Mformation on the ident:t> and quaritity of specific summanes of all observation: should each be gnen in the radionuchdes m ef0uents and wastes.
format presented in Table 4 A of Appendix B.
4.
Gross Radioactivity Measurements For abnormal releases, hourly meteorological data should be recorded for the periods of actual release and Gross r a dmact n ity measurements alone are should be included in the quarterly summanes of batch generally not acceptable for showing comphance with releaset e fn uer.t release hmits. I,lowever, gsoss radioac tmty 2.
Location of Monit ering measurements are otten the only practicable means of continuously monitoring ef0uents and therefore are All major and potentially significant paths for acceptable under certain speciDed conditions. Gross release of radioactive matenal during normal reactor radioactivity measurements are acceptable for the purpose of quantify ing radioactmty (3) when gross total
' Draft Regulatory Guide
- 1. A A " Calculation of Annual radioactaity concentrations are a small fraction of the Average Doses to Man f ro m Routine Relea ses of Reactor m a ximum permissible conce nt ranons ( M pCs) for Effluents for the Purpose of implemenung Appendn i," Draft
" unidentified mixtures" as speciDed in the notes of Regutatory Guide ! DD " Methods for Estimating Atrnospheric Appendix B to 10 (,F R Pa r t 20 or (b) when gross Dogersion of Gaseous E ffluents from Routme Releases." and Draft Reputatory Guide l.L E," Analy tical Models for t stimating r adioa c t n it y measurements are show n to be truly mdicaine of the actual quantit) and'or concentration of Radionotope Con ant ratio n m Different w ater Bodie s" m
At ta chment to Concluding S t at e rr~ n t, Numerical Gudes for radionuclides released.
Deugn Objectnes and Lamitmg Conditions :ar Operat on to Mee t the Cntenon %s Low as Practicable" for Radioac tne S.
Measurements of Specific Radionuclides Matenal in Light-water {'ooled Nucien Power Reactors, Dodet R M-50-2, USA EC, Februa ry 20,1974-ggg g
' " Final E nn ronme nt al Statement-Numencal Guides for radionuslides its hatch releases prior to their release to Desetn Objectnes and Limittng Conditions for Operation t the ens tr on ment. In those cases w he re analysis of 9
Matenal Meet the Critenon *As low as Practicable
- for R a dioa t h ve s
OMM M nhM Ed m Light water Cooled N uc!c ar Pow er Reactor f ffluents." % ASH-125R. Vol
- 1. Directorate of Regulatorv strontiumn0 cannot he made prior to release, Standards, US AEC, July 197 3 represer tatne samp!es should be collected from each 9
N9 1.21-3 lC U
batch of efCuents for the purpose of analysis at scme and in particulate form in gaseous effluents, samples for later t:me. The use of composite samples is acceptable, compositing should be collected in proportion to the and analyvs of such samples should be performed at rate of now of the effluent stream or in proportion to scheduled frequencies.
the volume of each batch of efCuent releases. Prior to analysis, the composite should be thoroughly mixed so Measurements should be made to quantify specific that the sample is representative of the average ef0uent radenuchdes in continuous releases by analyses of grab rele ase, samples collected at scheduled frequencies. The frequency of radionuchde analyses should be based on Periods of collection for composites should be as the degree of vanance of the concentrations and mixture short as practicable to preclude the loss of radioactive compositions from an established norm. Continuous material by deposition on walls of the sample container monitormg data as well as grab sample data should be or volatihzation of potentially volatile material. Periodic the bases for identifying this variance.
checks should be performed to identify any such Frequent compansons should be made between gross radioactidty measurements of continuous 8.
Time be+ ween Collection and Analysis monitors and analyses of specific radionuclides. These comparisons should be the bases for calibrating Measurements should be made as soon as practicable centmuous menitors to establish relationships between after collection to minimize loss of short lived monitor readmgs and concentrations or release rates of radionuclides by decay. Measurement of longer-lived radionuchdes in continuous effluent releases.
radionuclides sometimes can be simplified by ' allowing sufficient time before their analysis for the decay of 6.
Reprnentative Samples short lived radionuclides.
A sample should be representatin of the bulk Procedures should be instituted for handhng, stream or volume of ef0uent from which it is taken.
packaging, and storing samples to assure that loss of Provmons should be made to assure that representative radioactive materials or other factors causing sample samples are obtamed from well mixed streams or deterioration do not invalidate the analysis.
volumes of effluent by the selection of proper sampling equipment, the proper location of sampling points, and 9.
Corrections for Decay the deselopment and use of proper sampling procedures.
Pnor to samphng, large volumes of hquid waste Decay corrections should be made as though the should be mixed in as short a time interval as practicable efnuent were released uniformly throughout the to assure that any sediments or particulate solids are sampling period unless it is shown that most of the distributed uniformly in the waste mixture. Sample effluent was released during a particularly short ir.terval.
pomis should be located where there is a minimum of The exact time or time intervals of sample collection disturbance of Gow due to fittings and other physical should be recorded. To estimate radioactive decay in pooled samples, weighting should be charactenstics of the equipment and components.
composite or Sample nozzles should be inserted into the now or liquid apphed to the delay time of each portion and to the solume to ensure sampling the bulk volume of pipes and quantity of each portion in relation to the total quantity tanks. Sample lines should be flushed for a sufficient of the sample.
period of time prior to sample extraction in order to remove sediment deposits and air and gas pockets.
- 10. Sensitivity Penodically, a series of samples should be taken during The sensitivity lunits given for radioactivity analyses the interval of discharge to determine whether any differences exist as a function of time and to assure that in Appendix A of this guide are based on the potential mdividual samples are indeed representative of the significance m the environrnent of the quantities of radioactive materials released. For some radionuclides, ef0uent mixture.
lower detection limits than those given herein may be The general principles for obtaining valid samples of readily achievable and when measurements below the airborne radioactive material, the methods and materials stated sensitivity limits are attained, the results should for gas and pa rticle sampling, and the guides for be recorded and reported sa mp!mg from ducts and stacks contained in ANSI N131 1969 ' are generally acceptable and provide ade.
For certain mixtures of gamma-emitting nuchdes,it quate bases for the design and conduct of monitoring may not be possible to measure certain radionuclides at programs for auborne effluents.
the stated sensitivity limits when other radionuclides are present in the sample in much peater concentrations.
7 Composite Samples Also, it may not be pcssible to measure certain radionuclides whose gamma ray yields are low (e g.,
To be representative of the aserage quantities and Kr 85, Cr.51, etc.) at the stated sensitivity hmits. Under concentrations of radioactne matenals released m liquid these circumstances, and it, the case of radionuchdes 125 088
wtuch hase no gamnu rays and weak beta radiation (et, m-house to melude special met hod s or it e n <s of Fe-5 4, N-M etc.), a may be more appropriate to equipment not covered elsew he re.
Cahbration calculate releases of sush radionuclides usmg measured procedures should identify the speci0c equipment or ratios of these radionuchdes to those radionuchdes group t finstruments to which the rrocedures apply.
w hich are r o u t mely identified and measured.
Measurements should be made penodically to estabbsh Cahbranons of measurmg equipment should be and assure the contmued sahdity of the ratios used. Any perf rmed using reference standards certified by the National Bureau of Standards or standards that have reported data determmed by this method should be been cahbrated against standards ce rtified by the clearly identified.
National Bureau of Standards. Cahbration standards should have the necessars accuracy. stabihty, and range
- 11. Accuracy of Measurements required for their intended use.
a.
Errors in Measurements Cahbranons should generally be performed at regular mtervals. Frequency of cahbranon should be An estimate should be made of the error based on the reproduahhts and time stabdity of the associated with measurement of radioactne materials in sy stem. An instrument sy s' tem that gives a relatively ef0uents and sohd w ast es. Countmg statistics can wide range of readmgs when cahbrated against a given proude an estimate of the mmimum error mvolved in standard should be recahb rated at more frequent radioactmty a n aly se s.
Counting statisttes (e g.,
ntervals than one which gives measurements withir, a one.syma counting error) should be mcluded in the more narrow range. In many cases, it would be more records of measurements, since they proude a readdy appropriate to cahbrate measuring eqdpment before and calculable estimate of the statistical uncertamty due t after use m addition to or instead of calibration at c unung.
arbitranly scheduled mtervals. Cahbra:!on of measuring equipment before and after use permits detection of any The total or maumum error associated with the e r roneous readings or malfunctions that may have ef0uent measurement wd! include the cumulative errors occurred during use. Any momtonng system or resulting from the total operation of sampling and indmdual measurmg equipment should be recabbrated measurement. Because it may be sery difficult to assign or replaced whenever it is suspected of being out of 9 error terms for each parameter affectmg the fmal adiustment, excessively wom, or otherwise damaged and measurement, detailed statistical evaluations of error are not operatmg properly. Functional checks, i.e., routme not suggested. The objective should be to obtam an checks performed to demonst rate that a give n userall estimate of the error associated with g
g g
measurements of radioactne materials released in hquid g
g and gaseous efnuents and -
! waste.
that are not standards.
b.
Qua!ity Controls Conun uous radioactmty monitormg systems should be cahbrated against appropnate standards and Control checks and tests should be apphtd to the relationship estabbshed between concentration and the analy neal process by the ase of blind dyhcate monitor readmgs over the full range of the readout analy ses of selected ef0uent samples and by cross < heck device. Adequacy of the system should bejudged on the an inde pe ndent basis of reproducibuity, time stability, and sensitivity.
analy sis of selected samples with laboratory. Quahty controls should also be apphed to Penodic msemce cahbrations should also be performed the ennre sample. collection procedure to assure that to relate monitor " readings" to the concentranons representanve samples are obtamed and that samples are and/or release rates of radioactive matenal in the not thanged or affected poor to their analy sis because of morutored release path. These cahbrations should be handhng or because of their storage environment.
based on the resuhs of analyses for specific radionuchdes in grab samples from the release path.
- C21ibrations
- 12. Expression of Results of Measurements I n d mdual w ntten procedures should be a.
Units prepared and utih/ed for specific methods of cabbratmg radiological momtonng systems and measunng T he mformation and data on effluent releases equipment. Cahbration practwes for ancillary equipment meluded m report s to the Co mmission should be and systems are desenbed m Regulatory Guide 1.23, expressed m the umts given in Appendix B of this guide "Onsite Meteorological Programs," and elsewhere, ' and and reporteu :n the form gnen in paragraphs b and c O, where appropnate, they should be unhzed and inJuded below.
25 089 as a pa r t of the w nt ten procedures. Cahbration b.
Significant Figures procedures may be compdations of pubbshed standard practices or manuf acturers' instructions that accompany To avoid ambiguity, significant figures should imth.ned equQment or they may be specially wotten be used in recording the results of e f fluent 1.21 5
measurements. When several numbers are multiphed or mmmum sensit m t>
is 3 x 16' vC1/ml, the values dmded together, the result should be rounded off to as should be reported as <3.00E 09 few sigraficant figures as are present in the factor with the fewest signi6 cant figures When numbers are added
- 13. Radiolog!callmpact on Man or subtracted, the number with the fewest decimal places, not necessardy the fewest significant Ogures, puts Estimations of doses :o individuals and populations the hmit on the number of places that may justifiably be are recessary for sty assessment of the radiological carried in the sum or difference.
impact on man from the operation of nuclear power pbnts. Dose calculations should be made using the measured enluent and meteorological data and For the purpose of reporting in the format of Appenda B of this guide, numerical values should be acceptable dose models such as those provided in draft regulat or y guides for implementation of numerical rounded off to three figures.
guides. s To the estent that they are not inconsistent with the models provided in these draft guides, other c.
Numerical Values 8
dose models such as those given m WASH 1258 or thne used for calculating the estimated dose values R e sults of measurements, including given in the licensee's Environmental Report are also percentages, should be reported in external floating acceptable as bases for making dose calculations.
point form, usicg tne letter "E" to denote the exponent to the base 10. I-or e xample: Nc should appear as 2.00E+00, 0.00032 should appear as 3.20E44; 157.6 should appear as 1.58E+02; 2 67 should appear as The provisions and principles presented in
' 67 E +00'
\\ppendiceg A and B of this guide are acceptable to the Regulatory staff as bases for measuring and reporting of The term "not detected" should not be used. If radioactive materials in liquid and gaseous effluents and radioactivity in the sample (s) ts less than the maximum solid wastes from nuclear power plants, as we!! as for sensitmty of measurement, the value should be reported estimating doses to individuals and populations in tbc as less than the maximum senarrivity. For example,if the offsjte environs.
O 125 090 m,
APPENDIX A MEASURING RADIOACTIVE MATERIALS IN LIQUID AND GASEOUS EFFLUENTS AND SOLID WASTE lhis apperdix desenbes a momtormg program that eash change until it n show n that a pattern custs that is aaeptable to the Regulatory statt. The frequencies of can be used to predn t il e isotopw comp >sition of the e t ilue nt. In aJJition. r adn tius hJe anah ses shou lJ be samphng and analysis and the types of measurements desenbed are considered to be the mmimum acceptable.
perto ned when u mt in uous momtonng show s an lhls program shou:d be supplemented unexplainei sariance inun an estahlahed norrn which In U me casc%
w it h additional mea su r eme nt s breause of mdmdual may be mJNatne ot a change in the concentration and plan t design features or othe-factors. The need for wmpnition. lbe norm shoulJ be estabbshed as a range of readmgs t hat may be expected due to normal supplemental or modified programs is determmed on a operatmg conditions mcludmg anticipated operational case-bs -tase ben m c u r rens e s.
A.
GASEOUS EFFLUENTS 1he calibration of c o n t in u ous gross Contmuous mon 4toring should be conducted along r adio n t mt > momionng sy stems should he performed p r i n cipal gaseous ef fluent discharge paths. The by n o r malvmg agamst the results of specific r a d io n u clid e composition and quantities and radionushde a n a!) se s usmg estabhshed ratios of the concentranons of radioactive material in gaseous r espestne r adio n u s hde s to total a s t mt y. Whe n effluents shou!J be determmed and recorded. For the cahbratcJ m tlas f ashion, the p ro ss radioact nity penods of release. the records should also show, on a" meemements obtamed f rom contmuous monitors may hourly basis, the eustmg meteorological conditions of be used to Jeternune the total quantity of radioactivity wind direction. wind speed, and atmospherie stabiht) r ele ne d.
which are representatne of conditions at the pnneipa:
pomts of release (see Regulatory Guide 1.23. "Onsite b.
Itatch Releases M et eorological Programs" L I"' "' A l "" " I" 5 ' d '"C P C 5 ' * * '""" # " d > '
The smgle Pmsson (one sigma) error for discrete Jn anah sn shUu!d be made oI a lepIesCnI2 ne samf e oI measurements should be less than 50 percent for rdcase eaa planned release prior to dissharge to determme the rates at the design objectwe lesel. less than 30 percent at
'Jentity and quanti 3 of the panopal raJionusiides twice the design objectne release rate, and less than 20
'#IC"$0d' C""I * ""u s mo t or mg should also be percent at eight times the design objectne release rate.
conducted at appropriate pmnts to obtain inf ormation 1.
Fision and Actisation Gases on ihe quantity and panern of abunmal releases.
Dunng the release of gaseous wastes f.om the c.
se m,t,, a pomary system waste Fas holdup sy stem, the effluent momtor should t3e operating cnd set to alarm and to im those dnsharge pomis which hase input minate the automatic closure of the waste ga> discharge M two or more contributmg sourses mthm the plant, sahe before the hmit s specified m the t ec hmcal que momtonng of the major sources should be speaticatmns are exceeded pedorrned as a more sensitne ahernatne to momtormg a.
Continuous Releases the wmpmte ettluent stream when ha!k ddution results in consentratmns tno low f or accurate measurements.
For rea. tors w hah release gases contmuously, a The sen sit nit s of g r o ss radioactnity sample of the gaseous effluer t should be analy zed within one month atter the date of ininal crincahty of the menorements of lission and ' ovation gases. as a reactor and at least weekly thereafter to determme the muumum, shoulJ be suf fiuent to pernut measurement tion of the Atnity whah w ould result in idennt) and quanaty of the pnnapal radionuchdes
't a srp4 yy! air dose of id) ah Q i lu m&aJs due to gamma being released. A similar analysis of samples should be performed following each retuehng, process change, or k b Eliathn'at any location near cround iesel at or bty ond other occur re nt e that could alter the m ature of the site boundary and (2) an annud air dose of 20 mdhrads due to beta radianon at any locatmn near radionuthdes. For those processes or other condinom that chance siemfwantly te g wh n the average dady ground lew! at or bewnd the site boundar).
relene rate equak or exceeds that cross raJiontmt>
ilr w hen Ibe
] }le se n gj t ; g gi g gij 3dg s3 ftM eJ sb tit the glVe n in the t ec hnl.al s pe s n t'kJ I H ) n s I r a Jiiia.t ne ghes in represent atise sarnples i>l stead > 6 tate grim r adosastisits release rate increases b) pnrn W~ oser t! c preuous ste is, tate release rate at tin gr eo, enie,m 4,uM he such tha mmemranons of same pi.wer lew!h an andy sn 4>uu bt d4nclohowns 10 * / i u w menuohle 125 091 1 21 ?
2.
lodines when analyses were not performed, the average of the two adjacent data points spanrung this penod should be a.
Monitoring used. Rese estimates should be included in the efGuent records and reports; however, they should be clearly A representative sample from the principal identified as estimates, and the method used to obtain discharge paths should be drawn continuously through hese data thould be desenbed.
an iodine sampling device. ne sample collected in the device should be analyzed at least weekly for iodine-131.
b.
Sensitivity An analysis should also be made monthly or more often for iodine-133 and iodine-135' The sensitivity of analysis for radioactive material in particulate f rm should be sufficient to The results of these analyses should be used as permit measurement of a small fraction of the actmty the basis for recording, evaluating, and reporting the which would result in annual exposures of 15 millirems quantities of radiciodmes released during the sampling t any rgan f an m, dividualin an unrestricted area, penod. !n estimating releases for periods when analyses were not performed, the average of the two udjacent data pomts spanning this period should be used. These estimates should be included in the effluent records and
'I"I reports; however, they should be clearly identified as estimates, and the method used to obtain these data The release of tritium to the atmosphere should should be descnbed.
be determined for each be.ch released on an intermittent basis, and at least monthly for continuous releases.
ne sensitivity of the analysis of radiciodines should be sufficient to permit meastirement of a small The sensitivity of analysis of tritium released to fraction of the activity which wcc.id result in annual the atmosphere should be such that a concentration of exposures of 15 millirems to the thyroid ofindividuals in lor pCi/cc(of air)is measurable.
s unrestricted areas.
B.
LIQUID EFFLUENTS 3.
Particulates Dunng the release of radioactive wastes, the effluent a.
Monitocint control monitor should be set to laim and to initiate automatic closure of the waste discharge valve prior to A representative sample from the discharge exceeding the fimits specified in the technical paths should be drawn continuously through a specifications.
particulate filter. Measurements should be made on these filters to determme the quantities of radionuclides with Continuous monitoring should be provided for half-lives greater than 8 days that arr. released in liquid effluent releases. The radionuclide mixture of particulate form u the environment.
liquid effluents should be determined and recorded. For (1) The particulate filters shauld be changed the period (s) of release, the records should also show the and analyzed at least weekly f(,r the principal volume of water used to dilute the liquid effluent and gamma <mitting nuclides (at least for the radionuclides the cesulunt concentrations at the point (s)of release to barium-lanthanum.140 and iodine.131).When quantities unresdeted areas. If the effluent passes into a flowing of released radioactive materials are at low levels, ctream, data on the average flow of the stream during precluding accurate measurement of principal periods of effluent release should be collected and radionuclides, gross beta radioactivity measurements reported in the SupplementalInformation section of the shot.la ve made as a basis for estimating the quantity of report. (See Effluent and Waste Disposal Semiannual radioactive material released in the week.
Report, Appendix B.)
(2) A quarterly analysis for strontium 49 and strontium #0 should be made on a composite of all The single Poisson (one sigma) error for discrete filters from each sampling location collected during the measurements should be less than 50 percent for release qua rt er-rates at ine design objective level,less than 30 percent at (3) A monthly analysis for gross alpha twice the design objective release rate, and less than 20 radioactivity should be made on a composite of all filters percent at eight times the design objective release rate.
co!!ccted during the month from each sampling location.
1.
Batch Releases The results cf these analyses should be used as A representative sample of eech batch ofliquid the basis for recording and reporting the quantities of a.
radioactin material in particulate form released dunng effluent released should be saalyzed for the prmespal the sar,pling penod. In estimat% releases for $riodt gamma-emitting radionuclides.
'2'*
125 092
When o[vrational or other limitations preclude representative sample of the liquid ef nuent should be specitic pmma raJionuclide analysis of each batch, gross analyzed at least weekly to determme the identity and
~
radioactmty measurements should be made to estimate quantity of the pnncipal gamma <mittmg radionuclides the quannt) and concentrations of radioactive matenal being released. Arul) sis for other specific radAmuchdes released m the batch, and a weekly sample composited should be conducted m accordance with i above.
f rom proportional shquots from each batch releasej dunng the week should be enalyzed for the pnnetpal 3.
Sensitivity gamma-ernittmg radionuclides.
b.
A monthly sample c o m po sited from The sensalmties of analyses of radioactive nutenals proportional ahquots rom each batch released during in hquid efnuents should be sufficient to permit the f
the month should be analyzed for tntium and gross measurement of concentrations of IU'pCi/ml by gross ayha radioacuvity.
radiosa.mty measurements, 5 x 16' pCi/mi of each 5
'samma<mitting radionuthde,16 pCi/ml of each of the c.
A represe ntative sample from at least one dtssolved and entrained gaseous radionuclides, 10 '
representative batch per month should be analyzed for S
Ci/ml of gross alpha radioactivity, IU pCi/ml of dissobed and entra ned fission and activation gases' t ritium, and 5 x IU" pCi/ml of strontium 49 and d.
A quarterly sample composited from st ront ium.90.
proportional aliquots from each batch re: eased during the three month period should be analyzed for strontium 49 and strontium 40.
C.
SOLID WASTE The results of these analyses should be used as The total curie quantity snd radionuclide the basis for recordmg and reporting the quantities of radioactive material released in liquid effluents dunng composition of the sohd waste shipped offsite should be determined. Provisions should be made to monitor and the samphng penod. In estimating releases for a period t limit the curic quantity of matenal and the maximum when ans]yses were not performed, the average of th, two adjacent data points sparning this penod should be radiation lewl of each package of solid wane in order to used. Such estimates should be included in the effluent reduce radiation exposure to personnel and to meet the e
identified as estimates, and the method used to obtain records and reports; hov.ever, they should be clearly regulatory requirements of 10 CFR Part 71," Packaging f Radioactive Material for T ransp3rt and these data should be descnbed.
Transponadon of Radioactive Matenal under Certain Conditions" and of the Department of Transportation.
2.
Continuous Releases Monitoring of solid wastes in storage and preparatory to shipment should be performed to provide assurance that For continuous releases (e.g., secondary plant the radiation levels from waste m storage and m leakage), in addition to continuous monitonng, a transport do not exceed segulatory limits.
125 093 1 21 M
APPENDIX E EFFLUENT AND WASTE DISPOSAL REPORT Thu appendix desenbes the data and informatia (ach report (if appropriate), i.e., the MPC used in that should be mcluded in efnuent and waste disposal tccc dance with technical specifications and/or derived reports. The data and information should be reported in from the use of Notes to Appendix B 10 CFR Part 20.
a format sim21ar to that given in Tables 1 through 4 and the Supplemental Information sheet. Except as noted, 3.
Average Energy efnuent and solid waste data should be summanzed on a quarterly basis, although in some cases more detailed The release rate limits for fission and activation data may be needed. The need for reporting of gases in gaseous, effluents are usually based on the additional data to the Comnussion will be determined on average energy (E) of the radionuclide mixture in the effluent. The E value for the gamma and beta energies a case-by-case basis, per disintegration that is used should t included in the The reporting method includes the use of uniform report.
notation for numencal values and genera!!y defined 4.
Measurements and Approximations of Total guidance for reporting certain supplementalinformation.
Data from licensee's effluent and waste disposal reports Radioactisity are compded, and summary reports of nuclear power A summary description should be provided of the plant effluents are prepared by the Commrssion. The method (s) used to determine or measure total supplemental information reduces errors in processing radioactivity in effluent releases (total here means the and compJing of report data.
overall gross cune quantity). For example, gross radioactivity measurements (gross beta and/or gross in the report, a separate section should contain a gamma) may be used to approximate total radioactivity discussion of the radiological impact of facility in effluents, and/or analyses of specific radionuclides in operation on man. Calculations and estimates of selected or composited samples may be used to potential doses to indmduals and population doses determiae the radionuchde composition of the effluent.
should be summarized for the report (6-month) period, A summary descnption of the methods used for although in some cases more detailed data may be estimating overall errors associated witt rdioactivity needed. The need for these additional data to be measurements should also be provided.
re ported to the Commission is determined on a case-by-case basis.
5.
Batch Releases Meteorological data dunng continuous releases The report should provide information relating to should be subnutted m the format presented in Table batch releases ofliquid and aseous effluents which are F
4 A. ( Also see Regulatory Guide 1.23.) Data on meteoro-discharged to the environment. This information should hpcal conditions dunng batch releases should be reported include the number of releases, total time period for separately in the same format For the purpose of ttus batch releases, and the maximum, mean, and minimum guide, abnormal releases should be treated as batch time period of release.
releases, and the meteorological data obtamed during abnormal releases should be included m the batch release 6.
Abnormal Releases r e port.
The number of abnormal releases of radioactive A.
SUPPL EM ENT AL IN FOR MATION material to the environment should be reported. The total curies of radioactive matenals released as a result of 1.
Regulatory Limits abnormal releases should be included.
ne technical specification hmits for radioactive This information should be reported separately for m;tenals released in hquid and gaseous effluents should liquid and gaseous releases. The activity values should be mcluded in each report. If changes are made in also be included, as appropnate, in Tables I and 2.
h mit mg conditions of operation dunng the report Hourly meteorological data should be recorded for the gnod the appropnate hmits and dates should be penods of actual release and included in the quarterly mcluded.
summaries for batch releases in the format given in Table 4 A.
2.
Maximum Permissible Concentrations B.
GASEOUS EFFLUENTS Be maximum permissible concentrations (MPC) uwd to calculate permnsible release rates and Summary mformation should be reported in the ancentrations for air and water shou!d be included ir formats of Tables l A through IC. Table 1 A values
\\
l.21 10
shoulJ include the sums of au sources of release, i.e..
b.
Aseme release ute (uCixec) of radioatine routine and abnormal releases, continuous and batch, matenal in particulate form with half. lives greater than k clevated and ground level. The reported percent of d n s-technical specification hmits should be based on the c.
Per cen t of techmcal specihcation knut for combmed releases from multiple sources as given m the radmaane matenal in particulate form with half-Ines techmcal specifications. This also apphes to the releases greater than X day s.
from multucactor sites.
d.
Quarterly sums of total tunes for each of the particulate form determined :a be radionuchJes in For reactors that have techmcal specification umits released nased on anayses performed. (See B.I.d above for more than one puncipal point of release, separate and Tables I B and 10.)
Quarterly sums of total cunes of gross alpha
- r. anuchde data should be reported for each of these e.
release pomt s.
Data should be separated by release udioastinty determined to be released.
height,
i.e., elevated or ground level, and these data should be furt her subdivided by release mode, i.e.,
4.
Tritium contmuous or batch mode.(See Tables IB and 10.)
a.
Quarterly sums of total t unes of tntium Esnmates of the total error associated with certain determmed to be released in gaseous effluents.
total values should be provided m each report.(See Awuge release ute Mi%< > of trinurn\\
erant of appropnate tdmcal spedaan.on c
Table I A.) These error values should be the best effort or \\lPC imuts for tntium.
at an overall estimate of the errors associated with the total; m the report.
C.
LIQUID EFFLUENTS Report the following informatmn as indicated by Summary information should be reported in the Tables I A through IC.
formats of Tables 2 A and 2B. Table 2A values should mdude the quarterly sums of all releases of radioactive I.
Gases matenals m hquid effluents, i.e., routine and abnomul occurrences, continuous and batch. The reported a.
Ouartee sums of total curies of fission and percent of techrucal specification limits should be based activation gases released-on the tombmed releases f rom muluple sources as given b.
Average release rates (pCi/sec) of fission and in the technwat specificanons. This also apphes to the acuvation gases for the quarterly periods covered by the releases from.uulureactor sites.
report.
c.
Perce nt of techrucal specificat on hmit fo r Esnmates of the total error associated with certain releases of fissior and activation gases. This should be total values shoulJ be rrouded m each report. (See calculated in accordance with technical specification Tahle 2 A.) These enor uhies should be the best effort b mn s.
at an ose all esumate of the erron awocuted with the d.
Quarterly sums of total cunes for each of the totals m the report.
radionuthdes determmed to bc released, based on analyses of fission and activation gases. The data should Re port the followmg information, as inJicated bv be cateponzed by (1) elevated releases, batch and Tables 2 A and 2B.
continuous modes, and (2) ground. level relea;es, batch and contmuous modes. (See Tables I D and 10.)
1.
Nlised Fiwinn and Actisation Products Quanctly sums ol total curies of radmmne 2.
todines a
materul deleimmed to he relaased in liquid ef0uents Quarterly sums of tot al turies of iodme-131 (not meluJing intium, Jissobed and entumed gases. md a
released.
alpha-enaiting materul). (See Table 2 A.)
b.
Average release rate (pCi/sec) of iodme.131.
b.
Aserage conce nt ranon, (ufi!ml) of mixed c.
Per cent of techmcal specification hmit for insmn anJ astnation products K.l a above) released to indme 131.
umesins ted areas averaged mer the quartedy penods J.
Quarterly sums of total tunes of eash of the cme:cd by the report.
n o t o pes, iodme.131, iod me.13 3, an d iod me.13 6 Per:ent of a ppht able knut of ascuge determmed to be released. (See B 1.d above and lables conce nt r at ions relened to u mest uc t ed areas M. l.h I U '"d If I 2me) Inslude I b, knut used and the bases m the supplemental report mtornution.
L Particula tes d.
Q,urtc r h sono of intal cu ies foi each of the radionusl: des det ernuned to be r eleased in hqmd a Quarterly sum 3 of total tunes of raJioactne et tl ue nt s 'used on araly ses perf ormed Dat a should he "utenal m partisu; ate form with ha!f.Ines greater than x sep.u.n ea by n pe of rele.:se naide i.e.. connouous or dJs % de!CrIn!ned lo be released halt h. t h ! Jh!c 2 B l i 25 095
.n
2.
Tritium a.
Spent resins, filter sludges, enporator bottoms; b.
Oty compressible w a ste, contarrunated a.
Quarterly sums of total curies of tritium equiprnent, etc.;
detamined to be released in liquid effluents.
c.
Irrad ated components, control rods, etc.;
b.
Average concentrations (yCi/ml) of tritium d.
Other (fumhh description).
relewd in (Waid effluents to unrestricted areas, 2.
An estimate of the major nuclide composition iri the w rag d ever tte quarterly periods cowred by the categones of waste in D.! above.
report.
c.
Percent of applicable bmit of average 3.
The disposition of solid waste shipments. (Identify abou),i.e., percent of 3 x 16,unrestncted areas (C.2.b concer.trations rde: sed to the nurnber of shipm nts, the mode of transport, and pCi/ml. Include the limit the destination.)
and the bases in the supplemental report information.
4.
The esposition of irradiated fuel shipments.
3.
Dissolwd and Entrained Gases (Identify the number of shipments, the mode of transpart, and the destination.)
Q;,#.criy sums of total curies of gaseous a.
ra&oact.ie material determmed to be teleased in liquid Estimates of the total error associated with certain t tal values should be provided in each report. (See efDuent s.
b.
Average concentrations (pCi/ml) of dissolved Table 3.) These error values should be the best effort of an overall estimate of the errors associated with the and entrained gaseous radioactiv material released to unrestricted areas, averaged ever the qaarterly periods totals m the report.
E.
RADIOLOGICAL EtPACT ON MAN r nt t;chnical specification limit of average concentrations relea cd to unrotricted areas Potential doses to individuals and populations (C.3.b above). Include the ILnit used and ihe bases in the should be calculated using measured effluent and supplernental reprt information, meteorological data. A semiannual sumrrnry report d.
Quarterly sums of total curies for each of the should be submitted containing the fobowmg radionuchdes determined to be relea ed as dissolved and information:
entrajned gases in l'qi M effluer.?s.
1.
Total body and significant organ doses to 4.
Alpha Radioactisity indivkuals in unrestricted areas from receiving-water related exposure pathways.
Quarterly sums of total ctaies of gross 2.
Total body and skin doses to individuals exposed at -
alpha. emitting material determined to be released in the point of ma ximura offsite ground 4evel liquid effluents.
concentrations of radioar.tive materials in gaseous effluents.
5.
Volumes 3.
Organ doses to indi'sduals in unrestncted areas from radioactive iodine and adioactive mateitalin particulate Quarterly sums, m liters, ef total measured form from all pathways of expcsure.
a.
volume, prior to dilution, of iquid effluent reietud.
4.
Total body doses to individurds and populations in b.
Quarterly sums of total determir d volume,i.:
unrestricted areas from direct radiation from the facility.
liters, of dilution water t sed Junna, tne per;od of the 5.
Total body doses to the population and average report.
doses to inividuals in the population from all receiving-water-related pathways.
6.
Stream Flow 6.
Total body doses to the populatior, and average doses to individuals in the population from gaseous
%here the effluent passes into a flowing stream, effluents to a distsnce of 50 iniles from the site. If a data on the average flow of the stream during penods of significantly large population area is located just beyond effluent release should be collected and reported in the 50 miles from the site, the dose to this population group SupplementalInformation section of the report.
should be considered.
D.
SOLID WASTE F.
METEOROLOGICAL DATA The following information should be reported for The report should include the cumulative joint shipments of solid waste and irradiated fuel transported frequency distribution of wind speed, wind direction, from the site dt. ing the report period:
and atmospheric stabibty for the quarterly periods.
Similar data should be reported separatgly for the 1.
The semiannual total quantity in cubic meters and meteorological conditions during batch releases.,See the semiannual total radioactivity in cunes for the Regulatory Guide 1.23 and Tables 4A and 4B in this categories or types of waste. (See Tabk 3.)
appendix.)
\\
1.21 12
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Supplemental Information Facility Ucenwe 1.
Regulatory Umits a.
Fission and activation gases.
b.
lodines:
Particu!stes, half.hves >3 days 6
d.
laquid efiluents.
2.
himum Permissible Concentrations Provide the MPCs used in deternuning allowable release rates ur concentrations.
a.
Fissaan aad activation gases:
b.
lodines:
c.
Particulates, halt.hves >d daw u.
Liquid et tluent s-3.
Average Energy Provide the average energy (5 of the raJionuthde mature in teleases of tission and activation gases,if appheable.
4.
Measurements and Approximations of Total Radioactivity Proede the met hods used to measure or approumate the total radioactivity in ciquents and the methods used to determme radionushde composition.
6 a.
Fissnm and activation gases:
h.
lodmes:
c.
Pa rikulat es:
J.
Liquid etiluer.ts:
5.
Batch Releases Provide the following information relating to batch releases of radioactive materials m liquid and gaseous effluents.
a.
Uquid I.
%mber of batch releases:
Toial time penoJ tor hatch releases:
3.
Mimum time penod for a batch release:
4 Average time pern>d for batch releases 5.
M:nimum time penod for a hatch release-6 Aserage stream flow danng penods 01 releJse oI eItluent into a flowmg stream.
b.
Gaseous I.
Number of barch releases.
2.
Total time penod for batch releases:
3.
himum time penod for a batch release 4 Average time period for batch releases 5.
M.nimum time period for a batch release A
Abcormal Releases a.
Uquid I.
Number of re!e.ises 2.
Total astn1t> released 12 r-3 09"/
b.
Gaseous 1.
Num5cr of releases:
2 Total astnity released 1.21-13
TABLE 1A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (YEAR)
GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES l
Unit Csarter 1arter Est Total Error, %
j A, fision & active..on gases l
- 1. To:al release Ci E
E E
- 2. v.erage release rate for penod uCi/sec E
E
- 3. Pe: cent of Technical specitication lim.it Tc E
E B. Iodines
- 1. Total iodine-131 Ci E
E E
i
- 2. Averase release rate for penod uCt'sec E
E
[
- 3. Percent of techrucel spect5 cation lim:t
'1 E
E C. Particulates
- 1. Particulates with half-lises >8 davs Ci E
E E
I
- 2. Average re: case rate for period uCi/sec E
E
- 3. Percent et technical specitication limit Fc E
E
- 4. Gross alpha racioactmty Ci E j E
D. Tritium
- 1. Total release Ci E
E E
- 2. Average release rate for period uCi/sec E
E
- 3. Percent of technical spec 16 cation limit Tc E
E O
125 098 1.21 14
TABLE 1B EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (YEAR)
GASEOUS EFFLUENTS-ELEVATED RELEASE CONTINUOUS MODE B ATCH MODE Nucices Released U ni t Qua rt er Quarter Quarte r Guarter I. Fission gases k rypton45 Ci E
E l E
E k ry pton-85 m C
E E
E E
krypton-67 Ci E I E
t E
k ry pt on-88 Ci E
E E
E xenon-133 Ci E I E
E i E
xenUn-135 Ci E I E
E I E
xenon-135 m Ci E !
E E i E
xenon-138 Ci E i E
E E
Others (specify )
Ci E I E
E E
Ci E I E,_.
E E
Ci E
E_ _j E
E E
E unidentified Ci E
iQ Total for period Ci E
E 1 E
E
- 2. lodines
~
l iodine-131 Ci E
E i E
E iodine 133 C
E E i E
E iodine-135 Ci E
, _F; E
E Total for period Ci E
E E
E
- 3. Particulates strontium-89 Ci E
E E
E st rontium-90 i
Ci E
E i E
E cesium-134 I
Ci E
E E
E cesium 137 i
Ci E I E
E E
Ci
~~ l E
E E
barium lanthanum-140
^
Ci E
E I E
E Other: (sxcify i
_J i
Ci E
E i E
E Ci E I E I E
E umdentified l
Ci E
E E
E h
125 09?
1.21-15
TABLE 1C EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (YEAR)
GASEOUS EFFLUENTS-GROUND-LEVEL RELEASES CCNTINUOUS MODE BATCH MODE Nwctdes Reieased U nit Quarter Quarter Quarter Qi 1er
- 1. Fission gues kry pton-85 Ci E
E E
E k ry pt on,35 m Ci E
E E
E kry pton-67 Ci E
E E
E krypton 66 Ci E
E E
E xenon 133 I
Ci E
E E
E xenon 135 r
Ci E
E E
E xenon 135m i
Ci E
E E
C xenon 138 i
Ci E
E E
E Others (specify)
Ci E
E E
E l
Ci E
E E
E I
Ci E
E E
E unidentitled i
Ci E
E E
E Total for penod C
E E
E E l
E E
E iodine-133 Ci E
E E
E odine-135 Ci E
E E
E Total for perial Ci E
E E
E
- 3. Articula.
strontium 89 Ci E
E E
E st m ntium-90 Ci E
E E
E ces2um-134 Ci E
E E
E cesum 137 Ci E
E E
E banum-lanthanum 140
-Ci E
E E
E Others ( specify)
Ci E
E E
E C
E E
E E
Ci E
E E
E unidentified C:
E E
E E
O l.21 16
TABLE 2A SFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (YEAR)
LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Un+t Quarter Quarter Est. Total E rror. %
A. Fision and actintion products
- 1. Total ielease (not including antium, gases. alpha)
Ci E
E E
- 2. Average diluted concentration dunng period mci /ml E
E
- 3. Percent of apphcable limit E
E B. Tritium
- 1. Total release Ci E
E E
- 2. Average diluted concentraton during period mci /ml E
E
- 3. Percent of apphcable hmit
'A E
E C. Dissolved and entrained gases
- 1. Total release Ci E
E E
2 Average dduted concentraton dunng period uCi/ml E
'E
- 3. Percent of applicable hmit E
E D. Gross alpha radioactivity
- 1. Total release Ci E
E E
E. Volume of waste released (prior to dilution) liters E
E E
F. Volume of dilution uter used during period liters E
E E
\\25 \\D\\
1.21 17
TABLE 2B EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (YEAR)
LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE l Quarter Nuchdes Released Umt Quarter Quarter Quarter strontiume9 Ci E
E E
E strontium-90 C
E E
E E
cesium 134 Ci E
E E
E cesium 137 Ci E
E E
E iodine-131 Ci E
E E
E cobalt-58 Ci E
E E I E
cobalt-to Ci E
E h i E
iron 59 C
E E
E I E
zine-o5 Ci E
E E
E marganese-54 C
E E
E E
chronuum 51 Ci E
E E
E zirconium niobium-95 Ci E
E E
E molybdenum-99 Ci E
E E
E technetium-99m Ci E
E E
E barium-lanthanum 140 Ci E
E E
E cenum 141 Ci E
E E
E Other (specify)
Ci E
E E
E Ci E
E E
E Ci E
E E
E Ci E
E E
E Ci E
E E
E
_ unxientified Ci E
E E
E Total for period (above)
Ci E
E E
E xenon-133 Ci E
E E
E xenon-135 Ci E
E E
E O
l.21-18 125 102
TABLE 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (YEAR)
SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID W.biE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not ir adiated fuel) 6 rnonth E st T o tal
- 1. Type of waste unit p,,, c o g,, or, g
- a. Spent resins, tuter sludges, evaporator m'
E bottoms, etc.
Ci i
F
- b. Dry compressible waste, contaminated m'
L E
E equip, etc.
__. _C,i m
E.
- c. Irradiated components, control rods, etc.
Ci I
E
- d. Other (descnbe) m' E
Ci E
E
- 2. Estimate of maior nudide composition (by type of waste)
I' a.
I c
E E
b.
E c
E E
c.
c E
q E
d.
E a
E c
E 3.
Solid Waste Disposition Number of Shipments Mode of Transportation Destination B. IRR ADI ATED FUEL SHIPMENTS (Disposition)
Number of Shipments Mode of Transportation De sti na t ion Q
125 105 1.21 19
TABLE 4A HOURS AT EACH WIND SPEED AND DIRECTION a PERIOD OF RECORD:
STABILITY CLASS:
ELEVATION:
W+nd Fpeed Ingdd at 10m Levet Wind D eection 1-3 47 8-12 13 18 19 24
>24 TOTAL N
NNE NE ENE E
WNW NW NNW VARIABLE Total Periods of calm (hours):
llours of missing data:
a In the table, record the total number of hours of each category of wind direction for each calendar quarter. Provide similar tables separately for each atmospheric stability class and elevation.
O l.21-20 125 104
TABLE 4B CLASSIFICATION OF ATMOSPHERIC STABILITY Stabelity Pasqu.Il oe*
Temperature change classification cai.go,ies to.gr co witn me.gni e c/ toom>
Extremely unstablc A
25.0
<- 1.9 Moderately unstable B
20.0 1.9 to 1.7 Slightly unstable C
15.0
-1.7 to 1.5 Neutral D
10.0
.l.5 to.0.5 Slightly stable E
5.0 4.5 to 1.5 Moderately stable F
2.5 1.5 to 4.0 Extremely stable G
1.7
>4.0 a Standard deviation of horizontal wind direction fluctuation over a penod of 15 minutes to I hour.The values shown are average for each stabdity classification.
\\25
\\DS 1.21 21