Regulatory Guide 8.21

Health Physics Surveys for Byproduct Material at NRC-Licensed Processing and Manufacturing Plants

ML13350A223
Person / Time
Issue date:	05/31/1978
From:	NRC/OSD
To:
References
RG-8.021
Download: ML13350A223 (11)

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U.S. NUCLEAR REGULATORY COMMISSION May 1978 REGULATORY GUIDE

OFFICE OF STANDARDS DEVELOPMENT

REGULATORY GUIDE 8.21 HEALTH PHYSICS SURVEYS FOR BYPRODUCT MATERIAL AT

NRC-LICENSED PROCESSING AND MANUFACTURING PLANTS

A. INTRODUCTION

contains abundant information for use itn establishing radiation survey programs and selecting appropriate Paragraph 20.201(b) of 10 CFR Part 20. "Stand- methods, procedures. and equipment for their im- ards for Protection Against Radiation," requires that plementation (Refs. 3. 5. and 6).

each licensee make or cause to be made such surveys as may be necessary.for him to comply. with the Surveys'. arc a necessary supplmmint*r personnel regulations in Part 20. As used in Part 20, the term monitoring, which mn.asures indiVidtltal r`tion ex-

",survey" is defined as an evaluation or theradiation posures with devices worn b.I.lhe orkers'Refs. 3.

hazards incident to the production, use, release, dis- 5. 6. 8. and 9). . .. ..... . l:* ,

posal. or presence of radioactive materials or other sources of radiation under a specific sct of condi-

C. REGULATORY POSITION

tions. This guide identifies the types and frequencies of surveys that are acceptable to the NRC staff in Min this guide are accept- plants licensed by the NRC for processing byproduct material or manufacturing such material for distribu- ableýfiithe Nl*RC stuiff for estahlishing acceptable sur- tion. vey pr grams,.In accordance with thie as hlw as is Nso6b1y*achievable (ALARA) philosophy. -Man-

B. DISCUSSION

iffacttrs licensed by the NRC should have, a health p'h sics staff capable of developing and implementing

.survey programs as described below.

Surveys arc considered to be part of a 9-pretio, sive protection program established by L.licse's* I. Types of Surveys according to the philosophy and principl c.f Regula- tory Guide 8.10, "Operating Philosophy f "Z ain- I. I General Description taining Occupational Radiat' Exposures As Low As Is Reasonably Achievab niciplcs, methods, and Surveys performed in compliance with §20.201 of instrumentation for c * radiation.and con- 10 CFR Part 20 should include those necessary to

• tamination survr er ev f6ped early in the evaluate external cxposurC It) personnel, concentra- atomic energy togra n ave been discussed in tions of airborne radioactive materials in the facility, reports ofj l ronal, ouneiI on Radiation Protec- surface contamination levels, and radioactive tion ana ea CRP) (Refs. 1-3), the In- ternation bomic znergy Agency. (IAEA) (Refs.

4-8), and t jternational Commission on Radiolog- IThe word "survey." often used synonynmtusly with survcil.

lancc." ."monitoring.'" tr "'area monitoring." is uscd in this ical Protectioe"(Ref. 9). The health physics literature guide to connote the personal inspeclion of various localions in a facility using radioactive materials. with or without ,accompanying NRC-licensed processing and manufacturing plants are re- measurements, to determine the cfreetivenes', ot' o islures hit pln- ferred to in this guide as "'manufacturing plants.'" tect against radiation.

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evaluatinig the need for en seatyrewleion. WAh~naltint. 0C. M055. Atlentsin- O.'ect, ...... or ..It 0ftj,ts'en Cipot,

effluents from the facility. Environmental monitorinj urements of radioactive material concentrations in of effluents is beyond the scope of thi! air, at frequencies specified in Section C.2 of this guide.1 guide, for areas where operations could expose work- ers to the inhalation of quantities of radioactive mate- Radiation protection programs should include the* rial exceeding those specified in paragraph types of surveys discusscd below. 20. 103(b)(2). Special requirements for such monitor- ing may also be made a condition of the license.

1.2 Surveys or External Radiation Exposure Levels in Restricted Areas Air samples collected should be representative of the air in the workers' breathing zone. However, Radiation safety personnel' should survey loca-- when obtaining representative samples from the tions where individuals may be exposed to radiation breathing zone is not practicable, the samples should intensities that might result in radiation doses in ex- be obtained frotm a location at which the radioactivity cess of 10 percent of the limits of paragraph concentration in air is known to be greater than that

20. 101(a) of 10 CFR Part 20 in any calendar quartet of the workers' breathing zone. For example. sam- or where an individual is working with any unshieldcc pies taken outside the breathing zone are acceptable if sot'ce that produces a gamma or beta dose rate ex. the sampler head is located so that the concentration ceeding I mrad/h at I meter. of radioactive material in air at the location of the Preoperational. routine, and special surveys of sampler head is equal to or greater than the concen- these areas should be performed by the radiation pro- tration in the breathing zone.

tection staff as described in Section C.2 of this guide. When measuring the quantity of radioactive mate- Results of these surveys should be recorded as de- rial deposited on or in an air sample filter, the radia- scribed in Section C.3. In addition, workers should tion safety staff should include appropriate correc- monitor themselves if they are exposed to external tiotiq for alpha or beta absorption by the filter media radiation levels that could exceed any of the limits of and by material collected on the filter. Filter media paragraph 20.101(a). These surveys by workers used for the collection of alpha emitters should retain should consist of periodic instrument surveys during collected material on the filtcr surface. Overestimates work with radioactive materials. Workers should be of the volume of air that has passed through the filter properly trained to conduct such surveys. should be avoided by means of accurate calibration of Surveys are not acceptable for routine compliance the flow rate and by preventing or correcting for the with the personnel monitoring requirements of loss of flow due to the accumulation of material on

§20.202. However, in the event of accidental loss of the filter.

personnel dc.,imcttry data. e.g.. as a result of losing Breathing zone or general air sampling should be the dosimeter or chemical or physical damage to the cor.ducted while work is in progress unless the results dosimeter, the best alternative means of estimating of continuous sampling verify that the concentration the exposure may be to use survey data in conjunc- of radioactive material in the breathing zone is not tion with appropriate occupancy factors. In such likely to exceed 25 percent of the values given in 10

case, the estimate, including the survey data used.

CFR Part 20, Appendix B. Table I. Column i. The should be documented and retained indefinitely (see use of personal (lapel) samplers is acceptable for con- paragraph 20.401(c)(2)(ii)). Survey results supple- tinuous air sampling. The air sampling frequency, if ment personnel monitoring, when it is required, and not continuous, and the times selected for sampling tlhcy should be reviewed carefully by the Radiation should be based on the nature of the manufacturing Safety Officer in conjunction with personnel monitor- process involved and the probability that airborne ing records to identify potentially hazardous situa- radioactive material will be present. When assessing tions and to ensure that all personnel are adequately this probability is difficult, frequencies based on in- monitored.

formation given in Section C.2 and Table I of this

1.3 Measurements of Radioactive Material Con- guide are acceptable.

centrations in Air An air monitors may be needed to provide a warn- The radiation safety staff should perform mcas- ing signal that the concentration of airborne radioac- tivity has become unexpectedly high. For each room I However. the radiation safety program should include surveys or area where radioactive material is handled, the or records that indicate control of the quantities of radioactive ma- licensee should perform an analysis to determine terial released in air and water to unrestricted areas, as required b) whether an air monitor is necessar

y. Each analysis

10 CFR Part 20.

4 Reference to radiation safety staff or personnel in this guide is not intended to indicate that such staff necessarily consists ol I The term "air monitor" as used here refers to a device pro- more ihan one person designated as responsible for radiation safety, viding an air or particle collection system, a radiometric meas- The size and qualifications of the staff depend on the scope and urement system, a continuous recorder, a meter with preset alarm kind of manufacturing activities involving radioactive materials. capability, and an audible alarm system.

• 1

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should be kept available for inspection." An air present on a surface that can be transferred to a smear monitor should be provided if the analysis indicates test paper by rubbing with moderalc prcsture. Con- that it is likely that, before the air monitor alarm is siderable information is available to aid radiation pro.

actuated, accidental conditions could cause an intake tection personnel in the selection and use of' ir:stru- of radioactive material exceeding the intake that ments for performing surlface contamination surveys would result from inhaling such material for 4() hours appropriate to the radionuclides involved in manufac- at the concentrations specified in 10 CFR Part 20. turing plants (ReIs. I-10).

Appendix B, Table I. Column 1.1 Methods and instruments used in surface con- Workers should recognize that the principal func- lamination surveys should be sufficiently sensitive it)

tion of an air monitor is to alert personnel to take detect the nucl;des being monitored. Also. uniform immediate action to protect themselves from expo- methods for collecting and analting smear sample:.

sure to the unexpected release of airborne radioactive should he used over extended periods to time in order material. Inhalation exposures are in progress during to evaluate trends. Counting equipment used to the time between the release of the radioactive mate- analyze radioactive contamination on smear samples rial and the sounding of the alarm. Thus, every rea- should he properly calibrated and rnaintaii.ad and sonable effort should be taken to minimize this time should be capable of detecting the radiation from the period. In particular, the air inlet of the monitor smears. For example. smears containing how-energy should be located near the potential source of air- radiation emitters (e.g.. H-3. C-14. 1-125) should he borne radionuelides, preferably between the source analyzed with liquid scintillation or internal propor- and the workers. The use of long tubing or piping tional counters. Check or calibration source* should leading to the inlet should be avoided because of the be counted with each batch of smear samples.

high probability of alarm delay due to radionuclide The collection tif smear samples should gener- deposition on the interior walls of the tube or pipe.

ally be preceded by a rapid overall surveyv with a The dose to personnel may be reduced by selecting a portable. thin, end-window detector in order io low activity level setpoint for the alarm: however.

this may result in false alarms that weaken the work- a. Ensure that gross contamination levels are not ers' confidence in the monitor. These alternatives already too high for counting in sensitive equipment.

should be balanced io maximize safety. b. Minimize the chance for inadvertent spread tol contamination- by the smear survey or other activities The dose to personnel may also be reduced by pro- viding a high flow rate of air through the detection to be performed in the meantime, and chamber or filter. A device such as a limiting orifice c. Determine which areas require greater atten- that is intended to provide a constant flow rate should tion in smear testing.

not be used with an air monitor because it is more The instrument used should have a readout system important to maximize the volume of air drawn with a short time constant and should be equipped through the filter, thus reducing the time of exposure with earphones or an external speaker system.

before the alarm by using a higher flow rate, than to measure the concentration accurately. A standardized method for smear testing of a

1.4 Surface Contamination Surveys relatively uniform area should he used to aid in com- paring contamination at different times and places. A

Routine monitoring for radioactive contamination dry smear taken from an area of about 100 cnm- is that could be present on surfaces of floors. walls, acceptable to indicate levels of removable contamina- laboratory furniture, and equipment is a necessary tion.

part of the survey program. Failure to control surface contamination may result in unnecessary external or A diagram of each routinely surveyed area internal exposure of personnel to radiation. Although should be used for recording survey results. This pro- external radiation levels from radioactive contamina- cedurc will provide radiation safety personnel wilh a tion may at times be hazardous, the primary concern method for identifying trends as well as satisfying is to avoid internal exposure resulting from the intake regulatory requirements for survey records. The sur- of loose radioactive material by inhalation, ingestion. veyor will find it helpful to specify key locations ton or skin absorption. the survey diagram that are smear-tested at each sui- vcy and also to provide a space reminding the

1.4.1 Removable Contamination recorder to include:

For the purpose of this guide. "removable con- tamination" is that fraction of the contamination a. Contamination levels converted t) radioactiv- ity units in terms of equivalent alpha. beta, or gamma

6 Applicants should either provide thc name of the manufacturer and model number of the air monitor to be used or a copy of the emission per unit area, in units specified in 10 CFR

analysis that verifies that an air monitor is not required. Part 20.

To determine the quantity of radioactive material associated b. The make and model number of instruments

0

with this 40-hour exposure. multiply the concentration value specified in Appendix B to 10 CFR Part 20 by 4.8 x 10' mi. used in the survey and in counting the smear samples.

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c. The disintegration rate of each sample, staff and may be used without justification by the ap- plicant.

d. The background count.

e. All counting times, and 1.5 Protective Clothing and Equipment Contami- nation Surveys f. The name and date of the person making the evaluation and recording the results. Individuals working in areas where a potential for skin or clothing contamination exists should be pro- Provision should also be made on the diagram for vided with suitable protective clothing. If respiratory recording an instrument check with an appropriate protective equipment is needed to prolect against in- check or calibration source. halation of airborne radioactivity, the equipment should be used according to the instructions in Regu- The surveys discussed above are regularly latory Guide 8.15. "Acceptable Programs for Res- scheduled, conducted by radiation safety personnel, piratory Protection." Section 20.103 of 10 CFR Part and recorded on the survey diagrams. In addition. 20 specifies monitoring requirements when protection more frequent. informal radiation surveys should be factors are assumed to be provided by the use of res- conducted by the radiation workers themselves; they piratory protection devices.

need not be recorded. For example. a contamination Protective clothing and equipment should he sur- survey can be made by collecting a smear sample and veyed for contamination before the worker leaves the holding it against a thin (less than 2 mg/cm-) end- window detector while the detector is in an area restricted area. Since airborne radioactivity from con- taminated protective clothing is likely to be produced where radiation levels are less than about 0.05 by dislodging any absorbed radioactive particles dur- mrem/h. At these levels, any appreciable surface con- ing removal, fixed station monitors should also be tamination can be detected by simply holding the de- available in clothing change areas to survey clothing tector in a fixed position and moving the smear sam- before it is removed. In addition, suitable areas ple close to and away from the detector several times should be provided for surveying protective clothing and noting the meter readings. This method may be and equipment before storing them for further use or used for the majority of radionuclides processed in for decontamination and laundering.

manufacturing plants (excluding alpha and very low- energy beta emitters). When protective clothing contamination levels ex- ceed preselected limits, workers should be instructed Part 20 of 10 CFR d=oes not specify limits for to take care to avoid dispersal of contamination and surface contamination. Each applicant may propose to report the situation to the Radiation Sat'cty Office.

and justify what removable surface contamination A member of the radiation safety staff should then limits will be allowable before decontamination will survey and supervise any necessary decontamination be performed in each work area. These limits should or clothing disposal. The applicant may propose and be based on the need to avoid transfer of significant justify protective clothing contamination limits con- amounts of contamination to unrestricted areas and to sidered adequate for each restricted area; the limits maintain exposures as low as is reasonably achieva- given on line 4 of Table 2 are acceptable to the NRC

ble. The contamination limits for restricted areas pre- staff for use without justification by the applicant.

sented in Table 2 of this guide are acceptable to the NRC staff and may be used without justification by Contamination levels observed and procedures fol- the applicant. lowed for incidents requiring special surveys and de- contamination should be recorde

d. The record should

1.4.2 Fixed Contamination include the names of persons surveyed, a description of prior work activities, the probable causes, steps For the purposes of this guide, "fixed contami- taken to reduce future incidence of contamination.

nation" is defined as radioactivity remaining on a times and dates, and the surveyor's signature. This surface after repeated decontamination attempts fail information may be entered in a logbook. Individtial to significantly reduce the contamination level. Since worker surveys of themselves need not be recorded most detectors respond to both removable and fixed unless the limits on line 3 of Table 2 are exceeded.

contamination, limits should be based on total con- However, the radiation safety staff should maintain tamination. A total contamination survey, using in- daily surveillance to ensure that the workers continue struments suitable for the radionuclides involved. their own personal contamination surveys. Results of should be conducted simultaneously with each re- radiation safety surveillance should be recorded.

movable contamination survey. The applicant may propose and justify what total contamination limits In restricted areas with little potential for surface will be allowable for both restricted and in-plant un- contamination, personal clothing is often worn be- restricted areas before decontamination will be per- neath protective clothing. Such personal clothing formed. The limits appearing on line 2 of Table 2, multiplied by a factor of 5. are acceptable to the NRC

should be surveyed by the wearer before he or she leaves the restricted area. (However, this is neither U

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practicable nor necessary for employees working with personnel dosimetry reco rd. Complete records should only submicrocurie quantities of tritium or carhon- be maintained (if each incident of this nature.

14.) When personal clothing contamination levels ex- Since manufacturing plants often process 1;.rge ceed preselected limits. workers should be instructed to report the situation to the Radiation Safety Office. quantities of radioactive material. bioassay progratns A member of the radiation safety staff should then may be required. Acceptahle features of such pro- survey and supervise any necessary decontamination grams arc published in Regulatory Guides X.9.

or clothing disposal. The applicant may propose and "Acceptable Concepts. Models. Equations. and As- justify personal clothing contaminatio-i limits; the sumptions for a Bioassay Prgram.'" and M.I I. "'Ap- plications of Bioassay forI Uranium.'" or issued by the limits given on line 3 of Table 2 arc acceptable to the Radioisotopes Licensing Branch.

NRC staff and need not be justified by the anplicant.

Records should be maintained in the same manner as 1.7 Surveys of Equipment Prior to Release to Un- those for protective clothing contamination. restricted Areas For individuals whose work is conducted in re- Surface contamination:. Ntrcys should be con- stricted areas with a potential for high surface con- dueled for both removable and fixed contamination lamination levels, complete clothing changes are before potentially contamiatated equipment is released normally provided. In this case, personal clothing from restricted to unrestr:Ltcd areas. If contamination should be stored outside the restricted area. Surveys is detected, decontamination procedures should be of personal clothing are not necessary, provided the repeated until additional efforts do not significantly area in which the clothing is stored is surveyed as reduce contamination levels. The applicant may pro- discussed in Section C. I.4 of this guide and the sur- pose and justify total and removable contamination vey results are below the limits adopted ror in-plant limits below which uncontrolled release of equipment unrestricted areas. Particular attention should be paid is permitted. The limits given for unrestricted areas to surveying the body. hair. bottoms of the shoes or on line I of Table 2 are acceptable to the NRC staff feet. and the hands after removal of protective cloth- and need not be justified by the applicant.

ing and to washing before donning personal clothing.

1.6 Personal Surveys 1.8 Drinking WVaier Individuals whose duties require work in restricted Although it is highly unlikely that significant areas where radioactive contamination of body sur- internal exposures will result from ingesting drinking faces is probable should also survey all exposed areas water near worl. areas (Ref. 4). any water fountains of the body after showering and before donning per- in these areas should be smear-tested regularly, and sonal clothing or leaving the restricted area. Workers the water should be sampled and analyzed at least should be required to report the detection of contami- quarterly. Also. surveillance should be included in nation on the body to the Radiation Safety Office. the radiation safety program to ensure that workers Decontamination attempts, under the direction of observe rules to prevent ingestion tof radionuc;ides.

Radiation Safety Office personnel or a medical con- e.g.. rules pertaining to eating. drinking, or smoking sultant, should be repeated until (I) such attempts in work areas or while wearing potentially contami- cease to effect significant reductions or (2) such at- nated clothing, storing foods in work areas, or pipet- tempts threaten to damage the skin.' When decon- ting by mouth.

tamination attempts are terminated, there should be no further concern if the residual contamination does 1.9 Surveys of Packages Received and Packages not exceed preslected levels since the contamination Prepared for Shipment would no longer present a significant ingestion External radiation surveys and smear tests of ex- hazard. Such levels may be proposed and justified by ternal surfaces of packages received or packaged lfor the applicant: the limits given on line 5 of Table 2 are shipment should be carried out near the receiving or acceptable to the NRC staff and need not be justified packaging point to avoid inwarranted radiation expo- by the applicant. If residual contamination exceeds sures and inadvertent contamination of personnel or the selected limits, the affected individual should be the facility. Surveys and required labeling must com- released but periodic surveys should be made until ply with regulatory requirements (see §§20.205.

the limits are no longer exceeded. The resulting dose 32.19. and 32.70 through 32.74 of 10 CFR) and should be determined and entered in the individual's specific license conditions. Delivery of packages within the plant should also he monitored when car- ried by personnel rather than mechanical conveyors.

0 Decontamination attempts without the licensee'* medical con- Surveys should be made to determine when carts sultant present should be restricted to washing with mild soap and rather than hand carrying should be used. Packages water or it) decontamination procedures previously agreed upon by the medical consultant. If such attempts do not reduce the con- containing significant amounts of radioactive mate- lamination to acceptable levels. the aid of a physician should he rials should not be surveyed or opened until the con- obtained. tainers have been placed in the appropriate protective

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facility such as a radiological-type fumne hood or hot ity. and accuracy. Each source used for calibration cell. should be certified by the supplier as recommended No packages should be released for shipment or by the International CUMmission on Radiological transfer to tither users unless contamination levels of Units and Measurements (Ref. II) and .,nould be cor- internal sources or devices have been tested and cer- rected for decay as of the day on which the source is tified to meet the criteria of paragraph 35. 14(b)(5) for used for survey instrument calibration. All decay cor- Group VI products or license conditions for other rections should be included in the radiation safety products as provided in §35.14 or in the manufac- records system. A posted graph for each source is turer's license. Also. no packages may be released convenient, helpful in avoiding calculational errors.

for shipment or transfer when external radiation or easily available for inspection, and acceptable for ob- surface contamination levels exceed limits set by the taining source intensity within the required accuracy.

Department ot Transportation in Title 49 of the Code Survey instrument maintenance and calibration of Federal Regulations. Ext,.rnal radiatiin and con- should be performed at least annually. Also. a calih- tamination levels should be maintained ALARA. ration verification in an appropriate radiation field for I. 10 Checks on Posting of Caution Signs, Labels, at least one point near the midrange of each scale in Signals, Controls, and Notices to Employees use and a battery check are necessary at least as often The radiation safety staff should perform surveil- as every 3 months in order to ensure the accuracy and lance at least weekly to ensure that signs. labels, sig- operability of portable radiation survey instruments.

nals. other access controls. and required Notices to In addition, long-half-life :onslancy check sources Employees. copies o0 licenses, and tither items are should be used to check the continued accuracy of all properly posted. legible, and operative, as required instruments each time they are used.

by 10 CFR Parts l0 and 20 or license conditions. 1.13 Surveys of Protective Clothing Before and Radiation alarm signals and access controls should be After Laundering tested to verify proper operation under both the nor- mal and abnormal conditions that might be expected All garments with contamination levels exceeding t) occur. Care should he taken to minimize exposure tht,-, g.ven on line 3 of Table 2 should be either dis- to) personnel who are conductin. the tests. Any signs. pwed ,4, as radioactive waste or properly surveyed.

labels, or notices found ito be missing should be packaged. and labeled and sent to a laundry licensed promptly replaced. Temporary signs. signal-. or bar- to process and handle radioactively contaminated riers logether with appropriate worker notification clothing.

and instruction may be used in the interim when Each garment returned from a licensed laundry items as specified in 10 CI-R Parts 19 and 20 are not should be monitored before use. If contamination available, hut acceptable corrections should be pro- levels on the garment exceed those given on line 4 of vided as soon as practicable. Table 2. the garment should not be used.

1. II Leak Tests of Sources 1. 14 Ventilation Surveys Leak testing of sealed sources must be carried out in accordance with the terms and conditions of the Radiation safety personnel should conduct surveys manufacturer's materials license. Also. as provided monthly (or more frequently) to determine the face in paragraph 35.14(b)(5). sealed sources containing velocity of air at the entrance of radiological-type fume hoods in use to protect workers against the a. More than 100 microcuries of a byproduct ma- hazards from unencapsulated radioactive materials.4 ierial with a half-life of more than 30 days (except Such measurements should be made by using a prop- iridium-192 seeds encased in nylon ribbon) or erly calibrated thermoanemometcr or velometer to de- b. More than 10 microcuries of an alpha emitter termine whether the airflow has been reduced to un- acceptable levels by filter loading or the malfunction of blowers, fans, etc. The minimum average face must be leak tested for contaminalion or leakage at velocity for a fume hood with the sash in the operat- interv'als not to exceed 6 months unless a different ing position or for an opening in a special enclosure '4 I

interval is specified for a particular manufactured should be 150 ftlmin. as determined from at least five source under the provisions of paragraph 32.74(b). different measurement points.

Further provisions and exceptions to leak-testing re- quirements are established in paragraphs 35.14(b) Corrective action should be taken as soon as possi- I

and 35.14(c)( I ). ble when the face velocity is found to be deficient.

Work should be terminated if the average face veloc- I. 12 Calibration of Radiation Safety Instruments ity falls below 100 ft/min.

Portable survey instruments should be calibrated to Where filtered exhausts are employed, devices such as U-tube within =20 percent at a minimum of two points neir manometers or the equivalent sho~uld be pr(vided to indicate the the lower 25 percent and upper 25 percent readings of pressure drop across the filters. thus affording an early indication each scale in order to examine readability. operabil- of airflow loss at cnctioures.

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In addition to these surveys. each enclosure should 1. 16 Surveillance be equipped with a device that measures pressure drop across the hood filter. Workers should be in- 1. 16.1 Surveillance by Individual Performing structed to maintain daily checks of these devices and Surveys to notify radiation safety personnel when the pressure The term "surveillance." as used in this sec.

drop exceeds a preset level. tion. refers it) observations of radiological ,,orking A thermoanemometer or velometer should be used conditions in restricted areas made by the person ,.lho at least semiannually to determine the number of air performs the routine radiation and contamination sur- veys. Such surveillance, one of the most important changes per hour provided by the ventilation system in each room in which work with uncncapsulated aspects of a radiation protection program. allows health physics personnel to acquire detailed knol- radioactive materials is conducted. A minimum of six edge of each operation in order t) (1) identify wavs changes per hiur should be provided.

of preventing or minimizing exposures. (2) select ap- propriate times for making health physics.n .i.as- urements. and (3) adequately prepare for emergency

1. 15 Surveys in In-Plant Unrestricted Areas conditions. Health physics personnel .hould he suffi- ciently familiar with each operation to explain it in Unrestricted areas should be surveyed periodically detail, to describe potential hazards and the precau- to ensure that radiation and radioactive material are tions taken to minimize exposures. and to discuss adequately confined in restricted areas, except in how this knowledge of the operation has influenced cases where these materials must be transported be- the selection of appropriate times for performing tween areas. Such transportation should be surveyed health physics measurements.

or planned with the radiation safety staff. 1.16.2 Regular Inventory of Radioactive Material.

1. 15.1 Surface Contamination Surveys Audit of Procedures,. and Instruction of Personnel Removable surface contamination surveys in un- The surveillance program inc'udes:

restricted areas should be performed and recorded at frequencies consistent with the potential for spread- a. Regular inventory of radioactive materials and ing contamination but not less frequently than quar- their locations.

terly. With the exception of lunch rooms and snack b. Frequent audits of radiation safely procedures bars, random smear testing of floors and furniture is and the uses and amounts of material in process com- adequate. In lunch rooms and snack bars. equipment pared to licensed possession limits, and should also be surveyed. If such surveys reveal that c. Discussions with personnel to ensure their radioactive contamination is being transferred out of continued awareness ot safety procedures and the ap.

restricted areas, immediate corrective action should propriateness of their instruction and training for the be taken to eliminate such transfers, and decontami- tasks they are performing.

nation efforts in the unrestricted areas should be re- peated until it is evident that subsequent efforts These surveillance activities may be condu.tcd would not significantly reduce contamination levels. during the performance of other survey measurements If contamination is found in unrestricted areas, sur- or tests. The radiation safety staff should conduct veys should be performed on a more frequent sched- surveillance inspections in a manufacturing plant at ule as necessary until the source of contamination is least weekly. The surveillance should be perf'ormed ascertained and corrected. The applicant may propose at least annually by the Radiation Safety Officer in contamination levels. following decontamination ef- the presence of a management representative such as forts described above, for in-plant unrestricted areas. the plant manager to provide management with an The limits given on line I of Table 2 are acceptable awareness of the nature and importance of activities to the NRC staff and need not be justified by the conducted for personnel protection and plant safety.

applicant.

2. Frequency of Surveys

1.15.2 Radiation Surveys The frequency of routine surveys depends on the Radiation surveys in unrestrictcd areas should be nature. quantity, and use of radioactive material%, as performed and recorded at frequencies consistent well as the specific protective facilities, equipment.

with the types and quantities of materials in use but and procedures that are designed to protect the not less frequently than quarterly. These surveys worker from external and internal exposure.

should be made in areas adjacent to restricted areas and in all areas through which byproduct materials Generally. surveys should be performed before are transferred and temporarily stored before ship- radioactive materials are used in a new facility in ment. Dose rates in these areas shctld be evaluated order to establish a baseline of background radiation to determine whether they comply with the require- levels and radioactivity from natural sources, struc- ments of §20.105 of 10 CFR. tural components of the facility (including radon and

8.21-7

thoron emanation rates and concentrations), and any that licensees maintain records in the same units used already existing operations with radiation sources in in Part 20. Thus, external exposure rates should be nearby rooms or facilities. These baseline surveys recorded in estimated maximum dose equivalent units should be performed under the various conditions of to relevant parts of the body as specified in 10 CFR

containment, shielding design, and process heat loads Part 20. Air concentration measurement results in to be expected under manufacturing conditions. Sur- units of j.Ci/ml and surface contamination measure- veys of simulated process operations with ment results in units of dpm/l00 cm 2 or .Ci/100 cm2 nonradioactive reagents or smaller amounts of (or as in §20.5) should be recorded.

radioactive material should also be performed where appropriate to establish the performance of protective Record retention requirements are given in the reg- ulations cited above. Paragraph 20.401(c)(2) requires equipment and procedures before full-scale produc- tion using any new or untested facilities or processes.

that survey records be preserved for 2 years, except that records of air monitoring and (in the absence of Surveys should be repeated as soon as process op- personnel monitoring data) records of surveys to de- erations begin with normal levels of radioactive mate- termine external radiation dose are to be maintained rial and with all potentially exposed workers present until the NRC authorizes their disposition.

and conducting their job functions. Surveys should also be conducted after any significant changes in the Records may be maintained in logbooks or on spe- conditions that existed at the time of the most recent cial forms as long as they are clear, legible, under- survey, including changes in the quantities of standable. and authenticated by authorized personnel.

radioactive material handled or in protective equip- The signature of the person making the record and the ment and procedures. date of the signature should be on the same page as the rec9rd and should immediately follow each record Routine and repetitive surveys are necessary to entry. Either the original or a reproduced copy or mi- control the location of radioactive materials within croform (duly authenticated) may be maintained to handlingsystems and to ensure the continued integ- meet the storage requirements of §20.401.

rity of protective equipment and procedures. Surveys are also necessary for procedures in which sealed sources are handled outside shielded container

D. IMPLEMENTATION

For operations involving materials in gas. liquid, or The purpose of this section is to provide informa- finely divided forms, the survey program should be tion to applicants and licensees regarding the NRC

designed to monitor the continued adequacy of con- staff's plans for using this regulatory guide.

tainment and control of the materials involved.

Except in those cases in which the applicant or The minimum acceptable frequencies of surveys licensee proposes an acceptable alternative method, for manufacturing plants are given in Table I. The the staff will use the methods described herein in NRC staff considers the frequencies established in evaluating an applicant's or licensee's capability for Table I to meet the requirements of §20.101 of 10 and performance in complying with specified por- CFR. tions of the Commission's regulations after January

3. Records of Surveys 2, 1979.

Reference should be made to §§20.401 and 30.51 If an applicant or licensee wishes to use the method and Parts 31-35 of 10 CFR for rccordkeeping re- described in this regulatory guide on or before quirements regarding surveys related to the receipt, January 2, 1979, the pertinent portions of the applica- use, packaging, transfer, export, and disposal of by- tion or the licensee's performance will be evaluated product materia'l. The regulation in §20.401 requires on the basis of this guide.

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11M -ý

0

TABLE I

ACCEPTABLE FREQUENCIES FOR SURVEYS

Amounts (Curies) In Process at Any One Time Within Any Room Requiring Surveys External Radiation Surveys Radionuclide Group (nuclides with asterisks only)* Air Sampling"* Surface Contamination Weekly Monthly Weekly Monthly Quarterly Weekly Monthly Quarterly

1: H-3. C-14. F-18.1 K-42.0 If point source of ac- If point source of ac- <I ý1oo <10

Cu-64.° Tc-99m." In- tivity could cxcccd 50 tivity could exceed <10 <z 100

113m" mradh at I meter 0.5 mrad/h at I meter

!1: Br-82. Cr-51.° Fc-55. I So. <0.1 .10 <1

<ID

1-123." Hg-1971 <I

HiE: S-35. Au-198. Ca-47. 0.1 0."01 <0.01 >!0. 1 <0.1

1-132, Cc-141, Mixed Fis- <0.1 sion products., Sr-85. La-

140. Nb-95. Zn-65, Co-

58." Fe-59.° Na-24., Co-

57., Se-75.1 MN-99"

IV: Hf-181. Pm-147. P-32.* o.01 -0.001 <0.001 -. 0.1 - 0.01 <0.01 Ra-140." Th-234. Kr-tS. <0.01 0.1 lr-192." CI-36. Y-91. Ta- M82.Ca-45. Sr-X9. Cs-137.

'0 Co-60.1 Cc-144.° 1-126.

Eu-154. 1-131.* 1-125."

Tm-170. Na-22." Mn-54."

Ag-Ii0m.*iHg-203.° Rn-

222.' Sn- 1131 V: Tc-99.1-129, Ru-106 ,0.001 -:10-1 <0.001

<0.01

<0.011 VI: Ra-223. Po-210. Th-227. 10-1 < lo- -0.001 - .10_11 <10-"

Sr-90. Pb-210. Cm-242.

0.001 U-233 VII: Sm-147. Nd-144. Ra-226." 710' >1' * 0t o-, to- Cm-244, Ra-229. Pu-241 to0,

VIII: Am-233. Am-24l.* Np- 7 10-,  ::. 1-T <10- z to-- '

10-8t <i0-'

. 10-'4

237. Ac-227. Th-230. Nu-

2412. Nu-2311, Pu-240. Pit-

239. Th-22It. Cf-252

'Nucides Aith asterisk% are thoic mitre likely wrequire externnal radiation surkey%.

• As~uming cointifloutiti %ampling i% unneeev..ary (see Sectioin C. 1 3.

TABLE 2 LIMITS FOR REMOVABLE SURFACE CONTAMINATION IN MANUFACTURING PLANTS*

Type of Radioactive Material**

Alpha Emitters Low-Risk High Lower Beta or X-Ray Beta or X-ray Toxicity Toxicity Emitters Emitters Type of Surface (.Ci/cm 2) (/CI/cm2) (jACI/cm 2) (/Ci/cm 2)

I. Unrestricted areas 10*1 10*1 10,3 10.4

2. Restricted areas 101, I0"3 10"3 10.2

3. Personal clothing I0"" 10"4 10"' 10"1 worn outside of restricted areas

4. Protective clothing worn 10.4 10*3 l0"3 103 only in restricted areas

5. Skin 0Ils 10.- 10"'- 10"3

• As adapted from Table I of Reference 4. Averaging is acceptable over inanimate areas of up to 300 cml or. for floors, walls, and ceiling. 100 cm-. Averaging is also acceptable over 100 cm: for skin or. for the hands. over the whole area of the han

d. nominally

300 cm'.

-High toxicity alpha emitters include Am-243. Am-241. Np-237. Ac-227. Th-230. Pu-242. Pu-238. Pu-240. Pu-239. Th-228.

and Cf-252. Lower toxicity alpha em*Uers include those having permissible concentrations in air greater than that for Ra-226 (s) in t0

CFR Pan 20. Appendix B. Table I. Column I. Beta or x-ray emitter values are applicable for all beta or x.ray emitters other than those considered low risk. Low-risk nuclidcs include those whose beta energies arc <0.2 MeV maximum. whose gamma or x-ray emission is less than 0. 1 Rth at I meter per curie, and whose permissible concentration in air in 10 CFR Part 20. Appendix B. Table I

is greater than 10-' pCilml.

Note: Contamination limits for unrestricted areas in this table are considered to be compatible in level of safety with those for release of facilities and equipment for unrestricted use. as given in Regulatory Guide 1.86. 'Termination of Operating Licenses for Nucleur Reactors." and in "Guidelines for Decontamination of Facilities and Equipment Prior to Release for Unrestricted Use or Termination of Licenses for Byproduct. Source. or Special Nuclear Material." which is available from the Division of Fuel Cycle and Material Safety. Office of Nuclear Material Safety and Safeguards. U.S. Nuclear Regulatory Commission. Washington. D.C. 20555.

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REFERENCES*

I. National Commission on Radiological Protection 9. International Commission on Radiological Pro- (NCRP) Report No. 8. "Control and Removal tcction (ICRP) Publication 12. "General Princi- of Radioactive Contamination in Laboratories." ples of Monitoring for Radiation Protection of December 15, 1951. Workers," Pergamon Press. 1969.

2. NCRP Report No. 9, "Recommendations for 10. AAPM Monograph No. 1. '-Biophysical Aspects Waste Disposal of Phosphorus-32 and Iodine- of the Medical Use of Technetium-99m.'" J.G.

131 for Medical Users." November 2. 1951. Kereiakes and Karen R. Corey. Editors (avail-

3. NCRP Report No. 10. "Radiological Monitoring able from American Association of Physicists in Methods and Instruments," April 7. 1952. Medicine, Dr. James G. Kereiakes. E555 Medi- cal Sciences Building. University of Cincinnati.

4. International Atomic Energy Agency (IAEA) Cincinnati, Ohio 45267), 1976.

Technical Report Series No. 120. "Monitoring of Radioactive Contamination on Surfaces." II. International Commission on Radiation Units

1970. and Measurements (ICRU) Report No. 12. "Cer- tification of Standardized Radioactive Sources."

5. IAEA Safety Series No. 38. "'Radiation Protec- September 15. 1968.

tion Procedures," 1973.

6. IAEA Safety Series No. I, "Safe Handling of Radionuclides." 1973 Edition. Code of Practice Sponsored by the International Atomic Energy Agency (IAEA) and the World Health Organiza- IAEA rcports may be obtained from UNIPUR. Inc.. P.O. Box tion (WHO). 1973. 433. New York. N.Y. 10016.

7. IAEA Technical Report Series No. 133. "*Hand- ICRP reports may be ob;,incd from Pergamon Press. Maxill House. Fairview Park. Elmsford. Neu York 10523.

book on Calibration of Radiation Protection Monitoring Instruments." 1971. ICRU reports may be obtained from the International Commission on Radiation Units and Measurements. P.O. Box 30165. Wash-

8. IAEA Safety Series No. 25. "Medical Supervi- ingtn,, D.C, 20014.

sion of Radiation Workers," sponsored jointly NCRP reports may be obtained from NCRP Publication.%. P.O.

by IAEA. WHO, and ILO. 1968. Box 30175. Washington, D.C. 20014.

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