ML20128M197

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Part W - Radiation Safety Requirements for Wireline Svc Operations & Subsurface Tracer Studies
ML20128M197
Person / Time
Issue date: 11/20/1984
From:
NRC
To:
Shared Package
ML20127B584 List:
References
FRN-50FR13797, RULE-PR-19, RULE-PR-39 AB35-1, NUDOCS 8505310602
Download: ML20128M197 (15)
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PART W - RADIATION SAFETY REQUIREMENTS FOR WIRELINE SE W.1. Purpose TRACER STUDIES W.2 Scope-.

W.3 ~ Definitions W.4 Prohibitions W. 101 Limits on levels of radiation W. 102 Storage precautions W. 103 Transport precautions W.' 104 Radiation survey instruments W. 105 Leak testing of sealed sources W. 106 Quarterly inventory W. 107 Utilization records '

W. 108 Design, performance and certification criteria for sealed sources used in downhole operations W. 109 Labeling W. 110 Inspection and maintenance W. 201 Training requirements W. 202 Operating and emergency. procedures W. 203 Personnel monitoring W)301 Security

  • W. 302 Handling tools W. 303 Subsurface tracer studies W. 304 Particle accelerators W.401 Radiation surveys W. 402 Documents and records required at field stations W. 403 Documents and records required at

-temporary jobsites W.~501 Notifications Appendix A Subjects to be included in training course for logging supervisors-Appendix B Plaque l

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PART W RADIATION SAFETY REQUIREMENTS FOR WIRELINE SERVICE OPERATIONS AND SUBSURFACE TRACER STUDIES Sec. W.1 - Purpose. The' regulations in this part establish radiation safety requirements for persons using sources of radiation for wireline service operations including mineral logging, radioactive markers, and subsurface tracer studies. The requirements of this part are in addition to, and not in substitution for, the requirements of Parts A, B, C, D, and J of these regulations.

Sec. W.2 Scope. The regulations in this part apply to all licensees or ,

registrants who use sources of radiation for wireline service opera'tions including mineral logging, radioactive markers, or subsurface tracer

. studies. -

Sec. W.3 Definitions. As used in this part, the following definitions apply:

" Field station" means a facility where radioactive sources may be stored or used and from which equipment is dispatched to te=porary jobsites.

" Injection tool" means a device used for controlled subsurface injection of rndicactive tracer material.

" Logging supervisor" means the individual who provides personal supervision of the utilization of sources of radiation at the well site.

" Logging tool" means a device used subsurface to perform well-logging.

" Mineral logging" means any logging perfor=ed for the purpose of mineral exploration other than oil or gas.

" Personal supervision" ceans guidance and instruction by the supervisor who is physically present at the jobsite and watching the perfor=ance of the operation in such proximity that contact can be caintained and im=ediate .

assistance given as required.

" Radioactive carker" teans radioactive caterial placed subsurface or on a structure intended for subsurface use for the purpose of depth determi-nation er direction orientation.

" Source holder" means a housing or asse=bly into which a radioactive source is placed for the purpose of facilitating tha handling and use of the source in well-logging operations.

" Subsurface tracer study" means the release of a substance tagged with radioactive caterial for the purpose of tracing the covement or position.of the tagge.d substance in the well-bore or adjacent forcation.

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, W.3-W.103 c " Temporary jobsite" means a location to which radioactive caterials have been dispatched to perform wireline service operations or subsurface tracer II studies.

I "Well-bore" means a drilled hole in which wireline service operations and j , subsurface tracer studies are performed.

"Well-logging" means the lowering and raising of measuring devices or tools '

. i- which may contain sources of radiation into well-bores or cavities for the i '

purpose of obtaining information about the well and/or adjacent formations.

" Wireline" mean's a cable containing one or more electrical conductors which is used to lower and raise logging tools in the well-bore.

" Wireline service operation" means any evaluation or mechanical service which is performed in the well-bore using devices' on a wireline.

Sec. W.4 Prohibition. No licensee shall perform wireline service oper,a-tions with a sealed source (s) unless, prior to ccc=encement of the operation, the licensee has a written agree =ent with the well operator, well owner, drilling contractor, or land owner that:

(a) in the event a seale51 source is lodged downhole, a reasonable effort at recovery will be made; and -

(b) in the event a decision is cade to abandon the sealed source downhole, the requirements of W.501(c) [and the na=e of any other State Agency having applicable regulations) shall be cet.

Equipment Control Sec. W.101 Limits on Levels of Radiation. Sources of radiation shall be used, stored, and transported in such a manner that the transportation require =ents of Part C and the dose limitation requirements of Part D of these regulations are met.

Sec. W.102 Storage Precautions. ,

(a) Each cource of radiation, except accelerators, shall be provided with a storage tzd/or transport container. The container shall be prov,ided with a lock, or tamper seal for calibration sources, to prevent unauthorized removal of, or exposure to, the source of radiation.

-(b) Sources of radiation shall be stored in a =anner which will minimize dar.5er from explosion and/or fire.

Sec. W.103 Transport Preceutions. Transport containers shall be phys-ically secured to the transporting vehicle to prevent accidental loss, tampering, or unauthorized removal.

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W.104-W.105 Sec. W.104 Radiation Survey Instruments.

(a) The licensee or registrant shall maintain sufficient calibrated and operable radiation survey instruments'at each field station to make physical radiation surveys as required by this part and by D.201 of these -

, . regulations. Instru roentgen (2 58 x 10 gentation C/kg) pershall hourbe capable through at of measuring least 0.1 milli-20 milliroentgens (5.16 x 10'6 C/kg) per hour.

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~(b) Each radiation survey instrument shall be calibrated:

(1) at intervals not to exceed 6 months and after each instrument servicing; (2) at energies and radiation levels appropriate for use; and (3) so that accuracy within plus or minus 20 percent of the true radiation level can be de=onstrated on each scale.

(c) Calibration records shall be maintained for a period of 2 years for inspection by the Agency.

Sec. W.105 Leak-Testing 6f Sealed Sources.

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(a) Requirements. Each licensee using sealed sources of radioactive material shall have the sources tested for leakage. Records of leak test results shall be kept in units of microcuries and maintained for inspection by the Agency for 6. months after the next required leak test is performed or uqtil transfer or disposal of the sealed source.

(b) !!ethod of Testing. Tests for leakage shall be performed only by persons specifically authorized to perform such tests by the Agency, the U.S. Nuclear Regulatory Commission, an Agreement State, or a Licensing State. The test sample shall be taken from the surface of the source, source holder, or from the surface of the device in which the source is stored ~or mounted and on which one might expect contamination to accum-ulate. The test sample shall be analyzed for radioactive contamination, and the analysis shall be capable of detecting the presence of 0.005 micro-curie (185 Bq) of radioactive material on the test sample.

(c) Interval of Testing. Each sealed - source of radicactive caterial shall be tested at intervals not to exceed 6 months. In the absence of a certi-ficate from a transferor indicating that a test has been made prior to the transfer, the sealed source shall not be put into use until tested. If, for any reason, it is suspected that a sealed source may be leaking, it shall be removed from service immediately and tested for leakage as soon as practical.

(d) Leaking or Contaminated Sources. If the test reveals the presence of 0.005 microcurie (185 Bq) or more of leakage or contamination, the licensee shall. immediately withdraw the source from use and shall cause ~it to be decontaminated, repaired, or disposed of in accordance with these W3

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W.105-W.108 l .

regulations. A report describing the equipment involved, the test results, and the corrective action taken shall'be filed with the Agency. i

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(e) Exemption's. ' The following sources are exempted from the periodic leak

' test requirements of W.105(a) through -(d):

(1) hydrogen-3 sources;-

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l (2) sources of radioactive material with a half-life of 30 days or less;

. (3) sealed sources of radioactive material in gaseous form;

, (4) source's of beta- and/or gamma-emitting radioactive material with

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an activity of,100 miciocuries (3.7 MBq) or less; and.

(5) ' sources of alpha-emitting radioactive ~ material with an activity of 10 microcuries (0.370 MBq) or less. .

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}. Sec. W.106 ' Quarterly Inventory. Each licensee or registrant shall conduct a quarterly physical inventory to account for, all sources.of radiation.

Records of inventories shall be maintained for 2 years from the date of the inventory for-inspaction by the Agency and shall include the quantities and kinds of sources of radiation, the -location where- sources of radiation are assigned, the date of the inventory, and the name of the individual conducting the inventory.

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Sec. W.107 Utilization Records. Each licensee er registrant shall main-i tain current records, which shall be kept available for inspection by the I Agency for 2 years from the date of the recorded event,' showing the fol-

. lowing information for each source of radiation:

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(a) make, model number, and a serial number or a description of each j source of radiation used;

.(b) .the identity of the well-logging supervisor or field unit to whom assigned; (c) locations where used and dates of use; and (d) in the case of tracer caterials and radioactive markers, the utili-zation record shall indicate the radionuclide and activity used in a ,

-particular well.

i l Sec. W.108 Desien, Performance, and Certification Criteria for Sealed

-Sources Used in Downhole Operations.- .

, (a)' Each sealed source, except those containing radioactive material in ,

gaseous form, used in downhole operations and manufactured after (insert a date one year after the effective date of this part] shall be certified by the manufacturer, or other testing organization acceptable to the Agency,

  • to megt the following minimum criteria:

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W.108-W.109

-(1) be of doubly encapsulated construction; , _ _ .

(2). contain radioactive material whose chemical and physical forms l

! are as insoluble and non-dispersible as practical; and (3) has been individually pressure tested to at least 24,656 pounds

~ per square inch absolute (170 MN/m2 ) without failure.

(b) For sealed sources, except those containing radioactive material in gaseous form, acquired after [ insert a date one year after the effective date of.this part], in the absence of a certificate from a transferor certifying that an individual sealed source meets the require =ents of W.108(g),.the sealed source shall not be put into use until such deter-minations and testing have been performed.

(c) Each sealed source, except those containing radioactive material in gaseous form, used in downhole operations after [ insert a date. two years after the effective date of this part] shall be certified by the =anu-facturer, or other testing organization acceptable to the Agency, as meeting the sealed source performance require =ents for oil well-logging as contained in the American National Standard N542, " Sealed Radioactive Sources, Classification" in effect on [the effective date of this part] .

4 (d) Certification docu=ents shall be maintained for inspection by the Agency for a period of 2 years after source disposal. If the source is abandoned downhole, the certification documents shall be maintained until the Agency authorizes disposition.

Sec. W.109 Labeling.

(a) Each source, source holder, or logging tool containing radioactive -

material shall bear a durable, legible, and clearly visible marking or label, which has, as a minimum, the standard radiation caution symbol, without the conventional color requirement, and the following wording:

DANGER l /

RADIOACTIVE This labeling shall be on the s=allest ec=ponent transported as a separate piece of equipment.

(b) Each transport container shall have per:anently attached to it a durable, legible, and clearly visible label which has, as a minimum, the standard radiation cautien symaol and the following wording:

DANGERl / ,

.RADIOACTIVE l NOTIFY CIVIL AUTHORITIES [0R NAME OF C0K?ANY]

1 1/ or CAUTION , j l

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. 'W.110-W.201

'Sec. W.110' Inspection and Maintenance.

(a) Each licensee or registrant shall conduct, at intervals not.to exceed 6 months, a program of inspection and maintenance of source holders, log-sing' tools,1 source handling tools, storage containers, transport' con-l tainers, and injection . tools to assure proper labeling and physical condi ' '

tion.- ' Records of inspection and maintenance shall be maintained for a period of 2 years for inspection by the Agency. -

(b) If any' inspection conducted pursuant'.to W 110(a) reveals damage to labeling or-compenents critical to radiation safety, the device shall be removed from service until repairs have been made.-

.( c) The repair, opening, or modification of any sealed source shall be perfonned only by persons specifically authorized to do so .by the Agency, -

the U.S. Nuclear Regulatory Commission, an Agreement State, or a Licensing State. -

Requirements for Personnel Safety

. Sec. W.201 Training Recuirements.

(a)- No licensee or- registrant shall permit any individual to act as a , ,

. logging supervisor as defined in this part until such individual has:

(1)~ received, in a course recognized by the Agency, the U.S. Nuclear Regulatory Commission, an Agree =ent State, or a Licensing State, ,

instruction in'the subjects outlined in Appendix A of this part and

' demonstrated an understanding thereof;

-(2) read and received instruction in the regulations contained in Ethis:part and the applicable sections of Parts A, D, and J of these regulations or their equivalent, conditions of appropriate license or certificate of registration, and the licensee's or registrant's oper-ating and emergency procedures, and de=onstrated an understanding '

thereof; and (3) demonstrated cospetence to use sources of radiation, related handling tools, and radiation survey instruments which vill be used on the_ job.

(b) ^No licensee or registrant shall permit any individual to assist in the i handling of sources of radiation until such individual has: ,

(1) read or received instruction in the licensee's or registrant's operating and emergency precedures and demonstrated an understanding thereof; and (2) demonstrated co=petence to use, under the personal supervision of the logging supervisor, the sources of radiation, related handling tools, and radiation survey instruments which will be used on the job. -

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W.201-W.203 (c) The licensee or registrant shall maintain employee training records for inspection by the Agency for 2 years following termination of employment.

Sec. W.202 Operating and Emergency Procedures. The licensee's or' regis-trant's operating and emergency procedures shall include instructions in at least the following:

(a)' handling and use of sources of radiation to be employed so that no individual is likely to be exposed to radiation doses in excess of the standards established in Part D of these regulations; (b) methods and occasions for conducting radiation surveys; (c) methods and occasions for locking and securing sources of radiation;

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(d) personnel monitoring and the use of personnel conitoring equip =ent; (e) transportation to temporary jobsites and field stations, including the packaging and placing of sources of radiation in vehicles, placarding of vehicles, and securing sources ~of radiation during transportation; (f) minimizing exposure df individuals in the event of an accident; (g) procedure for notifying proper personnel in the event of r.n accident; (h) ' maintenance of records; (i) inspection and'caintenance of source holders, logging tools, source handling tools, s,torage containers, transport containers, and injection tools; (j) procedure to.be followed in the event a sealed source is lodged downhole; and (k) procedures to be used for picking up, receiving, and opening packages containing radioactive caterial.

-Sec. W.203 Personnel Monitoring.

(a) No licensee or resistrant shall permit any individual to act as a-logging supervisor or to assist in the handling o'.' sources of radiation unless each'such individual wears either a film ladge or a ther=c-luminescent desimeter (TLD). Each film badge er TLD shall be assigned to and worn by only one individual.

(b) Personnel monitoring records shall be maintained for inspection until the Agency authorizes disposition.

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. W.301-W.401 I

i Precautionary Procedures in Logging and Subsurface  !'

-Tracer Operations .

_Sec. W.301 ' Security. During_each logging or tracer application, the log-l- ging supervisor or.-other designated employee shall maintain direct surveil-lance of the operation to protect against unauthorized and/or unnecessary '

-entry into a restricted area, as defined in Part A of these regulations.

. 1 Sec. W.302 Handling Tools. The licensee shall provide and require the use i of tools that .will assure remote handl'ing of sealed sources other than low-activity calibration sources.

.i Sec. W.303 Subsurface Tracer Studies. i

-(a) Protective gloves and other appropriate protecti e clothing and equipment shall be used by all personn'el handling radioactive tracer material. Precautions shall be taken to avoid ingestion or inhalation of radioactive material.

(b) No licensee shall cause the injection of radioactive material into potable aquifers without prior written authorization from the Agency [and any other appropriate-state Agency].

Sec. W.304 Particle Accelerators. No licensee or registrant shall permit

' above-ground testing of particle accelerators, _ designed for use in well-logging, which results in the production of radiation, except in areas or ,

, facilities controlled or shielded so that the requirements of D.101 and  !

D.105 of these regulations, as applicable, are met. '

Radiation Surveys and Records .

Sec. W.401 Radiation Sm veys.

(a) ' Radiation surveys and/or calculations shall be made and recorded for each area where radioactive materials are stor,ed.

(b) Radiation surveys and/or calculations shall be made and recorded for j the radiation-levels in occupied positions and on the exterior of each vehicle used to transport radioactive material. Such surveys and/or.

calculations shall include each source of radiation or combination'of sources to be transported in the vehicle.

1 (c) After removal of the sealed source from the logging tool and before departing the jobsite, the logging tool detector shall be energized, or a survey meter used, to assure that the logging tool is free of contamina-tion. '

(d) Radiation surveys shall be made and recorded at the jobsite or well-head for each tracer operation, except those using hydrogen-3, carbon-14, and sulfur-35 These surveys shall include =easurements of radiation

- levels before and after the operation.

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W.401-W.403 (e) Records required pursuant to W.401(a) through (d) shall include the dates, the identification of individual (s) making the survey, the identi-fication of survey instrument (s) used, and an exact descriptien of the

' location of the survey. Records of these surveys shall So maintained for inspection by the Agency for 2 years afyer completion of the survey.

Sec. W.402 Documents and Records Required at Field Stations, leach licensee or registrant shall maintain, for inspection by the Agency, the 1 ~ following documents and records for the specific devices and ' sources used at the. field station:

(a) appropriate license, certificate of registration, or equivalent document; (b) ' operating and emergency procedures;

'(c) applicable regulations; (d) records of the latest survey instrument calibrations pursuant to' .

W.104; (e) records of the latest, leak-test results pursuant to W.105;

-(f) quarterly inventories' required pursuant to W.106; .

(g) utilization records required pursuant to W.107; (h) records of inspection and maintenance required pursuant to-W.110; and (i) survey records required pursuant to W.401.

Sec. W.403 Documents and Records Required at Temporary Jobsites. Each

. -licensee or registrant conducting operations at a temporary jobsite shall-have the following documents and records available at that site for

. inspection by the Agency:

.(a)_ operating and emergency procedures; (b) survey records required pursuant to W.401 for the period of operation at the site;-

(c) evidence of. current calibration for the radiation survey instruments in use at the site; and

-(d) when operating in the State under reciprocity, a copy of the appro-priate license, certificate of registration, or equivalent document (s).

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W.501 Notification j Sec. W.501 Notification of Incidents. - Abandon =ent, and Lost Sources.

4 (a) Notification of incidents and sources lost 'in other than downhole

  • logging operations shall be made in accordance with appropriate provisions of Part D of these regulations. -

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t (b) Whenever a sealed source or device containing radioactive material is

lodged downhole, the licensee shall I (1) monitor at the surface for the presence of radioactive contamin-ation with a radiation survey instru=ent or logging tool during logging tool recovery operations; and n (2) notify the Agency immediately by telephone if radioactive contam-ination is detected at the surface or if the source appears to be damaged.

(c) When it becomes apparent that efforts to recover the radioactive source will not be successful, the licensee shall (1) advise the well-operator of (the regulations of the appropriate State Agency regardi'ng abandon =ent and] an appropriate method of '

abandonment, which shall include (i) the ic=obilization and sealing in place of the radioactive ,

source with a, cement plug,

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(ii) the setting of a whipstock or other deflection device, and (iii) the mounting bf a permanent identification plaque, at the surface of the well, containing the appropriate inforcation required by W.501(d);

(2) notify the Agency by telephone, giving the circu= stances of the loss, and request approval of the proposed abandon =ent procedures; and (3) file a written report with the Agency within 30 days of the abandon =ent, setting forth the following information:

(1) date of occurrence and a brief description of atte= pts to recover the source, (ii) a description of the radioactive source involved, includ!

ing radionuclide, quantity, and chemical and physical form, (iii) surface location and identification of well, (iv) results of efforts to i==obilize and set the source in place, W10  !,

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(v) depth of.the radioactive source, ,

(vi) depth'of-the top of.the cement plug, depth of the well, 'and (vii)

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information contained on the permanent identification _ _

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-(viii) - ,

, plaque.

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-(d) -Whenever a sealed source contai'ning radioactive material is abandoned downhole,- the licensee shall provide a permanent plaque 2/ for posting the well or well-bore. This plaque shall:

(1); be constructed of long-lasting material, su'ch as stainless steel-

.or monel, and

} (2) contain the following information engraved on its face:

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'(i) the word " CAUTION",

(ii)~ the radiation symbol without the conventional color

- f: requirement,-

l (iii)- the date of abandonment, .

(iv) the name of the well operator or well owner,

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(v) . the well name and well identification nu=ber(s) or other.

!'+ designation,

-(vi) the sealed source (s) by radionuclide and quantity of ,

activity, ,

! -(vii) the source ' depth and the depth to the top of the plug,

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(viii) an appropriate warning, depending on the specific circumstances of each abandonment.3/

(e) The-licensee shall immediately notify the Agency by telephone and subsequently by confirming letter if the licensee knows or has reason to believe that radioactive material has been lost in or to an underground l

A 2/ An example of a suggested plaque is shown in Appendix B of this part.
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]/ -Appropriate warnings may include: (a) "Do not drill below plug back depth"; (b)."Do not enlarge casing"; or (c) "Do not re-enter the hole",

followed by the words, "before contacting the [ insert the name of the radiation control Agency]".

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.,. W.501 potable water source.. Such notice shall' designate the well location and shall describe the magnitude and extent of loss of radioactive material, I assess the consequences of such loss,'and explain efforts planned or being taken to mitigate these consequences.

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A APTEtIDIX A SUBJECTS TO RE INCLUDED IN TRAINING COURSES '

FOR LOGGING SUPERVISORS I. Fundamentals'of Radiation Safety i <

A. Characteristicq of radiation

. B._ Units of radiation dose and quantity of radioactivity C. Significance of radiation dose

.1. Radiation protection standards 1

2. Biological effects of radiation dose' D. Levels of radiation from sources of radiation E. Methods of minimizing radiation dose
1. Working time
2. Working distances 1
3. Shielding '

II. ? adiation Detection Instrumentation to be Used

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R A. . Use of radiation > survey instruments

1. Operation g

-l2. Calibration

3. Limitations ,

, B. Survey techniques , ,

C. : Use of personnel monitoring equipment .

III. Equipment to be Used A. Handling equipment B. Sources of radiation C. Storage and control of equipment D. Operation and control of equipment ,

~IV.- The Requirements of Pertinent Federal and State Regulations V. The Licensee's or Registrant's Written Operating and Emergency Procedures VI. ~The Licensee's or Registrant's Reccrd Keeping Procedures-e W13 ,

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APPENDIX B Exanple of Plaque for Identifying Wells Containing Sealed Sources Containing Radioactive P.aterial Abandoned Downhole i

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i ONE 2 CU.RIE CS-137 RADIOACTIVE SOURCE ABANDONEDi 3-3-75 AT 8400 FT. PLUG BACK DEPTH 8200 FT.

DO NOT RE-ENTER THIS WELL BEFORE CONTACTING

_ RADIATION CONTROL AGENCY.

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The size of the plaque should be convenient for use on active o,r inactive wells, e.g. , a 7-inch square. Letter size of the word " CAUTION" should be approxi=stely twice the letter size of the rest of the information, e.g.,1/2-inch and 1/4-inch letter size, respectively.

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  • i t June 1974

[8 'Q U.S. ATOMIC ENEGY COMMISSION iSb,Nes o n REGULATORY GU DE DIRECTORATE OF REGULATORY STANDARDS REGULATORY GUIDE 1.86 TERMINATION OF OPERATING LICENSES l FOR NUCLEAR REACTORS l

A. INTRODUCTION A licensee having a possessionenly license must retain, with the Part 50 license, authorization for special Section 50.51, " Duration of license, renewal," of 10 nuclear material (10 CFR Part 70, "Special Nuclear CFR Part 50, " Licensing of Production and Utilization Material"), byproduct material (10 CFR Part 30," Rules Facilities," requires that each license to operate a of General Applicability to Licensing of Byproduct production and utilization facility be issued for a Material"), and source material (10 CFR Part 40, specified duration. Upon expiration of the specified " Licensing of Source Material"), until the fuel, radio-period, the license may be either renewed or terminated active components, and sources are removed from the by the Commission. Section 50.82, " Applications for facility. Appropriate administrative controls and facility termination of licenses," specifies the requirements that requirements are imposed by the Part 50 license and the must be satisfied to terminate an operating license, technical specifications to assure that proper surveillance including the requirement that the dismantlement of the is performed and that the reactor facility is maintained facility and disposal of the component parts not be in a safe condition and not operated.

inimical to the common defense and security or to the health and safety of the public. This guide describes A possession-only license permits various options and

( methods and procedures considered acceptable by the procedures for decommissioning, such as mothballing, I ( Regulatory staff for the termination of operating entombment, or dismantling. The requirements imposed licenses for nuclear reactors. The Advisory Committee depend on the optic, selected.

on Reactor Safeguards has been consulted concerning this guide and has concurred in the regulatory position. Section 50.82 provides that the licensee may dis.

mantle and dispose of the component parts of a nuclear B. DISCUSSION re9ctor in accordance with existing regulations. For research reactors and critical facilities, this has usually When a licensee decides to terminate his nuclear meant the dicassembly of a reactor and its shipment reactor operating license, he may, as a first step in the offsite, sometimes to another appropriately licensed process, request that his operating license be amended to orgamzation for further use. The site from which a restrict him to possess but not operate the facility. The reactor has been removed must be decontaminated, as advantage to the licensee of converting to such a riecessary, and inspected by the Commission to deter.

possessionenly license is reduced surveillance require. mine whethey unrestricted access can be approved. In ments in that periodic surveillance of equipment im- the case of nuclear power reactors, dismantling has portant to the safety of reactor operation is no longer usually been accomplished by shipping fuel offsite, required. Once this possessiononly license is issued, making the reactor inoperable, and disposing of some of l

reactor operation is not permitted. Other activities the radioactive components.

related to cessation of operations such as unloading fuel from the reactor and placing it in storage (either onsite Radioactive components may be either shipped off-of offsite) may be continued. site for burial at an authorized bunal ground or secured I

USAEC REGULATORY GUIDES Cop es of pubbshed ou.dre erwy be obte.<=d by esquest md.catmo the d.ww.oas desired to the US. Atomic Energy Commessson. Weshengton, Dr. 20545 Reguietory Guedes are 6esued to oescrebe end make eweitable to the public Attent.on: Director of Regulatory stendeeds. Comtvunts and suggestions for ommes*on r t ons. o eneet n ues b a f he U E nergy cri. W h .E 4 evolueW spoofac problems or postuleted accidents, or to provide puedence to Attentoon; Chief. Pubhe Proceedngs stof f.

sus h is egg hIethods e d if f om hoes ou m vhe guides are tesued m tie fo%erme ten broad evisens-tie psHles sm*ll be acceptab.e if they provide a basis for the fondmga requesale to the ensuence or commuence of a permit or hcense by the Comm,ssoon. P React Prods u u.b .~me,or.o.c .. 5 .. o.upet ,e, ee

a. ts M:: rat .".*a.'"**

.or,;*2i,e"e:::"a"'" '""***"*'" M,"e;e"r*en"',%'!"2"e'c,,o., a s"' r'r'"- .

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on the site. Those radioactive materials remaining on the fluids and waste should be removed from the site.

site must be isolated from the public by physical barriers Adequate radiation monitoring, environmental surveil-or. other means to prevent public access to hazardous lance, and appropriate security procedures should be levels of radiation. Surveillance is necessary to assure the established under a possessionenly h ense to ensure that long term integrity of the barriers. The amount of the health and safety of the public is not endangered.

surveillance required depends upon (1) the potential hazard to the health and safety of the public from b. In Place Entombment. In-place entombment con-radioactive material remaining on the site and (2) the sists of sealing all the remaining highly radioactive or integrity of the physical barriers. Before areas may be contaminated components (e.g., the pressure vessel and released for unrestricted use, they must have been reactor internals) within a structure integral with the decontaminated or the radioactivity must have decayed biological shield after having all fuel assemblies, radio-to less than prescribed limits (Table !).

active fluids and wastes, and certain selected com-ponents shipped offsite. The structure should provide The hazard associated with the retired facility is integrity over the period of time in which significant evaluated by considering the amount and type of remaining contamination, the degree of confinement of quantities (greater than Table I levels) of radioactivity the remaining radioactive materials, the physical security remain with the material in the entombment. An appropriate and continuing surveillance program should provided by the confinement, the susceptibility to be established under a possessionenly license.

release of radiation as a result of natural phenomena, and the duration of required surveillance.

l

c. Removal of Radioactive Components and Dis.

mantling. All fuel assemblies, radioactive fluids and C. REGULATORY POSITION waste, and other materials having activities above ac-cepted unrestricted activity levels (Table I) should be

1. APPLICATION FOR A LICENSE TO POSSESS BIII removed from the site. The facility owner may then have NOT OPERATE (POSSESSION-ONLY LICENSE) unrestricted use of the site with no requirement for a license. If the facility owner so desires, the remainder of A request to amend an operating license to a possessionenly license should be made to the Director the reactor facility may be dismantled and all vestiges l rtmoved and disposed of. '

of Licensing. U.S. Atomic Energy Commission, Washing-ton, D.C. 20545. The request should include the following information: d. Conversion to a New Nuclear System or a Fossil Fuel System. This alternative, which applies only to nuclear power plants, utilizes the existing turbine system

a. A description of the current status of the facility.

with a new steam supply system. The original nuclear

b. A description of measures that will be taken to steam supply system should be separated from the electric generating system and disposed ofin accordance prevent criticality or reactivity changes and to minimize with one of the previous three retirement alternatives.

releases of radioactivity from the facility.

3. SURVEILLANCE AND SECURITY FOR THE RE.
c. Any proposed changes to the technical specifica-TIREMENT ALTERNATIVES WHOSE FINAL tions that reflect the possession only facility status and the necessary disassembly / retirement activities to be STATUS R EQUIRES A POSSESSION-ONLY LICENSE performed.

A facility which has been licensed under a posses-

d. A safety analysis of both the activities to be sion-only license may contain a significant amount of accomplished and the proposed changes to the technical radioactivity in the form of activated and contaminated specifications.

hardware and structural materials. Surveillance and commensurate security should be provided to assure that

e. An inventory of activated materials and their the public health and safety are not endangered.

location in the facility.

a. Physical security to prevent inadvertent exposure
2. ALTERNATIVES FOR REACTOR RETIREMENT of personnel should be provided by multiple locked barriers. The presence of these barriers should make it Four alternatives for retirement of nuclear reactor extremely difficult for an unauthorized person to gain l facilities are considered acceptable by the Regulatory l staff.These are: access to areas where radiation or contamination levels exceed those specified in Regulatory Position C.4. To prevent inadvertent exposure, radiation areas above 5
a. Mothballing. Mothballing of a nuclear reactor facility consists of putting the facility in a state of mR/hr, such as near the activated primary system of a power plant, should be appropriately marked and should protective storage. In general, the facility may be left intact except that all fuel assemblies and the radioactive not be accessible except by cutting of welded closures or the disassembly and removal of substantial structures 1.86-2

&.. .n .. , , . m n , w , . _s__ __-_--__-- * * ' ~ * ' '*' ~ ~~" "

and/or shielding material. Means such as a remote- (1) Environmental surveys, g . readout intrusion alarm system should be provided to i indicate to designated personnel when a physical barrier (2) Facility radiation surveys, is penetrated. Security personnel that provide access control to the facility may be used instead of the (3) Inspections of the physical barriers, and physical barriers and the intrusion alarm systems.

(4) Abnormaloccurrences.

b. The physical barriers to unauthorized entrance into the facility, e.g., fences, buildings, welded doors, and access openings, should be inspected at least 4. DECONTAMINATION FOR RElIASE FOR UN-quarterly to assure that these barriers have not deterior- RESTRICTED USE ated and that locks and locking apparatus are intact.

If it is desired to terminate a license and to eliminate

c. A facility radiation survey should be performed at any further surveillance requirements, the facility should least quarterly to verify that no radioactive materialis be sufficiently decontaminated to prevent risk to the escaping or being transported through the containment public health and safety. After the decontamination is barriers in the facility. Sampling should be done along satisfactorily accomplished and the site inspected by the most probable path by which radioactive material the Commission, the Commission may authorize the such as that stored in the inner containment regions license to be terminated and the facility abandoned or could be transported to the outer regions of the facility released for unrestricted use. The licensee should per-and ultimately to the environs. form the decontamination using the following guide-lines:
d. An environmental radiation survey should be performed at least semiannually to verify that no a. The licensee should make a reasonable effort to signficant amounts of radiation have been released to the eliminate residual contamination.

environment from the facility. Samples such as soil, vegetation, and water should be taken at locations for b. No covering should be applied to radioactive which statistical data has been established during reactor surfaces of equipment or structures by paint, plating,or ,

operations. other covering material untilit is known that contamina- i

[

i

e. A site representative should be designated to be tion levels (determined by a survey and documented) are below the limits specified in Table I. In addition, a I

responsible for controlling author.:ed access into and reasonable effort should be made (and documented) to movement within the facility. further minimize contamination prior to any such covering.

f. Administrative procedures should be established for the notification and reporting of abnormal occur- c. The radioactivity of the interior surfaces of pipes, rences such as (1) the entrance of an unauthorized drain lines, or ductwork should be determined by person or persons into the facility and (2) a significant making measurements at all traps and other appropriate change in the radiation or contamination levels in the access points, provided contamination at these locations facility or the offsite environment. is likely to be representative of contamination on the interior of the pipes, drain lines, or ductwork. Surfaces
g. The following reports should be made: of premises, equipment, or scrap which are likely to be contaminated but are of such size, constiuction, or (1) An annual report to the Director of Licensing, location as to make the surface inaccessible for purposes l U.S. Atomic Energy Commission, Washington, D.C. of measurement should be assumed to be contaminated 1 20545, describing the results of the environmental and in excess of the permissable radiation limits.

facility radiation surveys, the status of the facility, and an evaluation of the performance of security and d Upon request, the Commission may authorize a l surveillance measures. licensee to relinquish possession or control of premises, equipment, or scrap having surfaces contaminated in (2) An abnormal occurrence report to the Regula- excess of the limits specified. This may include, but is tory Operations Regional Office by telephone within 24 not limited to, special circumstances such as the transfer hours of discovery of an abnormal occurrence. The of premises to another licensed organization that will abnormal occurrence will also be reported in the annual continue to work with radioactive materials. Requests report described in the preceding item. for such authorization should provide:

Y

h. Records or logs relative to the following items (1) Detailed, specific information describing the
should be kept and retained until the license is'termi- premises, equipment, scrap, and radioactive contami-j nated, after which they may be stored with other plant nants and the nature, extent, and degree of residual records
surface contamination.

1.86 3 w .. .. ~ . .

7

(2) A detailed health and safety analysis indi- or a change in the technical specifications should be cating that the residual amounts of materials on surface reviewed and approved in accordance with the require-areas, together with other considerations such as the ments of 10 CFR $50.59.

prospective use of the premises, equipment,or scrap,are unlikely to result in an unreasonable risk to the health if major structural changes to radioactive components and safety of the public. of the facility are planned, such as removal of the pressure vessel or major components of the primary

e. Prior to release of the premises for unrestricted system, a dismantlement plan including the information use, the licensee should make a comprehensive radiation required by 650.82 should be submitted to the Commis-survey establishing that contamination is within the sion. A dismantlement plan should be submitted for all limits specified in Table 1. A survey report should be the alternatives of Regulatory Position C.2 except filed with the Director of Licensing, U.S. Atomic Energy ' mothballing. However, minor disassembly activities may Commission, Washington, D.C. 20545, with a copy to still be performed in the absence of such a plan, the Director of the. Regulatory Operations Regional provided they are permitted by existing operating and Office having jurisdiction. The report should be filed at maintenance procedures. A dismantlement plan should least 30 days prior to the planned date of abandonment. include the following:

The survey report should:

a. A description of the ultimate status of the facility (1) Identify the premises;
b. A description of the disman$ng activities and the erecautions to be taken.

(2) Show that reasonable effort has been made to reduce residual contamination to as low as practicable levels; s c. A safety analysis of the dismantling activities including any effluents which may be released.

. (3) Describe the scope of the survey and the general procedures followed;and d. A safety analysis of the facility in its ultimate status.

(4) State the finding of the survey in units specified in Table 1. Upon satisfactory review and approval of the dis-mantling plan, a dismantling order is issued by the After review of the report, the Commission may Commission in accordance with Q50.82. When dis-inspect the facilities to confirm the survey prior to mantling is completed and the Commission has been granting approval for abandonment. notified by letter, the appropriate Replatory Opera-tions Regional Office inspects the facility and verifies

5. REACTOR RETIREMENT PROCEDURES completion in accordance with the dismantlement plan.

If residual radiation levels do not exceed the values in As indicated in Regulatory Position C.2, several Table I, the Commission may terminate the license. If alternatives are acceptable for reactor facility retirement. these levels are exceeded, the licensee retains the If minor disassembly or "mothballing" is planned, this possession only license under which the dismantling could be done by the existing operating and mainte- activities have been conducted or, as an alternative, may nance procedures under the license in effect. Any' make application to the State (if an Agreement State) planned actions involving an unreviewed safety question for a byproduct materials license..

1.86-4 l

l l

I

s l

TABLE 1 i

) ACCEPTABLE SURFACE CONTAMINATION LEVELS NUCLIDEa AVERAGEb c MAXIMUMbd REMOVABLEb e U-nat, U-235, U-238, and 5,000 dpm a/]00 cm2 15,000 dpm a/100 cm 2 1,000 dpm a/100 cm2 LP associated decay products C

Transuranics, Ra 226, Ra 228, 100 dpm/100 cm2 300 dpm/100 cm2 20 dpm/100 cm2 V Th 230 Th 228,Pa-231, Ac 227,1125,1129 Th nat, Th-232, Sr-90, 1000 dpm/100 cm2 3000 dpm/100 cm 2 200 dpm/100 cm2 #

Ra-223, Ra-224, U 232, 1 126,1-131,I-133 Beta gamma emitters (nuclides . 5000 dpm M/100 cm2 15,000 dpm M/100 cm2 1000 dpm M/100 cm2 ,,,-

with decay modes other than alpha '

y emission or spontaneous fission) except Sr 90 and others noted above.

g g e r( - (- $ g*k 610 0 h Iht 4,.

aWhere surface contamination by both alpha- and beta-gamma-emitting nuclides exists, the limits established for sipha- and ,0 b

beta-gamma-emitting nuclides should apply independently.

bas used in this table, dpm (disintegrations per minute) means the rate of emission by radioactive material as determined by corre ting the counts per minute observed by an appropriate detector for background, efficiency, and geometric factors associated with the instrumentation.

CMeasurements of average contaminant should not be averaged over more than I square meter. For objects of less surface area, the average should be derived for each such object- y dThe maximum contamination level applies to an area of not more than t00 cm2 ,- -Q,

%e amount of removable radioactive material per 100 cm 2of surface area should be by wiping that area with dry filter or soft absorbent paper, applying moderate pressure, and assessing the amount of radioactive material on the wipe with an appropriate instrument of known efficiency, When removable contamination on objects of less surface area is determined, the pertinent levels should be reduced proportionally and the entire surface should be wiped-9 1.86 5

mem r U.S. NUCLEAR RESULATORY COMMISSION s.p nbwis7s REGULATORY GUIDE i

@o.@..o OFFICE OF STANDARDS DEVELOPMENT REGULATORY GUIDE 8.20 APPLICATIONS OF BIOASSAY FOR l-125 AND l-131 A. INTRODUCTION vitro of materials excreted or removed fmm the body Section 20.108, " Orders Requiring , Furnish-ing of Bioassay Services," of 10 CFR Part 20, Intake-The total quantity of radioactive

" Standards for Pmtection Against Radiation, material entering the body.

indicates that the Nuclear Regulatory Commis-sion (NRC) may incorporate into a license pro- In vivo measurements-Measurement of gamma-visions requiring a specific program of or x-radiation emitted from radioactive material '

bioassay measurements as necessary or located within the body for the purpose of desirable to aid in determining the extent of an detecting or estimating the quantity of radio-individual's exposure to concentrations of active Ir.Merial present.

radioactive material. In certain cases, the requirement of bioassay may also be included in In vitm measurements-Measurement of radio- i the license by reference to procedures specify- activity in samples of material excreted fmm ing in vivo measurements, measurements of the human body.

radioactive material in excreta, or both.

This guide provides criteria acceptable to the NRC staff for the development and implementa- 1. Conditions Under which Bioasesy is Necessary tion of a bioassay program for any licensee

  • handling or processing I-125 or I-131. It a. Routine 1 bioassay is necessary when an 8

further provides guidance to such licensees individual handles in open foryn. unsealed regarding the selection of workers who should quantities of radioactive iodine that exceed participate in a program to detect and measure those shown in Table 1 of this guide. The

("

possible internal radiation exposure..The guide is programmatic in nature and does not deal quantities shown in Table 1. apply to both the quantity handled at any one time or integrated with measurement techniques and procedures. as the total amount of activity introduced into a process by an employee over any 3-month B. DISCUSSION period.

The topics treated in this guide include de- b. When quantities handled in unsealed terminations of (1) whether bioassay should be form are greater than 10% of Table 1 values, performed, (2) frequencies of bioassay, (3) who should participate, (4) the actions to take eLine. Indicate .ud.tanuve change. tres previous is.ue.

based on bioassay results, and (5) the partic- a Routine mean. here that an individu.1 1. a..igned on a ular results that should initiate such actions. scheduled and repeatable be.t. to .ubmit .pecimen. for bion..ay or to report for in vivo sea.uren.nts. Either r.diochemical co u .c m the For the user's convenience, the following y' *",*f, *' urin ,9,ge, ,

terms are presented with their definitions as In some cases. however. . lic.n..e may .i.h to corrobor.te l utamate. tram urinaly.a data .ita = vivo determinations.

used in this guide: since there are ad.quate reference. in the hter.ture to hel a i devi.e bio asy n ud at.. this guide do not include Bioassay-The determination of the kind, recommend.d .nalytsc.1 procedure.. sach sn. tan. tion .hould adopt procedure. or obtain service. be.t .uited to it. own quantity or concentration, and location of ""d'

  • radioactive material in the human body by direct (in vivo) measurement or by analysis in asa discuulon in th. tootnote to Table 1 of thi. ruid..

Co ent. .bc.ld b. t to the S.cret.ry of the F -- U.S.

USNRC REGULATORY GUIDES

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routina bloarsay may etill be necessary undsr 3. Types c f Bionssays 'Ihat Should Be Performed certain circumstancm. A written juttific: tion far not perfcraing cuch mrsuremelits thould a. Bwlina (preemploynint er preopera-be prepared and record:d far sub:equent re- tional). Prior to b: ginning w2rk with r dio-view during NRC inspections tithenever bio- active iodine in sufficient quantity that bio-assay is not performed and ' the quantities assay is specified in regulatory position 1. f handled exceed 10% of the levels in Table 1.

b. Routine. At the frequency specified in
c. Except as stated in regulatory posi- regulatory position 4.

tion 1.e, bioassay is not required when pro-cess quantities handled by a worker are less c. Emergency. As soon as possible after any than 10% of those in Table 1. incident that might cause thyroid uptakes to exceed burdens given in regulatory posi-

' tion 5.a(2), so that actions recommended in

d. In nuclear reactor installations, employ-ees should be bioassayed by an in vivo count regulatory position 5.a(2)(b) can be most within 30 days after the end of exposure in eMective.

' work locations where concentrations exceeded,

d. Postoperationaland with Separation Phys-or might have exceeded, 9 x 10-8 pCi/ml .

Ical. A bioassay should be performed within 2 averaged over any 40-hour period. Table 1 and regulatory position 4 regarding frequency of weeks of the last possible exposure to I-1,25 or bioassays are not applicable to reactor I-131 when operations are being discontinued or when the worker is terminating activities licensees. with potential exposure to these radionuclides.

e. Special bioassay measurements should e. Diagnostic. Followup bioassay should be be perfomed to verify the effect.veness of performed within 2 weeks of any measurements respiratory protection devices and protective exceeding levels given as action points in clothing. If an individual waarang a respiratory regulatory position 5 in order to confirm the protective device or protective clothing is sub- initial results and, in the case of a single jected to a concentration of I,125 or I-131 (in intake, to allow an estimate of the effective any form) in air such that has or her antake half-life of radioiodine in the thyroid.

with no protection would have exceeded the limits specified in paragraph 20.103(a)(1) of 4. Frequency 10 CFR Part 20,8 bioassays should be per-formed to determine the resulting actual I-125 a. Initial Routine. Except in situations t or I-131 intake. These special bioassay proce- where thyroid burdens may exeded quantities dures should also be conducted for personnel specified in regulatory position 5.a(2), a bio- 0 wearing respirators if for any reason the I-125 assay sample or mea,surement should be or I-131 concentration in air and the duration obtained within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> following entry of an Iof exposure are unknown or cannot be conser- individual into an area where bioassay is (vatively estimated by calcult. tion. performed in accordance with regulatory posi-tions 1 and 2 (but waiting at least 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for distribution of a major part of the iodine to the thyroid *) and every 2 weeks or mo. e

2. Participation '

frequently thereafter as long as the conditions described in regulatory positions 1 and 2 All workers handling radioactive iodine or exist. When work with radioactive iodine is on sufficiently close to the process so that intake an infrequent basis (less frequently than every is possible (e.g., within a few meters and in 2 ireeks), bioassay should be performed within the same room as the worker handling the 10 days of the end of the work period during material) should participate in bioassay pro- which radioactive iodine was handled (but not grams described in regulatory position 1. sooner than 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> unless emergency actions to obtain an early prognosis and thyroid blocking treatment are appropriate *).  ;

8Muldplying the concentrauens given in Appendix B to 10 CFR Part 20. Table I, Column 1, 5 x 10-' pCVal for I-125 b. After 3 Months. When a periodic meas-(soluble) and 9 x 10** pCual for I-131 (sonable), by 6.3 x los n! give the corruponding quarterly intake of the rupective urement frequency has been selected in todian by inhalados. Then quarterly intaku would be about aCCordance with regulatory position 4.a. It may 3.2 pCs for 1 12s and 5.7 pci for t 131, which would give a thymid dose commitment of about 7.5 rems to a 20-gram thyroid be changed to quar.terly if, after 3 months, all integrated over au future time using effective half.uva of 41.s the following conditaons are met:

days for I-12s and 7.6 days for I 131 and using a quality factor (QF) of 1.7 to calculate effective disintegranon energy in the (1) The average thyroid burden for case of I-125. (This QF of 1.7 is used for conservausa, even though the laternational rhsion on Radionogical Protection each individual working in a given area was (19s9) and the National CouncH on Radiation Protection (1971) '

have published a QF of 1, because some calculations in more *NCRP Report No. 55, " Protection of the Thyroid Gland in recent scientifle literature have suggested the use of QF values the Event of Releases of Radiciodine." National councQ on higher than 1 for electron or beta energies of 0.03 MeV or Radiation Protection and Measurements, Washington, D.C. ,

less.) August 1,1977, p. 21. '

i 8.20-2 l 1

1 ;

i

( ,. .

less than 0.12 pCi of I-125, less than 0.04 pCi $ 20.103 of 10 CFR Part 20 to be exceeded, the j of I-131, and less than the corresponding pro- licensee should restrict the worker from i portionate amounts of a mixture of these further exposure until the source of exposure

$% nuclides during the initial 3-month period: is discovered and corrected.

l-i (2) The quarterly average radiciodine (c) Corrective actions that will elim-concentration (pCi/ml) in air breathed by any inate or lower the potential for further expo-worker (as obtained when measurements of sures should be implemented.

radiciodine concentrations in air are required)

~

does not e ceed 25% of the concentration values (d) A repeat bioassay should be for " soluble"(s) iodine given in Appendix B to taken within 2 weeks of the previous measure-10 CFR' Part 20, Table I, Column 1, (5 x 10-8 ment and should be evaluated within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> pCi/ml for I-125 and 9 x 10-e pCi/ml for I-131), after measurement in order to confirm the i.e., 25% of these concentrations multiplied by presence of internal radiciodine and to obtain the total air breathed by an employee at work an estimate of its effective half-life for use in during one calendar quarter, 6.3 x 10s ml, estimatint dose commitment.

does not exceed 0.8 pCi of I-125 or 1.4 pCi of I-131. The appropriate proportionate amount 5 (e) Reports or notification must be of a mixture of these nuclides should be used provided as required by El 20.405, 20.408, as a guide when both I-125 and I-131 are and 20.409 of 10 CFR Part 20 or as required present; and by conditions of the license pursuant to E 20.108 of 10 CFR Part 20.

(3) The working conditions during the 3-month period with respect to the potential for (2) If the thyroid burden at any time exposure are representative of working condi- exceeds 0.5 pCi of I-125 or 0.14 pCi of I-131, tions during the period in which the quarterly the following actions should be taken:

bioassay frequency will be employed, and there is no reasonable expectation that the critaria'in * (a) Carry out all steps described in regulatory positions 4 b(1) and 4.b(2) above regulatory position 5.a(1).

will be exceeded.

(b) As soon as possible, refer the

c. After Use of Respiratory Protection De- case to appropriate medical consultation for l vices.Between 6 and 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after respiratory recommendations regarding therapeutic proce-protective devices, suits, hoods, or gloves are dures that may be carried out to accelerate f- used to limit exposure as stated in regulatory removal of radioactive iodine from the body.

l position 1.e. This should be done within 2-3 hours after y exposure when the time of exposure is kAown For individuals placed on a quarterly so that any prescribed thyroid blocking agent schedule, sampling should be randomly distri- would be effective.*

buted over the quarter but should be done within one week after a procedure involving (c) Carry out repeated measurements the handling of I-125 or I-131. This will pro- at approximately 1-week intervals at least until vide a more representative assessment of expo- the thyroid burden is less than 0.12 pCi of I-125 sure conditions. or 0.04 pCi of I-131. If there is a possibility of longer-term compartments containing I-125 or

5. Action Points and Cm. _g ,, ; Actions I-131 that require evaluation, continue meas-
a. Biweekly or More Frequent Measurements urements as long as necessary to ensure that appreciable exposures to these other compart-(1) Whenever the thyroid burden at the ments do not go undetected.

I time of measurement exceeds 0.12 pCi of I-125 or 0.04 pCi of I-131, the following actions b. Quarterly Measurements. Carry out should be taken: actions at levels as indicated under regulatory-position 5.a(1) and (2). If measurements, and (a) An investigation of the opera- surveys indicate an appreciable likelihood that i'

tions involved, including air and other in-plant a worker will receive further exposures surveys, should be carried out to determine exceeding the criteria of regulatory posi-the causes of exposure and to evaluate the tions 4.b(1) and 4.b(2), reinstitute biweekly potential for further exposures, or more frequent bioassays.

(b) If the investigation indicates that further work in the area might result in exposure of a worker to concentrations that D. IMPLEMENTATION

, would cause the limiting intakes established in i i'

-- 'see Appendia a to this guide tor a desertption and example The purpose of this section is to provide in-or usens tass comenom ter asztures. formation to applicants and licensees regarding L

a A

8.20-3

I the JiRC ctaff's plans f;r u:ing this regulatory incorporated in th .ir licenses in accordance guide. with 6 20.108 of 10 CFR Part 20.

Except in thos3 cases in which tha cpplicant- If an rpplicant er licenses wish:s to use the or licensee proposes an acceptable alternative method, the staff will use the methods method or beforedescribed December in 15, this 1979, regulatory portions of the application or the licensee's guide on l the pertinent {h d }

l described herein after December 15,1979, in performance will be evaluated on the basis of evaluating the radiation protection programs of licenseca who have bioassay requirements this guide.

9 s

Tsbie 1 ACnVfrY LEVELS ABOVE WHICH BIOASSAY FOR I 125 OR f 131 IS NECESSARY ActivityHandled in Unsealed Fonn Making Baoamey Necemary*

VolatGe Bound to

' or Nonvolatue Dispetsible* Agent

  • Types of Operation 10 mci l Processes in open room or bench, with possible escape 1 mci '

of iodine from process vessels i 10 mci 100 mci l Processes with possible escape of iodine carried out I within a fume hood of adequate design, face velocity,  ;

and performance reliability f 100 mci 1000 mci -*

Processes. carried out within gloveboxes, ordinarily closed, but with possible release of fodine from process and occasional exposure to contaminated box and box leakage

_ aquantities may be considered the cumulative amount in process handled by a worker during a 3-month period; e.g., the total quantity introduced into a chemical or physical process over a 3-month period, or on one or more occantons in that period, by opening stock reagent containere from which radioactive iodine may escape. Quantittee in the right-hand column may be used when it can be shown that activity in process is always chemiceDy bound and processed in such a manner that 1-135 or I-131 wSI remain in nonvolatile form and deuted to concentrations less than 0.1 mCf/ag of nonvolatile agent. Capsules (such as gelatin capsules given to patients for diagneetic tests) may be considered to contain the radioiodine in nonfree form, and bionssay wouM not be necessary unless a capsule were inadvertently opened (e.g.,

dropped and crushed). However, certain compounds where radioiodine is normauy bound are known to release radionodine a

when the materialis in procese, and the left-hand column may then be applicable. In those laboratorise working only with bl35 in radioimmunassey (RIA) kita, the quantities of I-135 are very aman and in less volatae forms; thus, bloessay requirements may be judged from the right-hand column. In field operations, where reagent containers are opened

' outdoors for eleple operatione such as pouring liquid solutions, the above table does not apply; bionesay should be performed whenever an individual employee handles in open form (e.g., an open bottle or container) more than 50 mci et any one time.

Operations involving the routine use of I-126 or I-131 in en open room or bench should be discouraged. Whenever practicable, sealed bottles or containere holding more then 0.1 act of I-135 or I-131 should be opened at least initiauy within hoods having adequate face velocittee of 0.5 m/sec or more.

I 8.20-4 f

1

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APPENDIX A ,

j SUGGESTED REFERENCES TO ASSIST IN ESTABl.lSHING A 810 ASSAY PROGRAM In response to public comments, this list of publications is provided to assist the licensee in estab-lishing measurements and administrative procedures for a bioassay program appropriate to his opera-tions. This list is not intended to be exhaustive and does not replace the need for professional assis-tance in establishing analytical procedures or services.

1. American NationalStandard, ANSI N'4.3-1973, Radiological Protection, Pergamon Press,

" Thyroid Radiolodine Uptake Measurements Oxford, p. 17, 1968.

Using a Neck Phantom," American National' Standards Institute, Inc.,1430 Broadway, 9. ICRP Publication 10A, "The Assessment of New York, N.Y. 10018, ' approved Internal Contamination Resulting from August 24, 1973. Recurrent or Prolonged Uptakes," Recom-mendations of the International Commission

2. R. C. Brown, "tas! Ingestions in' Research on Radiological Protection, Pergamon Personnel," Operational Health Physics , Press, Oxford,1969.

pp. 276-278, 1976, proceedings of the Ninth Midyear Topical Symposium of the 10. A. L. Orvis, "What Is a ' Reportable' Thy-Health Physics Society, Denver, Colorado, roid Burden?" op. cit. , Ref. 2. , pp. 268-February 1976 (P. L. Carson, W. .R. 271.

Hendee, and D. C. Hunt, Eds. , Central Rocky Mountain Chapter, Health Physics 11. P. Plato A. P. Jacobson, and S. Homan, Society, P.O. Box 3229, Boulder, Colorado "In Vivo Thyroid Monitoring for Iodine-131 80303,$15). ' in the Environment," Int. J. A lied Radiat.

3. E. J. Browning, K. Banerjee, and W. E. 545, 76-~~and Isotopes, vol. 27, pp.

Reisinger, Jr. , " Airborne Concentration of I-131 in a Nuclear Medicine Laboratory," J. 12. Radiological Protection Bulletin 25, " Safe Nucl. Med. , vol.19, pp.1078-1081,1978T Working with Iodine-125," National Radio-

  • logical Protection Board, Harwell, Didcot,

, 4. J. G. Dare and A. H. Deutchman, "The Oxon, England, pp. 19-20, 1978.

Decay Scheme of Iodine-125 and Its Rela-tionship to Iodine Bioassay," op. cit., 13. R. P. Rossi, J. Ovadia, K. Renk, A. S.

Ref. 2, pp. 250-254. Johnston, and S. Pinsky, " Radiation Safety Considerations in the Management of

5. B . C. Fasiska, " Radiation Safety Proce- Patienta Receiving Therapeutic Doses of dure and Contamination Control Practices 1stI," op. cit. , Ref. 2, pp. 279-286.

Involved in High LevelI-131ThyroidThera-

- py Cases," op. cit. , Ref. 2, pp. 287-291. 14. C. T. Schmidt, " Thyroid Dosimetry of 188I and an Instrumental Bioassay Procedure,"

6. A. Gavron and Y. Feige, " Dose Distribu- Program and Abstracts: Twenty-Third An-nual Cont on Bioassay, Environmen'tal, tion and Maximum Permissible Burden of and Analytical Chemistry, 1851 in the Thyroid Gland ," Health IDO-12083, Physics, vol. 23, pp. 491-499,1972. St.15,16,1977.
7. B. Y. Howard, " Safe Handling of Radio- 15. A. Taylor, J. W. Verba, N. P. Alasraki, iodinated Solutions," op. cit. , Ref. 2, pp. and W. C. McCutchen, " Monitoring of I-125 247-249. Contamination Using a Portable Scintillation Camera," J. Nucl. Med. , vol.19, pp. 431-
8. ICRP Publication 10 " Report of Commit- 432, 1978.

tee IV on Evaluation of Radiation Doses to Body Tissues from Internal Contamination 16. Technical Reports Series No.148, " Control Due to Occupational Exposure," Recommen- of Iodine in the Nuclear Industry," Inter-dations of the International Commission on national Atomic Energy Agency, Vienna,'1973.

8.20-5

_ _ _ s I  :

APPENDIX B CALCULATION OF ACTION LEVELS FOR MIXTURES OF l-126 AND l 131 B.1 Controning Instantaneous Thyroid Burdens period when air concentration data are avail-able to assess the potential exposure of the  :

worker either to random single intakes or to Regulatory position 4.b(1) is based on con- variable or constant continuous exposures. The l trolling the instantaneous amount in the thy- quantities of 0.8 pCi of I-125 and 1.4 pCi of I-roid and is taken as 25% of the maximum per, 131 were obtained by calculating 25% of the mis:ible organ burden (MPOB) of I-125 or I-131 total quarterly intakes of 3.2 pCi of I-125 or th-t would give a dose rate of 0.6 rem / week if 5.7 pCl of I-131 (see footnote 3) that would be continuously present in the thytvid. If a mix- inhaled when breathing a total of 6.3 x 10s al ture of both nuclides is present in the thyroid and X is the fractional activity that is I-125, a per quarter working at the standard man 3-month interval may be resumed when the breathing rate for 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> per week for 13 total activity of I-125 and I-131 is below weeks.

Example 0.12X + 0.04(1 - X)

If the average quarterly concentrations esti-Example mated from air sampled in a worker's breathing zone are 3 x 10-8 pCi/ml for I-125 and 5 x 10-If thd measurements of I-125 and I-131 in a pCi/ml for I-131, the total quarterly intakes work r's thyroid are 0.10 pCi of I-125 and 0.05 are:

pCi of I-131, the fractional I-125 activity is 3 x 10-8 x 6,.3 x 10s = 1.89 pCi 1-125 X = 0.10/(0.10 + 0.05)

= 0.667 5 x 10-s x 6.3 x 10s = 3.15 pCi I-131 Then Total = 5.04 pCi

-0.12X + 0.04(1 - X) = 0.12(0.667) + 0.04(0.33) Also, X, the proportion of I-125, is 1.89/5.04 =

= 0.0932 0.375 -

Total = 0.10 + 0.05 = 0.15 pCi Thus the control level for maintaining biweekly or more frequent bionssay checks is:

Tliu3, in this case, the worker involved should remain on the biweekly (or more fre-quent) schedule and should not be put on the 0.8X + 1.4(1 - X) = 0.8(0.375) + 1.4(1 - 0.375)

Total = 1.18 pCi for this mixture.

quarterly frequency.

Since the intake of 5.04 pCi is greater than B.2 ControBing TotalIntakes 1.18, this employee should stay on the more Regulatory position 4.b(2) is based on con- frequent bioassay schedule, trolling total intakes s during a quarterly Note: The numbers of significant digits carried

  • in the above calculations do not imply teena oYrd N I-t"N Ethat ar N . "xpoIe nE diffe'Ne"e penas ibs. concentreuena are any given degree of accuracy of mea-surement. Enough digits are carried to e a ruuts of the fact tversely proportional to effective half-lives whereas an MPo8 allow following the arithmetic for pur-D calculated assuming a coastaat burden la the organ of con-corn that is malatained by coatinuous intake of actartty poses of the examples.

mainneed by an equal rete et eumsmauen from the errea.

8.20-6

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