Regulatory Guide 8.39

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Release of Patients Administered Radioactive Materials
ML083300045
Person / Time
Issue date: 04/30/1997
From:
Office of Nuclear Regulatory Research
To:
References
RG-8.039, Rev. 0
Download: ML083300045 (24)
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U.S. NUCLEAR REGULATORY COMMISSION April 1997 Revision 0

REGULATORY GUIDE

OFFICE OF NUCLEAR REGULATORY RESEARCH

REGULATORY GUIDE 8.39 (Draft was issued as DG-8015)

RELEASE OF PATIENTS ADMINISTERED

RADIOACTIVE MATERIALS

A. INTRODUCTION

Section 35.75, Release of Individuals Containing Radiopharmaceuticals or Permanent Implants, in 10 CFR Part 35, Medical Use of Byproduct Material, permits licensees to authorize the release from its control of any individual who has been administered radiopharmaceuticals or permanent implants containing radioactive material if the total effective dose equivalent to any other individual from exposure to the released individual is not likely to exceed 5 millisieverts (0.5 rem).

Further, 10 CFR 35.75(b) requires that the licensee provide the released individual with instructions, including written instructions, on actions recommended to maintain doses to other individuals as low as is reasonably achievable if the total effective dose equivalent to any other individual is likely to exceed 1 millisievert (0.1 rem). If the dose to a breast-feeding infant or child could exceed

1 millisievert (0.1 rem) assuming there were no interruption of breast-feeding, the instructions shall also include (1) guidance on the interruption or discontinuation of breast-feeding and (2) information on the consequences of failure to follow the guidance.

In addition, 10 CFR 35.75(c) requires that the licensee maintain a record of the basis for authorizing the release of an individual, for 3 years after the date of release, if the total effective dose equivalent is calculated by (1) using the retained activity rather than the activity administered, (2) using an occupancy factor less than 0.25 at 1 meter, (3) using the biological or effective half-life, or (4)

considering the shielding by tissue.

The NRC issues regulatory guides to describe and make available to the public methods that the NRC staff considers acceptable for use in implementing specific parts of the agencys regulations, techniques that the staff uses in evaluating specific problems or postulated accidents, and data that the staff needs in reviewing applications for permits and licenses. Regulatory guides are not substitutes for regulations, and compliance with them is not required. Methods and solutions that differ from those set forth in regulatory guides will be deemed acceptable if they provide a basis for the findings required for the issuance or continuance of a permit or license by the Commission.

This guide was issued after consideration of comments received from the public.

Regulatory guides are issued in 10 broad divisions: 1, Power Reactors; 2, Research and Test Reactors; 3, Fuels and Materials Facilities; 4, Environmental and Siting; 5, Materials and Plant Protection; 6, Products; 7, Transportation; 8, Occupational Health;

9, Antitrust and Financial Review; and 10, General.

Electronic copies of this guide and other recently issued guides are available through the NRCs public Web site under the Regulatory Guides document collection of the NRCs Electronic Reading Room at http://www.nrc.gov/reading-rm/doc-collections/ and through the NRCs Agencywide Documents Access and Management System (ADAMS) at http://www.nrc.gov/reading-rm/adams.html, under Accession No. ML003739575.

In 10 CFR 35.75(d), the licensee is required to maintain a record, for 3 years after the date of release, that instructions were provided to a breast-feeding woman if the radiation dose to the infant or child from continued breast-feeding could result in a total effective dose equivalent exceeding 5 millisieverts (0.5 rem).

In this guide, the individual to whom the radioactive material has been administered is called the patient.

This guide provides guidance to the licensee on determining (1) when the licensee may authorize the release of a patient who has been administered radiopharmaceuticals or permanent implants containing radioactive material, (2) when instructions to the patient are required by 10 CFR 35.75(b), and

(3) when records are required by 10 CFR 35.75(c) and (d) to be generated and maintained. The guide lists activities for commonly used radionuclides and their corresponding dose rates with which a patient may be released in compliance with the dose limits in 10 CFR 35.75.

The information collections contained in this regulatory guide are covered by the requirements in

10 CFR Part 35, which were approved by the Office of Management and Budget, approval number

3150-0010. The NRC may not conduct or sponsor, and a person is not required to respond to, a collection of information unless it displays a currently valid OMB control number.

B. DISCUSSION

The activities at which patients could be released were calculated by using, as a starting point, the method discussed in the National Council on Radiation Protection and Measurements (NCRP) Report No. 37, Precautions in the Management of Patients Who Have Received Therapeutic Amounts of Radionuclides (Ref. 1).

NCRP Report No. 37 uses the following equation to calculate the exposure until time t at a distance r from the patient:

0.693 t / Tp

34.6 Q 0 Tp (1 e )

D( t ) = 2 (Equation 1)

r Where D(t) = Accumulated exposure at time t, in roentgens,

34.6 = Conversion factor of 24 hrs/day times the total integration of decay (1.44),

= Specific gamma ray constant for a point source, R/mCi-hr at 1 cm, Q0 = Initial activity of the point source in millicuries, at the time of the release, Tp = Physical half-life in days, r = Distance from the point source to the point of interest in centimeters, t = Exposure time in days.

RG-8.39, Page 2

This guide uses the NCRP equation (Equation 1) in the following manner to calculate the activities at which-patients may be released.

  • The dose to an individual likely to receive the highest dose from exposure to the patient is taken

0.693 t / Tp to be the dose to total decay. Therefore, (1 e ) is set equal to 1.

  • It is assumed that 1 roentgen is equal to 10 millisieverts (1 rem).
  • The exposure rate constants and physical half-lives for radionuclides typically used in nuclear medicine and brachytherapy procedures are given in Appendix A to this guide.
  • Default activities at which patients may be released are calculated using the physical half-lives of the radionuclides and do not account for the biological half-lives of the radionuclides.
  • When release is based on biological elimination (i.e., the effective half-life) rather than just the physical half-life of the radionuclide, Equation 1 is modified to account for the uptake and retention of the radionuclide by the patient as discussed in Appendix B.
  • For radionuclides with a physical half-life greater than 1 day and no consideration of biological elimination, it is assumed that the individual likely to receive the highest dose from exposure to the patient would receive a dose of 25 percent of the dose to total decay (0.25 in Equation 2) at a distance of 1 meter. Selection of 25 percent of the dose to total decay at 1 meter for estimating the dose is based on measurements discussed in the supporting regulatory analysis (Ref. 2) that indicate the dose calculated using an occupancy factor, E, of 25 percent at 1 meter is conservative in most normal situations.
  • For radionuclides with a physical half-life less than or equal to 1 day, it is difficult to justify an occupancy factor of 0.25 because relatively long-term averaging of behavior cannot be assumed.

Under this situation, occupancy factors from 0.75 to 1.0 may be more appropriate.

Thus, for radionuclides with a physical half-life greater than 1 day:

34.6 Q 0 Tp (0.25)

D ( ) = (Equation 2)

(100 cm) 2 For radionuclides with a physical half-life less than or equal to 1 day and if an occupancy factor of 1.0 is used:

34.6 Q 0 Tp (1)

D ( ) = (Equation 3)

(100 cm) 2 Equations 2 and 3 calculate the dose from external exposure to gamma radiation. These equations do not include the dose from internal intake by household members and members of the public because the dose from intake by other individuals is expected to be small for most radiopharmaceuticals (less than a few percent) relative to the external gamma dose (see Section B.3, Internal Dose, of Appendix B). Further, the equations above do not apply to the dose to breast-feeding infants or children who continue to breast-feed. Patients who are breast-feeding an infant or child must be considered separately, as discussed in Regulatory Position 1.1, Release of Patients Based on Administered Activity.

RG-8.39, Page 3

C. REGULATORY POSITION

1. Release Criteria Licensees should use one of the following options to release a patient who has been administered radiopharmaceuticals or permanent implants containing radioactive material in accordance with regulatory requirements.

1.1 Release of Patients Based on Administered Activity In compliance with the dose limit in 10 CFR 35.75(a), licensees may release patients from licensee control if the activity administered is no greater than the activity in Column 1 of Table 1. The activities in Table 1 are based on a total effective dose equivalent of 5 millisieverts (0.5 rem) to an individual using conservative assumptions of (1) administered activity, (2) physical half-life,

(3) occupancy factor of 0.25 at 1 meter for physical half-lives greater than 1 day, and, for conservatism, an occupancy factor of 1 at 1 meter for physical half-lives less than or equal to 1 day, and (4) no shielding by tissue. The total effective dose equivalent is approximately equal to external dose because the internal dose is a small fraction of the external dose (see Section B.3, Internal Dose, of Appendix B). In this case, no record of the release of the patient is required unless the patient is breast-feeding an infant or child as discussed in Regulatory Position 3.2, Records of Instructions for Breast-Feeding Patients. The licensee may demonstrate compliance by using the records of activity that are already required by 10 CFR 35.32 and 35.53.

If the activity administered exceeds the activity in Column 1 of Table 1, the licensee may release the patient when the activity has decayed to the activity in Column 1 of Table 1. In this case, a record is required by 10 CFR 35.75(c) because the patients release is based on the retained activity rather than the administered activity. The activities in Column 1 of Table 1 were calculated using either Equation 2 or 3, depending on the physical half-life of the radionuclide.

If a radionuclide not listed in Table 1 is administered, the licensee can demonstrate compliance with the regulation by maintaining, for NRC inspection, a calculation of the release activity that corresponds to the dose limit of 5 millisieverts (0.5 rem). Equation 2 or 3 may be used, as appropriate, to calculate the activity Q corresponding to 5 millisieverts (0.5 rem).

The release activities in Column 1 of Table 1 do not include consideration of the dose to a breast- feeding infant or child from ingestion of radiopharmaceuticals contained in a patients breast milk. When the patient is breast-feeding an infant or child, the activities in Column 1 of Table 1 are not applicable to the infant or child. In this case, it may be necessary to give instructions as described in Regulatory Positions 2.2 and 2.3 as a condition for release. If failure to interrupt or discontinue could result in a dose to the breast-feeding infant or child in excess of 5 millisieverts (0.5 rem), a record that instructions were provided is required by 10 CFR 35.75(d).

1.2 Release of Patients Based on Measured Dose Rate Licensees may release patients to whom radionuclides have been administered in amounts greater than the activities listed in Column 1 of Table 1 provided the measured dose rate at I meter (from the surface of the patient) is no greater than the value in Column 2 of Table 1 for that radionuclide. In this case, however, 10 CFR 35.75(c) requires a record because the release is based on considering shielding by tissue.

RG-8.39, Page 4

Table 1. Activities and Dose Rates for Authorizing Patient Releasea COLUMN 1 COLUMN 2 ACTIVITY AT OR BELOW DOSE RATE AT 1 METER, AT OR

WHICH PATIENTS MAY BE BELOW WHICH PATIENTS MAY

RELEASED BE RELEASEDb RADIONUCLIDE (GBq) (mCi) (mSv/hr) (mrem/hr)

Ag-111 19 520 0.08 8 Au-198 3.5 93 0.21 21 Cr-51 4.8 130 0.02 2 Cu-64 8.4 230 0.27 27 Cu-67 14 390 0.22 22 Ga-67 8.7 240 0.18 18 I-123 6.0 160 0.26 26 I-125 0.25 7 0.01 1 I-125 implant 0.33 9 0.01 1 I-131 1.2 33 0.07 7 In-111 2.4 64 0.2 20

Ir-192 implant 0.074 2 0.008 0.8 P-32 (c) (c) (c) (c)

Pd-103 implant 1.5 40 0.03 3 Re-186 28 770 0.15 15 Re-188 29 790 0.20 20

Sc-47 11 310 0.17 17 Se-75 0.089 2 0.005 0.5 Sm-153 26 700 0.3 30

Sn-117m 1.1 29 0.04 4 Sr-89 (c) (c) (c) (c)

Tc-99m 28 760 0.58 58 Tl-201 16 430 0.19 19 Y-90 (c) (c) (c) (c)

Yb-169 0.37 10 0.02 2 a. The activity values were computed based on 5 millisieverts (0.5 rem) total effective dose equivalent.

b. If the release is based on the dose rate at 1 meter in Column 2, the licensee must maintain a record as required by 10 CFR 35.75(c) because the measurement includes shielding by tissue. See Regulatory Position 3.1, Records of Release, for information on records.

c. Activity and dose rate limits are not applicable in this case because of the minimal exposures to members of the public resulting from activities normally administered for diagnostic or therapeutic purposes.

NOTES: The millicurie values were calculated using Equations 2 or 3 and the physical half-life. The gigabecquerel values were calculated based on the millicurie values and the conversion factor from millicuries to gigabecquerels.

The dose rate values are calculated based on the millicurie values and the exposure rate constants. In general, the values are rounded to two significant figures. However, values less than 0.37 gigabecquerel (10 millicuries) or 0.1 millisievert (10 millirems) per hour are rounded to one significant figure. Details of the calculations are provided in NUREG-1492 (Ref. 2).

Although non-byproduct materials are not regulated by the NRC, information on non-byproduct material is included in this regulatory guide for the convenience of the licensee.

Agreement State regulations may vary. Agreement State licensees should check with their State regulations prior to using these values.

RG-8.39, Page 5

If a radionuclide not listed in Table 1 is administered and the licensee chooses to release a patient based on the measured dose rate, the licensee should first calculate a dose rate that corresponds to the

5 millisievert (0.5-rem) dose limit. If the measured dose rate at 1 meter is no greater than the calculated dose rate, the patient may be released. A record of the release is required by 10-CFR 35.75(c). The dose rate at 1 meter may be calculated from Equation 2 or 3, as appropriate, because the dose rate at 1 meter is equal to Q/10,000 cm2.

1.3 Release of Patients Based on Patient-Specific Dose Calculations Licensees may release patients based on dose calculations using patient-specific parameters.

With this method, based on 10 CFR 35.75(a), the licensee must calculate the maximum likely dose to an individual exposed to the patient on a case-by-case basis. If the calculated maximum likely dose to an individual is no greater than 5 millisieverts (0.5 rem), the patient may be released. Using this method, licensees may be able to release patients with activities greater than those listed in Column 1 of Table 1 by taking into account the effective half-life of the radioactive material and other factors that may be relevant to the particular case. If the dose calculation considered retained activity, an occupancy factor less than 0.25 at 1 meter, effective half-life, or shielding by tissue, a record of the basis for the release is required by 10 CFR 35.75(c).

Appendix B contains procedures for performing patient-specific dose calculations, and it describes how various factors may be considered in the calculations.

2. Instructions

2.1 Activities and Dose Rates Requiring Instructions Based on 10 CFR 35.75(b), for some administrations the released patients must be given instructions, including written instructions, on how to maintain doses to other individuals as low as is reasonably achievable after the patients are released.1 Licensees may use Column 1 of Table 2 to determine the activity above which instructions must be given to patients. Column 2 provides corresponding dose rates at 1 meter, based on the activities in Column 1. If the patient is breast-feeding an infant or child, additional instructions may be necessary (see Regulatory Position 2.2, Additional Instructions for Release of Patients Who Could be Breast-Feeding After Release).

The activities or dose rates in Table 2 may be used for determining when instructions must be given. When patient-specific calculations (as described in Appendix B) are used, instructions must be provided if the calculation indicates a dose that is greater than 1 millisievert (0.1 rem).

If a radionuclide not listed in Table 2 is administered, the licensee may calculate the activity or dose rate that corresponds to 1 millisievert (0.1 rem). Equation 2 or 3, as appropriate, may be used.

2.2 Additional Instructions for Release of Patients Who Could be Breast-Feeding After Release The requirement in 10 CFR 35.75(b) that a licensee provide instructions on the discontinuation or the interruption period of breast-feeding, and the consequences of failing to follow the recommendation, presumes that the licensee will inquire, as appropriate, regarding the breast-feeding status of the patient.1 The purpose of the instructions (e.g., on interruption or discontinuation) is to permit licensees to release a patient who could be breast-feeding an infant or child when the dose to the infant or child could exceed

5 millisieverts (0.5 rem) if there is no interruption of breast-feeding.

1 The NRC does not intend to enforce patient compliance with the instructions nor is it the licensees responsibility to do so.

RG-8.39, Page 6

If the patient could be breast-feeding an infant or child after release, and if the patient was administered a radiopharmaceutical with an activity above the value stated in Column 1 of Table 3, instructions on discontinuation or on the interruption period for breast-feeding and the consequences of failing to follow the recommendation must be provided. The patient should also be informed if there would be no consequences to the breast-feeding infant or child. Table 3 also provides recommendations for interrupting or discontinuing breastfeeding to minimize the dose to below 1 millisievert (0.1 rem) if the patient has received certain radiopharmaceutical doses. The radiopharmaceuticals listed in Table 3 are commonly used in medical diagnosis and treatment.

If a radiopharmaceutical not listed in Table 3 is administered to a patient who could be breast- feeding, the licensee should evaluate whether instructions or records (or both) are required. If information on the excretion of the radiopharmaceutical is not available, an acceptable method is to assume that 50 percent of the administered activity is excreted in the breast milk (Ref. 2). The dose to the infant or child can be calculated by using the dose conversion factors given for a newborn infant by Stabin (Ref. 3).

2.3 Content of Instructions The instructions should be specific to the type of treatment given, such as permanent implants or radioiodine for hyperthyroidism or thyroid carcinoma, and they may include additional information for individual situations. However, the instructions should not interfere with or contradict the best medical judgment of physicians. The instructions may include the name of a knowledgeable person to contact and that persons telephone number in case the patient has any questions.

Additional instructions appropriate for each modality, as shown in examples below, may be provided.

2.3.1 Instructions Regarding Radiopharmaceutical Administrations For procedures involving radiopharmaceuticals, additional instructions may include the following.

  • Maintaining distance from other persons, including separate sleeping arrangements.

Minimizing time in public places (e.g., public transportation, grocery stores, shopping centers, theaters, restaurants, sporting events).

  • Precautions to reduce the spread of radioactive contamination.
  • The length of time each of the precautions should be in effect.

RG-8.39, Page 7

Table 2. Activities and Dose Rates Above Which Instructions Should be Given When Authorizing Patient Releasea COLUMN 2 COLUMN 1 DOSE RATE AT 1 METER ABOVE

ACTIVITY ABOVE WHICH WHICH INSTRUCTIONS ARE

INSTRUCTIONS ARE REQUIRED REQUIRED

RADIONUCLIDE (GBq) (mCi) (mSv/hr) (mrem/hr)

Ag-111 3.8 100 0.02 2 Au-198 0.69 19 0.04 4 Cr-51 0.96 26 0.004 0.4 Cu-64 1.7 45 0.05 5 Cu-67 2.9 77 0.04 4 Ga-67 1.7 47 0.04 4 I-123 1.2 33 0.05 5 I-125 0.05 1 0.002 0.2 I-125 implant 0.074 2 0.002 0.2 I-131 0.24 7 0.02 2 In-111 0.47 13 0.04 4 Ir-192 implant 0.011 0.3 0.002 0.2 P-32 (b) (b) (b) (b)

Pd-103 implant 0.3 8 0.007 0.7 Re-186 5.7 150 0.03 3 Re-188 5.8 160 0.04 4 Sc-47 2.3 62 0.03 3 Se-75 0.018 0.5 0.001 0.1 Sm-153 5.2 140 0.06 6 Sn-117m 0.21 6 0.009 0.9 Sr-89 (b) (b) (b) (b)

Tc-99m 5.6 150 0.12 12 Tl-201 3.1 85 0.04 4 Y-90 (b) (b) (b) (b)

Yb-169 0.073 2 0.004 0.4 a. The activity values were computed based on 1 millisievert (0.1 rein) total effective dose equivalent.

b. Activity and dose rate limits are not applicable in this case because of the minimal exposures to members of the public resulting from activities normally administered for diagnostic or therapeutic purposes.

NOTES: The millicurie values were calculated using Equations 2 or 3 and the physical half-life. The gigabecquerel values were calculated based on millicurie values and the conversion factor from millicuries to gigabecquerels. The dose rate values were calculated based on millicurie values and exposure rate constants. In general, values are rounded to two significant figures. However, values less than 0.37 gigabecquerel (10

millicuries) or 0.1 millisievert (10 millirems) per hour are rounded to one significant figure. Details of the calculations are provided in NUREG-1492 (Ref. 2).

Although non-byproduct materials are not regulated by the NRC, information on non-byproduct material is included in this regulatory guide for the convenience of the licensee.

Agreement State regulations may vary. Agreement State licensees should check with their State regulations prior to using these values.

RG-8.39, Page 8

Table 3. Activities of Radiopharmaceuticals that Require Instructions and Records When Administered to Patients Who Are Breast-Feeding an Infant or Child COLUMN 1 COLUMN 2 COLUMN 3 ACTIVITY ACTIVITY EXAMPLES OF

ABOVE WHICH ABOVE WHICH RECOMMENDED

INSTRUCTIONS A RECORD IS DURATION OF

ARE REQUIRED REQUIRED INTERRUPTION OF

RADIOPHARMACEUTICAL (MBq) (mCi) (MBq) (mCi) BREAST-FEEDINGa I-131 NaI 0.01 0.0004 0.07 0.002 Complete cessation (for this infant or child)

I-123 NaI 20 0.5 100 3 I-123 OIH 100 4 700 20

I-123 mIBG 70 2 400 10 24 hr for 370 MBq

(10 mCi)

I-125 OIH 3 0.08 10 0.4 I-131 OIH 10 0.30 60 1.5 Tc-99m DTPA 1,000 30 6,000 150

Tc-99m MAA 50 1.3 200 6.5 12.6 hr for 150 MBq

(4 mCi)

Tc-99m Pertechnetate 100 3 600 15 24 hr for 1,100 MBq

(30 mCi)

12 hr for 440 MBq

(12 mCi)

Tc-99m DISIDA 1,000 30 6,000 150

Tc-99m Glucoheptonate 1,000 30 6,000 170

Tc-99m HAM 400 10 2,000 50

Tc-99m MIBI 1,000 30 6,000 150

Tc-99m MDP 1,000 30 6,000 150

Tc-99m PYP 900 25 4,000 120

Tc-99m Red Blood Cell In Vivo 400 10 2,000 50 6 hr for 740 MBq Labeling (20 mCi)

Tc-99m Red Blood Cell In Vitro 1,000 30 6,000 150

Labeling Tc-99m Sulphur Colloid 300 7 1,000 35 6 hr for 440 MBq

(12 mCi)

Tc-99m DTPA Aerosol 1,000 30 6,000 150

Tc-99m MAG3 1,000 30 6,000 150

Tc-99m White Blood Cells 100 4 600 15 24 hr for 1,100 MBq

(5 mCi)

12 hr for 440 MBq

(2 mCi)

GA-67 Citrate 1 0.04 7 0.2 1 month for 150 MBq

(4 mCi)

2 weeks for 50 MBq

(1.3 mCi)

1 week for 7 MBq

(0.2 mCi)

RG-8.39, Page 9

COLUMN 1 COLUMN 2 COLUMN 3 ACTIVITY ACTIVITY EXAMPLES OF

ABOVE WHICH ABOVE WHICH RECOMMENDED

INSTRUCTIONS A RECORD IS DURATION OF

ARE REQUIRED REQUIRED INTERRUPTION OF

RADIOPHARMACEUTICAL (MBq) (mCi) (MBq) (mCi) BREAST-FEEDINGa Cr-51 EDTA 60 1.6 300 8 In-111 White Blood Cells 10 0.2 40 1 1 week for 20 MBq

(0.5 mCi)

Tl-201 Chloride 40 1 200 5 2 weeks for 110 MBq

(3 mCi)

a. The duration of interruption of breast-feeding is selected to reduce the maximum dose to a newborn infant to less than 1 millisievert (0.1 rem), although the regulatory limit is 5 millisieverts (0.5 rem). The actual doses that would be received by most infants would be far below 1 millisievert (0.1 rem). Of course, the physician may use discretion in the recommendation, increasing or decreasing the duration of interruption.

NOTES: Activities are rounded to one significant figure, except when it was considered appropriate to use two significant figures. Details of the calculations are shown in NUREG-1492, Regulatory Analysis on Criteria for the Release of Patients Administered Radioactive Material (Ref. 2). If there is no recommendation in Column 3 of this table, the maximum activity normally administered is below the activities that require instructions on interruption or discontinuation of breast-feeding.

Although non-byproduct materials are not regulated by the NRC, information on non-byproduct material is included in this regulatory guide for the convenience of the licensee.

Agreement State regulations may vary. Agreement State licensees should check with their State regulations prior to using these values.

The Society of Nuclear Medicine published a pamphlet in 1987 that provides information for patients receiving treatment with radioiodine (Ref. 4). This pamphlet was prepared jointly by the Society of Nuclear Medicine and the NRC. The pamphlet contains blanks for the physician to fill in the length of time that each instruction should be followed. While this pamphlet was written for the release of patients to whom less than 1,110 megabecquerels (30 millicuries) of iodine-131 had been administered, the NRC

still considers the instructions in this pamphlet to be an acceptable method for meeting the requirements of 10 CFR 35.75(b) provided the times filled in the blanks are appropriate for the activity and the medical condition.

If additional instructions are required because the patient is breast-feeding, the instructions should include appropriate recommendations on whether to interrupt breast-feeding, the length of time to interrupt breast-feeding, or, if necessary, the discontinuation of breast-feeding. The instructions should include information on the consequences of failure to follow the recommendation to interrupt or discontinue breastfeeding. The consequences should be explained so that the patient will understand that, in some cases, breastfeeding after an administration of certain radionuclides should be avoided. For example, a consequence of procedures involving iodine-131 is that continued breastfeeding could harm the infants or childs thyroid. Most diagnostic procedures involve radionuclides other than radioiodine and there would be no consequences; guidance should simply address avoiding any unnecessary radiation exposure to the infant or child from breast-feeding. If the Society of Nuclear Medicines pamphlet is given at release to a patient who is breastfeeding an infant or child, the pamphlet should be supplemented with information specified in 10 CFR 35.75(b)(1) and (2).

The requirement of 10 CFR 35.75(b) regarding written instructions to patients who could be breastfeeding an infant or child does not in any way interfere with the discretion and judgment of the physician in specifying the detailed instructions and recommendations.

RG-8.39, Page 10

2.3.2 Instructions Regarding Permanent Implants For patients who have received permanent implants, additional instructions may include the following.

A small radioactive source has been placed (implanted) inside your body. The source is actually many small metallic pellets or seeds, which are each about 1/3 to 1/4 of an inch long, similar in size and shape to a grain of rice. To minimize exposure to radiation to others from the source inside your body, you should do the following for ______ days.

  • Stay at a distance of _____ feet from _____________________.
  • Maintain separate sleeping arrangements.
  • Minimize time with children and pregnant women.
  • Do not hold or cuddle children.
  • Avoid public transportation.
  • Examine any bandages or linens that come into contact with the implant site for any pellets or seeds that may have come out of the implant site.
  • If you find a seed or pellet that falls out:

- Do not handle it with your fingers. Use something like a spoon or tweezers to place it in a jar or other container that you can close with a lid.

- Place the container with the seed or pellet in a location away from people.

- Notify one of the persons listed in this instruction.

3. Records

3.1 Records of Release There is no requirement for recordkeeping on the release of patients who were released in accordance with Column 1 of Table 1. However, if the release of the patient is based on a dose calculation that considered retained activity, an occupancy factor less than 0.25 at 1 meter, effective half- life, or shielding by tissue, a record of the basis for the release is required by 10 CFR 35.75(c). This record should include the patient identifier (in a way that ensures that confidential patient information is not traceable or attributable to a specific patient), the radioactive material administered, the administered activity, and the date of the administration. In addition, depending on the basis for release, records should include the following information.

1. For Immediate Release of a Patient Based on a Patient-Specific Calculation: The equation used, including the patient-specific factors and their bases that were used in calculating the dose to the person exposed to the patient, and the calculated dose. The patient-specific factors (see Appendix B of this guide) include the effective half-life and uptake fraction for each component RG-8.39, Page 11

of the biokinetic model, the time that the physical half-life was assumed to apply to retention, and the occupancy factor. The basis for selecting each of these values should be included in the record.

2. For Immediate Release of a Patient Based on Measured Dose Rate: The results of the measurement, the specific survey instrument used, and the name of the individual performing the survey.

3. For Delayed Release of a Patient Based on Radioactive Decay Calculation: The time of the administration, date and time of release, and the results of the decay calculation.

4. For Delayed Release of a Patient Based on Measured Dose Rate: The results of the survey meter measurement, the specific survey instrument used, and the name of the individual performing the survey.

In some situations, a calculation may be case-specific for a class of patients who all have the same patient-specific factors. In this case, the record for a particular patients release may reference the calculation for the class of patients.

Records, as required by 10 CFR 35.75(c), should be kept in a manner that ensures the patients confidentiality, that is, the records should not contain the patients name or any other information that could lead to identification of the patient. These recordkeeping requirements may also be used to verify that licensees have proper procedures in place for assessing potential third-party exposure associated with and arising from exposure to patients administered radioactive material.

3.2 Records of Instructions for Breast-Feeding Patients If failure to interrupt or discontinue breast-feeding could result in a dose to the infant or child in excess of 5 millisieverts (0.5 rem), a record that instructions were provided is required by 10 CFR 35.75(d). Column 2 of Table 3 states, for the radiopharmaceuticals commonly used in medical diagnosis and treatment, the activities that would require such records when administered to patients who are breast- feeding.

The record should include the patients identifier (in a way that ensures that confidential patient information is not traceable or attributable to a specific patient), the radiopharmaceutical administered, the administered activity, the date of the administration, and whether instructions were provided to the patient who could be breast-feeding an infant or child.

4. Summary Table Table 4 summarizes the criteria for releasing patients and the requirements for providing instructions and maintaining records.

D. IMPLEMENTATION

The purpose of this section is to provide information to licensees and applicants regarding the NRC staffs plans for using this regulatory guide.

Except in those cases in which a licensee proposes an acceptable alternative method for complying with 10 CFR 35.75, the methods described in this guide will be used in the evaluation of a licensees compliance with 10 CFR 35.75.

RG-8.39, Page 12

REGULATORY ANALYSIS

Regulatory Analysis on Criteria for the Release of Patients Administered Radioactive Material (NUREG-1492, February 1997), provides the regulatory basis for this guide and examines the costs and benefits. A copy of NUREG-1492 is available for inspection and copying for a fee at the NRC Public Document Room, 2120 L Street NW., Washington, DC. Copies may be purchased at current rates from the U.S. Government Printing Office, P.O. Box 37082, Washington, DC 20402-9328 (telephone (202)

512-2249); or from the National Technical Information Service by writing NTIS at 5285 Port Royal Road, Springfield, VA 22161.

RG-8.39, Page 13

Table 4. Summary of Release Criteria, Required Instructions to Patients, and Records To Be Maintained CRITERIA FOR RELEASE RECORDS

PATIENT GROUP BASIS FOR RELEASE RELEASE INSTRUCTIONS NEEDED? REQUIRED?

All patients, Administered activity Administered activity Yes - if administered activity No including patients Column 1 of Table 1 > Column 1 of Table 2 who are breast- feeding an infant or child Retained activity Retained activity Yes - if retained activity Yes RG-8.39, Page 14 Column 1 of Table 1 > Column 1 of Table 2 Measured dose rate Measured dose rate Yes - if dose rate > Column 2 Yes Column 2 of Table 1 of Table 2 Patient-specific Calculated dose 5 mSv Yes - if calculated dose Yes calculations (0.5 rem) > 1 mSv (0.1 rem)

Patients who are All the above bases for Additional instructions required Records that instructions were breast-feeding an release if: provided if:

infant or child Administered activity Administered activity > Column

> Column 1 of Table 3 2 of Table 3 or or Licensee calculated dose from Licensee calculated dose from breast-feeding > 1 mSv continued breast-feeding > 5 mSv

(0.1 rem) to the infant or child (0.5 rem) to the infant or child

REFERENCES

1. National Council on Radiation Protection and Measurements (NCRP), Precautions in the Management of Patients Who Have Received Therapeutic Amounts of Radionuclides, NCRP

Report No. 37, October 1, 1970. (Available for sale from the NCRP, 7910 Woodmont Avenue, Suite 800, Bethesda, MD 20814-3095.)

2. S. Schneider and S. A. McGuire, Regulatory Analysis on Criteria for the Release of Patients Administered Radioactive Material, NUREG1492 (Final Report), NRC, February 1997.2

3. M. Stabin, Internal Dosimetry in Pediatric Nuclear Medicine, in Pediatric Nuclear Medicine, Edited by S. Treves, Springer Verlag, New York, 1995.

4. Guidelines for Patients Receiving Radioiodine Treatment, Society of Nuclear Medicine, 1987.

This pamphlet may be obtained from the Society of Nuclear Medicine, 1850 Samuel Morse Drive, Reston, VA 20190-5316.

2 Copies may be purchased at current rates from the U.S. Government Printing Office, P. 0. Box 37082, Washington, DC

20402-9328 (telephone (202) 512-2249; or from the National Technical Information service by writing NTIS at 5285 Port Royal Road, Springfield, VA22161. Copies are also available for inspection and copying for a fee from the NRC

Public Document Room at 2120 L Street NW. (Lower Level), Washington, DC. The PDRs mailing address is Mail Stop LL-6, Washington, DC 20555; telephone (202) 634-3273; fax (202) 634-3343.

RG-8.39, Page 15

APPENDIX A

Table A-1. Half-Lives and Exposure Rate Constants of Radionuclides Used in Medicine EXPOSURE EXPOSURE

RATE RATE

HALF- CONSTANTc HALF- CONSTANTc LIFE (R/mCi-h LIFE (R/mCi-h at 1 RADIONUCLIDEa (DAYS)b at 1 cm) RADIONUCLIDEa (DAYS)b cm)

Ag-111 7.45 0.150 Pd-103 implant 16.96 0.86e Au-198 2.696 2.3 Re-186 3.777 0.2 Cr-51 27.704 0.16 Re-188 0.708 0.26 Cu-64 0.529 1.2 Sc-47 3.351 0.56 Cu-67 2.578 0.58 Se-75 119.8 2.0

Ga-67 3.261 0.753 Sm-153 1.946 0.425 I-123 0.55 1.61 Sn-117m 13.61 1.48 I-125 60.14 1.42 Sr-89 50.5 NAf I-125 implant 60.14 1.11d Tc-99m 0.251 0.756 I-131 8.04 2.2 TI-201 3.044 0.447 In-111 2.83 3.21 Y-90 2.67 NAf Ir-192 implant 74.02 4.594 Yb-169 32.01 1.83 P-32 14.29 NAf a. Although non-byproduct materials are not regulated by the NRC, information on non-byproduct material is included in this regulatory guide for the convenience of the licensee.

b. K. F. Eckerman, A. B. Wolbarst, and A. C. B. Richardson, Federal Guidance Report No. 11, Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion, Report No. EPA-520/1-88-020, Office of Radiation Programs, U.S. Environmental Protection Agency, Washington, DC, 1988.

c. Values for the exposure rate constant for Au-198, Cr-51, Cu-64,1-131, Sc-47, and Se-75 were taken from the Radiological Health Handbook, U.S. Department of Health, Education, and Welfare, pg. 135, 1970. For Cu-

67,1-123, In-111, Re-186, and Re-188, the values for the exposure rate constant were taken from D. E.

Barber, J. W. Baum, and C. B. Meinhold, Radiation Safety Issues Related to Radiolabeled Antibodies, NUREG/CR-4444, U.S. NRC, Washington, DC, 1991. For Ag-111, Ga-67,1-125, Sm-153, Sn-117m, Tc-

99m, T1-201, and Yb-169, the exposure rate constants were calculated because the published values for these radionuclides were an approximation, presented as a range, or varied from one reference to another. Details of the calculation of the exposure rate constants are shown in Table A.2 of Appendix A to NUREG-1492, Regulatory Analysis on Criteria for the Release of Patients Administered Radioactive Material, U.S. NRC,

February 1997.

d. R. Nath, A. S. Meigooni, and J. A. Meli, Dosimetry on Transverse Axes of 125I and 192Ir Interstitial Brachytherapy Sources, Medical Physics, Volume 17, Number 6, November/December 1990. The exposure rate constant given is a measured value averaged for several source models and takes into account the attenuation of gamma rays within the implant capsule itself.

e. A. S. Meigooni S. Sabnis, R. Nath, Dosimetry of Palladium-103 Brachytherapy Sources for Permanent Implants, Endocurietherapy Hyperthermia Oncology, Volume 6, April 1990. The exposure rate constant given is an apparent value (i.e., with respect to an apparent source activity) and takes into account the attenuation of gamma rays within the implant capsule itself.

f. Not applicable (NA) because the release activity is not based on beta emissions.

Appendix A to RG-8.39, Page A-1

APPENDIX B

PROCEDURES FOR CALCULATING DOSES

BASED ON PATIENT-SPECIFIC FACTORS

A licensee may release a patient who has been administered an activity higher than the values listed in Column 1 of Table 1 of this regulatory guide if dose calculations using patient-specific parameters, which are less conservative than the conservative assumptions, show that the potential total effective dose equivalent to any individual would be no greater than 5 millisieverts (0.5 rem).

If the release of a patient is based on a patient-specific calculation that considered retained activity, an occupancy factor less than 0.25 at 1 meter, effective half-life, or shielding by tissue, a record of the basis of the release is required by 10 CFR 35.75(c).

The following equation can be used to calculate doses:

0.693 t / Tp

34.6 Q 0 TE (1 e )

D( t ) = (Equation B-1)

r2 Where D(t) = Accumulated dose to time t, in rems

34.6 = Conversion factor of 24 hrs/day times the total integration of decay (1.44)

F = Exposure rate constant for a point source, R/mCi x hr at 1 cm Q0 = Initial activity at the start of the time interval Tp = Physical half-life in days E = Occupancy factor that accounts for different occupancy times and distances when an individual is around a patient r = Distance in centimeters. This value is typically 100 cm t = exposure time in days B-1. Occupancy Factor B-1.1 Rationale for Occupancy Factors Used To Derive Table 1 In Table 1 in Regulatory Guide 8.39, the activities at which patients could be released were calculated using the physical half-life of the radionuclide and an occupancy factor at 1 meter of either

0.25 (if the radionuclide has a half-life longer than 1 day) or 1.0 (if the radionuclide has a half-life less than or equal to 1 day). The basis for the occupancy factor of 0.25 at 1 meter is that measurements of doses to family members as well as considerations of normal human behavior (as discussed in the supporting regulatory analysis (Ref. B-1)) suggest that an occupancy factor of 0.25 at 1 meter, when used in combination with the physical half-life, will produce a generally conservative estimate of the dose to family members when instructions on minimizing doses to others are given.

Appendix B to RG-8.39, Page B-1

An occupancy factor of 0.25 at 1 meter is not considered appropriate when the physical half-life is less than or equal to 1 day, and hence, the dose is delivered over a short time. Specifically, the assumptions regarding patient behavior that led to an occupancy factor of 0.25 at 1 meter include the assumption that the patient will not be in close proximity to other individuals for several days. However, when the dose is from a short-lived radionuclide, the time that individuals spend in close proximity to the patient immediately following release will be most significant because the dose to other individuals could be a large fraction of the total dose from the short-lived radionuclide. Thus, to be conservative when providing generally applicable release quantities that may be used with little consideration of the specific details of a particular patients release, the values calculated in Table I were based on an occupancy factor of 1 at 1 meter when the half-life is less than or equal to 1 day.

B-1.2 Occupancy Factors To Consider for Patient-Specific Calculations The selection of an occupancy factor for patient-specific calculations will depend on whether the physical or effective half-life of the radionuclide is used and whether instructions are provided to the patient before release. The following occupancy factors, E, at 1 meter, may be used for patient-specific calculations.

  • E = 0.75 when a physical half-life, an effective half-life, or a specific time period under consideration (e.g., bladder holding time) is less than or equal to 1 day.
  • E = 0.25 when an effective half-life is greater than 1 day if the patient has been given instructions, such as,

- Maintain a prudent distance from others for at least the first 2 days,

- Sleep alone in a room for at least the first night, Do not travel by airplane or mass transportation for at least the first day,

- Do not travel on a prolonged automobile trip with others for at least the first 2 days,

- Have sole use of a bathroom for at least the first 2 days,

- Drink plenty of fluids for at least the first 2 days.

  • E = 0.125 when an effective half-life is greater than 1 day if the patient has been given instructions, such as,

- Follow the instructions for E = 0.25 above,

- Live alone for at least the first 2 days,

- Have few visits by family or friends for at least the first 2 days.

  • In a two-component model (e.g., uptake of iodine-131 using thyroidal and extrathyroidal components), if the effective half-life associated with one component is less than or equal to one day but is greater than one day for the other component, it is more justifiable to use the occupancy factor associated with the dominant component for both components.

Example 1: Calculate the maximum likely dose to an individual exposed to a patient who has received 2,220 megabecquerels (60 millicuries) of iodine-131. The patient has been provided with instructions to maintain a prudent distance from others for at least 2 days, lives alone, drives home alone, and stays at home for several days without visitors.

Appendix B to RG-8.39, Page B-2

Solution: The dose to total decay (t = ) is calculated based on the physical half-life using Equation B-1. (This calculation illustrates the use of physical half-life. To account for biological elimination, calculations described in the next section should be used.)

34.6 Q 0 Tp E

D ( ) =

r2 Since the patient has been provided with instructions for reducing exposure as recommended for an occupancy factor of E = 0.125, the occupancy factor of 0.125 at 1 meter may be used.

34.6 (2.2R

  • cm 2 / mCi
  • hr )(60mCi)(8.04 d )(0.125)

D( ) =

(100 cm) 2 D() = 4.59 millisieverts (0.459 rem)

Since the dose is less than 5 millisieverts (0.5 rem), the patient may be released, but 10 CFR 35.75(b) requires that instructions be given to the patient on maintaining doses to others as low as is reasonably achievable. A record of the calculation must be maintained pursuant to 10 CFR 35.75(c)

because an occupancy factor less than 0.25 at 1 meter was used.

B-2. Effective Half-Life A licensee may take into account the effective half-life of the radioactive material to demonstrate compliance with the dose limits for individuals exposed to the patient that are stated in 10 CFR 35.75.

The effective half-life is defined as:

Tb x Tp Teff = (Equation B-2)

Tb + Tp Where Tb = biological half-life of the radionuclide Tp = physical half-life of the radionuclide.

The behavior of iodine-131 can be modeled using two components: extrathyroidal iodide (i.e.,

existing outside of the thyroid) and thyroidal iodide following uptake by the thyroid. The effective half- lives for the extrathyroidal and thyroidal fractions (i.e., F1 and F2, respectively) can be calculated with the following equations.

Tb1 x Tp T1eff = (Equation B-3)

Tb1 + Tp Tb 2 x Tp T2 eff = (Equation B-4)

Tb 2 + Tp Tb1 = biological half-life for extrathyroidal iodide Tb2 = biological half-life of iodide following uptake by the thyroid Tp = physical half-life of iodine-131.

Appendix B to RG-8.39, Page B-3

However, simple exponential excretion models do not account for (a) the time for the iodine-131 to be absorbed from the stomach to the blood and (b) the holdup of iodine in the urine while in the bladder. Failure to account for these factors could result in an underestimate of the dose to another individual. Therefore, this guide makes a conservative approximation to account for these factors by assuming that, during the first 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> after the administration, about 80 percent of the iodine-131 administered is removed from the body at a rate determined only by the physical half-life of iodine-131.

Thus, an equation to calculate the dose from a patient administered iodine-131 may have three components. The first component is the dose for the first 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> (0.33 day) after administration. This component comes directly from Equation B-1 using the physical half-life and a factor of 80 percent. The second component is the dose from the extrathyroidal component from 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to total decay. In this component, the first exponential factor represents the activity at t = 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> based on the physical half-life of iodine-131. The second exponential factor represents the activity from t = 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to total decay based on the effective half-life of the extrathyroidal component. The third component, the dose from the thyroidal component for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to total decay, is calculated in the same manner as the second component. The full equation is shown as Equation B-5.

D ( ) =

34.6Q 0

(100cm) 2

{ E1Tp (0.8)(1 e

0.693( 0.33) / Tp

)}

0.693( 0.33) / Tp 0.693( 0.33) / Tp

+e E 2 F1 T1eff + e E 2 F2 T2ef f (Equation B-5)

F1 = Extrathyroidal uptake fraction F2 = Thyroidal uptake fraction El = Occupancy factor for the first 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> E2 = Occupancy factor from 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to total decay.

All the other parameters are as defined in Equations B-1, B-3, and B-4. Acceptable values for F1, T1eff, F2, and T2eff are shown in Table B-1 for thyroid ablation and treatment of thyroid remnants after surgical removal of the thyroid for thyroid cancer. If these values have been measured for a specific individual, the measured values may be used.

The record of the patients release required by 10 CFR 35.75(c) is described in Regulatory Position 3.1 of this guide.

Example 2, Thyroid Cancer: Calculate the maximum likely dose to an individual exposed to a patient who has been administered 7,400 megabecquerels (200 millicuries) of iodine-131 for the treatment of thyroid remnants and metastases.

Solution: In this example, we will calculate the dose by using Equation B-5 to account for the elimination of iodine-131 from the body, based on the effective half-lives appropriate for thyroid cancer.

The physical half-life and the exposure rate constant are from Table A-1. The uptake fractions and effective half-lives are from Table B-1. An occupancy factor, E, of 0.75 at 1 meter will be used for the first component because the time period under consideration is less than 1 day. However, for the second and third components, an occupancy factor of 0.25 will be used because (1) the effective half-life associated with the dominant component is greater than 1 day and (2) patient-specific questions were provided to the patient to justify the occupancy factor (see Section B.1.2, Occupancy Factors To Consider for Patient-Specific Calculations, of this Appendix B).

Appendix B to RG-8.39, Page B-4

Table B-1. Uptake Fractions and Effective Half-Lives for Iodine-131 Treatments Extrathyroidal Component Thyroidal Component Uptake Fraction Effective Half-Life Uptake Fraction Effective Half-Life Medical Condition F1 T1eff (day) F2 T2eff (day)

Hyperthyroidism 0.20a 0.32b 0.80a 5.2a Postthyroidectomy 0.95c 0.32b 0.05c 7.3b for Thyroid Cancer a. M. G. Stabin et al., Radiation Dosimetry for the Adult Female and Fetus from Iodine-131 Administration in Hyperthyroidism, Journal of Nuclear Medicine, Volume 32, Number 5, May 1991. The thyroid uptake fraction of 0.80 was selected as one that is seldom exceeded by the data shown in Figure 1 in this referenced document. The effective half-life of 5.2 days for the thyroidal component was derived from a biological half- life of 15 days, which was obtained from a straight-line fit that accounts for about 75 percent of the data points shown in Figure 1 of this Journal of Nuclear Medicine document.

b. International Commission on Radiological Protection (ICRP), Radiation Dose to Patients from Radiopharmaceuticals, ICRP Publication No. 53, March 1987. (Available for sale from Pergamon Press, Inc., Elmsford, NY 10523.) The data in this ICRP document suggest that the extrathyroidal component effective half-life in normal subjects is about 0.32 days. Lacking other data, this value is applied to hyperthyroid and thyroid cancer patients. For thyroid cancer, the thyroidal component effective half-life of

7.3 days is based on a biological half-life of 80 days (adult thyroid) as suggested in this ICRP document.

c. The thyroidal uptake fraction of 0.05 was recommended by Dr. M. Pollycove, M.D., NRC medical visiting fellow, as an upper limit postthyroidectomy for thyroid cancer.

Substituting the appropriate values into Equation B-5, the dose to total decay is D ( ) =

34.6(2.2)(200)

(100 cm) 2

{(0.75)(8.04)(0.8)(1 e 0.693( 0.33) / 8.04 )}

+ e 0.693( 0.33) / 8.04 (0.25)(0.95)(0.32)

+ e 0.693( 0.33) / 8.04 (0.25)(0.05)(7.3)

D() = 4.53 millisieverts (0.453 rem)

Therefore, thyroid cancer patients administered 7,400 megabecquerels (200 millicuries) of iodine-131 or less would not have to remain under licensee control and could be released under

10 CFR 35.75, assuming that the foregoing assumptions can be justified for the individual patients case and that the patient is given instructions. Patients administered somewhat larger activities could also be released immediately if the dose is not greater than 5 millisieverts (0.5 rem).

In the example above, the thyroidal fraction, F2 = 0.05, is a conservative assumption for persons who have had surgery to remove thyroidal tissue. If F2 has been measured for a specific patient, the measured value may be used.

Example 3, Hyperthyroidism: Calculate the maximum likely dose to an individual exposed to a patient who has been administered 2,035 megabecquerels (55 millicuries) of iodine-131 for the treatment of hyperthyroidism (i.e., thyroid ablation).

Appendix B to RG-8.39, Page B-5

Solution: In this example, we will again calculate the dose using Equation B-5, Table A-1, and Table B-1 to account for the elimination of iodine-131 from the body by using the effective half-lives appropriate for hyperthyroidism. An occupancy factor, E, of 0.25 at 1 meter will be used for the second and third components of the equation because patient-specific instructions were provided to justify the occupancy factor (see Section B.1.2, Occupancy Factors To Consider for Patient-Specific Calculations).

Substituting the appropriate values into Equation B-5, the dose to total decay is D ( ) =

34.6(2.2)(55)

(100 cm) 2

{(0.75)(8.04)(0.8)(1 e 0.693(0.33) / 8.04 }

+ e 0.693( 0.33) / 8.04 (0.25)(0.20)(0.32)

+ e 0.693( 0.33) / 8.04 (0.25)(0.80)(5.2)

D() = 4.86 mSv (0.486 rem)

Therefore, hyperthyroid patients administered 2,035 megabecquerels (55 millicuries) of iodine-131 would not have to remain under licensee control and could be released under 10 CFR 35.75 when the occupancy factor of 0.25 in the second and third components of the equation is justified.

In the example above, the thyroidal fraction, F2 = 0.8, is a conservative assumption for persons who have this treatment for hyperthyroidism. If F2 has been measured for a specific patient, the measured value may be used.

B-3. Internal Dose For some radionuclides, such as iodine-131, there may be concerns that the internal dose of an individual from exposure to a released patient could be significant. A rough estimate of the maximum likely committed effective dose equivalent from internal exposure can be calculated from Equation B-6.

Di = Q (10-5)(DCF) (Equation B-6)

Where Di = Maximum likely internal committed effective dose equivalent to the individual exposed to the patient in rems Q = Activity administered to the patient in millicuries

10-5 = Assumed fractional intake DCF = Dose conversion factor to convert an intake in millicuries to an internal committed effective dose equivalent (such as tabulated in Reference B-2).

Equation B-6 uses a value of 10-5 as the fraction of the activity administered to the patient that would be taken in by the individual exposed to the patient. A common rule of thumb is to assume that no more than 1 millionth of the activity being handled will become an intake to an individual working with the material. This rule of thumb was developed in Reference B-3 for cases of worker intakes during normal workplace operations, worker intakes from accidental exposures, and public intakes from accidental airborne releases from a facility, but it does not specifically apply for cases of intake by an individual exposed to a patient. However, two studies (Refs. B-4 and B-5) regarding the intakes of individuals exposed to patients administered iodine-131 indicated that intakes were generally of the order of 1 millionth of the activity administered to the patient and that internal doses were far below external Appendix B to RG-8.39, Page B-6

doses. To account for the most highly exposed individual and to add a degree of conservatism to the calculations, a fractional transfer of 10-5 has been assumed.

Example 4, Internal Dose: Using the ingestion pathway, calculate the maximum internal dose to a person exposed to a patient who has been administered 1,110 megabecquerels (33 millicuries) of iodine-131. The ingestion pathway was selected since it is likely that most of the intake would be through the mouth or through the skin, which is most closely approximated by the ingestion pathway.

Solution: This is an example of the use of Equation B-6. The dose conversion factor DCF for the ingestion pathway is 53 rems/millicurie from Table 2.2 of Reference B-2.

Substituting the appropriate values into Equation B-6, the maximum internal dose to the person is Di = (33 mCi)(10-5)(53 rem/mCi)

Di = 0.17 mSv (0.017 rem)

In this case, the external dose to the other person would be no greater than 5 millisieverts (0.5 rem), while the internal dose would be about 0.17 millisievert (0.017 rem). Thus, the internal dose is about 3 percent of the external gamma dose. Internal doses may be ignored in the calculations if they are likely to be less than 10 percent of the external dose since the internal dose would be significantly less than the uncertainty in the external dose.

The conclusion that internal contamination is relatively unimportant in the case of patient release was also reached by the NCRP. The NCRP addressed the risk of intake of radionuclides from patients secretions and excreta in NCRP Commentary No. 11, Dose Limits for Individuals Who Receive Exposure from Radionuclide Therapy Patients (Ref. B-6). The NCRP concluded, Thus, a contamination incident that could lead to a significant intake of radioactive material is very unlikely.

For additional discussion on the subject, see Reference B-1.

REFERENCES FOR APPENDIX B

B-1. S. Schneider and S.A. McGuire, Regulatory Analysis on Criteria for the Release of Patients Administered Radioactive Material, USNRC, NUREG-1492, February 1997.3 B-2. K. F. Eckerman, A. B. Wolbarst, and A. C. B. Richardson, Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion, Federal Guidance Report No. 11, U. S. Environmental Protection Agency, Washington, DC, 1988.

B-3. A. Brodsky, Resuspension Factors and Probabilities of Intake of Material in Process (or Is 10-6 a Magic Number in Health Physics?), Health Physics, Volume 39, Number 6, 1980.

B-4. R. C. T. Buchanan and J. M. Brindle, Radioiodine Therapy to Out-patients-The Contamination Hazard, British Journal of Radiology, Volume 43, 1970.

3 Copies may be purchased at current rates from the U.S. Government Printing Office, P. 0. Box 37082, Washington, DC

20402-9328 (telephone (202) 512-2249; or from the National Technical Information service by writing NTIS at 5285 Port Royal Road, Springfield, VA 22161. Copies of drafts are also available for inspection and copying for a fee from the NRC Public Document Room at 2120 L Street NW. (Lower Level), Washington, DC. The PDRs mailing address is Mail Stop LL-6, Washington, DC 20555; telephone (202) 634-3273; fax (202) 634- 3343.

Appendix B to RG-8.39, Page B-7

B-5. A. P. Jacobson, P. A. Plato, and D. Toeroek, Contamination of the Home Environment by Patients Treated with Iodine-131, American Journal of Public Health, Volume 68, Number 3,

1978.

B-6. National Council on Radiation Protection and Measurements, Dose Limits for Individuals Who Receive Exposure from Radionuclide Therapy Patients, Commentary No. 11, February 28, 1995.

Appendix B to RG-8.39, Page B-8


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