ML20149L609
| ML20149L609 | |
| Person / Time | |
|---|---|
| Issue date: | 05/07/1996 |
| From: | Glenn J NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| To: | Shelton B NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20149C780 | List: |
| References | |
| FRN-61FR52388, RULE-PR-20, RULE-PR-32, RULE-PR-35, RULE-PR-36, RULE-PR-39 AF46-1-026, AF46-1-24, AF46-1-26, NUDOCS 9605160101 | |
| Download: ML20149L609 (32) | |
Text
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Af-46 -l May 7, 1996 MEMORANDUM TO:
Brenda Jo. Shelton, Chief, IRMB, DISS, IRM FROM:
John E. Glenn, Chief, RPHEB, DRA, RES Original Signed By: merr Trottier
SUBJECT:
FRN AND SUPPORTING STATEMENT FOR OMB APPROVAL FOR PROPOSED RULE, "10 CFR PARTS 20, 32, 35, 36, AND 39, MINOR CORRECTIONS,
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CLARIFYING CHANGES, AND A MINOR POLICY CHANGE" We have prepared for your review and comment the following attached documents:
(1) FR notice of OMB review of proposed reduction of information collection requirements, (2) supporting statement, and (3) a draft of the FR notice containing the proposed rule.
We plan to submit the proposed rule package to the EDO in June 1996. If you have any questions or comments, please contact Jayne M. McCausland at 415-6219.
Attachments:
1.
FR Notice of OMB Review of Information Collection 2.
Supporting Statement 3.
Draft FR Notice Containing the Proposed Rule DISTRIBUTION:
RPHEB Subj/RF JEGlenn CTrottier AKRoecklein JMMcCausland RP\\EB:D RPHEB:DRA RP EB:D RP land AK e ein CTr tt er JEGlenn 5/3 96 6
/96 05'/0//96
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[7590-01-P]
NUCLEAR REGULATORY COMMISSION 10 CFR Parts 20, 32, 35, 36, 39 RIN 3150-AF10 Minor Corrections and Clarifying Changes AGENCY: Nuclear Regulatory Commission.
ACTION:
Proposed rule.
SilMMARY: An NRC interoffice task force to review the Commission's regulations has determined that several minor corrections and clarifying changes are needed in 10 CFR Part 20 and also in Parts 32, 35, 36, and 39 to bring these parts into conformity with the Commission's revised radiation protection requirements of 10 CFR Part 20. This proposed rule would make the minor corrections and clarifying changes to the NRC's regulations that were identified by the task force.
EFFECTIVE DATE:
Comment period expires (75 days following publication in the Federal Register).
Comments received after this date will be considered if it is practical to do so, but the Commission is able to assure consideration only for comments received on or before this date.
ADDRESSES: Mail written comments to: Secretary, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; Attention:
Docketing and Service Branch.
Deliver comments to:
11555 Rockville Pike, Rockville, Maryland, between 7:45 am and 4:15 pm Federal workdays.
Comments on the proposed rule may also be submitted electronically in i
either ASCII text or Wordperfect format (version 5.1 or later) by calling the NRC Electronic Bulletin Board on FedWorld.
The bulletin board may be accessed using a personal computer, a modem, and one of the commonly available i
communications software packages, or directly via Internet.
If using a personal computer and modem, the NRC rulemaking subsystem on FedWorld can be accessed directly by dialing the toll free number:
1-800-303-9672.
Communication software parameters should be set as follows:
parity to i
none, data bits to 8, and stop bits to 1 (N,8,1).
Use ANSI or VT-100 terminal emulation.
The NRC rulemaking systems can then be accessed by selecting the
" Rules Menu" option from the "NRC Main Menu."
For further information about options available for NRC at FedWorld, consult the " Help /Information Center" j
from the "NRC Main Menu." Users will find the "FedWorld Online User's Guides" particularly helpful. Many NRC subsystems and databases also have a
" Help /Information Center" option that is tailored to the particular subsystem.
The NRC subsystem on FedWorld can also be accessed by a direct dial phone number for the main FedWorld BBS:
703-321-3339; Telnet via Internet:
fedworld. gov (192.239.92.3); File Transfer Protocol (FTP) via Internet:
ftp.fedworld. gov (192.239.92.205); and World Wide Web using the "Home Page":
www.fedworld. gov (this is the Uniform Resource Locator (URL)).
If you contact FedWorld using Telnet, you will see the NRC area and menus, including the Rules Menu.
Although you will be able to download documents and leave messages, you will not be able to write comments or upload files (comments).
If you contact FedWorld using FTP, all files can be accessed and downloaded 2
but uploads are not allowed; all you will see is a list of files without descriptions (normal Gopher look). An index file listing all files within a subdirectory, with descriptions, is available.
There is a 15-minute time limit for FTP access.
Although FedWorld also can be accessed through the World Wide Web, like FTP that mode only provides access for downloading files and does not display the NRC Rules Menu.
If using a method other than the NRC's toll free number to contact FedWorld, the NRC subsystem will be accessed from the main FedWorld menu by selecting "F - Regulatory, Government Administration and State Systems" or by entering the command "/go nrc" at a FedWorld command line. At the next menu, select "A - Regulatory Information Mall," and then select "A - U.S. Nuclear Regulatory Commission" at the next menu.
If you access NRC from FedWorld's
" Regulatory, Government Administration" menu, you may return to FedWorld by selecting the " Return to FedWorld" option from the "NRC Main Menu." However, if you access NRC at FedWorld by using NRC's toll-free number, you will have full access to all NRC systems, but you will not have access to the main FedWorld system.
For more information on NRC bulletin boards, call Mr. Arthur Davis, Systems Integration and Development Branch, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, telephone (301) 415-5780; e-mail AXD30nrc. gov.
Copies of the supporting statement submitted to OMB and comments received may be examined at the NRC Public Document Room at 2120 L Street NW.
(Lower Level), Washington, DC.
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FOR FURTHER INFORMATION CONTACT: Jayne M. McCausland, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, Washington, DC 20555, telephone (301) 415-6219, e-mail JMM2 0 nrc. gov.
SUPPLEMENTARY INFORMATION:
On May 21, 1991, a final rule was published in the Federal Register (56 FR 23300) that amended 10 CFR Part 20 to update the NRC's standards for protection against radiation.
Subsequent amendments were published to (1) change the mandatory implementation date to January 1,1994, and make conforming changes to the text to reflect the new implementation date (57 FR 38588),(2) remove or modify provisions to reflect the new implementation date for NRC's revised standards for radiation protection (58 FR 67657), and (3) restore provisions inadvertently removed or modified (59 FR 41641 and 60 FR 20183). This proposed rule would make additional minor corrections and clarifying changes to the NRC regulations for the purpose of greater clarity-and to further fecilitate implementation.
This proposed rule would make the following changes to 10 CFR Parts 20, 32, 35, 36, and 3".:
(1) lu 5 20.1003, " Definitions," clarifying changes and minor corrections would be made to tt.e following:
(a)
The term " Airborne radioactivity area" would be deleted and replaced with " Airborne radioactive material area" to clarify that radioactivity is a property of matter and, as such, cannot be airborne. A conforming change would also be made in 5 20.1902(d) to permit licensees the 4
option of either posting new signs to reflect this change or keeping the current signs.
(b)
The definition of " Declared pregnant woman" would be revised to M
specify that the written declaration of pregnancy may be given to the licensee or to the employergf the employer is the licensee.
This is necessary to ensure that the licensee responsible for work assignments involving exposure is aware of the declaration of pregnancy so that appropriate dose restriction i
can be imposed.
The change would also specify the duration of the effectiveness of a woman's declaration.
l (c)
The term " Eye dose equivalent" (EDE) would be deleted and replaced with " Lens dose equivalent" (LDE) to avoid confusion between the acronyms for 4
dose to the lens of the eye and effective dose equivalent IEDE).
(d)
The definitions of "High radiation area" and "Very high radiation area" would be revised to make clear that these area designations are based on radiation levels from sources external to the individual receiving the dose.
(e)
The definition of " Individual monitoring devices" would be revised to correct the terminology for thermoluminescence dosimeters.
(2)
In 5 20.1101(b), the word " practicable" would be changed to
" practical" to remove the basis for an incorrect perception among some licensees that, by using the word " practicable" in this section, the NRC is requiring licensees to use any dose averting technique capable of being used even if the technique is unproven or impractical.
I (3)
In 5 20.120? olanned special exposures, paragraph (a) would be revised to clarify the meaning of " higher exposure." The proposed new wording j
would state that planned special expeutres are authorized only in exceptional l
5 I
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situations when alternatives that might avoid the dose are unavailable or impractical.
(4)
In 5 20.1208(a), (c), (c)(2), and (d), the phrase " dose to an embryo / fetus" rould be changed to read " dose equivalent to the embryo / fetus" to make clear that the dose limit specifically applies to the dose equivalent, which is the technically correct term.
(5)
In 5 20.1501(a)(2)(i), the phrase "The extent of radiation levels;..." would be revised to read "The magnitude and extent of radiation levels;...." to more clearly reflect the intended meaning.
(6)
In 5 20.1501(a)(2)(iii), the phrase "The potential radiological hazards that could be present." would be revised to read "The potential radiological hazards." to improve clarity.
(7)
In i 20.1502, the words "from radiation sources under the control of the licensee" would be added after " exposure to radiation" in paragraph (a) l to improve clarity and to make it clear that a licensee is not responsible for sources not under its control.
(8)
In 5 20.1502(a)(2) and (b)(2), monitoring requirements are stated as one-tenth of applicable limits in a year for minors and pregnant women, even though the dose limits described in (a)(2) apply for an entire year to minors while in (b)(2) the dose limit applies only to the 9-month gestation period of a declared pregnant woman. These paragraphs would be separated and revised accordingly to make this section more precise and technically correct.
In addition, the criterion for monitoring minors and declared pregnant women 7
is proposed to be changed from 50 y in a year (or 9 months) to 100 tyr.
This change would constitute a small burden reduction with no loss in worker health 6
and safety.
The 100-millirem value for monitoring was selected for the following reasons:
(a)
The value is consistent with the 100-millirem training requirement in the recently revised 519.12 (60 FR 36038, July 13,1995).
- Thus, monitoring would not be required at doses that are below the doses at which the NRC believes workers should be trained; 4 (b)
The value is consistent with the 100-millirem dose limit for members of the public. in 5 20.1301(a).
It is not necessary or appropriate to require monitoring of' workers who are receiving less dose than permitted for j
members of the public; ifW (c)
Tee ing nitori require t of 50
. lirems year is diffic t to asure and docu nt with ta te-of-art perponnel monitor equ ent.
It i not logi 1 to re ire monit ing at evels not cap e of be'ing me ur by existi perso el monitor ng equi ent.
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(9)
In 5 20.1902(d), a proposed change to the posting requirement would permit the use of two new signs as well as current signs. This would conform i
to the proposed revision to the rule that substitutes the term " Airborne radioactive material area" for the term " Airborne radioactivity area."
f (10)
In 5 20.1903, a new paragraph would be added to exempt teletherapy rooms in a hospital from posting requirements as long as access is controlled to prevent the exposure of workers and members of the public to radiation or radioactive materials. The purpose of this change is to avoid the unwarranted and potentially unsettling effect that " GRAVE DANGER, VERY HIGH RADIATION AREA" signs may have on patients.
(11)
In i 20.1906(d), a revision would require licensees to notify the NRC Operations Center, instead of an NRC Regional Office, upon receiving and 7
I
e i
opening packages when radiation levels exceed regulatory limits. This would provide for consistency within the prompt notification requirements already contained in 5 20.2201. A conforming change would also be made to the prompt notification requirements in 5 20.2202.
(12)
In 5 20.2101, a revision would permit licensees to include both the new SI units and the old (special) units of dose on records required by this part.
Each of the recorded dose quantities would be recorded in the appropriate special unit and, if so desired, followed by the appropriate SI unit in parentheses. An additional revision is proposed to this section to replace the term " eye dose equivalent" with " lens dose equivalent" to avoid confusion with EDE for " effective dose equivalent."
(13)
In 5 20.2106(a)(2) and (a)(3), the references to " body burden" would be deleted because this term is obsolete and is not defined in revised 10 CFR Part 20.
In its place, 5 20.2106(a)(4) would be revised by adding a reference to 5 20.1204(a), which requires licensees to take measurements of (1) concentrations of radioactive materials in air in work areas, or (2) quantities of radionuclides in the body, or (3) quantities of radionuclides excreted from the body, or (4) combinations of these measurements in order to determine internal dose. This, in effect, uses records of measurements of concentrations in air, quantities of radioactive material in the body, excreta, or any combination of these that would be needed, instead of " body burden," for calculating committed effective dose equivalent (CEDE). We believe this information is clearly necessary to document the licensees' recorded calculations of CEDE. Adding this reference does not impose any additional recordkeeping burden on licensees because they already record this information to calculate CEDE under 5 20.1204.
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(14) A revision to i 20.2202(d) would permit all licensees to submit incident reports, via telephone, to the NRC Operations Center only.
Currently, this section requires that power reactor licensees submit reports to the NRC Operations Center, but all other licensees must submit both a telephone report to the NRC Operations Center and a telegram, mailgram, or facsimile to the Regional Office.
This change would ensure consistency in the prompt notification requirements contained elsewhere in this part and would be a reduction in the information collection burden.
(15)
In i 32.54(a), the reference to "I 20.203(a)" would be corrected to read "i 20.1901."
(16)
In 5 35.20, "ALARA program," paragraph (c) would be removed because the prescriptive requirements that are to be included in the program are redundant to the ALARA requirements contained in 10 CFR Part 20.
(17)
Safety precautions and survey requirements for restricted and unrestricted areas are specified in il 35.315, 35.415, 35.641, and 35.643.
Sections 35.315(a)(4) and 35.415(a)(4) would be revised to remove the references to restricted and unrestricted from the term area. Sections 35.641(a)(2)(i) and (a)(2)(ii) and 35.643(a) would be revised to be consistent with definitions of dose to occupationally exposed individuals and dose to members of the public. Also, in 5 35.643(a)(1), a misreference to i 20.1301(c) would be corrected to read i 20.1301(a).
The.500-mrem limit permitted by application and NRC approval under 5 20.1301(c) was never intended to be allowed under this section in Part 35.
Rather, it was always the intent of the NRC to apply the 100-mrem limit covered under i 20.1301(a) to this section, 9
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(18)
In 5 36.23(g), posting requirements for a panoramic irradiator area would be revised to conform with posting requirements appropriate to high or very high radiation areas in 5 20.1902. The posting requirements in Part 36 currently require a posting appropriate to a high radiation area.
(19)
In 5 39.33, " Radiation detection instruments," a conforming change to paragraph (a) would be made by deleting the term "milliroentgens" and replacing it with the term " millirems" to be consistent with revised Part 20 units.
Because NRC recognizes that most licensees may still use radiation detection instruments that measure radioactivity in units of roentgens, measurements taken in roentgens could continue to be recorded in terms of roentgen, provided that the measurements can readily be converted to rem for
]
records reqM red under 10 CFR Part 20.2101(a).
i Environmental Impact:
Categorical Exclusion The NRC has determined that this proposed rule is the type of action described in categorical exclusion in 5 51.22(c)(2); namely, the amendments to the regulations in this chapter are either corrective or clarifying in nature and do not substantially modify existing regulations and actions on petitions for rulemaking relating to these amendments.
Therefore, neither an environmental impact statement nor an environmental assessment has been prepared for this proposed rule.
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Paperwork Reduction Act Statement This proposed rule amends information collection requirements that are subject to the Paperwork Reduction Act of 1980 (44 U.S.C. 3501 et seq.).
This rule has been submitted to the Office of Management and Budget for review and approval of the paperwork requirements.
Because the rule will relax existing information collection requirements, by deleting the redundant requirement to notify the regional office by telegram in many cases, the public burden for this collection of information is expected to be reduced by approximately 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per reporting event, times approximately 250 reports per year, or 250 hours0.00289 days <br />0.0694 hours <br />4.133598e-4 weeks <br />9.5125e-5 months <br /> per year over the entire industry. This reduction includes the time required for reviewing i
instructions, searching existing data sources, gathering and maintaining the data needed, and completing and reviewing the collection of information.
Send comments regarding the estimated burden reduction or any other aspect of this ccliection of information, including suggestions for reducing this burden, to the Information and Records Management Branch (T-6F33), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; and to the Desk Officer, Office of Information and Regulatory Affairs, NE0B-3019, (3150-
), Office of Management and Budget, Washington, DC 20503.
Existing requirements were approved by the Office of Management and Budget approval numbers 3150-0001, -0010, -0014, -0130, and -0158.
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_ -. ~. -- -.
Regulatory Analysis The following Regulatory Analysis discusses the impacts of the changes described above.
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Clarifying changes are proposed to the definitions for "high radiation area" and "very high radiation area" in 10 CFR 20.1003.
In addition, the term i
4
" Airborne radioactivity area" would be deleted from 10 CFR 20.1003 and replaced with the term " Airborne radioactive material area" to improve I
clarity, and a conforming change would be made in 10 CFR 20.1902(d). No additional burden is anticipated by the change to 10 CFR 20.1902(d) because licensees would merely be provided'with more options for choosing signs to be conspicuously posted in an airborne radioactive material area. Clarifying changes are also proposed to 10 CFR 20.1101(b); 20.1206; 20.1208(a), (c),
i t
1 (c)(2), and (d); 20.1501(a)(2)(i) and (iii); 20.1502; 35.315, 35.415, 35.641,
)
and 35.643.
Part 20 conforming changes are proposed to 10 CFR 36.23(g) and 39.33(a), and minor corrections are proposed to (1) the definition for Individual monitoring devices in 10 CFR 20.1003, (2) paragraph (a) of 10 CFR 32.54, and (3) paragraph (c) of 10 CFR 35.20. No impact is anticipated to result from any of these actions.
Further revisions to 10 CFR Part 20 and the anticipated impacts are discussed below:
In 10 CFR 20.1003, the definition of " declared pregnant oman" would be revised to specify that the written declaration of pregnanc be given to the licensee or to the employer, if the employer is the licensee. The change would also specify the duration of the effectiveness of a woman's declaration.
With regard to notifying the licensee rather than the employer, usually the 12
employer is the licensee.
For these situations, there would be no impact.
When the licensee is not the employer; for example, if the woman's employer had a contract with the licensee, there would be less burden because the notification would be given directly to the licensee without the need to be handled by the employer.
In no case should there be more burden to the licensee. With regard to the duration of the declaration, there would be no additional burden on the licensee because it would now be clear to the licensee when the dose restrictions can be removed.
In 10 CFR 20.1003, the term " eye dose equivalent" (EDE) would be deleted and replaced with " lens dose equivalent" (LDE) to avoid confusion between the acronyms for dose to the lens of the eye and effective dose equivalent (EDE).
This is consistent with the current language on NRC Forms 4 and 5, which are used by licensees, so this change would have little impact. Some licensees may need to revise procedures.
In 10 CFR 20.1502(a)(2) and (b)(2), monitoring is required at one-tenth of the applicable limits in a year for minors and pregnant women, even though the dose limits described apply for an entire year to minors while the dose limit applies to the 9-month gestation period for declared pregnant women.
These paragraphs would be separated and revised accordingly to make this section more precise and technically correct, in addition, the 100-millirem l
value for monitoring, rather than one-tenth of the applicable limits (50 millirem), is proposed for the following reasons:
(1)
The value is consistent with the 100-millirem training requirement in the recently revised 10 CFR 19.12 (60 FR 36038, July 13, 1995).
- Thus, monitoring would not be required at doses that are below the doses at which the NRC believes workers should be trained.
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(2)
The value is consistent with the 100-millirem dose limit for members of the public in 10 CFR 20.1301(a).
It is not necessary or appropriate to require monitoring for workers who receive less dose than is permitted for members of the public.
r
)
Current tate-of-t -art personnel onitoring equi ent and' 1'say t c nIques aryn bio r
cap'aMe reliable a
ents a -50 mi
' rems pjryear.
This change may be a small burden reduction in that the change may 4
reduce the monitoring that would be done. On othef a d, theAI d f r monit ring.i ge6ehally ba o r than bryp cise y (oje ddo(es. As a consequence, there may not be significantly less worker monitoring because of this change.
In 10 CFR 20.1902, paragraph (d) would be revised to permit the use of current signs as well as two new signs that would conform to a new term,
" airborne radioactive material area," which is defined in 10 CFR 20.1003 as the replacement for the term " airborne radioactivity area." No additional burden is anticipated from this change because licensees would merely be provided with more options in choosing signs for posting in an airborne radioactive material area.
In 10 CFR 20.1903, a new paragraph (d) is proposed te waive the posting requirements in teletherapy rooms in a hospital because of the unwarranted unsettling effect that specific types of signs may have on patients. This change would have a beneficial effect because patients will not be disturbed 4
by signs that say " GRAVE DANGER, VERY HIGH RADIATION AREA." There would be no decrease in safety because the safety precautions in 10 CFR 35.615, " Safety precautions," particularly the access control requirements, are considered 14
i adequate to protect against inadvertent exposure to the radiation beam. This change is considered to be a burden reduction.
Currently, licensees are required in 10 CFR 20.1906(d) to notify the final delivery carrier and, by telephone and telegram, facsimile, or mailgram, the appropriate NRC regional office when, upon receiving and opening packages, radiation levels exceed regulatory limits.
Under the proposed revision to 10 CFR 20.1906(d), licensees would no longer be required to report such occurrences to the NRC regional office but would be required to notify the NRC Operations Center only, and only by telephone, of such occurrences.
This would provide consistency in the prompt notification requirements contained elsewhere in this part.
This is considered to be a lessening of burden because the requirement for written notification would be eliminated.
In 10 CFR 20.2101, a revision would permit licensees to use both the new
~
SI units and the old (special) units of quantities on records required by this l
part. However, each quantity should be recorded in the appropriate special unit, and if so desired, followed by the appropriate SI unit in parenthesis.
This change would place no additional burden on licensees because it merely provides them with an option to use the SI units.
In 10 CFR 20.2106(a)(2) and (a)(3), the references to " body burden" l
would be deleted because this term is obsolete and is not defined in the revised 10 CFR Part 20.
Instead, a reference to 10 CFR 20.1204(a) would be added in 10 CFR 20.2106(a)(4) that would merely clarify the records needed to i
document licensee determination of committed effective dose equivalent (CEDE).
This change should not impose additional recordkeeping burden on licensees i
because records under 10 CFR 20.2106 would be based only on the measurements 15 i
9 used to make a determination of internal dose, and licensees already record this information to calculate CEDE under 10 CFR 20.1204.
A revision to 10 CFR 20.2202(d) would allow all licensees, not just
)
power reactor licensees, to submit incident reports only to the NRC Operations l
Center, and only by telephone.
Currently, this section requires that power reactor licensees submit reports to the NRC Operations Center, but all other licensees are required to submit both a telephone report to the NRC Operations Center and a telegram, mailgram, or facsimile to the Regional Office.
This change would ensure consistency in the prompt notification requirements stated elsewhere in this part. This change would mean a reduction in burden for the licensees because it would simplify their notification requirements.
Backfit Analysis The NRC has determined that the backfit rule in 5 50.109, does not apply to this final rule and, therefore, that a backfit analysis is not required for this final rule because these amendments do not involve any provision that would impose backfits as defined in 5 50.109(a)(1).
List of Subjects 10 CFR Part 20 Byproduct material, Criminal penalties, Licensed material, Nuclear materials, Nuclear power plants and reactors, Occupational safety and health, 16
Packaging and containers, Radiation protection, Reporting and recordkeeping
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requirements, Special nuclear material, Source material, Waste treatment and
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f 1
ll disposal.
10 CFR Part 32 Byproduct material, Criminal penalties, Labeling, Nuclear materials, Radiation protection, Reporting and recordkeeping requirements.
10 CFR Part 35 Byproduct material, Drugs', Health facilities, Health professions, Incorporation by reference, Medical devices, Nuclear materials, Occupational safety and health, Penalty, Radiation protection, Reporting' and recordkeeping requirements.
1 10 CFR Part 36 Byproduct material, Cri:ninal penalties, Nuclear material, Oil and gas exploration - well logging, Reporting and.recordkeeping requirements, j
Scientific equipment, Security measures, Source. material, Special nuclear material.
10 CFR Part 39 Byproduct material, Nuclear material, Oil and gas exploration - well logging, Penalty, Reporting and recordkeeping requirements, Scientific equipment, Security measures, Source material, Special nuclear material.
17
l PART 20 - STANDARDS FOR PROTECTION AGAINST RADIATION 1.
The authority citation for Part 20 continues to read as follows:
AUTHORITY:
Secs. 53, 63, 65, 81, 103, 104, 161, 182, 186, 68 Stat. 930, 933, 935, 936, 937, 948, 953, 955, as amended (42 U.S.C. 2073, 2093, 2095, 2111, 2133, 2134, 2201, 2232, 2236), secs. 201, as amended, 202, 206, 88 Stat.
[
j 1242, as amended, 1244, 1246 (42 U.S.C. 5841,.5842, 5846).
i l
2.
In i 20.1003, replace the terms Airborne radioactivity area and l
l Eye dose eauivalent with the terms Airborne radioactive material area and Lens dose eauivalent, respectively, with no change to the definitions. The definitions for Declared creanant woman, High radiation area, Individual l
monitorina devices, and Very hiah radiation area are revised in alphabetical order to read as follows:
1 20.1003 Definitions.
l l
l l
Airborne radioactive material area means a room, enclosure, or area in which airborne radioactive materials, composed wholly or partly of licensed material, exist in concentrations --
(1)
In excess of the derived air concentrations (DACs) specified in Appendix B to il 20.1001-20.2402, or (2)
To such a degree that an individual present in the area without respiratory protective equipment could exceed, during the hours that an
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E l
individual is present in a week, an intake of 0.6 percent of the annual limit on intake (ALI) or 12 DAC-hours.
a l
Declared pregnant woman means a woman who has voluntarily informed the licensee, ~ or her employer if the employer is the licensee, in writing, of her i
i pregnancy and the estimated date of,conceptiop., The declaration shall remain in effect until thejdeclared regnant woman -irr: bi t' rr withdraws the l'
declaration in writing 4 ed. 5 M
/*f [7 l
Hiah radiation area means an area, accessible to individuals, in which radiation levels from radiation sources external to the body could result in i
an individual receiving a dose equivalent in excess of 0.1 rem (1 mSv) in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> at 30 centimeters from the radiation source or 30 centimeters from any surface that the radiation penetrates.
Individual monitorina devices (individual monitoring equipment) means devices designed to be worn by a single individual for the assessment of dose equivalent such es film badges, thermoluminescence dosimeters (TLDs), pocket ionization chambers, and personal (" lapel") air sampling devices.
Lens dose eauivalent applies to the external exposure of the lens of the eye and is taken as the dose equivalent at a tissue depth of 0.3 centimeter (300 mg/cm').
Very hiah radiation area means an area, accessible to individuals, in which radiation levels from radiation sources external to the body could 19
1 l
result in an individual receiving an absorbed dose in excess of 500 rads (5 grays) in I hour at 1 meter from a radiation source or 1 meter from any surface that the radiation penetrates.
5 20.1101 Radiation protection programs.
3.
In 5 20.1101, paragraph (b) is amended by deleting the word
" practicable" and replacing it with the word " practical."
s-3 4.
In 5 20.1206, paragraph (a) is revised to read as follows:
Id W"?
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5 20.1206 Planned special exposures.
(a)
The licensee authorizes a planned special exposure only in an exceptional situation when alternatives that might avoid the additional dose estimated to result from the planned special exposure are unavailable or impractical.
5.
In 5 20.1208, paragraphs (a), (c), and (d) are revised to read as l
follows:
i 20.1208 Dose equivalent to an embryo / fetus.
(a)
The licensee shall ensure that the dose equivalent to the embryo / fetus during the entire pregnancy, as a result of occupational exposure 20 i
of a declared pregnant woman, does not exceed 0.5 rem (5 mSv).
(For recordkeeping requirements, see 5 20.2106.)
(b)
(c)
The dose equivalent to the embryo / fetus shall be taken as the sum of--
(1)
(2)
The dose equivalent to the embryo / fetus from radionuclides in the embryo / fetus and radionuclides in the declared pregnant woman.
(d)
If the dose equivalent to the embryo / fetus is found to have exceeded 0.5 rem (5 mSv), or is within 0.05 rem (0.5 mSv) of this dose, by the time the woman declares the pregnancy to the licensee, the licensee shall be deemed to be in compliance with paragraph (a) of this section if the additional dose to the embryo / fetus does not exceed 0.05 rem (0.5 mSv) during the remainder of the pregnancy.
6.
In 5 20.1501, paragraphs (a)(2)(i) and (a)(2)(iii) are revised to i
read as follows:
5 20.1501 General.
(a) j (2)
(i) The magnitude and extent of radiation levels; and (iii)The potential radiological hazards.
21
t 7.
In 5 20.1502, paragraph (a)(3) is renumbered to (a)(4) and the a
i text of paragraph (a) and paragraphs (a)(2), (b)(1), and (b)(2) are revised as follows:
i 20.1502 Conditions reauirina individual monitorina of external and internal j
)
occupational dose.
l (a)
Each licensee shall monitor occupational exposure to radiation from i
j radiation sources under the control of the licensee and shall' supply and require the use of individual monitoring devices by --
(1) 1
[
(2) Minors likely to receive, in 1 year, from radiation sources external to the body, a dose equivalent in excess of 0.1 rem; (3) Declared pregnant women likely to receive, during the entire l
pregnancy, a dose equivalent in excess of 0.1 rem (1 mSv); and
]
~(4)
Individuals entering a high or very high radiation' area.
i (b) i, (1) Adults likely to receive, in 1 year, an intake in excess of 10 percent of the applicable All(s) in table 1, Columns 1 and 2, of Appendix B to 4
55 20.1001-20.2402; and i
(2) Minors likely to receive, in 1 year,.a committed effective dose equivalent in excess of 0.1 rem; and i
(3) Declared pregnant women likely to receive, during the entire i'
pregnancy, a committed effective dose equivalent' in excess of 0.1 rem (1 mSv).
~1
)
i 22 i
s
8.
In i 20.1902, paragraph (d) is revised to read as follows:
5 20.1902 Posting reauirements.
(d)
Posting of airborne radioactive material areas.
The licensee shall post each airborne radioactive material area with a conspicuous sign or signs bearing the radiation symbol and the words " CAUTION, AIRBORNE RADI0 ACTIVITY AREA," or " DANGER, RADI0 ACTIVITY AREA," or " CAUTION, AIRBORNE RADI0 ACTIVE MATERIAL AREA," or " DANGER, AIRBORNE RADI0 ACTIVE MATERIAL AREA."
9.
In i 20.1903, a new paragraph (d) is added to read as follows:
5 20.1903 Exceptions to postina reauirements.
% g 3 f. us' f*
(d)
Rooms in hospitals Iclinicsusedforteletherapyareexemptfrom the requirement to post caut'on signs pursuant to i 20.1902 provided that there is control of access and that the personnel in attendance will take the necessary precautions to prevent the exposure of workers and members of the public to radiation or radioactive materials in excess of the limits established in this part.
10.
In i 20.1906, paragraph (d) is revised to read as follows:
5 20.1906 Procedures for receiving and opening packaaes.
23
t (d)
The licensee shall immediately notify the final delivery carrier and the NRC Operations Center (301-816-5100), by telephone, when--
)
3 1
\\
11.
In 5 20.2101, paragraph.(b) is redesignated as paragraph (c) and revised, and a new paragraph (b) is added to read as follows:
5 20.2101 General provisions.
5 (b)
The licensee may show quantities in SI units in parentheses following each of the units specified in (a), above; in the records required by this part; however, all quantimies must be recorded as stated in paragraph (a) of this section.
(c)
The licensee shall make a clear distinction among the quantities ent'ered on the records required by this part (e.g., total effective dose equivalent, shallow-dose equivalent, lens dose equivalent, deep-dose equivalent, committed effective dose equivalent).
12.
In 5 20.2106, paragraphs (a)(2), (a)(3), and (a)(4) are revised to read as follows:
5 20.2106 Records of individual monitoring results.
(a)
(1)
(2)
The estimated intake of radionuclides (see i 20.1202); and l
24 1
j
(3)
The committed effective dose equivalent assigned to the intake of radionuclides; and (4)
The specific information used to calculate the committed effective dose equivalent pursuant to 55 20.1204(a) and (c); and 13.
In 5 20.2202, paragraph (d)(2) is revised to read as follows:
5 20.2202 Notification of incidents.
(d)
(2)
All other licensees shall make the reports required by paragraphs (a) and (b) of this section by telephone to the NRC Operations Center (301) 816-5100.
PART 32 - SPECIFIC DOMESTIC LICENSES TO MANUFACTURE OR TRANSFER CERTAIN ITEMS CONTAINING BYPRODUCT MATERIAL 14.
The authority citation for Part 32 continues to read as follows:
Authority:
Secs. 81, 161, 182, 183, 68 Stat. 935, 948, 953, 954, as amended (42 U.S.C. 2111, 2201, 2232, 2233); sec. 201, 88 Stat. 1242, as amended (42 U.S.C. 5841).
[
25
_~
-. ~.
i 3
)
- 5 32.54 IAmendedl.
l 15.
In 5 32.54, paragraph (a) is amended by revising the reference to "5 20.203(a)" to read "5 20.1901."
A l
i PART 35 -- MEDICAL USE OF BYPRODUCT MATERIAL j
16.
The authority citation for Part 35 continues to read as follows:
}
Authority: Secs. 81, 161, 182, 183, 68 Stat. 935, 948, 953, 954, as amended (42 U.S.C. 2111, 2201, 2232, 2233); sec. 201, 88 Stat. 1242, as j
amended (42 U.S.C. 5841).
,i 5 35.20 IAmendedl.
'17.
In 5 35.20, delete paragraph (c) in its entirety.
i i
1 j
18.
In 5 35.315, paragraph (a)(4) is revised to read as follows:
l i
l 5 35.315 Safety precautions.
l (a) l t
(4)
Promptly after administration of the dosage, measure the dose
{
rates in contiguous areas with a radiation measurement survey instrument to I
demonstrate compliance with the requirements of Part 20 of this chapter, and-i:
retain for 3 years a record of each survey that includes the time and date of the survey, a plan of the area or list of points surveyed, the :aeasured dose i
26
,-y v
e w
i
)
i
[
b b
rate at several points expressed in millirem per hour, the instrument used to-make the survey, and'the initials of the individual who made the survey.
t I
19.
In 5 35.415, paragraph _(a)(4).is revised to read as follows:
i 35.415 Safety precautions.
(a):
(4)
Promptly after implanting the material, survey the dose rates in contiguous areas with a radiation measurement survey instrument to demonstrate-compliance with the requirements of Part 20 of this chapter, and retain for 3 years a record of each survey.that includes the time and date of the survey, 1
a plan of the area or list of points surveyed, the measured dose rate at several points expressed in millirem per hour, the instrument used to make the survey, and the initials of the individual who made the survey.
20.
In 5 35.641, paragraphs (a)(2)(i) and (a)(2)(ii) are revised to read as follows:
l 5 35.641 Radiation surveys for teletherapy facilities.
(a)
(2) i 27
~._ __ __.-
i (i)
Radiation dose quantities per unit time in restricted areas are not likely to cause a:iy occupationally exposed individuals to receive a dose l
in excess of the limits specliied in 5 20.1201 of this chapter; and i
(ii)
Radiation dose quantities per unit time in unrestricted areas are not likely to cause any individual member of the public to receive a dose in excess of the limits specified in 5 20.1301 of this chapter.
21.
In 5 35.643, paragraphs (a) and (a)(1) are revised to read as follows:
5 35.643 Modification of teletherapy unit or room before beginnino a treatment program.
(a)
If the survey required by 5 35.641 indicates that any individual member of the public is likely to receive a dose in excess of the limits specified in 5 20.1301 of this chapter, before beginning the treatment program the licensee shall:
(1)
Either equip the unit with stops or add additional radiation shielding to ensure compliance with 5 20.1301(a) of this chapter.
PART 36 -- LICENSES AND RADIATION SAFETY REQUIREMENTS FOR 1RRADIATORS 22.
The authority citation for Part 36 continues to read as follows:
Authority:
Secs. 81, 82, 161, 182, 183, 186, 68 Stat. 935, 948, 953, 954, 955, as amended, sec. 234, 83 Stat. 444, as amended (42 U.S.C. 2111, l
28
4 2112, 2201, 2232, 2233, 2236, 2282); secs. 201, as amended, 202, 206, 88 Stat.
1242, as amended, 1244, 1246 (42 U.S.C. 5841, 5842, 5846).
23.
In 5 36.23, paragraph (g) is revised to read as follows:
5 36.23 Access control.
(g)
Each entrance to the radiation room of a panoramic irradiator and each entrance to the area within the personnel access barrier of an underwater irradiator must have a sign appropriate to a high or very high radiation area l
as covered under 5 20.1902.
Radiation postings for panoramic irradiators must comply with the posting requirements covered under 5 20.1902, except that signs may be removed, covered, or otherwise made inoperative when the sources are fully shielded.
PART 39 - LICENSES AND RADIATION SAFETY REQUIREMENTS FOR WELL LOGGING 24.
The authority citation for Part 39 continues to read as follows:
Authority:
Secs. 53, 57, 62, 63, 65, 69, 81, 82, 161, 182, 183, 188, 68 Stat. 929, 930, 932, 933, 934, 935, 948, 953, 954, 955, as amended, sec. 234, 83 Stat. 444, as amended (42 U.S.C. 2073, 2077, 2092, 2093, 2095, 2099, 2111, 2112, 2201, 2232, 2233, 2236, 2282); secs. 201, as amended, 202, 206, 88 Stat.
1242, as amended, 1244, 1246 (42 U.S.C. 5841, 5842, 5846).
29
25.
In 5 39.33, paragraph (a) has been revised to read as follows:
5 39.33 Radiation detection instruments.
(a)
The licensee shall keep a calibrated and operable radiation survey instrument capable of detecting beta.and gamma radiation at each field station and temporary jobsite to make the radiation surveys required by this part and by Part 20 of this chapter. To satisfy this requirement, the radiation survey instrument must be capable of measuring 0.1 millirem per hour through at least 50 millirems per hour.
Dated at Rockville, Maryland, this day of 1996.
For the Nuclear Regulatory Commission.
James M. Taylor, Executive Director for Operations.
30
i 25.
In 5 39.33, paragraph (a) has been revised to read as follows:
]
5 39.33 Radiation detection instruments.
(a)
The licensee shall keep a calibrated and operable radiation survey
{
instrument capable of detecting beta and gamma radiation at each field station i
i and temporary jobsite to make the radiation surveys required by this part and i
l by Part 20 of this chapter.
To satisfy this requirement, the radiation survey instrument must be capable of measuring 0.1 millirem per hour through at least 50 millirems per hour.
l j
Dated at Rockville, Maryland, this day of 1996.
For the Nuclear Regulatory Commission.
i 4
a
\\
James M. Taylor, Executive Director for Operations.
l Distribution:
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