ML20203F448
| ML20203F448 | |
| Person / Time | |
|---|---|
| Issue date: | 02/09/1999 |
| From: | Lohaus P NRC OFFICE OF STATE PROGRAMS (OSP) |
| To: | Miskin G NEW YORK, STATE OF |
| References | |
| NUDOCS 9902180141 | |
| Download: ML20203F448 (38) | |
Text
, ,
Mr. G:ne Miskin, Director Bureau of Radiological Health New York City Department of Health 2 Lafayette Street,11'" Floor New York, NY 10007
Dear Mr. Miskin:
As requested, we have reviewed the proposed transportation amendments to the New York City Health Code, Section 175.01, Applicability and inapplicability, Communications, Section 175.02, Definitions, and Section 175.1.05, Transportation and Packaging of Radioactive Materials, that were received by Duncan White of Region I on January 11,1999. We have compared the amendments with our previous comments dated March 5,1998l The regulations were reviewed by comparison to the equivalent NRC regulations in 10 CFR Part 71. We also discussed our ,
review of the regulations with you on January 29,1999. l As a result of our review, we have no comments. Please note that we have limited our review i
to regulations required for compatibility and/or health and safety. Under our current procedure, a finding that a New York City regulation meets the compatibility and health and safety categories of the equivalent NRC regulation may only be made based on a review of the final i
New York City regulation. However, we have determined that if your proposed regulations were '
adopted without significant change, they would meet the compatibility and health and safety categories established in OSP Procedure SA-200 (formerly B.7). i We request that when the proposed regulations are adopted and published as final regulations, ,
a copy of the "as published" regulations be provided for our review. As requested in our All '
Agreement _ States Letter SP-96-027,"Reauest to Hiahliaht Chanaes to Aareement State -
Reaulations Submitted to the NRC for Compatibility Review"(March 1,1996), please highlight the final changes and send one copy in a computer readable format, if possible.
If you have any questions regarding the comments, the compatibility and health and safety categories, or any of the NRC regulations used in this review, please contact me or Duncan )
White, Regional State Agreements Officer, Region I at (610) 337-5042.
Sincerely,
'OlginalSigned By:
PAULH.LOHAUS Paul H. Lohaus, Director Office of State Programs l
100048 4 Distribution:
DlR RF (9-8) DCD (SP05)
SDroggitis PDR (YESJ_. NO )
DOCUMENT NAME: G:\SNS\LBUREAUO.WPD *See previous concurrence. !
To ,eceive a cop f of this ticcument.1,ulicato in the teor: 'C' = Copy without attachment / enclosure "E" = Copy with attachment / enclosure "N* = No copy OFFICE RSAO/ @ OSP Pyhl OSP:D , l OGC NAME DWhite:nb " 3% , SSalomon' PHLohaus hMi# FCameron DATE OR/M /99 LM' 02/l /99 02/1 /99 J. d4 02A)9 /99*
'"'$$80141$90209 99O OSP FILE CODE: SP-AG-20 PDR STPRO ESON
} g,j
I Mr. Gene Miskin, Director l Bureau of Radiological Health New York City Department of Health 2 Lafayette Street,11 Floor ;
New York, NY 10007
Dear Mr. Miskin:
As requested, we have reviewed the proposed transportation amend ents to the New York City Health Code, Section 175.01, Applicability and inapplicability, Comm nications, Section 175.02, Definitions, and Section 175.105, Transportation and Packaging of adioactive Materials, that were received by Duncan White of Region I on January 11,1999. We have compared the amendments with our previous comments dated March 5,1998. The regulations were reviewed by comparison to the equivalent NRC regulations in 10 CFR Part 7'1. We also discussed our review of the regulations with you on January 29,1999.
As a result of our review, we have no comments. Please note tt]ht we have limited our review ,
to regulations required for compatibility and/or health and safety'. Under our current procedure, a finding that a New York City regulation meets the compatibili and health and safety categories of the equivalent NRC regulation may only be mad based on a review of the final i New York City regulation. However, we have determined tha if your proposed regulations were adopted without significant change, they would meet the co atibility and health and safety categories established in OSP Procedure SA-200 (formerly .7).
We request that when the proposed regulations are adopt and published as final regulations, a copy of the "as published" regulations be provided for o review. As requested in our All ;
Agreement States Letter SP-96-027,"Recuest to Hiablio Chances to Aareement State Reaulations Submitted to the NRC for Comoatibility Revidw" (March 1,1996), please highlight the final changes and send one copy in a computer readable format, if possible, if you have any questions regarding the comments, th compatibility and health and safety categories, or any of the NRC regulations used in this eview, please contact me or Duncan White, Regional State Agreements Officer, Region I (610) 337-5042.
Sin rely, i P ul H. Lohaus, Director Office of State Programs ,
Distribution:
DIR RF (9-8) DCD (SPOS)
SDroggitis PDR (YES_f._ NO )
BUsilton NY DEC File DOCUMENT NAME: G:\SNS\LBUREAUO.WPD t o . , , m o o cc..co - .n. . . o v.c .. . ,c . %
OFFICE RSAO/ @ l OSP Cth1 OSP:D , I // M NAME DWhite:nb " it & , SSalomon' / PHLohaus f)M 4v FCameron DATE OR/$ /99 W 02/ l /99~ 02/1 /99 d.W -
02//6 /99 k OSP FILE CODE: SP-AG-20-4
w .- .
- **et y 5L UNITED STATES B NUCLEAR REGULATORY COMMISSION g
WASHINGTON, D.C. 20006 4001
% ,,,,, February 9,1999 Mr. Gene Miskin, Director :
Bureau of Radiological Health '
New York City Department of Health 2 Lafayette Street,11* Floor New York, NY 10007 i
Dear Mr. Miskin:
l As requested, we have reviewed the proposed transportation amendments to the New York City J Health Code, Section 175.01, Applicability and inapplicability, Communications, Section 175.02, !
Definitions, and Section 175.105, Transportation and Packaging of Radioactive Materials, that ;
were received by Duncan White of Region I on January 11,1999. We have compared the amendments with our previous comments dated March 5,1998. The regulations were reviewed i by comparison to the equivalent NRC regulations in 10 CFR Part 71. We also discussed our l
review of the regulations with you on January 29,1999. ;
1 As a result of our review, we have no comments. Please note that we have limited our review l to regulations required for compatibility and/or health and safety. Under our current procedure, a finding that a New York City regulation meets the compatibility and health and safety categories of the equivalent NRC regulation may only be made based on a review of the final New York City regulation. However, we have determined that if your proposed regulations were adopted without significant change, they would meet the compatibility and health and safety categories established in OSP Procedure SA-200 (formerly B.7).
We request that when the proposed regulations are adopted and published as final regulations, a copy of the "as published" regulations be provided for our review. As requested in our All Agreement States Letter SP-96-027, "Reauest to Hiahliaht Chanaes to Aareement State Reaulations Submitted to the NRC for Compatibility Review" (March 1,1996), please highlight the final changes and send one copy in a computer readable format, if possible.
If you have any questions regarding the comments, the compatibility and health and safety categories, or any of the NRC regulations used in this review, please contact me or Duncan White, Regional State Agreements Officer, Region I at (610) 337-5042.
~
rely, l J
[aul H. Lohaus, Director l s F
Office of State Programs
c, .
.~. ', . .
. i
,# l t
DEPARTMENT OF HEAL.TH l BOARD OF HEAI.TH '
NOTICE OF INTENTION TO AMEND SECTIONS 175.01.175.0 AND REENACT SECTION 175.105 OF THE NEW YO IN COMPLIANCE WITH SECTION 1043(b) OF THE i PURSUANT TO THE AUTHORITY GRANTED TO !
OF SAID CHARTER, NOTICE IS HEREBY GIV OF SECTION 175.105 OF THENEW YORK CITY HEALTH CODE. i !
NOTICE IS HEREBY GIVEN THAT THE HEARING ON THE PROPOSAL ON JANUARY 28,1999 FROM 10.
DEPARTMEN l THE 20TH Fl.OOR CONFERENCE ROOM AT 2 LAFAYETTE STREE YORK 10013.
PERSONS INTERESTED IN PRE-REGISTERING TO SPEAK SHOULl WRITING, PATRICIA J. CARUSO, SECRETARY,125 WORTH STR PLEASEINCLUDE A YORK 10013 - CN 31; (212) 788-5010 BY MONDAY, JANUARY 25,1999.
TELEPHONE NUMBER WHERE,IF NECESSARY, YOU MAY BE REACHED ,
NORMAL WORKING HOURS. SPEAKERS WILL BE LIMIT l
PERSONS WHO REQUEST THAT A SIGN LANGUAOE IN; FORM OF REASONABLE ACCOMMODATION HEARING ARE ASKED TO NOTIFY PATRICIA J. CARUSO SECRETARY,1 FOR A DI:
l STREET, NEW YORK,NEW YORK 10013 - CN 31; (212) 788-5010 BY TH .
14,1999. !
REGISTRATION WILL BE ACCEPTED AT THE DOOR UNTI!
PREFERENCE WILL BE GIVEN TO THOSE WHO PREREGISTER. !
WRITTEN COMMENTS REGARDING THE PROPOSAL MUST BE]
PATRICI A J. CARUSO, SECRETARY,125 WORTH STREET, NEW YORK,NEW '
CN 31 ON OR BEFORE, JANUARY 28,1999. '
\
BE ADVISED THE A TRANSCRIPT OF THE PUBLIC HEARING :
COMMENTS WILL BE.PROVIDED TO EACH MEMBER OF Tilel TO A FINAL CONSIDERATION OF THE PROPOSAL.
1 l
)
i )
~
q . .
$TATUTORY AUTHORITY i
These amendments to the New York City Health Code (" Health Code") are pmmulgated pursuant to Sections 556,558 and 1043 of the New York City Charter (" Charter"). Section 556 of the '
Charter grants the Department of Health jurisdiction to regulate matters affecting health in the City of New York. Section 556(s) of the Charter specifically empowers the Department to regulate radioactive materials. Section 558 (b) and (c) of the Charter empower the Board of Health to amend the Health j Code and to include in the Health Code all matters to which the Department's authority extends. i Section 1043 of the Charter grants the Department of Health rule making powers. !
Further, these amendments are enacted in accordance with Section 274(o) of the Federal Atomic Energy Act of 1954, as amended, providing for a State's compatibility with standards adopted ;
and enforced by the Atomic Energy Commission ("AEC"), and later the Nuclear Regulatory !
Commission ("NRC"), one ofits successor agencies; an Agreement entered into between the United l States Atomic Energy Commission and the State of New York on October 15,1%2 and AEC l document #AEC-R 94/3, prepared prior to the final Agreement between the State ofNew York and the l AEC which serves as the basis for such final Agreement. l STATEMENT OF BASIS AND PURPOSE The New York City Depin uocat of Health is one of the agencies that implements the
~
Agreement between New York State and the U.S. Nuclear Regulatory Commission ("NRC") to ;
regulate the use of radioactive materials under Section 274 of the Atomic Energy Act of 1954. The Agreement requires that the City's Radiation Control Program be compatible with the NRC's program ,
for regulation of materials subject to the Agreement. Generally, states are allowed three years to enact
~
compatible regulations.
In 1995, the U.S. Nuclear Regulatory Commission ("NRC") revised its regulations goveming j transportation of radioactive material found in 10 CFR Part 71, to bring the United States into :
compatibility with Intemational Atomic Energy Agency ("lAEA") Safety Series 6 Revisions. l (Regulations for the Safe Transport of Radioactive Material,1985 Edition, Safety Series No. 6). The revised NRC regulations, in combination with corresponding amendments by the U.S. Department of Transportation (" DOT") (codified at 49 C.F.R. Parts 171, et seq.) brought the United States into accord with the IAEA regulations. The NRC's and DOT's regulations became effective April 1,1996.
Existing Section 175.105 of the Health Code regulates the packaging, preparation for shipment and transportation of radioactive materials in New York City, except those directly related to national defense. The Health Code requirements apply to all persons who transport, or offer for transport radioactive material within or through the City. The Bureau of Radiological Health proposes to repeal and reenact the current Section 175.105 to ensure compatibility with 10 CFR Part 71.
~ The proposed reenactment continues regulation of intra city radioactive materials at the same levels of safety and security as all other shipments regardless of point of departure or destination (e.g.,
interstate, intercounty).
Section 175.02, the definition section of Article 175, is also amended to achieve compatibility with the NRC regulations goveming transportation. Other actions in the resolution include amendment of Section 175.01(c) to update the current mailing address for the Bureau of Radiological Health; and .
2
.. , .- _._ _ ,_ , _1
cmendment cf Section 175.03 OX6XivXB) to del:te references to specific provisions in the current version of Section 175.105 to reflect the proposed reenacted Section 175.105.
A. Amendments to the Health Code Renardinn Matters of Compatibility !
New York City, as one of the jurisdictions covered by the " Agreement State" program with the NRC, must comply with certain federal regulations, deemed " matters of compatibility", enacted into Title 10 of the CFR by adopting essentially equivalent regulations.
- It is proposed that certain definitions contained in Section 175.02 be amended to l conform with 10 CFR Part -71 because such definitions have been deemed matters of :
compatibility by the NRC. l
- It is proposed that existing Section 175.105 regulating the packaging and transportation of radioactive materials be repealed and reenacted. The proposed new Section 175.105 would require compliance with certain federal regulations when shipping radioactive materials, such regulations having been deemed matters of compatibility by the NRC. Incorporation of these ,
amendments into the Health Code is critical in order for the City to be deemed compatible by l
' the NRC. i
- It is proposed to amend Section 175.030) to delete references contained therein to specific subsections in existing section 175.105, to make that section consistent with the
~
proposed reenactment of section 175.105.
B. Technical Amendments Made to Conform with Federal Renulations
_ lt is proposed that Appendix A and accompanying Tables be repealed and reenacted and proposed Appendix A Determination of As and A2 values, Table A-1 Ai and A2 Values for Radionuclides and Table A-2 General Values for Ai and A2 be added in order to conform with 10 CFR Part 71, such Tables being deemed matters ofcompatibility by the NRC.
C. Other Amendments To Article 175 It is proposed to amend Section 175.01 to update the address of the Bureau of Radiological Health provided therein to which communications regarding Article 175 should be addressed.
STATEMENT PU'RSUANT TO CHARTER SECTION 1042 - REGULATORY AGENDA This proposal was inadvertently omitted from the Department's regulatory agenda, however, enactment of the amendment is required as a matter of compatibility with federal governmtat regulations.
THE PROPOSAL IS AS FOLLOWS:
matter in brackets [] to be deleted
. matter underlined is new 3
.. _ _ _ _ _._ _ _ _ _ . ~ . _ _ _ _ . _ _ _ _ _ _
RESOLVED, that subdivisi:n (1) cf subsection (c) cf Section 175.01 cf the New York City Health Code as enacted on the seventh day of June, nineteen hundred and ninety four, be and the same hereby is amended to be printed together with explanatory notes to read as follows:
{l75.01 Applicability and inapplicability, communications (c)' Communications. (1) Except as otherwise provided for in this Code, or as authorized by the Department, all applications, notifications, reports or other communications filed pursuant to this Code j shall be addressed to the Department at: l
' l l
l Bureau ofRadiological Health !
.1 j
~
[111 Livingston Street-Room 2006 Brooklyn,New York 11201-5078.]
2 Imravette Street.1Ith Floor NewYork.NewYork 10013 i !
l i NOTES: Subdivision (1) of subsection ~(c) was amended on to update the address of the Bureau of Radiological Health.
[
1
~
RESOLVED further, that subdivisions (1), (52), (78), (89), (116), (123), (144), (228) and (231) of subsection (a) of Section 175.02 are amended and subdivisions (88), (233) and (234) of subsection l (a) of Section 175.02 are repealed, to be printed together with explanatory notes to read as follows:
, $175.02 Definitions.
l (a) As used in this Code, the following definitions shall apply:
- (1) "Ai means the maximum activity of special form radioactive material permitted in a Type A package. "A2" means the maximum activity of radioactive material, other than special form,
[ radioactive] LSA and SCO material, permitted in a Type A package. These values are either listed in l Table [1] A-l, Appendix A of (175.105 of this Code or may be derived in accordance with the procedure prescribed in such Appendix A.
l i (52)- " Conveyance" means; [any vehicle, aircraft, vessel, freight container, or hold, compartment, or o
defined deck area of an inisnd waterway craft or seagoing vessel.] (1) "For transport by oublic highway
! or rail" any transoort vehicle er larne freinht container:
(2) "For transport by water
- any vessel. or any hold. compartment. or defined deck area of a vessel includine any transport vehicle on board the vessel: and (3) "For tranmort by aircraft" any aircraft.
. (78) ' " Exclusive use" (also referred to in other regulations as " sole use" or " full load") means the sole use of a conveyance by a single consignor for which all initial, intermediate, and final loading and unloading are carried out in accordance with the direction of the consignor or consignee. The consinnor and the carrier must ensure that any loading or unloading is performed by oersonnel havine radiolonical trainine and resources essiverinte for safe handline of the consignment. The consinnor must iss= swific instructions. in writina. for maintenance of exclusive use shioment controls. and include them with the shinoina nacer information provided to the carrier by the consinnor.
4
. . . :: : l (88) iReservedl [^' Fissile classification ' means the categorization of fissile material packages into one .
of the following three ciassca scarrding to the controls needed to provide nuclear criticality safety l during transportation: :
(i) Fissile Class 1: A package which may be transported in unlimited numbers and in any arrangement, j L
and which requires no nuclear criticality safety controls during transportation. A transport index is not assigned for purposes of nuclear criticality safety but may be required because of external radiation ;
level.
(ii) Fissile Class II: A package which may be transported together with other packages in any ;
arrangement but, for criticality control, in numbers which do not exceed an aggregate transport index of l
- 50. These shipments require no other nuclear criticality safety control during transportation. i Individual packages may have a transport index not less than I and not more than 10. ,
(iii) Fissile Class 111: A shipment of packages which is controlled in transportation by specific arrangements between the shipper and the carrier to provide nuclear criticality safety.]
1 (89) " Fissile material" means [any special nuclear material consisting of, or containing one or more, i fissile radionuclides. Fissile radionuclides are) plutonium-238, plutonium-239, plutonium,241, uranitun-233, [and] uranium-235 or any combination of these radionuclides. [Neither natural nor depid.ai uranium is fissile material. Fissile materials are classified in fl75.105 according to the controls needed to provide nuclear criticality safety during transportation.] Unirradiated natural ,
uranium and depleted uranium. and natura! uranium or denleted uranium that has been irradiated in thermal reactors only are not included in this definition. Certain exclusions from fissile material controls are orovided in 10 CFR 71.53.
(116) " Licensed Material" means radioactive material received, possessed, produced, used, !
' transferred or disposed of under a general or specific license issued by the Department or any ;
radioactive material which is subiect to the licensure reauirement of this Code. !
(123) " Low specific activity (LSA) material" means [any of the following: 1 (i) uranium or thorium ores and physical or chemical concentrates of those ores; l (ii) unirradiated natural or depleted uranium or unirradiated natural thorium; (iii) tritium oxide in aqueous solutions provided the concentration does not exceed 185 MBq (5.0 millicuries) per milliliter,-
(iv) material in which the radioactivity is essentially uniformly distributed and in which the estimated average concentration per gram of contents does not exceed:
(A) 3.7 KBq (0.0001 millicurie) of radionuclides for which the A2 quantity in Appendix A of
{l75.105 is not more than 1.85 GBq (0.05 curie);
(B) 185 KBq (0.005 millicurie) of radionuclides for which the A2 quantity in Appendix A of f175.105 is more than 1.85 GBq (0.05 curie), but not more than 37 GBq (I curie); or (C) 11.1 MBq (0.3 millicurie) of radionuclides for which the A2 quantity in Appendix A of
{l75.105 is more than 37 GBq (I curie).
(v) objects of nonradioactive material with external contamination of radioactive material.
provided that the radioactive material is not readily dispersible and the surface contamination, when aveaged over an area of I square meter, does not exceed 3.7 KBq/cm2 (0.0001 millicurie/CM2) of radionuclides for which the A2 quantity in Appendix A of f 175.105 is not more than 1.85 GBq (0.05 curie), or 37 KBq/CM2 (0.001 millicurie/CM2) for other radionuclides.] radioactive material with limited specific activity that satisfies the descriptions and limits set forth below. Shieldine materials 5
sunoundinn tise LSA material may not be considered in detenninine the estimated averane specific activity of the a=eka=e contaase LSA material must be in one of three aroups:
(1) LSA-I.
(i) Ores cantainine only naturally occurrinn radionuclides (e.n.. uranium. thorium) and uranium or thorium .x-r- + ' -ies of such ores: or (ii) Solid unirradi=*ad natural uranium or deoleted uranium or natural thorium or their solid or liauid comoounds or mixtures: o,t
- (iii) Radia=etive mat ~ial. Other than fi=*ile mat ~ial. for which the Ag value is unlimited
- or (iv) Mill tailinea cantaminatad earth. cermic. rubble. other debris. and activated ma'~ial in which the radiametive .c id is ~~atially uniformly distributed. and the averane specific activity does not exceed 104 Age.
(2) LSA-II. .
- (i) Water with tritium cerwhat;on un to 0.8 TBa/ liter (20.0 Ci/ liter): or l
(ii) M-*=ial in which the radiamenive mat ~ial is -tially uniformly distributad and the avemne j d 4 maarific activity daan not excaad 10 Ayn for solids and === and 10 Ayn for lianide l Q),LSA-III. Malida (e a - canaalid=*ad ===*= activatad ==*~iale) in which:
(i) The radioactive material is ~~atially uniformly distributed throuahout a solid or a _ collection of ;
salid obiects. or is esserifially uniformly distributed in a solid comonet bindinn anent (such as <;oncrete.
bitumen. ceramic. etc.h ,
(ii) The radioactive mat ~ial is relatively insoluble. or it is intrinsically contained in a relatively insoluble ==*~ial. so that- even nadar lane of n=ekaaine the loss ofindiasetive material oer n=ekaae !
by leachiar when olaced in water for 7 days. would not exceed 0.1 A 7: and 4
(iii)The averane specific activity of the solid does not exceed 2x10 Age. l
!- (144) " Package" means the packaging together with its radioactive contents as presented for transport. !
, l
!: (1) " Fissile m=*~ial n=ek==e" means a fissile material onckanina together with its fissile material i
, contents. )
~
. (2)"Tvoe B orkaae" ma=ns rs i <oe B nackmaina tonether with its radioactive contents. On anoroval by the NRC. a Tvoe B onckane desian is designated by NRC as B(U) unless the nackmae has a maximum normal om.iina cressure of more than 700 kPa (100 lb/in )2 naune or a pressure relief device that ]
would allow the release of radioactive material to the environment under the tests soecified in 10 CFR ]
71.73 (hvoothetical accident conditions). in which case it will receive a desinnation B(M). B(U) refers j to the need for unilateral anoroval ofinternational shioments: B(M) refers to the need for multilateral j ano: oval of international:shioments. There is no distinction made in how osckanes with these l
. desinnations may be used in domestic transoortation. To determine their distinction for intemational l transoostation. see USDOT renulations in 49 CFR Part 173. A Tvoe B onckane aooroved before !
Scotember 6.1983. was designated only as Tvoe B. Limitations on its use are specified in 10 CFR I ll.dl i
!' (211) "Special form radioactive material" means radioactive material which satisfies the following i conditions.
(i) it is either a single solid piece or is contained in a sealed capsule that can be opened only by i destroying the capsule, i l 4
6 :
i i~
i 1
- (ii) the piece or capsule has at least one dimension not less than 5 mm_(0.2 inch);cnd l l (iii) it satisfies the [ test] requirements of 10 CFR 71.75. A special form encapsulation designed in !
accordance with the requirements of 10 CFR 71.4[(0)] in effect on June 30,1983, (see 10 CFR Part 71. l l ;
1 revised as of January 1.1983). and constructed prior to July 1,1985, and a special form encaosulation i
j desinned in accordance with the reouirements of 10 CFR 71.4 in effect on March 31.1996. (see 10 i CFR Pan 71. revised as of January 1.1983). and constructed before April 1.1998. may continue to be ,
l used. [A special form encapsulation either designed or constructed after June 30,1985 must meet l
! requirements of this paragraph applicable at the time ofits design or construction.] Any other special i form erm!stion munt m~' the soecifie=* ions of this definition.- l t
l (228) " Transport index" means the dimensionless number, rounded up to the [first decimal place] i
' i next tenth. placed on the label of a package to designate the degree of control to be exercised by the carrier during transportation. %e trananort index is determined as follows: ;
(1) For non-fissile material a=ekaaen the number determined by multiolving the maximum radiation I level in millisievent (mSv) cer hour at one meter (3.3 ft) from the extemal surface of the aaekaae by i 100 (eauivalent to the maximum radiation level in millirem ner hour at one meter (3.3 flik or (2) For ff==ile material nackaaes. the number determined by multiolving the maximum radiation level ,
in millisievert oer hour at one meter (3.3 ft) from the extemal surface of the packane by 100 (eauivalent l to the mavimum radiation level in millirem oer hour at one meter (3.3 ft)). or. for criticality control ourna=a= the number obtained as described in 10 CFR 71.59. whichever is larner. [ne transport index
~is the number expressing the maximum radiation level in millirem per hour at I meter fmm the extemal surface of the package.] j (231) " Type A package" means [a package that does not meet Type B package requirements.] g n=ckmoing that. tonether with its radioactive contents limited to Aj or A 7as aooropriate. meets the !
reauirements of U.S. DOT 49 CFR 173.410 and 173.412 and is designed to retain the intenrity of ;
containment and shieldinn reauired by this part under normal conditions of transoort as demonstrated !
by the tests set forth in 49 CFR.173.465 or 173.466. as aoorooriate. j (233) IReservedl [" Type B package" means a Type B packaging together with its radioactive 1 contents. Type B package design is designated as B(U) or B(M). B(U) refers to the need for unilateral approval ofinternational shipments; B(M) refers to the need for multilateral approval. There is no ;
distinction made in how packages with these designations may be used in domestic transportation. To :
determine their distinction for international transportation, refer to 49 CFR Part 173. Type B p4 age approved prior to September 6,1983 was designated only as Type B. Limitations on its use are ;
l specified .in 10 CFR 71.13.]
. (234) IReservedl [" Type B packaging" means a packaging designed to retain the integrity of containment and shielding when subjected to the nonnal conditions of transport and hypothetical accident test conditions set forth in 10 CFR Part 71.]
l
. NOTES: Subdivisions (1), (52), (78), (89), (116), (123), (144), (228) and (231) of subsection (a) were amended and subdivisions (88), (233) and (234) of subsection (a) were repealed on to conform to definitions in 10 CFR Part 71 to ensure compatibility with the NRC. In addition, the definition of" Licensed Material" was clarified to include radioactive material that requires a license even if one has not been obtained as well as radioactive material that is the subject of a general or specific license.
7
RESOLVED further, that subparagraphs (A) and (B) of paragraph (iv) of subdivisi:n (6) of subsection (j) of section 175.03 of such code as enacted on the seventh day of June, nineteen hundred and ninety four, be and the same hereby are amended to be printed together with explanatory notes, to read as follows:
g175.03 (j)(6)(iv)(B)
The licensee or registrant shall immediately notify the final delivery carrier and, by telephone and telegram, mailgram, or facsimile, the Department when:
(A) removable radioactive surface contamination exceeds the limits specified in [ Table 1 of] Q175.105 1
ef the Code; or
\
(B) external radiation levels exceed the limits specified in {175.105 [(c)(4)(ix) and (x)) of this Code.
NOTES: Subparagraphs (A) and (B) of parag aph (iv) of subdivision (6) of subsection (j) were amended on to reflect the reer:rted i175.105.
RESOLVED further, that Section 175.105 of said Code as enacted on the seventh day ofJune, nineteen hundred and ninety four be and the same hereby is repealed and reenacted to be printed together with explanatory notes, to read as follows:
8
6175.105 Transportation and Packagine of Radioactive Materials ub) GeneralProvisions (1) Purpose and Scope :
(2) Records (3) Comoleteness and accuracy ofinformation.
(4) Reauirement for license.
(5) Definitions.
(6)Transoortation oflicensed material. ~
(b) Exemotions (I) Exemotion of physicians. l (2) Exemotion for low-level materials (c) GeneralLicenses (I) General license: NRC-anoroved oackane.
(2) Previously approved nad==a (3) General license: U.S. Der,eruner,t of Transportation specification container.
(4) General License: Use of foreien anoroved onckane. !
(d) Operatine Controls and Procedures (1) Anoticability ofoperatina controls and orocedures. ;
(2) Preliminary determinations. 1 (3) Routine determinations. l (4) Airtransport ofolutonium, i (5) Openine instructions.
(6) Records. i (7) Inspection and tests.
l (8) Reports. j (9) Advance notification of shioment ofirradiated reactor fuel and nuclear waste.
(e) Ouality Assurance (1) Ouality assurance reauirements (2)Ouality assurance organization (3)Ouality assurance oronram.
(4) Packare desian control.
(S) Procurement document control.
(6) Instructions. orocedures. and drswines.
(7) Document control.
(8) Control of ourchased material. cauipment. and services.
(9) Identification and control of materials. parts. and components.
(10) Control of special orocesses.
(I1)Intemal insocctios (12) Test control.
(13) Control of measuring and test cautoment.
(14) Handlina. storane. and shionine control.
(I S) inspection. test. and operatine status.
(16) Nonconformina materials. oarts. or comoonents.
(17) Corrective action.
(18) Ouality assurance records.
(19) Audits.
Apnendix A-Determination ofA fand A?
Table A Ag and Ay Valuesfor Radionuclides Table A-2 General Values for Af and A ?
9
- - . - .- . _ - - . - - - - - - - - - - ~ . - _ . - - . - _ =.
'a .. . ..
i - i l
L i 4 t l (a). General Pmvisions l i i (1)
- Purnose andScone ;
I' (i) lhis =ceian ==*-klinham r=airamants for n=ekaaino- r,ranaration for shioment. and trananortation !
of!!caa=A man-ial. 'Ihe ==ek==ine and transoort oflicaa-d material are also subiect to other sections !
of thie cada (e e 66175.03.175.101) and to the reaal=* ions of other =aancies (e.n.. the U.S. Naela- ;
paent=*ary Cnami== tan (NRC). the U.S. Daametmaa' of Tran=aare=*ian (USDOT) mad the U.S. Paet=1 Service') havine iuriadic+iaa over maana of traneannt and other analin= hic r* ate and laeal laws and ;
reoniatina. h remd.=--- :- of this =antion are in .=ddition to. and not in enhe+itatian for. other i requirements. ;
(ii) 'Ihis =a' tan anolies'to any nerson who delivers licensed material to a carrier for transoort. !
- :g: ---t the =^-is! - a the v .n - ; of the serecm's facility. r!=.' or +d. - L ' site of- or !
tr==== arts e kat ==*=ial on atiklic hiehways or into any nahlic area. No mo4=i -, of thi= =e+ian >
pythprizes possession oflicensed material. l.
(iii) 'Ihe resh-- - = of thi= =e'i5n anolv to any cerson who h== a licanaa or who is reouired to obtain a licaana cur ===at to thin Cada if the eerson delivers radiaan+ive ==*~ial to a -maa or cantrace ,
carrier for trea=aart or tr==== arts the ==*=ial aa+=ida the nanfinae of the eerson's facility or athar l puthorized place of use.
i (2) ' Records. ,
Fach racnrd reouired by thie aansion must be lenible throuchaut the retention oeriod saanified by thin Code. The record may be the orieinal or a reoroduced copy or a micmform onovided that the copy or microform is mat'--- - ^-4 by authorized nersonnel and that the microform is cannhle of producine a clear copy nwoeshaut the reouired setention oeriod. h record may also be stored in electronic media with the canability for oraducina lenible. accurate. and comolete recontis durina the reouired retention paiod, Racards each as !a**ars. drawinae naarificatione must include all certinent information such as
=eamne initiale and nion=haes. The licensee shall maintain adaaaate safeenards ===innt tamnerine with and loss of records.
(3) Comoleteness and accuracy ofinformation.
(i) Information orovided to the Denaitment by an anolicant for a license. or by a licensee. or information reauired by anolicable laws or renul:.tions. or licensed conditions to be maintained by the anolicant or the licerisee must be complete and accurate in all material ramaan*=
(ii) Each moolicant or licensee shall notify the Department ofinformation identified by the aDDlicant or licensee as havina. for the renulated activity. a sinnificant imolication for oublic health and safety or common defense and security. An anolicant or licensee violates this reouirement if the anolicant or licensee fails to notify the Deseitinent of information that the anolicant or licensee has identified as I havine'a'sinnificant imolication for oublic health and safety or common defense and security.
Notification must be orovided to the Department within two workinn days of identifyinn the
' information. This reauirement is not aoolicable to information that is already reauired to be provided to the Deoartment by other reoorting or updatinn reouirements. !
l
' ' Postal Service Manual (Domestic Mail Manual), section 124.3, which is incorporated by teference at 39 CFR I 11.1. !
10
- . t 7
(4) Reauirement for license. ,
fi) Except as authori=1 in a neneral license or a specific license issued by the Department. or as ;
exemoted in this section. no person mav-
- (A) Deliver licensed ma'arial to a carrier for transoort: or (B) Trantnort licensed material. j (ii) Exsistions from the reauirement for licanae in 6175.105(aV4) are soecified in 6175.105 (bV2).
Ccd liw== for which no NRC aaekana naaroval is reauired are issued in 66175.105(cV3) and !
i 175.105(cV4). The oeneral lieanne in 6175.105(cYl) reauires that an NRC certificate of compliance or '
other r=kaee anomval be i=anad for the ancknoe to be n-I undar the neneral license. The transport of licesd material or delivery oflicensed n=tarial to a carrier for transport is subiect to the operatinn :
cunhols and pracadures reauisiests of 6175.105(d). to'the auality assurance reauirements of i
6175.105(e). and to the eeneral orovisions of 6175.105(a). includinn USDOT renulations referenced in 6175.IO5(aV6). .
, (5)
Definitions.
ne followine terms are defined herein for the ouroose of this section. These definitions are in addition to thane in 6175.02. To ea=ne .x-irstibility with international houssodation standards. all limits in i this maetion are niven in terms of dual unita: The International System of Units (SI) followed or oracadad by U.S. n'aadard or enetamary units. The U.S. customary units are not exact couivalents. but ;
are roundadto a convenient value. nrovidine a functionally cauivalent unit. For the ournose of this l
=ction. either unit may be used. . j (i) "Certificata holder" maans a nerson who has been issued a certificate of comoliance or other packnoc aooroval by the U.S. Nuclear ,Renulatory Commission.
(ii) "Close ref1 action by water" means immadiate contact by water of sufficient thickness for l maximum reflection of neutrons.
(iii)' " Containment svetam" manns the ===ambly of cosisencats of the onckaning intended to retain the i radieartive material during transoort.
(iv) " Low toxicity aloha emitters" manna natural uranium. deoleted uranium. natural thorium:
uranium-235. uranium-238. thorium-232. thorium-228 or thorium-230 when contained in ores or ohveical or elwmical concentrata= or tailinas: or aloha emitters with a half-life ofless than 10 days.
(v) "Marimum normal ooeratino ora =mee" =aanc the maximum naune pressure that would develoo
- .in the cordainment system in a period of 1 year under the heat condition specified in 10 CFR 71.71(cY1). in the abaence of ventina extemal cooline by an ancillary system. or operational controls during transport.
(vi) " Natural thorium" m=na thorium with the naturally occurrina distribution of thorium isot.o.gg
- (an=aatially 100 weinht nercerit thorium-232).
(vii) "Ootimum intersoersed l$vdronenous moderation" means the presence of hydronenous material between aneknoen to such an extent that the maximum nuclear reactivity results.
(viii)" Surface Contaminatad Obiect (SCO)" means a solid oblect that is not itself classed as radioactive material. but which has radioactive material distributed on any ofits surfaces. SCO must.bg in one of two aroups with surface activity not exceedina the followinn limits:
(A) SCO-1: A solid object on which:
11
+
3 l (a) The non-fixed contamination on the accessible surface averaned over 300 cm (or the area of the l 2 2 d 2
, surface ifless than 300 cm ) does not exceed 4 Ba/cm (10 microcurie /cm ) for beta and namma and i
Iow toxicity alpha emitters. or 0.4 Bo/cm 2(10'5 microcurie /cm 2) for all other aloha emitters:
2 (b) The fixed contamination on the accessible surface averaned over 300 cm (or the area of the surface 2 4 2 2 ifless than 300 cm ) does not exceed 4x10 Ba/cm (1.0 microcurie /cm ) for beta and namma and low !
toxicity aloha emitters. or 4x103 Ba/cm (0.12 microcurie /cm )2 for all other aloha emitters: and
]
- ~ (c) The non-fixed contamination olus the fixed contamination on tiie inaccessible surface avemned l 2 d 2 over 300 cm (or the ara of the surface if less than 300 cm ) does not exceed 4x10 Ba/cm gg 2
l i microcurie /cm 2
) for l#.a and namma and low toxicity aloha emitters. or 4x10' Ba/cm2 (0.1 '
- microcurie /cm2 ) for all other alpha emitters. )
(B) SCO-II: A solid obiect on which the limits for SCO-I are exceeded and on which: !
2 l (a) The non-fixed contamination on the accessible surface averaned over 300 cm (or the area of the 2 2 surface ifless than 300 cm ) does not exceed 400 Ba/cm (10-2 microcurie /cm') for beta and namma i and low toxicity aloha emitters or 40 Ba/cm 2(10'3 microcurie /cm 2) for all other aloha emitters:
l 2
(b)'Ihe fixed contamination on the accessible surface averaned over 300 cm (or the area of the surface l 2 2 ifless than 300 cm ) does not exceed 8x10 Ba/cm 2(20 microcuries/cm ) for beta and namma and low 5
l 2
1pxicity aloha emitters. or 8x10' Ba/cm2(2 microcuries/cm ) for all other aloha emitters: and (c) The non-fixed contamination plus the fixed contamination on the inaccessible surface avemned 2 2 5 2 over 300 cm (or the area of the surface if less than 300 cm ) does not exceed 8x10 Ba/cm (20 4
microcuries/cm 2
) for beta and namma and low toxicity aloha emitters. or 8x10 Ba/cm2 (2 microcuries/cm2) for all other alpha emitters.
(xi) Uranium- natural. depleted. enriched (A) " Natural uranium" means uranium with the naturally occurring distribution of uranium isotopes (approximately 0.711 weinht percent uranium-235. and the remainder by weight essentially uranium-216.h (B) "Deoleted uranium" means uranium containine less uranium-235 than the naturally occurrine distribution of uranium isotooes.
(C) " Enriched uranium" means uranium containine more uranium-235 than the naturally occurrina distribution of uranium isotopes.
l (6) Transoortation oflicensed material.
l (i) Each person who transoorts licensed material outside the site of usage. as specified in the license or !
where transport is on oublic hinhways. or who deliv-rs licensed material to a carrier for transport.
shall comply with the applicable reauirements of the USDOT regulations in 49 CFR Parts 170 through I 89 aoorooriate to the mode of transoort.
(A) The oerson shall partihularly note USDOT regulations in the followine areas' fa) Packagine-49 CFR Part 173: Suboarts A and B and I.
j fb) Markinn and labeline-49 CFR Part 172: Suboart D. Sections 172.400 through 172.407.
Sections 172.436 through 172 440. and Suboart E.
fc) Placardinn- 49 CFR Part 172: Suboast F. especially Sections 172.500 throuch 172.519. !
172.556. and Anoendices B and C.
l 12 i
t i (d) Accident reconinn-49 CFR Pan 171: Sections 171.15 and 171.16. [
- t j (c) Shinoinn oaoers and eiummmy information-49 CFR Past 172: Suboarts C and G.
l //) Hanrdous matarial employee trainino-49 CFR Part 172: Suboart H. [
1 (r) Hanrdous triatarial shioner/carnr renistration -49 CFR Part 107: Suboart G. 3 (B) The person shall also note USDOT renulations certaininn to the followinn modes of I
transportation ,
(a) Rail-49 CFR Part 174: Suboarts A thmunh D and K. .l:
j (b) Air-49 CFR Part 175. !
1 (c) Vessel-49 CFR Part 176: Suboarts A throunh F and M.
(d) Public Hish'way-49 CFR Part 177 and Parts 390 throuah 397.
I i (ii) If USDOT reaal=*iana are not aanliamble to a shioment of licensed material. the oerson shall i wnivioi to the standards and reaui wia of the USDOT specified in 6175.105(aV6Yi) to the same j j extent as if the shioment or E.ossadatio. were subiect to USDOT renulations. '
(b) Exemption !
(1) Exemotion ofchvsicians. ?
Any ohysician licensed by a State to dinnense druns in the oractice of 'nedicine is exempt from 6175.105 (aV6) with resoect to tmnsoort by the ohveician oflicensed material for use in the oractice of '
medicine. However. any physician operatino under this exemntion must be licensed under anolicable i
sections of this Code. Such E-nsson must not be by public modae of Emusconetion includine but not limited to. buses. subways. trams. taxicabs. car servicae trains. ferrys. or other means which would be !
. retumed immediately to public use after transportinn licensed ==*arial.
l i
(2) Exemotion forlow-levelmaterials.
(i) A licensee is exempt from all reauirements of this = action with respect to shioment or carriane of a i package containinn radioactive material havine a saarific activity not areater than 70 Bo/a (0.002 BCih ;
(ii) A licensee is exemot from all reouirements of this eaction. other than 6175.105(aV6) and 6175.105(dV4). with resoect to shioment or carrince of the followinn onckanes. orovidad the anck=aes contain no fissile material. or the fissile material exemotion standards of 10 CFR 71.53 are satisfied:
(A) A nackane containino no more than a Tvoe A auantity of radiaac'ive material:
(B) A anck==e in which the only radianctive mavarial is low sreific activity (LSA) nietaial or surface contaminatad obiects (SCO). orovidad the extemal radiation level at 3 m from the unshielded material or obiects does not excaad 10 mSv/h (I rem /h): or
'(C) A nackane transnorted within locations within the United States which contains only americium or clutonium in special form with an mooreonte radiaactivity not to excaad 20 curies.
(iii) A licensee is exemot from all reauirements of this =etion. other than 6175.105(aV6) and 6175.105(dV4). with resoect to shioment or carriane of low-saarific-activity (LSA) material in aroup LSA-l. or surface contaminated obiects (SCOs) in aroup SCO-l.
, 13
^
i i' General Licenses ,
(c)
( l (1) General license: NRC-acoroved occkare.
(i) A oeneral li==e is hereby i aad to any licensee of the Deoartment to transoort. or to deliver to a ;
2 carrier for tran=aaet. li-=ad m=*a ial in a anekaae for which a license. certificate of comoliance. or ;
athar naamval h== h=a issuad by the NRC. ;
k (ii) "Ihis aaaaral lie-a=a anolies only to a licensee who-(A) Has a aunlity ===a maca omaram anamved by the Denaitment as satisfyinn the omvisions of 6175.105(e) of this Code. )
(B) Has a cooy of the certifiesta of comolimaca or other anoroval of the a=ekaae. and has the i drawinen and other daeamante referaaaad in the anomval ral=' inn to the use and maintenance of the packagina and to the actions to be taken before shipment: !
(C) Camalian with the terms and canditions of the license.- certificate.' or other aooroval. as !
=aalie=hla- and anolicable omvisions of the anaratine cantrols and omcedure , reaul-o A of l 6175.105(d). the anality --oce reauironents of 6175.105(e). and the neneral omvisions of -
6175.105(a): and I
(D) Suhmite in writias to the Dan =*maat before the li-=aa's first use of the onckane. the licensee's amme and licaame munber and the anek=-a idaatifie=+ ion number soecified in the nackane approval.
(iii) This eeneral licanam anolies only when the anakane anoroval authorizes use of the ancknoe under this generallicense.
(iv) For a Tvoe B or f1==ile rc=*a'ial anekaae. the da=len of which was aooroved by NRC before April
' l.1996. the emneral license is unbiaat to the eAAitional restrictions contained in 10 CFR 71.13.
(2) Previousivacorovednalux.
(i) A Tyne B aneka=e oreviousiv maaroved by NRC but not desinnated as B(U) or B(M) in the IAantifie=+ ion anmher of the NRC Certifie=** of Cnmalinaea may be used under the eeneral license of 6175.105(cYl) with the followinn additional conditions:
(A) Fabrie=* ion of the anekaaine was ==*infactorily completed by Aunust 31. 1986. as
. deimw-ue+i by analientian ofits madal number in =er? x2 with 6175.105(dV2Wiii):
(B) A 'a=ek=ae a=aA for a shiamaat to a lar=' ion outside the United States is subiect to multilateral maamval. as defined in USDOT regulations at 49 CFR 173.403: and
-(C) A serial number that uniauelv identifies each n=ckmaine which conforms to the aooroved
' da= ion is assionad to. and leeibly and' durably marked on. the outside of each eackmainn.
(ii) A Tvoe B(U) anekaae= a Tvoe B(M) aarka=e- a low soecific activity (LSA) material oackane or a fissile matdrial a=ckane= oreviously anomved by the NRC but without the desinnation "-85" in the identification number of the NRC Certificate of Compliance. may be used under the neneral license of 6175.105(cYl) with the followinn additional conditions:
(A) Fabriention of the oschase is satisfactorily comoleted by April 1.1999 as demonstrated by anolication ofits model number in accordance with 6175.105(dW2Wiii) of this Code:
(B) A anck=ae used for a shioment to a location outside the United States is subiect to multilateral aooroval as defined in USDOT renulations at 49 CFR 173.403: and 14
. . :. - l I
(C) A serial number which uniauelv identifies each nackmoinn which confonns to the anoroved !
daion is ===ioned to and lenibly and durably marked on the outside of each oackanine. [
i (3) Generallicense: U.S. Denartment ofTransnortation soecification container.
(i) A meneral lieanne is issa-d to any licensee of the Department to transport. or to deliver to a carrier !
for transaart. licen=d ma'~ial in a specification container for fissile material or for a Tvoe B auantity of r=dk+1!ve rnatarial as saarified in USDOT renulations at 49 CFR Parts 173 and 171 (ii) This manaral licaana anolies only to a liceo=* who has a cuality assurance pronram approva.d by l the Ikaartment as =atiervine the provisions of 6175.105(e) of this Code. l (iii) This eeneral license aoolies op' .o a licensee who- !
(A) lias a copy of the soecific + ion: and (B) Comolies with the terms a. tconditions of the specification and the anolicable orovisions of j the'oneratia= and orar*Ames reuuirements in 6175.105(d). the anality assurance reauiienients in j 6175.105(e) and the eeneral omvisions contained in 6175.105(a).
(iv) This canaral license is subiect to the limitation that the specification container may not be used for i a <hiaman' to a lae='ian outside the United States. except by multilateral anoroval. as defined m i USDOT renulations at 49 CFR 173.403. l (4) GeneralLicense: Use offoreign aoorovedcackare.
l (i) A neneral licanae is issued to any licensee of the Denartment to i .ossort. or to deliver to a carrier j for i.ausoit. licensed material in a onckane the desian of which has been nooroved in a foreign l antiaaal competent authority certificate that has been revalidated by USDOT as meetinn the anolicable !
reauircuneiits of49 CFR 171.12. .
l (ii) Except as otherwise provided herein. the neneral license applies only to a licensee who has a f ouality assurance omeram aooroved by the Deoartment as satisfyinn the anolicable orovisions of l 6175.105(e) of this Code.
(iii) This neneral license anolies only to shioments made to or from locations outside the United States.
(iv) *Ihis eeneral license aoolies only to a licensee who- .
(A) Has a copy of the nonlicable certificate. the revalidation. and the drawinns and other l daeaments referenced in the certificate. relatina to the use and maintenance of the oackaninn and l to the actions to be taken before shioment: and I (B) Comolies with the terms and conditions of the certificate and revalidation. and with the l anolicable provisions of the eswaho and procedures reaulionients in 6175.105(d). the auality !
assurance reaulimoee;s in 6175.105(e) and the meneral orovisions in 6175.105(a). With respect to l
the cuality assurance orovisions of 6175.105(e) of this Code. the licensee is exemot from desian. t construction. and fabrication consideration l i
(d) Operatina Controls and Procedures (1) Anolicability ofoveratine controls and orocedures. l A licensee subject to this section. who. under a neneral or specific license. transports licensed material [
or delivers licensed material to a carrier for transoort. shall comolv with the reauirements of this l i
l$ \
t
9 . .
=_>h-etion. with the cuality assurance reauirements of 6175.105 (e). and with the neneral orovisions of 6175.105(a) of this Code.
.(2) ' Preliminary determinations.
Before the first use of any n=ekaaine for the shioment oflicensed =='arial-(i) The licaa aa shall ascertain that there are no cracks. oinholes. uncontrolled voids. or other defects that could =ionifie=ntiv radae, the effectivana== of the n=ek=aine-2 (ii) Where the maximum normal oneratine cressure will exceed 35 kPa (5 lbf/in ) naune. the licensee 3
< hall test the cantainment system at an intemal ora ===e at laaet 50 cercent hieher than the maximum i nonnat oneratino ora ==re. to verify the can=hility of that system to maintain its structural intenrity at '
that pressure: and (iii) The li==: ahall can=airaan Iv and durably mark the anekaaine with its madal number. serial i numhar. nross weicht- and a a=ekana identifie= tion numhar ===ioned by the NRC. Before eselving the mada! namhar. the li-maa shall -h.. ir.a that the ==ekaaine han haan fabrie= tad in amerdr.cc with the desian .mw.d by the NRC.
(3) Routine determinations Before each shioment oflicensed material. the licensee shall ensure that the onckane with its contents
=tiefies the anolicable reauirements of this section and of the license. The licensee shall determine lhal
(i) Ihe nack==e is oroner for the contents to be shioned: i
. 1 (ii) The onckane is in unimnaired ohysical condition except for superficial defects such as marks or dgils; .
(iii) Each closure device of the nack=oine including any reauired easket. is properly installed and secured and free ofdefects- l (iv) Any svetem for cantninine liauid ir =danuately sealed and has adannata en=ca or other specified orovision for exoansion of the liauid:
l (v) Any oressure relief device is operable and set in accordance with written procedures.
(vi) The n=ekmae has been loaded and closed in accordance with written proceduty.!i;
. (vii)Any structural cart of the oackane that could be used to lift or tie down the nackane dyr.t. rig l tran=nort is rendered inoperable for that ourpose. unless it satisfies the desian reauirements of 10 CFR j 71.45-(viii)The level of non-fix$d (removable) radioactive contamination on the extemal surfaces of each n=4=oe offered for shioment is as low as reasonably achievable. and within the limits specified in USDOT renulations in 49 CFR 173.443:
(ix) External radiation levels around the nackane and around the vehicle. if aoolicable. will not exceed
- the limits specified in 10 CFR 71.47 at any time durine transoortation:
(x) Accessible packane surface temocratures will not exceed the limits specified in 10 CFR 71.43(n) at any time durina transportation: and (xi) For fissile material. any moderator or neutron absorber. if reauired. is present and in oroner condition.
16 l I
(4) Air transoort ofolutonium.
(i) Notwithstandinn the orovisions of any neneral licenses and notwithstandina any exemotions
=*= tad directly in this section or included indirectly by citation of 49 CFR chapter 1. as may be maalic=hle. the licensee shall assure that olutonium in any form. whether for imoort. exnort. or domestic shioment. is not transported by air or delivered to a carrier for air transport unless:
(A) The clutonium is contained in a medical device desianed for individual human aoolication: or (B) The plutonium is contained in a material in which the specific activity is not areater than 70 Ba/n (0.002 uCi/a) of ==tarial and in which the radioactivity is essentially uniformly distributed: or (C) The clutonium is shioned in a sinnie osckane containina no more than ar. A, cuantity of I olutonium in any isotone or form. and is shioned in accortlance with 6175.105(aV6): or i (D) The plutonium is shinoed in a nackaoe soecifically authorized for the shioment of plutonium by i mir in the Certificate of Comoliance for that a=ekaoe issued by the E (ii) Nothine in 6175.105(dV4Vi) is to be interoreted as removinn or diminishina the recuirements of10 CFR 73.24
\
(iii) For a shioment of olutonium by air which is subject to 6175.105(dV4KiVD). the licensee shall.
throunh special arrannement with the carrier. reauire comoliance with 49 CFR 175.704. U.S. l Denartment of Ti.rssortation renulations anolicable to the air transoort of olutonium. )
1
($) Ooening instructions.
Before delivery of a nackage to a carrier for transoort. the licensee shall ensure that any soecial l instructions needed to safelv open the nackane have been sent to. or otherwise made available to. the !
consinnee for the consinnee's use in accordance with 6175.03(iV6) of this Code.
(6) Records.
(i) Each licensee shall maintain. for a ceriod of 3 years after shioment. a record of each shioment of licensed material not exemot under 6175.105(bV2). showine where anolicable-(A) Identification of the cackaoina by model number and serial number:
(B) Verification that there are no sinnificant defects in the onckagine. as shiooed:
(C) Volume and identification of coolant:
(D) Tvoe and auantity of licensed material in each oackane. and the total auantity of each shipment:
(E) For each item ofirradiated fissile material-(a) Identification by model number and serial number:
fb) Irradiation and decay history to the extent aooropriate to demonstrate that its nuclear and thermal characteristics'comoly with license conditions: and fc) Any abnormal or unusual condition relevant to radiation safety:
(F) Date of the shioment:
(G) For fissile packanes and for Tvoe B packanes. any special controls exercised:
(H) Name and address of the transferee:
17
_ _ . . _ _ _ _ _ _ . _ _ . _ ~ - _ . . _ ____.____._____
i (I) Address to which the shioment was made: and j
- 0) Results of the determinations reauired by 6175.105(dW3) and by the conditions of the packane anoroval. l (ii) The licensee shall make available to the Deoartment for insocction. upon reasonable notice. all !
records reauired by this section. Records are only valid if stamoed. initialed. or sinned and dated by authorized oersonnel or otherwise authenticated.
-(iii)he licensee shall maintain sufficient ' written records to furnish evidence of the anality of a=ckmaina. The records to be maintained include results of the determinations reouired by l 6175.105(dW2): desinn. fabrication. and assembly records. results of reviews. insocctions. tests. and audits: results of monitoring work nerformance and materials analyses: and results of maintenance. !
modification and repair activities. Innn~ tion. test. and audit records must identify the insoector or data recorder. the tvoe of observation. the results. the accentability and the action taken in connection with ;
any deficierwiae noted. He rawds must be retained for 3 years after the life of the nackmainato which :
they apolv. l
' (7)
. Insoection and tests.
(i) The licensee or certificate holder shall oermit the Department. at all reasonable times. to inspect the licensed material. nackanina. nremises. and facilities in which the licensed material or onckanine is used. orovided. constructed. fabricated. tested. stored. or shioned.
1 (ii) ne licensee shall nerform. and oermit the Denartment to nerform. any tests the Department deems necessary or anoropriate for the administration of the reauisnws of this section.
(iii) ne licensee shall notify the Denartment at least 45 days before fabrication of a nackane to be used for the shioment oflicensed material havine a decay heat load in excess of SkW or with a maximum 2
normal operatine pressure in excess of103kPa (15 lbf/in ) ,,,,,,
(8) Reoorts.
The licensee shall report to the Deoartment within 30 days- l (i) Any instance in which there is sinnificant reduction in the effectiveness of any aooroved Tvoe B. l
, or fissile. oackanina durine use: i a l (ii) Details of any defects with safety sinnificance in Tvoe B. or fissile. nackanina after first use. with '
the means employed to repair the defects and orevent their recurrence: or (iii) Instances in which the conditions of anoroval in the ceitificate of compliance were not observed in making a shioment. l (9) Advance notification ofshioment ofirradiated reactor fuel and nuclear waste.
(i) As specified in 66175.105(dW9)(ii). (iii) and (iv). each licensee shall orovide advance notification to the novemor of a State. or th'enovernor's designee. and the Department. of the shioment oflicensed material. through. or across the boundary of the State. before the transport. or delivery to a carrier. for trans00rt, of licensed material outside the confines of the licensee's olant or other olace of use or 119 BEL (ii) Advance notification is reauired under this subdivision for shioments of irradiated reactor fuel in ouantities less than that subicet to advance notification reauirements of 10 CFR 73.37(f). Advance 18
.. : 1
. 1
. . 1 notification is also reauired under this subdivision for shioment of licensed material. other than l
- irradiated fuel.- meetine the followinn three conditions:
)
(A) The licensed material is reauired by this section to be in Tvoe B nackaoinn for transoortation: l l (B) The licensed material is beinn transoorted to or across a State boundary en route to a disoosal !
- facility or to a collection noint for trananort to a dienosal facility
- and i
j (C) The auantity oflicensed material in a sinnie nacknoe exceeds the least of the followinn:
l fa) 3000 timqthe Ai value of the radionuclides as soecified in apoendix A. Table A-1 for ;
- special form radioactive material
- !
I (b) 3000 times the A, value of the radionuclides as soecified in aonendix A. Table A-1 for
^
l normal form radioactive matarial: or l
- fc) 1000 TBa (27.000 Ci). j i (iii) Procedures for submittino advance notifie=' ion.
(A) The notification must be mada in writino to the office of ameh noorooriate novemor or novernor's desinnee and to the Denartmant-(B) A notification delivered by mail must be E-:4..arked at !a==* 7 days before the beginning of !
the 7-day neriod durine which danarture of the ahinment is antima'ad to accur. '
(C) A notification delivered by ma==anoer must raaeh the office of the novernor or of the novernor's desinnee and the Dess...=.; at least 4 days before the beninninn of the 7 dev neriod !
durinn which deoarture of the shioment is estim='ad to neces !
fa) A list of the names and mailine addra==ae of the nevernors' desinnees receivinn advance - j notification of transoortation of nuclear waste was oublished in the Federal Renister on June l 30.1995 (60 FR 34306). -
l fb) The list will be oublished annually in the Federal Register on or about June 30 to reflect any channes in information. l' fc) A list of the names and mailinn addraeaae of the novernors' daciences is available on I t
reauest from the Director. Office of Stata Pmaramm U.S. Nuclear Renulatory Commission.
Washinnton. DC 20555-0001. l (D) The licensee shall retain a coov of the notification as a record for 3 years (iv)Information to be furnLhad in advance notification of shipment. Rach advance notification of i
shioment ofirradiated reactor fuel or nuclear wa=te must contain the followinn infernistion: !
(A) The name. address. and teleohone number of the shioner. carrier. and receiver of the irradiated ;
reactor fuel or nuclear waste shiomant- '
i (B) A descriotion of the irradiatad ra=etor fuel or nuclear e :te contained in the shioment. as i specified in the renidations of USDOT in 49 CFR 172.202 and 172.203(d):
(C) The noint of orinin of the shiomen; and the 7-day oeriod durine which departure of the shioment is estimated to occur:
(D) The 7-day oeriod durine which arrival of the shioment at State boundaries is estimated to i occur; '
I (E) "the destination of the shioment. and the 7-day oeriod durinn which arrival of the shipment is i
estimated to occur. and I i
19
. .. . . l (F) A noint of contact. with a teleohone number. for current shioment information.
(v) Revision notice. A licensee who finds that schedule information oreviousiv fumished to a l novernor or novemor's designee. or the Department. in accordance with this subdivision. will not be i met. shall teleohone a responsible individual in the office of the novernor of the State or of the I novernor's desinnee. and the Department. and inform that individual of the extent of the delav bevond l J
the schedule originally reported. The licensee shall maintain a record of the name of the individual contacted for 3 years.
(vi) Cancellation notice.
(A) Each licensee who cancels an irradiated reactor fuel or nuclear waste shipment for which advance notification has been sent shall send a cancellation notice to the novemor of each State or to the novemor's desinnee oreviously notified. and to the Department.
(B) The licensee shall state in the notice that it is a cancellation and identify the advance notifia=*ian that is baine w-hi The tiema- ahall r**ain a cooy of th- notice as a record for 3 23R11 4
\
(e) OualitY Assurance f,
(1) Oualitv assurance reauirements.
5 (i) Purpose. This subsection describes cuality assurance reauirements apolvinn to design. ourchase.
fabrication. handline. shinoina. storinn. cleanina. assembly. insoection. testing. operation.
rnmintenance. reoair. and modification of components of nackagine that are imoortant to safety. As used i in this subsection. "auality assurance" comorises all those olanned and systematic actions necessary to orovide adeauate confidence that a system or comoonent will oerform satisfactorily in service. Ouality
}
- assurance includes auality control. which comorises those anality assurance actions related to control 3
of the physical characteristics and anality of the material or comoonent to credetermined reauirements.
- (ii) Establishment of orogram. Each licensee shall establish. maintain. and execute a cuality assurance j oronram satisfying each of the aoolicable criteria of 66175.105(eV1) through 175.105(eVl9) and j
satisfyinn any specific crovisions that are aoolicable to the licensee's activities including procurement
- of oackaning. The licensee shall acolv each of the aoolicable criteria in a nraded acoroach. i.e.. to an extent that is consistent with its importance to safety.
(iii) Anoroval of oronram. Before the use of any oackane for the shioment oflicensed material subiect to this subsection each licensee shall obtain Deoartment aooroval of its auality assurance program.
Each licensee shall file a description ofits auality assurance oronram. includine a discussion of which reauirements of this subsection are aoolicable and how they will be satisfied. with the Department.
(iv) Existing oackane desians. The orovisions of this caranraoh apoly to oackanes that have been nooroved for use by the NRC before January 1.1979. and which have been designed in accordance wjih the provisions of 10 CFR Part 71 i;Ltfiect at the time of aoolication fpr.oackane approval. Those packanes will be accepted as having been designed in accordance with a cuality assurance oronram that
~ satisfies the provisions of 6175.10jfe)(1Vii) of this Code.
(v) Existing oackanes. The provisions of this caranraoh apolv to packanes that have been aooroved for use by the NRC before January 1.1979: have been at least partially fabricated orior to that date: and for which the fabrication is in accordance with the provisions of 10 CFR Part 71 in effect at the time of apolication for approval of packane desinn. These oackanes will be accepted as havinn been fabricated 20 7
1
t and assembled in accordance with a cuality assurance oronram that satisfies the provisions of ;
6175.105(eVIVii) of this Code. !
(vi) Previously approved oronrams. An NRC-anoroved auality assurance pronram that satisfies the -
aoolicable criteria of Appendix B of 10 CFR Part 50. and that is established. maintained. and executed with renard to transoort onckanes. will be accepted as satisfyinn the reauirements of 6175.105(eVIVii) of this Code. Before first use. the licensee shall notify the NRC and the Department of its intent to apolv its previously approved Anoendix B pronram to transoortation activities. The licensee shall identify the pronram by date of submittal to the NRC and date ofNRC aooroval.
(2). Oualltv assurance creanization.
(i) The licensee shall be resoonsible for the establishment and execution of the auality assurance ,
erwrimi. The licensee may delenate to others. such as contractors. anents. or consultant = the work of i
establishina and ema'ine the anality assurance oronram. or any cast of the anality assurance oronram. !
but shall retain responsibility for the mwiimi. The licensee shall clearly establish and delinaa'e. in i writina. the authority and daties of persons and orennivations nerformine activities affectinn the safety- !
related functions of stmetures. systems. and compersian. These activities include performine the functions associated with attainine auality obiectives and the cuality assurance functions. ,
t (ii) The au .lity assurance functions are- !
(A) Assurinn that an anomoriate anality assurance oronram is established and effectivelv i executed: and j (B) Verifying. by orocedures such as checkino auditina. and insoection. that activities affectinn ,
the safety-related functions have been oerformed correctiv.
l (iii)'lle eersons and organizations nerforminn auality as'urances functions must have sufficient i authority and ornanizational freedom to- l (A) Identify auality oroblems:
1 (B) Initiate. recommend. or provide solutions: and i (C) Verify implementation of solutions. l (iv) The persons and ornanizations nerformina auality a==urance functions shall report to a I mananement level that assures that the reauired authority and ornanintional freedom. includinn !
sufficient indeoendence from cost and schedule. when opposed to safety considerations. are provided. ;
I (v) Because of the many variables involved. such as the number of nersonnel. the tvoe of activity ,
beine performed. and the location or lac *tions where activities are oerformed. the organizational structure for executinn the cuality assurance pronram may take various forms. orovided that the persons and ornanizations assinned the auality ===arance functions have the reauired authority and oreani=tional freedom.
\
, (vi)liier.oective of the ornanizational stmeture. the individual (s) assinned the resoonsibility for RFsuring effective execution of any portion of the cuality assurance orogram, at any location where activities subiect to this subsection are beine nerformed. must have direct access to the levels of jganagement necu.Wuv to Derform this function.
21
1 (3) Ouality assurance orogram.
l (i) The licensee shall establish. at the earliest oracticable time consistent with the schedule for i accomolishine the activities. a auality assurance program that comoties with the reauirements of j 66175.105(eVI) throuah 175.105(eVl9). The licensee shall document the anality assurance oronram by
- written procedures or instructions and shall carry out the oronram in accordance with those orocedures j throuahout the oeriod durinn which the nachaoine is used. The licensee shall identify the material and
- comoonents to be covered by the cuality assurance oronram. the maior ornanizations particinatine in j the vros.ni. and the desinnated functions of these oreani=tions.
! (ii) The licensee. throunh its auality assurance pronram. shall orovide control over activities affectinn
- the cuality of the identified materials and components to an extent consistent with their imoortance to
! safety. and as necessary to assure conformance to the nooroved desian of each individual aackaae used i for the shioment of radioactive material. The licensee shall assure that activities affectinn ouality are '
! accomplished under suitably controlled conditions. Controlled conditions include the use of
- anoropriate eauinment suitable enviivenwiii=1 conditions for -mnlishine the activity. such as
- adeaunte claanlinaae and assurance that all crereauisites for the niven activity have been natiefied. The l licenace shall take into account the need for special controls. on ==i test cauioment tools. and skills ,
j to attain the reauired anality. and the need for verification of auality by insoection and test.
- i i (iii) The licensee shall base the reauirements and procedures of its cuality assurance pronram on the followine considerations concemina the complexity and oronosed use of the nackane and its l components:
t 4 (A) The imoact of malfunction or failure of the item to safety:
l (B) The desian and fabrication complexity or uniaueness of the item:
t i (C) The need for special controls and surveillance over orocesses and cauipment:
1 i (D) Th~edenree to which functional comoliance can be demonstrated by inspection or test: and (E) The auality history and denree of standardization of the item. '
4 (iv) The licensee shall orovide for indoctrination and training of nersonnel oerformine activities
- l affectina auality. as n~~ary to assure that suitable proficiency is achieved and maintained. The
! licensee shall review the status and adeauacy of the auality assurance orogram at established intervals.
i Mananement of other ornanizations participatina in the auality assurance program shall review ;
i regularly the status and adeauacy of that part of the auality assurance orogram which they are '
! executina.
l l (4) Package desien control.
(i) The licensee shall establish measures to assure that aoolicable reauirements and the oackage
' desinn. as specified in the license for those materials and components to which this subdivision applies. '
are correctiv translated into specifications. drawinns. orocedures. and instructions. These measures
! must include provisions to assure that nooropriate cuality standards are specified and included in I
desian documents and that deviations from standards are controlled. Measures must be established for .
the selection and review for suitability of anolication of materials. oarts. eauipment. and processes that
! are essential to the safety-related functions of the materials. narts. and components of the packaning.
(ii) The licensee shall establish measures for the identification and control of desian interfaces and for j coordination amonn oarticipatina desian ornanizations. These measures must include the establishment
- of written orocedures. amonn carticipatina desian ornanizations. for the review. anoroval. release.
{ distribution. and revision of documents involving desinn interfaces. The desian control measures must 22 l
- . . - - _ - ~ - - - - - --
orovide for verifyinn or checkinn the adeauacy of desinn. by methods such as desian reviews. alternate
- or simolified calculational methods. or by a suitable testine pronram. For the verifyinn or checkinn !
, orace== the licensee shall desinnate individuals or aroups other than those who were responsible for I the oriainal desinn. but who may be from the same ornanization. Where a test oronram is used to verify ,
the adeauacy of a specific desian feature in lieu of other verifyinn or checkinn orocesses. the licensee shall include suitable aualification testing of a prototvoe or sample unit under the most adverse desian !
conditions. The licensee shall apolv desian control measures to items such as the followinn:
(A) Criticality chysics. radiation shielding. stress. thermal. hydraulic. and accident analyses: :
(B) Comoatibility of materials:
l (C) Accessibility for inservice insocction. maintenance. and repair:
(D) Features to facilitate decontamination: and .
E) Delineation of esDt-Dee criteria for insocctions and tests. l 1
(iii)The licensee shall subiect da= ion channes. includinn field channes. to desian control measures i commensurate with those anolied to the original desien. Channes in the conditions specified in the r=+ ace anoroval reauire the Deb-weat's aooroval. i (5) Procurement document control. }
The licensee shall establish measures to assure that adeauate cuality is reauired in the documents for '
orocurement of material. eauipment. and services. whether ourchased by the licensee or by its contractors or subcontractors. To the extent necessary. the licensee shall reauire contractors or subcontractors to Drovide a auality assurance oronram consistent with the anolicable orovisions of this i section.
l l
(6) Instructions, orocedures, anddrawings. l The licensee shall orescribe activities affectine anality by documented instructions. orocedures. or drawinns of a tvDe aDDroDriate to the Circumstances and shall reauire that these instructions.
orocedures. and drawinns be followed. The instmetions. orocedures. and drawinns must include ADDiDDriate cuantitative or cualitative acceptance criteria for determining that important activities have been satisfactorily accomolished.
(7) Document control.
The licensee shall establish measures to control the issuance of documents such as instructions.
orocedures. and drawings. including channes. which orescribe all activities afTecting auality. These measures must assure that documents. including channes. are reviewed for adeauncy. approved for release by authorized personnel. and distributed and used at the location where the prescribed activity is nerformed. These measures snust assure that channes to documents are reviewed and aooroved.
(8) Controlofourckasedmaterial eautoment. andservices.
(i) The licensee shall establish measures to assure that ourchased material. eauipment. and services.
whether purchased directly or through contractors and subcontractors. conform to the orocurement ;
documents. These measures must include provisions. as aooropriate. for source evaluation and l selection. obiective evidence of auality furnished by the contractor or subcontractor. inspection at the :
contractor or subcontractor source. and examination of oroducts on dehverv. ;
23 ,
l
(ii) The licensee shall have available documentary evidence that material rnd eauinment conform to the procurement specifications before installation or use of the material and eauioment. The licensee shall retain. or have available. this documentary evidence for the life of the packace to which it aonlies.
The licensee shall assure that the evidence is sufficient to identify the specific reauirements met by the purchased material and eauipment.
(iii)The licensee shall assess the effectiveness of the control of auality by contractors and subcontractors at intervals consistent with the importance. complexity. and auantity of the product or services.
(9) Identification and control ofmaterials varts. and components.
The licensee shall establish measures for the identification and control of materials, parts. and components. These measures must assure that identification of the item is maintained by heat number.
cart number. or other appropriate means. either on the item or on records traceable to the item, as reauired thmuchout fabrication. installation. and use of the item. These identification and contml measures must be designed to prevent the use of incorrect or defective materials. oarts. and components.
(10) Control ofspecialprocesses.
The licensee shall establish measures to assure that special processes. includinn weldina. heat treating, and nondestructive testing. are controlled and accomplished by aualified personnel using aualified procedures in accordance with applicable codes. standards. specifications. criteria, and other special reauirements.
(11) Internalinspection.
The licensee shall establish and execute a procram for inspection of activities affectina auality by or for the orcanization performine the activity. to verify conformance with the documented instructions.
procedures. and drawinns for accomplishine the activity. The inspection must be nerformed by individuals other than those who performed the activity beine insoected. Examination. measurements, or tests of material or oroducts processed must be performed for each work operation where necessary to assure cuality. If' direct inspection of processed material or products is not carried out, indirect control by monitorine processine methods. eauipment. and personnel must be provided. Both inspection and process monitorine must be provided when cuality control is inadeauate without both. If mandatory inspection hold points, which reauire witnessina or insnectine by the licensee's desinnated goresentative and beyond which work should not proceed without the consent of its desienated representative. are reauired. the specific hold ooints must be indicated in anoropriate documents.
(12) Test control.
The licensee shall establish a test orocram to assure that all testinn reauired to demonstrate that the packacina components will perform satisfactorily in service is identified and performed in accordance with written test procedures that incomorate the reauirements of this section and the reauirements and acceptance limits contained in the nackane anoroval. The test orocedures must include provisions for assurina that all prereauisites for the niven test are met, that adeauate test instrumentation is available and used. and that the test is performed under suitable environmental conditions. The licensee shall document and evaluate the test results to assure that test reauirements have been satisfied.
24
(13) Control ofmeasurine and test eautoment. I The licensee shall establish man = tees to assure that tools. naunes. instmments and other m:
testina devices used in activities affectinn cuality are oronerly controlled. calibrated. and adiusted at snecified times to maintain accuracy within nacana'y limits.
(H) Handline. storare. and shinoins control.
i The licensee shall establish maamres to control. in acerdance with instructions. the handl shinoine. cleaninn. and oreservation of materials and eauipment to be u=~I in c+ckanine to orevent ,
damane or deterioration. When n&e8=y for carticular products. snacial orotective environments. such as inen nas atmosohere. and soecific moisture content and temocrature levels must be specified and !
orovided. '
l t
(13) insDection. test. and ODerating status.
(i) ne licen_=aa shall ='ablish ma==mes to indina'a_ by the use of mark'an such as stamss. ta==
lebels. routino eds. or other suitable maana the **=ms of in=+3 ions and tests serferised usej individual items of the narleanino Da=, maaemes must orovide for the identification of items that
' have satisfactorily an===A reauired in=nar+ ions and taats_ where n&euv to sielude inadvertent !
bysassine of the inr+1ons and **=t= '
-(ii) ne licensee shall aetablish ma==es to identify the oseratine status of components of the s sackanina. such as taooina valves and switches. to orevent inadvertent oseretion.
(l6) Nonconformine materials. oarts. or comoonents.
l
,The licensee shall establish measures to control materials. narts. or components that do not conform to the licensee's reauirements to orevent their inadvertent use or in=tallation. These measures '
include. as assisertate_ orocedures for identification. documentation. seirenation. disposition. and ;
notification to affected ornanizations. Nonconformina items must be reviewed and accepted. rejected.
repaired. or reworked in scardance with documented procedures. . i (17) Corrective action. !
l The licensee shall establish maammes to mesure that conditions adverse to cuality. such as deficiencies.
deviations. defective material and cauipment. and nonconformances. are promotiv identified and ;
corrected, in the case of a sinnificant condition adverse to auality. the measures must assure that the :
cause of the condition is deterwin A and corrective action taken to sielude repetition. The l
identification of the sinnificant condition adverse to auality. the cau=a of the co'ndition. and the !
corrective action taken must be documented and renoned to assisariate levels of mananemI i
?
(18) Oualltv assurance records. '
i The licensee shall mair ain su'fficient written ranards to de=eribe the activities affectine auality. The .
records must include the instructions. orocedures. and drawinns reauired by subdivision (6) of this I subsection. to siescribe auality assurance activities and must include closely related soecifications such as reauired aualifications of sersonnel. orocedures. and cauipment. The rewrds must include the instructions or precedures which establish a records retention pronram that is consistent with aoolicable reaulienients and desinnata= factors such as duration. location. and assinned responsibility. The j licensee shall retain these records for 3 years bevond the date when the licensee last encanes in the activity for which the auality assurance oronram was develooed. If any nortion of the written ,
i 25
v ..
procedures or instructions is superseded. the licensee shall retain the superseded material for 3 years after it is suoerseded. !
(19) Audits, The licensee shall carry out a conioid.ensive system of olanned and oeriodic audits. to verify comoliance with all asoects of the auality assurance oronram. and to determine the effectiveness of the inoir m. The audits must be performed in accordance with written orocedures or checklists by anoropriately trained personnel not havine direct resoonsibilities in the areas beine audited. Audited results must be denmane~i and reviewed by mananement havinn resoonsibility in the area audited.
Follow-uo action. includinn reaudit of deficient areas. must be taken where indicated.
Annendix A-Determination ofay andA?
- 1. Values of A1 and A; for individual radionuclides. which are the bases for many activity limits elsewhere in this Code are niven in Table A-1. The curie (Ci) values specified are obtained by convertine from the Ternhaeauerel (TBa) finure. The curie values are exor=~i to three sinnificant fieures to assure that the difference in the TBa and Ci aumatities is one tenth of one cercent or less.
Where' values of As or Ag are unlimited. it is for radiation control numoses oniv. For nuclear criticality safety. some materials are subiect to controls olaced on fissile matarial.
II. For individual radionuclides whose identities are known. but which are not listed in Table A-1. the detenination of the values of A iand A reauires 7 Deshnent nooroval. except that the values of Ai and A_, in Table A-2 may be used without obtainine D whi. cat anoroval.
III. In the calculations of A 1and A; for a radionuclide not in Table A-1. a sinnie radioactive decay chain. in which radionuclides are cresent in their naturally occurrine oroportions. and in which nq daughter nuclide has a half-life either lonner than 10 days. or lonner than that of the carent nuclide.
shall be considered as a sinnie radionuclide. and the activity to be taken into account. and the A or A, 1
value to be aoolied shall be those corresoonding to the carent nuclide of that chain. In the cace of radioactive decay chains in which any daunhter nuclide has a half-life either lonner than 10 days. or
~
arcater than that of the carent nuclide. the carent and those daunhter nuclides shall be considered as mixtures ofdifferent nuclides.
IV. For mixtures of radionuclides whose identities and resoective activities are known. the following conditions a:miv:
(a) For special form radioactive material. the maximum auantity trananorted in a Tvoe A oackane:
B(i)
,A,(i) l l
(b) For normal form radioactive material. the maximum avantity transoorted in a Tvoe A nackane: !
g B(i) 61
[A(i), 2 I
Where B(i) is the activity of radionuclide i and A1 (i) and Azfi) are the A3-and A; values for l radionuclide i. respectivels Alternatively. an A 1value for mixtures of special form material may be determined as follows:
26
- . . ;- e
3- ..
L -
1
- 1 1 i
!- A, for mixture -- ,
i- - f(i)
- ),
4
[A,(l)
, j
' I Where fri) is the fraction of activity of nuclide i in the mixture and Aifi) is the ensisedate A value for _ i nuclide i. l An A; value for mixtures of normal form ns=*arial may be determined as follows:
L i .
4 1
A, for mixture =
2, f(i) ,-
5 I,A(i) 2 i ,
n.
l t
Where fri) is the fraction of activity of nuclide i in the mixture and A;(i) is the anorooriate A; value for nuclide i. ,
V. When the identity of each radionuclide is known. but the indiv@a=1 activities of some of the radionuclides are not known. the radio =elida may be aronnad and the lowest As or A7 value. as !
anoropriate. for the radiam-lida in each aroun may be used in anolvinn the formal == in naranraoh IV.
Groups may be based on the total minha activity and the total beta /emmma activity when t_ha=, are ,
, 'known. usine the lowest A ior A values 7 for the alahs emitters and beta /ommma emitters. .
t Table A Af andA> Values for EnknuclMn 1
Symbol ur l Element and y . sgf Ai(T8q)'MA i(Cl) < > 1A (T8q)nt 4A:(Cl) -
Specificactivity .
radieneclide atomic member l (T8ela) (Ci/m) !
Ac-225 Actinium (89) 0.6 16.2 Ix10i 0.270 2.tx10t 5.8x10' !
Ac.227 40 1080 2x104 5.41x10* 2.7 7.2x10' ,
Ac-228 0.6 16.2 0.4 10.8 8.4x10' 2.2x10*
{
Aa-105 Silver (47) 2 54.1 2 54.1 1.1x10' 3.0x10' Aa-108m 0.6 16.2 0.6 16.2 9.7x 10 2.6x10' I AaIl0m 0.4 10.8 0.4 10.8 1.8x10' 4.7x10' Aa-f ll 0.6 16.2 0.5 13.5 - 5.8x10' l.6x10' Al-26 Aluminum (13) 0.4 10.8 0.4 - 10.8 7.0x10* 1.9x10* '
Am-241 Americium (95) 2 54.1 2x10* 5.4ix10 4 1.3x10' 3.4 l Am-242m 2 54.1 2x10 5.4.t x104 3.6x10" 1.0x10' !
Am 243 2 54.1 2x10* 5.41x104 7.4x104 - 2.0x10 4 Ar-37 A. 'IS) 40- 1080 40 1080 3.7x10' 9.9xlC' Ar-39 20 541 20 541 1.3 3.4x10' !
Ar-41 0.6 16.2 0.6 16.2 1.5x10' 4.2x10' Ar-42 0.2 5.41 0.2 5.41 9.6 2 2.6x 10 As-72 - Arsenic (33) 0.2 5.41 0.2 5.41 6.2x 10' l .7x 10' l As-73 40 1080 40 1080 i 8.2x10' 2.2x 10*
As-74 1 27.0 0.5 13.5 3.7x 10' 9.9x 10'
- As-76 0.2 5.41 0.2 5.41 5.8x 10' l.6x10' As 77 20 541 0.5 13.5 3.9x10' l.0x10* i At-2il Astatine (85) 30 811 2 $4.1 7.6x10' 2.1x10* !
Au.193 Gold (79) 6 162 6 162 3.4x10' 9.2x 10' Au-194 1 27.0 1 27.0 1.5x 10' 4.1 x 10' Au-195 10 270 10 270 1.4x10' - '
3.7x 10'
-27
Symbol of Element cnd ~ . .. r A (TBq) . As (Cl) .;As (T8q) ? A (Cl) Specific activity radionuclide atomic number (TBq/t) (Ci/g)
Au-l% 2 54.I 2 54.1 4.0x10' l.1x10' Au-198 3 81.1 0.5 13.5 9.0x l 0' 2.4 x10' Au-199 10 270 0.9 24.3 7.7x 10' 2.t x t 0' Da 131 Barium (56) 2 54.1 2 54.1 3.1 x 10' 8.4 x10' Ba-133m 10 270 0.9 24.3 2.2x 10' 6. I x 10' Ba-133 3 81.1 3 81.1 9.4 2.6x 10' Ba-140 0.4 10.8 0.4 10.8 2.7x 10' 7.3 x 10' Be 7 Beryllium (4) 20 54l 20 541 1.3x10' 3.5x t 0' Be-10 20 541 0.5 13.5 8.3x 10 d
2.2x104 Bi-205 Bismuth (83) 0.6 16.2 0.6 16.2 1.5x10' 4.2x 10' Bi 206 0.3 8.11 0.3 8.11 3.8x10' l.0x10' Bi-207 0.7 18.9 0.7 18.9 1.9 5.2x10' Bi 210m 0.3 8.l l 3x10 4 0.811 2.t x104 5.7x10 d
Bi-210 0.6 16.2 0.5 13.5 4.6x10' I.2x10' Bi-212 0.3 8.11 0.3 8.11 5.4x10' l.5x10' Bk-247 Bestelium(97) 2 54.1 2x10 4 5.4 t x104 3.8x10 4 1.0 Bk-249 40 1080 8xlo-3 2.16 6. t x 10' I .6x 10' !
Br 76 B c.....-435) 0.3 8.11 0.3 8.11 9.4x 10' 2.5xl0' Br-77 3 81.1 3 81.1 2.6x 10' 7. t x10' Br-82 , 0.4 10.8 0.4 10.8 4.0x10' l.tx10' C Il C.ibn(6) 1 27 0.5 13.5 3.1 x 10' 8.4 x10' C-14 40 1080 2 54.1 1.6xl0" 4.5 Co-41 Calcium (20) 40 1080 40 1080 3.1xl04 8.5x104 Co-45 40 1080 0.9 24.3 6.6x10 2 1.8x10' Ca-47 0.9 24.3 0.5 13.5 2.3x10' 6. I x 10' Cd-109 Cadmium (48) 40 1080 1 27.0 9.6x10'
~
2.6x 10' Cd-II3m 20 541 9x10 4 2.43 8.3x 10' 2.2x 10 2
Cd-Il5m 0.3 8.I I 0.3 8. l l 9.4x10 2 2.5x 10' Cd-l15 4 108 0.5 13.5 1.9x10' 5.1 x 10' Cc-139 Cerium (58) 6 162 6 162 2.5x1026 .8x10' Ce143 0.6 16.2 0.5 13.5 2.5x10' 6.6x t 0' Cc-144 0.2 5.41 0.2 5.41 1.2x10' 3.2x 10 3
Cf248 Californium (98) 30 811 3x104 8.lix10 4 5.8x10' l .6x 10' Cf-249 2 54.1 2x10 d
5.41xl04 1.5xl0 4 4.1 Cf-250 5 135 5xl0* I.35x104 4.0 1.1x10 2 Cf-251 2 54.1 2x10' 5.41x104 5.9x10 4 1.6 Cf-252 0.1 2.70 Ix104 2.70x10 4 2.0x10' 5.4x 10 2
Cf-253 40 1080 6x104 1.62 1.tx10' 2.9x t 0' i Cf 254 3x10 4 8.IIx10 4 6xl0* 1.62x104 3.1xl0' 8.5x10' Cl-36 Chlorine (17) 20 541 0.5 13.5 1.2x104 3.3 x104 ;
Cl-38 0.2 5.41 0.2 5.41 4.9x 10' l.3x10' Cm-240 Curium (%) 40 1080 2x10 4 0.541 7.5x10 2
2.0x 10' Cm-24 l 2 54.1 0.9 2
{
24.3 6. t x10 1.7x 10' i Cm-242 40 1080 Ix104 0.270 1.2x 10' 3.3x 10' Cm 243 3 81.1 3x10 4 8.lix10 4 1.9 5.2 x 10' i Cm-244 4 108 4x10 d 1.0Bx104 3.0 8. t x 10' {
Cm-245 2 54.1 2x10 d 4 5.41x104 6.4x 10 1.7x10 4 Cm-246 2 54.1 2x10 d 5.4 t x 10-3 1.tx10 4 3.1 x 104 Cm-247 2 54.1 2x10 d 5.41x104 3.4 x10 4
9.3x 104 Cm-248 4x10-2 1.08 5x10 4 1.35x104 1.6x10" 4.2x10 4 Co-55 Cobah(27) 0.5 13.5 0.5 13.5 1.1x10' 6 3.1 x 10 Co 56 0.3 8.11 0.3 8.1 I 1.1x10' 3.0x 10' Co-57 8 216 8 216 3.1 x 10 2
8.4 x10' Co-58m 40 1080 40 1080 2.2x10' 5.9x 10
Co 58 I 27.0 1 27.0 1.2x10' 3.2x 10' Co 60 0.4 10.8 0.4 10.8 4.2 x 10' l.1x10' Cr-51 Chromium (24) 30 StI 30 811 3 4x10' 9.2x l0' Cs-129 Cesium (55) 4 108 4 108 2.Ex 10' 7.6x 10' Cs-131 40 1080 40 1080 3.8 x 10' l.0x10' 28
_~ .- - . . . . - - .- - - . _ _ . _ _ - - - . . - - . -..
Symbol of . Elemsat and Ai(TBq) A (Cl) . A (TBq) A (Cl) Specific activity radienuclide atomic number (TBq/g) (Ci/g)
' Cs-132 1 27.0 1 27.0 5.7x 10' l.5x10' Cs-134m 40 1080 9 243 3.0x 10' 8.0x 10' Cs-134 0.6 16.2 0.5 13.5 4.8 x 10' l.3x10' Cs-135 4 4 40 1080 0.9 24.3 4.3x 10 1.2x10 Cs-136 0.5 13.5 0.5 13.5 2.7x 10' 7.3 x 10'
. Cs-137 2 54.1 0.5 13.5 3.2 8.7x 10' Cu-64 Copperf29) 5 135 0.9 24.3 1.4x10' 3.9x106 Cu-67 9 243 0.9 24 3 2.8x 10' 7.6x 10' Dy-159 Dysprosium (66) 20 541 20 541 2.1 x102 5.7x 10' Dy-165 0.6 16.2 0.5 13.5 3.0x10' 8.2x l 0*
j Dy 166 03 8.11 0.3 8.11 8.6x 10' 23x10' 1 Er-169 Erbium (68) 40 1080 0.9 243 3.1x10' 83x 10*
Er-171 0.6 16.2 0.5 13.5 9.0x 10' 2.4x10' Es-253 Einsteinium (99)* 200 5400 2.1:104 5.4 100
! Es-254 30 til 3x10 4 8.lix104 Es-254m 0.6 16.2 0.4 10.8 Es-255 j Eu-147 Europium (63) 2 54.I 2 54.1 1.4 x 10' 3.7x 10' Eu-148 0.5 13.5 0.5 13.5 6.0xl0 2 1.6x10' Eu-149 20 541 20 54I 3.5x102 9.4x102
- Eu-150 0.7 18.9 0.7 18.9 6.t x10' I.6x10' Eu-152m 0.6 16.2 0.5 13.5 8.2x 10' 2.2x 10' Eu-152 0.9 24 3 0.9 243 6.5 f.8xl0 2 Eu-154 0.8 21.6 0.5 13.5 9.8 2.6x102 Eu-155 20 54l 2 54.1 1.8x10' 4.9xl0 2 Eu-156 0.6 16.2 0.5 13.5 70x10 3 5.5x 10' ,
F-18 Fluorine (9) 1 27.0 0.5 13.5 3.5x10' 9.5x10' Fe-52 fron(26) 0.2 5.41 0.2 5.41 2.7x 10 5
73x10' Fe-55 40 1080 40 1080 8.8x 10' 2.4 x 10' Fe-59 0.8 21.6 0.8 21.6 1.8x 10' 5.0x 10' l Fe-60 40 1080 0.2 5.4 I 7.4x 10 2.0x 10 3 Fm-255 Fermium (100)* 40 IGod 0.8 21.6 Fm-257 10 270 8:13* 21.6 x 10 I Ga-67 Gallium (31) 6 162 6 162 2.2x 10' 6.0x 10' Ga-68 0.3 8.11 0.3 8. I I 1.5x10' 4. t x 10' Ga-72 0.4 10.8 0.4 10.8 1.1x10' 3. I x l0*
Gd-I46 Gadolinium (64) 0.4 10A 0.4 10.8 6.9x103 1.9x 10' '
Gd-148 3 81.1 3:10 8.11:104 1.2 3.2 x 10' Gd I53 10 270 5 135 13x10 3 J.5 x 10' Gd 159 4 108 0.5 13.5 3.9x 10' l.1x10' Ge 68 Germanium (32) 0.3 8.11 03 8.1 I 2.6x 102 7.1 x 10' Ge-11 40 1080 40 1080 5.8x 10' l.6x10' Ge-77 03 8.11 03 8.11 1.3x10' 3.6xl0' H-3 Hyda.g41) Sect-Tritium Hf-172 Hafnium (72) 0.5 13.5 0.3 8.11 4.lx10' l.1x10' Hf-175 3 81.1 3 81.1 3.9x10 3 1.tx10' Hf-181 2 54.1 0.9 24.3 6.3 x103 1.7x10' Hf-182 4 108 3 x10'3 0.811 8.1x104 2.2 x l 0
Ha-194 Mercury (80) 1 27.0 1 27.0 1.3 x t 0-' 3.5 Hg-195m 5' 135 5 135 1.5x 10' 4.0x10' Ha-197m 10 270 0.9 24.3 2.5x 10' 6.7x 10' Hg-197 10 270 10 270 9.2x 10' 2.5x t 0' Hg-203 4 108 0.9 243 5. t x10 2
1.4x10' Ho 163 i Holmium (67) 40 1080 40 1080 2.7 7.6x 10' '
Ilo-166m 0.6 16.2 0.3 8.11 g,g 6.6x10 2 110 166 0.3 8.11 03 8.11 2.6x 10' 7.0x 10' I-123 lodine (53) 6 162 6 162 7.1 x 10' l.9x10' I-124 0.9 24.3 0.9 24.3 93x10' 2.5 x 10' l-125 20 541 2 54.1 6.4x 10 3 1.7x 10' -
29
i **
.- . . t Symbol of Element and 2 '
@ A (T8g)L iAs(Cl)- 7 A (T8q) ' " A (Cl) Specific activity i radioneellde seemic rreber '
(T8e/a) (Cum) l-126 2 54.1 0.9 24.3 2.9x 10' 8.0x 10' l129 !
Unlimited Unlimited Unlimited Unlimited 6.5x10* 1.8x10 d !
l-131 3 81.1 0.5 13.5 4.6x 10' l.2x10' )
1-132 0.4 10.8 0.4 10.8 3.8x 10' l.0x10' I-133 0.6 16.2 0.5 13.5 4.2x10' l.txi@
l 134 0.3 l 8.11 0.3 8.11 9.9x 10' 2.7x 10' l 135 0.6 16.2 0.5 13.5 1.3xt0' 3.5xl#
in-til Indium (49) 2 54.1 2 {
54.1 1.5x10' 4.2x 10' i in-II3m 4 108 4 108 6.2x10' l.7x10' i in-ll4m 0.3 8.11 03 8.11 8.6x10' I 23x10' in-ll5m 6 162 0.9 24 3 2.2x10' 6.1xl@
tr-IS9 Iridium (77) 10 270 10 270 1.9x10' 5.2x 10' ,
Ir-190 0.7 18.9 0.7 18.9 23x10' 6.2x10' [
lt192 1 27.0 0.5 13.5 3.4x10' 9.2x10' +
tr-193m 10 270 10 270 2.4x 10' 6.4x10' Ir-194 l 0.2 5.41 0.2 5.41 3.1x10' 8.4x10' K-40 !
Potassium (19) 0.6 16.2 0.6 16.2 2.4x10-' 6.4xl0* i K 42 0.2 5.4I 0.2 5.41 2.2x10' 6.0xIF K-43 1.0 27.0 0.5 3.3xlf 13.5 1.2x10' Kr K.y ^ 36) 40 1080 40 1080 7.8x t0* 2.Isl0'3 !
Kr45m 6 162 6 162 3.0x10' 8.2xlf l Kr45 20 541 10 270 1.5x10' 3.9x10' {
Kr47 0.2 5.41 0.2 5.41 I.0xit
~
2.8x10' La 137 Lanthanum (57) 40 1080 2 54.1 1.6x10-' 4.4x1014-140 0.4 10.8 0.4 10.8 2.1xl0* 5.6x 10' Lu-172 Luletium(71) 0.5 13.5 0.5 13.5 4.2x10' I.Ix10' Lu-173 8 2I6 8 216 5.6x10' I.5x10' Lu 174m 20 541 8 216 2.0x10' 53x10' Lu-74 8. 216 4 108 2.3x10' 6.2x 10'
. Lu-177 30 811 0.9 243 4.Ix10' l.1x10' MFP (see 49 CFR 173.433) (see 49 CFR 173.433)
Ma-28 Maanesium(12) 0.2 5.41 0.2 5.41 2.0x10' 5.4xit Mn 52 Mann 225) 03 8.11 0.3 8.11 1.6x10* 4.4x 10' Mn Unlimited Unlimited Unlimited Unlimited 6.8x10 I.8x 10-'
Mn-54 1 27.0 I 27.0 2.9x10' 7.7x 10' Mn-56 0.2 5.41 0.2 5.4I 8.0x10' 2.2x 10' Mo.93 Molybdenum (42) 40 1080 7 189 g,g 4.1x10 2 Mo-99 0.6 16.2 0.5 13.5' l.8x10' 4.8x l0' N-13 Nitrosen(7) 0.6 16.2 0.5 13.5 5.4x10' l.5x t 0' No.22 Sodium (ll) 0.5 13.5 0.5 13.5 23x10' 63x10' No-24 0.2 5.41 0.2 5.4I 3.2x10' 8.7xl@
Nb-92m Niobium (41) 0.7 18.9 ' O.7 18.9 5.2x10' l.4x10' Nb 93m 40 1080 6 162 8.8 2.4x10' NI44 0.6 16.2 0.6 16.2 6.9x 10 l.9xl(/' j Nb-95 1 27.0 1 27.0 1.5x10' 3.9x10' Nb 97 0.6 16.2 0.5 13.5 9.9x 10' 2.7x10' Nd-147 Neodymium (60) 4 108 0.5 13.5 3.0x 10' 8.t x10' Nd-149 0.6 16.2 0.5 13.5 4.5x10' l.2x10' Ni-59 Nickel (28) 40 1080 40 1080 3.0x10 8.0x 10 !
Ni-63 0' 1080 30 811 2.1 5.7x 10' Ni-65 0.3 8.11 03 8.11 7.t x10' l.9x10' Np-235 Neptunium (93) 40 1080 40 1080 5.2x 10' I.4x10' Np-236 7 189 lx 10 d 2.70x 10 4.7x 10 1.3x 10~'
Np 237 2 54.1 2x10 d 5.41x103 2.6x10 7.1x 10-'
Np-239 6 162 0.5 13.5 8.6x10' 23x10' Os-185 Osmium (76) I 27.0
(
1 27.0 2.8x10' 7.5x t o' i Os-191m 40 1080 40 1080 4.6x10' l.3xlf Os 191 10 270 0.9 24.3 1.6sI0' 4.4x 10' Os-193 0.6 16.2 0.5 13.5 2.0x 10' 5.3x10' 30
_-._______...__._.__m.__
. . f : l h
Symbol of . Element and r . 2 e.A:(TBq)1 a At (Cl)4 : A (TBq) A (Cl) Specific activity I
radienselide atomic ammber i Os-194 (TBola) (Ci/a) 0.2 5.41 0.2 5.41 1.1x10' 3.1x 103 !
P 32 5 f - 415) 03 8.11 03 8.11 I.tx10' 2.9x10' !
P-33 40 1080 0.9 243 5.8x 10' l.6x10' Pa-230 Protactinium (91) 2 54.1 0.I l 2.70 1.2x10' 33x10' Pa-231 0.6 16.2 6x 10-' l.62x103 1.7x 10 4.7x104 Pa-233 5 135 0.9 24 3 7.7x103 2. t x 10' I
" I'b-201 1 M82) I 27.0 1 27.0 6.2x 10' l.7x10' Pb-202 40 1080 2 54.1 d f 1.2x10 3.4v104 Pb-203 3 81.1 l 3 81.1 1.1x10' 3.0x10' Pb-205 Unlimited Unlimited Unlimited {
Unlimited 4.5x10* 1.2xl0 d i Pb-210 0.6 16.2 9xl0* '
0.243 2.8 7.6x 10' Pb-212 0.3 8.11 03 8.11 5.tx10' l .4x l0' i Pd 103 Palladium (46) 40 1080 40 1080 2.8x10' 7.5x10' !
Pd-107 Unlimited Unlimited Unlimited Unlimited 1.9x10 4 5.lx10d Pd-109 0.6 i 16.2 0.5 13.5 7.9x 10' 2.1x10* !
Pm-143 - Promethium (61) 3 81.1 3 81.1 13xt03 3.4x10' !
Pm-led -
0.6 16.2 0.6 16.2 9.2x 10' 2.5x l0' Pm-l45 30 SII !
7 189 5.2 1.4x103 Pm-147 40 j 1080 0.9 243 3.4x10' 93x103 i Pm-148:n -
0.5 13.5 0.5 13.5 7.9xl03 2.1x10' !
Pm-149 0.6 16.2 0.5 13.5 1.5x10' 4.0x10' ;
Pm-151 3 81.1 0.5 13.5 2.7x10' 73xl0' '
Po-208 Polonium (84) 40 1080 2x10* 0.541 2.2x10' 5.9x103 Po-209 40 i 1080 2x 10 O.541 6.2x 10-'
Po-280
- I.7x10' (
40 1080 2x104 0.541 1.7x103 4.5x10' ;
Pr 142 Prasoodymium (59) 0.2 5.41 0.2 5.41 43x10' l.2x10' i Pr-143 4 108 0.5 13.5 2.5x10' 6.7x10' Pt-188 Platinum (78) 0.6 16.2 0.6 16.2 2.5x10' 6.8x10' Pt-191 3 l 81.1 3 81.1 8.7x 10' ft 193m 2.4x10' l 40 1080 9 243 5.8x10' l.6x10' Pt193 40 1080 40 1080 1.4
(
Pt 195m 3.7x10'
- i 10 270 2 54.1 6.2x 10' Pt197m I.7x10' i 10 270 0.9 243 i
3.7x10' l.0x10' Pt-197 20 541 0.5 13.5 3.2x10'
(
Pu-236 8.7x10' ;
Plutonium (94) 7 189 7x10 d 1.89x104 2.0x10' 53xl03 i Pu-237 20 541 20 541 4.5x103 1.2x10' Pu-238 2 54.1 2x10* 5.41x10 ' 63x10 l.7x10' Pu-239 2 54.I 2x10* 5.41x104 23x10-3 6.2x 10-3 Pu-240 2 54.1 2xl0* 5.41x l0*' 8.4x104 23x10" Pu-241 40 [
1080 Ix104 0.270 '
3.8 1.0x103 Pu-242 2 54.1 2x10' 5.41x 10-' I.5x10 d 3.9x 10-3 Pu-244 03 8.11 i 2x10* 5.41x104 6.7x104 f.8x104 !
Ra-223 Radium (88) 0.6 16.2 3x104 0.811 I.9x10' Ra-224 5.tx10' 03 8.11 6x104 I.62 Ra 225 5.9x 10' I.6x10' 0.6 16.2 2x103 0.541 1.5x10' 3.9x10' f Ra 226 0.3 8.11 2x104 0.541 3.7x 10'3 1.0 Ra-228 0.6 16.2 I
4x104 1.08 1.0x10' 3 Rb-si 2.7x10 Rubidium (37) 2 54.1 0.9 243 l Rb-83 3.1x10' 8.4x10*
2- 54.1 2 54.1 i Rb 84 6.8x103 f.8x10' 1 27.0 0.9 24 3 Rb-86 1.8x10' 4.7x10' 03 8.11 0.3 8.11 Rb-87 3.0x10' 8.1x10' Unlimited Unlimited Unlimited Unlimited 3.2x 10* 8.6x 10* !
Rb (natural) Unlimited Unlimited Unlimited Unlimited 6.7x10' l.8x10' Re 183 Rhenium (75) 5 135 5 135 Re 184m 3.8x103 1.0x10' ,
3 81.1 3 81.1 1.6x103 43x10' Re184 1 27.0 1 27.0 6.9x103 I.9x 10' Re 186 4 108 0.5 13.5 Re-187 Unlimited 6.9x 10' l.9xt0' Unlimited Unlimited Unlimited i
Re I88 1.4x10* 3.8x 10*
0.2 5.4 I 0.2 5.41 3.6x10' 9.8x 10' 31 n'. _ _ ,-- - _ .- . - - - , . - . . ,
y* *.
~
Symbol of Elesment cod 1 iAs(TBq)? ? As (Cl) ; ~A (T84 ),
A3 (Ci) SPecificactivity radieneelide atomic number (TBq/a) (Ci/mi Re-189 4 108 0.5 13.5 2.5x10' 6.8x 10' Rc (natural) Unlimited Unlimited Unlimited Unlimited 2.4x10' Rh-99 Rhodium (45) 2- 54.1 2 54.1 3.0x 10' 8.2x10' Rh-101 4 108 4 108 4. t x 10' l.1x10' Rh-102m 2 54.1 0.9 24.3 2.3x t 02 6.2x 10' Rh-102 0.5 13.5 0.5 13.5 4.5x 10' l.2x10' Rh-103m 40 1080 40 1080 1.2x10' 3.3x10' r.h 105 10 270 0.9 24 3 3.1x 10' 8.4x 10' Rn-222 Radon (86) 0.2 5.41 4x 10 O.108 5.7xtoi 1.5xl0' Ru-97 Ruthenium (44) 4 108 4 108 I.7x10' 4.6x10' Ru-103 2 54.1 0.9 243 1.2x10'- 3.2x 10'
)
Ru-105 0.6 16.2 0.5 13.5 2.5x10' 6.7x10*
Ru 106 0.2 5.41 0.2 5.41 1.2x10' 3.3x10' S-35 Sulfur (16) 40 1080 2 54.1 f.6x10' 43x10' Sb.122 Antimony (51) 03 8.11 03 8.11 I.5x10' 4.0x10' Sb 124 0.6 16.2 0.5 13.5 6.5x10' l.7x10' )
Sb-125 2 $4.I 0.9 243 3.9x10' l.0x10' i l Sb-126 0.4 10.8 0.4 10.8 3.1x10' 8.4x10' Sc.44 Scandium (21) 0.5 13.5 0.5 13.5 6.7x10' I.8x10' Sc 0.5 13.5 0.5 13.5 13x10' 3.4x10' Sc-47 9 243 0.9 24.3 3.1x10' 83x10' Sc 48 03 8.11 03 8.11 5.5x10' l.5x10' So 75 Selenium (34) 3 81.1 3 81.1 5.4x103 1.5x10' I Se-79 40 1080 2 54.1 2.6x10-3 7.0x10-3 Si-31 Si h .'14) 0.6 16.2 0.5 13.5 1.4x10' 3.9x10' i Si-32 40 10800 0.2 5.41 3.9 1.tx103 l Sm 145 Samarium (62) 20 541 20 541 9.8x10' 2.610' Sm-147 Unlimited Unlimited Unlimited Unlimited 8.510-'O ' 2.310*
Sm-151 40 1080 4 108 9.710 2.6x 10' Sm 153 !'
4 108 0.5 13.5 1.6x 10' 4.4x10' Sn II3 Tin (50) 4 . 108 4 108 3.7x102 1.0x10' Sn-ll7m 6 162 2 54.1 3.0x10' 8.2x10*
Sn-119m '40 1080 40 1080 1.4x10 3 3.7x10' Sn-121m 40 l 1080 0.9 24 3 2.0 5.4x10' .
Sn-123 0.6 16.2 0.5 13.5 3.0x103 8.2x l0' '
Sn-125 0.2 5.41 0.2 5.41 4.0x10' l.Ix10' Sn-126 03 8.11 03 8.11 1.0I0 ' 2.8103 Sr42 Strontium (38) 0.2 5.41 0.2 5.41 23x10' 6.2x 10*
Sr45m 5 135 5 135 1.2x10' 33x10' Sr45 2 54.1 2 54.1 8.8x 102 2.4x10' Sr47m 3 81.1 3 81.1 4.8x 10' 13x 10' !
Sr-89 0.6 16.2 0.5 13.5 f.tx10' 2.9x10' >
St-90 0.2 5.41 0.1 2.70 5.1 1.4x103 Sr-91 !
03 8.11 03 8.11 I.3x10' 3.6x10' Sr-92 0.8 l 21.6 0.5 13.5 4.7x 10' l.3x10' ;
T Tritium (l) 40 1080 40 1080 3.6x 10' 9.7x10' ;
Ta-178 Tantalum (73) - 1 27.0 1 27.0 4.2 x 10' 1.tx10' To-179 30 811 l
30 811 4.1x10' l.1x10' Ta-182 0.8 21.6 0.5 13.5 2.3x102 6.2x10' Tb-157 Terbium (65) 40 1063 10 270 5.610-' I.5x10' 7b-158 I 27.0 0.7 18.9 5.610' l.5x 10' 7b 160 0.9 243 0.5 13.5 J.2x102 1.1x10' Tc-95m 2 i Technetium (43) 54.1 2 54.1 8.3x103 2.2x l0* ;
Tc-96m 0.4 10.8 0.4 10.8 1.4x10* 3.8x10' Tc-% 0.4 10.8 0.4 t
10.8 1.2x10' 3.2x10' Tc-97m 40 1080 40 1080 5.6x103 1.5x10' Tc.97 Unlimited Unlimited Unlimited Unlimited 5.2x 10-' l .4 x10-3 Tc.98 0.7 18.9 0.7 18.9 3.2x 10* 8.7x10 d Tc-99m 8 216 8 216 1.9x10' 53x10' 32
SymbolCf Element and ' K As (TBq): A (TBq)
Ai (Cl) As (Cl) Spectfic activity radionuclide atomic number (TBq/g) (Ci/g) 4 Tc-99 40 1080 0.9 24 3 63x10 d TeIl8 1.7x104 1 Tellurium (52) 0.2 5.41 0.2 5.41 6.8x 10' l.8x10' Te-12im 5 135 5 135 2.6x 102 7.0x 10' Te-125 2 54.1 2 54.1 2.4 x 10' Te-123m 6.4 x 10' 7 189 7 189 3.3x103 8.9x 10' Te-125m 30 8ll 9 243 6.7x 102 l.8x10' Te-127m 20 541 0.5 13.5 3.5x 102 Te-127 9.4 x 10' 20 541 0.5 13.5 9.8x 10' Te-129m 2.6x t0' 0.6 16.2 0.5 13.5 1.tx10' 3.0x 10* !
Te-129 0.6 16.2 0.5 13.5 7.7x 10' 2.t x10' Te-13 Im 0.7 I 8.9 i 0.5 13.5 3.0x 10' 8.0x10' Te-132 0.4 10.8 {
0.4 10.8 1. t x 10*
n-227 3.0x10' *
{
norium(90) 9 243 Ix104 0.270 1.t x10' 3.1x10' j D 228 03 8.11 4x10 d 1.08x104 3.0x10' 8.2x103 l Th-229 03 8.11 3x104 8.lix10d 7.9x104 2.1 x l04 n 230 2 54.1 2x10 d i
5.41 x 10 7.6x10d 2.Ix104 D-231 40 1080 0.9 {
243 2.0x10' 5.3 x 10' Th-232 Unlimited Unlimited Unlimited Unlimited 4.0x10* I.tx104 !
Th-234 0.2 5.41 0.2 5.41 8.6x103 2.3x10' Th (natural) Unlimited Unlimited Unlimited Unlimited 8.t x t 0* 2.2x t 04 Ti-44 Titanium (22) 0.5 13.5 0.2 5.41 6.4 1.7x10'11-200 hallium(81.1) 0.8 21.6 0.8 21.6 2.2x10' 6.0x10' T1-201 10 270 10 270 7.9x 10' TI202 2.1x10' 2 54.l 2 54.1 TI-204 2.0x 103 53x 10*
4 108 0.5 13.5 1.7x 10' 4.6x 103 Tm-167 Thulium (69) 7 189 7 189 3.1x 10' Tm-168 8.5x10*
0.8 21.6 0.8 21.6 Tm-170 3.1xl0 3 83x 10' 4 108 0.5 Tm-171 13.5 2.2x10 3 6.0x 10' 40 1080 10 270 4.0x10' t.lx10' U-230 Uranium (92) 40 1080 Ix104 0.270 1.0x10' 2.7xl0*
U-232 3 81.1 U-233 3x10d 8.IIx104 83x10" 2.2xl0' 10 270 1x104 2.70xI04 3.6x1O d
9.7xI04 U-234 10 270 lx104 2.70x10 2 2.3 x 10 6.2x 10-'
U-235 Unlimited Unlimited Unlimited Unlimited 8.0x 10-*
U-236 2.2x 10*
10 270 lx104 2.70x104 2.4 x 10+ 6.5x10 4 U-238 Unlimited Unlimited Unlimited Unlimited 1.2x10 4 4 U (natural) 3.4x 10 Unlimited Unlimited Unlimited Unlimited U (enriched 2.6x10* 7.t x104 Unlimited Unlimited Unlimited Unlimited -
U (enriched 10 270 (see 117.143415% or less) 1x104 2.70x104 U (depleted) Unlimited -(sce 49 CFR 173.434 knore than 5%)
Unlimited Unlimited Unlimited -
V-48 Vanadium (23) 0.3 8.11 (see 49 CFR l73.434) 0.3 8.11 63x 10' V 49 40 l.7x10' 1080 40 '
W 178 Tungsten (74) 1080 3.0x102 8.t x 10' 1 27.0 1 27.0 4 "
W 181 1.3x10 3.4x 10' 30 811 30 3 811 2.2x 10 6.0x 10' W 185 40 1080 0.9 24 3 3.5xl0 2 W 187 9.4x 10' 2 54.1 0.5 13.5 2.6x 10' 7.0x 10' W-188 0.2 5.41 0.2 5.41 3.7x10 2 Xe-122 Xenon (54) 0.2 1.0x10' 5.41 0.2 5.41 Xe-123 0.2 .
4.8 x 10' 13xl0*
5.4 l 0.2 5.41 Xe-127 4 4.4x 10' l.2x10' 108 4 108 Xc-13 Im 1.0x10' 2.8x 10' 40 1080 40 Xe-133 1080 3.1 x 10' 8.4 x 10' 20 541 20 541 6.9x 10' l9x10' Xe-135 4 108 4 108 d Y-87 Yttrium (39) 9.5x10 2.6x t 0' 2 54.1 2 Y.88 54.1 1.7x10' 4.5x 10' 0.4 10.8 0.4 Y 90 10.8 5.2x103 I.4x10' 0.2 5.41 0.2 ,
Y 9fm 5.41 2.0x10' 5.4x10' 2 54.1 2 Y-91 54.1 I.5x t0* 4 2xt0' 0.3 8.11 03 Y-92 8. l l 9.1x 10 3 2.5x 10' 0.2 5.41 0.2 5.41 3.6x 10' 9.6x 10*
t 33
,.- ~ _ - .~. . . -. . . . - ~ . . - . _ - . - _ . . - -
- 1. ,+, . .
Symbolof . Element and t.x . '
- A (TBq), As (Cl)
_rsdisamelide atomic ammber. -A (T8q). A (Cl) ~~
Y-93 Specific activity 0.2 5.41 (TBq/t)
Yb-169 0.2 (Ci/a)
Ytterbium (70) 3 Bl.I 5.41 1.2x10' Yb 175 3 3.3x10' ~
30 81.1 8.9x103 Zn45 811 0.9 2.4x 10' -
Zinc (30) 2 24.3 Zn ',^ . 54.1 2 6.6x 10' l.8x10' -
2 54.1 .
Zn49 54.I 0.5 3.0x 103 8.2x 10' ~
4 13.5 1.2x10' t Zr.88 108 0.5 3.3 x 10' ~
Zirconium (40) 3 13.5 1.8x t D' "Zr.93 81.1 3 4.9x t 0' ~
40 81.1 Zr.95 1080 6.6x103 1.8xl9' 0.2 5.41
~l 27.0 9.3 x 10
Zr-97 0.9 2.5x 10 -
0.3 24.3 7.9x103 8.11 0.3 2.1x 10' -
8.11 7. Ix 10' l.9x10' -
TABLE A-2.--GENERAL VALUES FOR Al AND A 2 h I '
Me$ M M Siiff M EM M B1WRM9&
Only beta - or gamma-emitting nuclides are BEMPWM9Bn!
known to be present............................
............ 0.2 5 Alpha-emitting nuclides are known to be 0.02 0.5 present, or no relevant data are available.... ....
0.10 2.70 2 x10-5 5.41x10
4 NOTES: This section was repealed and reenacted on _
j compatibility to conform to NRC regulations foundas in transportation ofradioactive material.
a matter of 10 g andCFR Palt 1.
j If adopted this resolution shall take effect immediately York City Charter.
ote ew in accordan 34