ML20097D394
| ML20097D394 | |
| Person / Time | |
|---|---|
| Issue date: | 04/01/2020 |
| From: | Office of Nuclear Material Safety and Safeguards |
| To: | |
| Beardsley M | |
| Shared Package | |
| ML20097D175 | List: |
| References | |
| Download: ML20097D394 (11) | |
Text
DRAFT B 03/27/2020 1
DEPARTMENT OF PUBLIC HEALTH AND ENVIRONMENT 1
Hazardous Materials and Waste Management Division 2
RADIATION CONTROL - TRANSPORTATION OF RADIOACTIVE MATERIALS 3
6 CCR 1007-1 Part 17 4
[Editors Notes follow the text of the rules at the end of this CCR Document.]
5 6
Adopted by the Board of Health September 20, 2017August 19, 2020, effective date November 14, 7
2017October 15, 2020.
8 PART 17: TRANSPORTATION OF RADIOACTIVE MATERIALS 9
GENERAL PROVISIONS 10 11
[ * *
- INDICATES NO CHANGES TO THIS PORTION OF THE RULE]
12 13 17.1.4 Applicability.
14 17.1.4.1 This part applies to any person who transports radioactive material or delivers 15 radioactive material to a carrier for transport.
16 (1)
This part applies in particular to any licensee authorized by specific or general 17 license to receive, possess, use, or transfer licensed material, if the licensee 18 delivers that material to a carrier for transport, transports the material outside the 19 site of usage as specified in the license, or transports that material on a public 20 highway.
21 (2)
The transport of licensed material or delivery of licensed material to a carrier for 22 transport is subject to the:
23 (a)
General provisions of 17.1 through 17.5, including referenced DOT 24 regulations; 25 (b)
Quality assurance requirements of 10 CFR Part 71; and 26 (c)
Operating controls and procedures requirements of 17.11 through 17.17.
27 28 29 30 17.1.5 Published Material Incorporated by Reference.
31 Commented [JSJ1]:
Editorial note 1: All comments (such as this one) shown in the right side margin of this draft document are for information only to assist the reader in understanding the proposed rule change during the review and comment process.
These side margin notes are not part of the rule and all comments will be deleted prior to publication of the final rule.
Editorial note 2: Alignment and formatting corrections and minor typographical adjustments may be made in the rule and may not be specifically identified with a side margin comment.
Editorial note 3: The acronym RATS-20##-# refers to the U.S. Nuclear Regulatory Commission (NRC) regulatory action tracking system. This system is used to identify and summarize changes to federal regulations that may be required for adoption by an NRC agreement state. To maintain agreement state status, Colorados radiation regulations must be compatible with federal regulations of the NRC.
Colorado statute also prescribes that the radiation control regulations must be consistent with the model regulations of the Conference of Radiation Control Program Directors, Inc. (CRCPD). To date, the CRCPD model regulation equivalent to part 17 has not been updated for consistency with the 2018 federal rule changes.
Commented [JSJ2]:
These dates reflect anticipated adoption and effective dates based on the current rulemaking schedule.
Dates are subject to change pending additional review, approvals, and department rulemaking and Board of Health schedule.
Commented [JSJ3]:
A new provision is added to this section for consistency with the Colorado Administrative Procedure Act (24 103(12.5)(a)(2), CRS).
CODE OF COLORADO REGULATIONS 6 CCR 1007-1 Part 17 Hazardous Materials and Waste Management Division 2
In accordance with Section 24-4-103(12.5)(c), CRS, https://www.colorado.gov/cdphe/radregs 32 identifies where incorporated material is available to the public on the internet at no cost. If the 33 incorporated material is not available on the internet at no cost to the public, copies of the 34 incorporated material has been provided to the State Publications Depository and Distribution 35 Center, also known as the State Publications Library. The State Librarian at the State Publication 36 Library retains a copy of the material and will make the copy available to the public.
37 The materials incorporated by reference in this Part include only those versions that were 38 in effect at the time of the most recent adoption of this Part, and not later amendments to 39 the incorporated material, unless a prior version of the incorporated material is otherwise 40 specifically noted, and in such case that prior version shall apply.
41 17.2 Definitions.
42 17.2.1 Definitions of general applicability to these regulations are in Part 1, Section 1.2.2.
43 17.2.2 Terms used in Part 17 have the definitions set forth as follows.
44 "Certificate holder" means a person who has been issued a Certificate of Compliance or other 45 package approval by the NRC.
46 "Certificate of Compliance" (COC) means the certificate issued by the NRC under subpart D of 10 47 CFR Part 71 which approves the design of a package for the transportation of radioactive 48 material 49 50 51 Criticality Safety Index (CSI)" means the dimensionless number (rounded up to the next tenth) 52 assigned to and placed on the label of a fissile material package, to designate the degree of 53 control of accumulation of packages, overpacks, or freight containers containing fissile material 54 during transportation. Determination of the criticality safety index is described in 10 CFR Part 55 71.22, 71.23, and 71.59. The criticality safety index for an overpack, freight container, 56 consignment or conveyance containing fissile material packages is the arithmetic sum of the 57 criticality safety indices of all the fissile material packages contained within the overpack, freight 58 container, consignment or conveyance.
59 60 61 62 Low specific activity material (LSA material) means radioactive material with limited specific 63 activity which is nonfissile or is excepted under Part 17 and which satisfies the descriptions and 64 limits set forth in the following section. Shielding materials surrounding the LSA material may not 65 be considered in determining the estimated average specific activity of the package contents. The 66 LSA material must be in one of three groups:
67 68 69
CODE OF COLORADO REGULATIONS 6 CCR 1007-1 Part 17 Hazardous Materials and Waste Management Division 3
(3)
LSA-III. Solids (e.g., consolidated wastes, activated materials), excluding 70 powders, that satisfy the requirements of 10 CFR Part 71.77, in which:
71 72 73 74 Packaging means the assembly of components necessary to ensure compliance with the 75 packaging requirements of 10 CFR Part 71. It may consist of one or more receptacles, absorbent 76 materials, spacing structures, thermal insulation, radiation shielding, and devices for cooling or 77 absorbing mechanical shocks. The vehicle, tie-down system, and auxiliary equipment may be 78 designated as part of the packaging.
79 80 81 82 Regulations of the DOT means the regulations in 49 CFR Parts 100-189 and Parts 390-397 83 (October 1, 2016).
84 Regulations of the NRC means the regulations in 10 CFR Part 71 (January 1, 2016) for 85 purposes of Part 17.
86 87 88 89 LICENSE-RELATED REGULATORY REQUIREMENTS 90 17.3 Requirement for License.
91 No person shall transport radioactive material or deliver radioactive material to a carrier for 92 transport except as authorized in a general or specific license issued by the Department, an 93 Agreement State, a Licensing State, or NRC, or as exempted in 17.4 94 17.4 Exemptions.
95 17.4.1 Common and contract carriers, freight forwarders, and warehouse workers which are subject to 96 the requirements of the DOT in 49 CFR Part 170 through 189, or the U.S. Postal Service in the 97 Postal Service Manual (Domestic Mail Manual), are exempt from the requirements of Part 17 to 98 the extent that they transport or store radioactive material in the regular course of their carriage 99 for others or storage incident thereto. Common and contract carriers who are not subject to the 100 requirements of the DOT or U.S. Postal Service are subject to 17.3 and other applicable 101 requirements of these regulations.
102 103 104
CODE OF COLORADO REGULATIONS 6 CCR 1007-1 Part 17 Hazardous Materials and Waste Management Division 4
105 17.4.3 Fissile materials meeting the requirements of one of the paragraphs (a) through (f) in 10 CFR 106 Part 71.15 are exempt from classification as fissile material, and from the fissile material package 107 standards of 10 CFR Part 71.55 and 10 CFR Part 71.59, but are subject to all other requirements 108 of 10 CFR Part 71, except as noted in paragraphs (a) through (f) in 10 CFR Part 71.15.
109 110 111 112 17.7 General License: NRC-Approved Packages.
113 17.7.1 A general license is hereby issued to any licensee of the Department to transport, or to deliver to 114 a carrier for transport, licensed material in a package for which a license, NRC issued Certificate 115 of Compliance, or other approval has been issued by the NRCDepartment.
116 17.7.2 This general license applies only to a licensee who has a quality assurance program approved by 117 the DepartmentNRC as satisfying the provisions of Subpart H (excluding 71.101(c)(2), (d), and 118 (e) and 71.107 through 71.125) of 10 CFR Part 71.
119 17.7.3 Each licensee issued a general license under Section 17.7.1 shall:
120 17.7.3.1 Maintain a copy of the NRC issued Certificate of Compliance, or other approval 121 of the package, and the drawings and other documents referenced in the 122 approval relating to the use and maintenance of the packaging and to the actions 123 to be taken before shipment; 124 17.7.3.2 Comply with the terms and conditions of the license, NRC issued Certificate of 125 Compliance, or other approval issued by the DepartmentNRC, as applicable, 126 and the applicable requirements of Subparts A (excluding 71.11), G (excluding 127 71.85(a)-(c), and 71.91(b)), and H (excluding 71.101(c)(2), (d), and (e) and 128 71.107 through 71.125) of 10 CFR Part 71; and 129 17.7.3.3 Prior to the licensee's first use of the package, submit to the Department in 130 writing:Submit in writing before the first use of the package to: ATTN:
131 Document Control Desk, Director, Division of Fuel Management, Office of 132 Nuclear Material Safety and Safeguards, using an appropriate method 133 listed in 10 CFR Part 71.1(a), the licensees name and license number and 134 the package identification number specified in the package approval.
135 (1)
The licensees name and license number; and 136 (2)
The package identification number specified in the package approval.
137 17.7.4 The general license in 17.7.1 applies only when the package approval authorizes use of the 138 package under this general license.
139 17.7.5 For a Type B or fissile material package, the design of which was approved by NRC before April 140 1, 1996, the general license in 17.7.1 is subject to additional restrictions of 10 CFR Part 71.19.
141 17.8 General Licenses: Use of Foreign-Approved and Other Approved Packages 142 Commented [JSJ4]:
Language is updated in 17.7 based on a past NRC comment in correspondence dated March 8, 2018 associated with RATS 2015-3, and changes identified in RATS 2019-2 for consistency with the current 10 CFR Part 71.17.
The proposed language clarifies that only NRC issues the Certificate of Compliance document and grants the general license for transportation.
The revised language in 17.7.2 and 17.7.3 also clarifies that prior to the first use of a package, documentation must be submitted to NRC rather than the Department.
(See March 8, 2018 letter re rescinding of prior NRC comment).
Provision 17.7 is also formatted for alignment.
NRC Compatibility B.
Commented [JSJ5]:
The text of provisions (1) and (2) are incorporated into 17.7.3.3 above, following the format and flow of the federal rule.
CODE OF COLORADO REGULATIONS 6 CCR 1007-1 Part 17 Hazardous Materials and Waste Management Division 5
17.8.1 A general license is issued to any licensee of the Department to transport, or to deliver to a 143 carrier for transport, licensed material in a package, the design of which has been approved in a 144 foreign national competent authority certificate, that has been revalidated by the DOT as meeting 145 the applicable requirements of 49 CFR Part 171.23.
146 17.8.2 Except as otherwise provided in this section, the general license applies only to a licensee who 147 has a quality assurance program approved by the DepartmentNRC as satisfying the applicable 148 provisions of 10 CFR Part 71.101 through 71.137, excluding 71.101(c)(2), (d), and (e) and 71.107 149 through 71.125.
150 17.8.3 This general license applies only to shipments made to or from locations outside the United 151 States.
152 17.8.4 Each licensee issued a general license under Section 17.8.1 shall:
153 (1)
Maintain a copy of the applicable certificate, the revalidation, and the drawings 154 and other documents referenced in the certificate, relating to the use and 155 maintenance of the packaging and to the actions to be taken before shipment; 156 and 157 (2)
Comply with the terms and conditions of the certificate and revalidation, and with 158 the applicable requirements of Part 17, sections 17.1 through 17.5, 17.10 through 159 17.17, and Subparts A (excluding 71.11), G (excluding 71.85(a)-(c), and 160 71.91(b)), and H (excluding 71.101(c)(2), (d), and (e) and 71.107 through 71.125) 161 of 10 CFR Part 71..
162 17.9 General Licenses: Fissile Material Transport 163 17.9.1 A general license is hereby issued to any licensee to transport fissile material, or to deliver fissile 164 material to a carrier for transport, if the licensee meets the requirements of 10 CFR Part 71.22 165 and the material is shipped in accordance with 10 CFR Part 71.22 and each applicable 166 requirement of Part 17.
167 17.9.2 A general license is hereby issued to any licensee to transport fissile material in the form of 168 plutonium-beryllium (Pu-Be) special form sealed sources, or to deliver fissile material in the form 169 of plutonium-beryllium (Pu-Be) special form sealed sources to a carrier for transport, if the 170 licensee meets the requirements of 10 CFR Part 71.23 and the material is shipped in accordance 171 with 10 CFR Part 71.23 and each applicable requirement of Part 17.
172 QUALITY ASSURANCE 173 17.10 Quality Assurance Requirements.
174 17.10.1 Subpart H of 10 CFR Part 71 describes quality assurance requirements applying to design, 175 purchase, fabrication, handling, shipping, storing, cleaning, assembly, inspection, testing, 176 operation, maintenance, repair, and modification of components of packaging that are important 177 to safety. As used in Subpart H of 10 CFR Part 71, quality assurance comprises all those 178 planned and systematic actions necessary to provide adequate confidence that a system or 179 component will perform satisfactorily in service. Quality assurance includes quality control, which 180 comprises those quality assurance actions related to control of the physical characteristics and 181 quality of the material or component to predetermined requirements.
182 17.10.2 Each licensee is responsible for satisfying the applicable quality assurance requirements that 183 apply to its use of a packaging for the shipment of licensed material subject to the applicable 184 Commented [JSJ6]:
Language is updated in 17.10.1 to address changes described in RATS 2019-2 for consistency with 10 CFR Part 71.101 and to address editorial comments in NRC correspondence dated March 8, 2018.
As noted by NRC in RATS 2019-2, the proposed language clarifies that for Colorado licensees (or those working under reciprocity), the Department rather than NRC is to approve the quality assurance plan before the use of packages subject to the requirements of Subpart H of 10 CFR Part 71.
NRC Compatibility C.
Commented [JSJ7]: Provision updated for consistency with 10 CFR Part 71.101(c)(1) per RATS 2019-2. (See agreement state notes associated with this item).
CODE OF COLORADO REGULATIONS 6 CCR 1007-1 Part 17 Hazardous Materials and Waste Management Division 6
requirements of set forth in Subpart H of 10 CFR Part 71 (excluding 10 CFR 71.101(c)(2), (d),
185 and (e) and 10 CFR 71.107 through 71.125).
186 17.10.3 Before the use of any package for the shipment of licensed material subject to Subpart H 187 of 10 CFR Part 71, each licensee shall obtain Department approval of its quality assurance 188 program. Each licensee shall file with the Department, a description of its quality 189 assurance program, including a discussion of which requirements of Subpart H of 10 CFR 190 Part 71 are applicable and how they will be satisfied.
191 17.10.24 Radiography containers.
192 A program for transport container inspection and maintenance limited to radiographic exposure 193 devices, source changers, or packages transporting these devices and meeting the requirements 194 of Part 5, sections 5.12(4).4 through 5.12(6).6 or equivalent Agreement State or NRC 195 requirement, is deemed to satisfy the requirements of 17.7.2 and 10 CFR Part 71.101(b).
196 17.11 Advance Notification of Shipment of Nuclear Waste.
197 17.11.1 As specified in 17.11.3, 17.11.4, and 17.11.5, each licensee shall provide advance notification to 198 the governor of a state, or the governors designee, of the shipment of licensed material (nuclear 199 waste), within or across the boundary of the state, before the transport, or delivery to a carrier, for 200 transport, of licensed material outside the confines of the licensees plant or other place of use or 201 storage.
202 17.11.2 As specified in 17.11.3, 17.11.4, and 17.11.5 of this section, after June 11, 2013, each licensee 203 shall provide advance notification to the Tribal official of participating Tribes referenced in 204 17.11.4.3(3), or the officials designee, of the shipment of licensed material, within or across the 205 boundary of the Tribes reservation, before the transport, or delivery to a carrier, for transport, of 206 licensed material outside the confines of the licensees plant or other place of use or storage.
207 17.11.3 Advance notification is also required under this section for the shipment of licensed material, 208 other than irradiated fuel, meeting the following three conditions:
209 17.11.3.1 The licensed material is required by this part to be in Type B packaging for 210 transportation; 211 17.11.3.2 The licensed material is being transported to or across a state boundary en route 212 to a disposal facility or to a collection point for transport to a disposal facility; and 213 17.11.3.3 The quantity of licensed material in a single package exceeds the least of the 214 following:
215 (1) 3000 times the A1 value of the radionuclides as specified in Appendix 17A, Table 216 A1 for special form radioactive material; or 217 (2) 3000 times the A2 value of the radionuclides as specified in Appendix 17A, Table 218 A1 for normal form radioactive material; or 219 (3) 1000 TBq (27,000 Ci).
220 17.11.4 Procedures for submitting advance notification 221 17.11.4.1 The notification must be made in writing to:
222 (1)
The office of each appropriate governor or governors designee; 223 Commented [JSJ8]: Section 17.11 formatted for alignment.
CODE OF COLORADO REGULATIONS 6 CCR 1007-1 Part 17 Hazardous Materials and Waste Management Division 7
(2)
The office of each appropriate Tribal official or Tribal officials designee; 224 (3)
The Department.
225 17.11.4.2 A notification delivered by mail must be postmarked at least 7 days before the 226 beginning of the 7 day period during which departure of the shipment is 227 estimated to occur.
228 17.11.4.3 A notification delivered by any other means than mail must reach the office of the 229 governor or of the governors designee or the Tribal official, or Tribal officials 230 designee at least 4 days before the beginning of the 7-day period during which 231 departure of the shipment is estimated to occur.
232 (1)
A list of the names and mailing addresses of the governors designees receiving 233 advance notification of transportation of nuclear waste was published in the 234 Federal Register on June 30, 1995 (60 FR 34306) 235 (2)
Contact information for each State, including telephone and mailing addresses of 236 governors and governors designees, and participating Tribes, including 237 telephone and mailing addresses of Tribal officials and Tribal officials designees, 238 is available on the NRC Web site at: https://scp.nrc.gov/special/designee.pdf.
239 (3)
A list of the names and mailing addresses of the governors designees and Tribal 240 officials designees of participating Tribes is available on request from the 241 Director, Division of Material Safety, State, Tribal, and RulemakingMaterials 242 Safety, Security, State, and Tribal Programs, Office of Nuclear Material Safety 243 and Safeguards, U.S. Nuclear Regulatory Commission, Washington, DC 20555-244 0001.
245 17.11.4.4 The licensee shall retain a copy of the notification as a record for 3 years.
246 17.11.5 Information to be furnished in advance notification of shipment.
247 17.11.5.1 Each advance notification of nuclear waste shall contain the following 248 information:
249 (1)
The name, address, and telephone number of the shipper, carrier, and receiver 250 of the nuclear waste shipment; 251 (2)
A description of the nuclear waste contained in the shipment, as required by 49 252 CFR Part 172.202 and 172.203(d);
253 (3)
The point of origin of the shipment and the 7-day period during which departure 254 of the shipment is estimated to occur; 255 (4)
The 7-day period during which arrival of the shipment at state boundaries or 256 Tribal reservation boundaries is estimated to occur; 257 (5)
The destination of the shipment, and the 7-day period during which arrival of the 258 shipment is estimated to occur; and 259 (6)
A point of contact with a telephone number for current shipment information.
260 17.11.6 Revision notice 261 Commented [JSJ9]: Due to an NRC organizational change, the Division title is modified here, consistent with the 2018 changes to 10 CFR 71.97(c)(3)(iii).
NRC Compatibility B NRC RATS 2018-3
CODE OF COLORADO REGULATIONS 6 CCR 1007-1 Part 17 Hazardous Materials and Waste Management Division 8
17.11.6.1 A licensee who finds that schedule information previously furnished to a governor 262 or governors designee or a Tribal official or Tribal officials designee, in 263 accordance with this section, will not be met, shall:
264 (1)
Telephone a responsible individual in the office of the governor of the state or of 265 the governors designee or the Tribal official or Tribal officials designee an inform 266 that individual of the extent of the delay beyond the schedule originally reported; 267 and 268 (2)
Maintain a record of the name of the individual contacted for 3 years.
269 17.11.7 Cancellation notice 270 17.11.7.1 Each licensee who cancels a nuclear waste shipment, for which advance 271 notification has been sent, shall:
272 (1)
Send a cancellation notice to the governor of each state, or governor's designee 273 previously notified, each Tribal official or Tribal officials designee previously 274 notified and to the Department; 275 (2)
State in the notice that it is a cancellation and identify the advance notification 276 that is being cancelled; and 277 (3)
Retain a copy of the notice for 3 years.
278 279 280 281 17.14 Preliminary Determinations.
282 Before the first use of any packaging for the shipment of radioactive material the licensee shall ascertain 283 that the determinations in paragraphs (a) through (c) of 10 CFR Part 71.85 have been made by the 284 certificate holder.
285 17.15 Routine Determinations.
286 287 288 289 17.15.7 Any structural part of the package which could be used to lift or tie down the package during 290 transport is rendered inoperable for the purpose unless it satisfies design requirements specified 291 in 10 CFR Part 71.45; 292 17.15.8 The level of non-fixed (removable) radioactive contamination on the external surfaces of each 293 package offered for shipment is as low as reasonably achievable and within the limits specified in 294 49 CFR Part 173.443.
295 17.15.8.1 Determination of the level of non-fixed (removable) contamination shall be based 296 upon wiping an area of 300 square centimeters of the surface concerned with an 297
CODE OF COLORADO REGULATIONS 6 CCR 1007-1 Part 17 Hazardous Materials and Waste Management Division 9
absorbent material, using moderate pressure, and measuring the activity on the wiping 298 material.
299 (1)
The number and location of measurements shall be sufficient to yield a 300 representative assessment of the removable contamination levels.
301 (2)
Other methods of assessment of equal or greater detection efficiency may be 302 used.
303 17.15.8.2 In the case of packages transported as exclusive use shipments by rail or 304 highway only, the non-fixed (removable) radioactive contamination:
305 (1)
At the beginning of transport shall not exceed the levels specified in 49 CFR Part 306 173.443; and 307 (2)
At any time during transport shall not exceed 10 times the levels specified in 49 308 CFR Part 173.443.
309 17.15.9 External radiation levels around the package and around the vehicle, if applicable, shall not 310 exceed:
311 17.15.9.1 2 mSv/h (200 millirem per hour) at any point on the external surface of the 312 package at any time during transportation; 313 17.15.9.2 A transport index of 10.0.
314 17.15.10 For a package transported in exclusive use by rail, highway or water, radiation levels 315 external to the package may exceed the limits specified in 17.15.9 but shall not exceed 316 any of the following:
317 17.15.10.1 2 mSv/h (200 millirem per hour) on the accessible external surface of the 318 package unless the following conditions are met, in which case the limit is 10 319 mSv/h (1000 millirem per hour);
320 (1)
The shipment is made in a closed transport vehicle, 321 (2)
Provisions are made to secure the package so that its position within the vehicle 322 remains fixed during transportation, and 323 (3)
No loading or unloading operation occurs between the beginning and end of the 324 transportation.
325 17.15.10.2 2 mSv/h (200 millirem per hour) at any point on the outer surface of the vehicle, 326 including the upper and lower surfaces, or, in the case of a flat-bed style vehicle, 327 with a personnel barrier, at any point on the vertical planes projected from the 328 outer edges of the vehicle, on the upper surface of the load (or enclosure, if 329 used), and on the lower external surface of the vehicle; 330 (1)
A flat bed style vehicle with a personnel barrier shall have radiation levels 331 determined at vertical planes.
332 (2)
If no personnel barrier is in place, the package cannot exceed 2 mSv/h (200 333 millirem per hour) at any accessible surface.
334 Commented [JSJ10]:
Sections 17.15.9 through 7.15.15 are formatted for alignment of text.
CODE OF COLORADO REGULATIONS 6 CCR 1007-1 Part 17 Hazardous Materials and Waste Management Division 10 17.15.10.3 0.1 mSv/h (10 millirem per hour) at any point 2 meters from the vertical planes 335 represented by the outer lateral surfaces of the vehicle, or, in the case of a flat-336 bed style vehicle, at any point 2 meters from the vertical planes projected from 337 the outer edges of the vehicle; and 338 17.15.10.4 0.02 mSv/h (2 millirem per hour) in any normally occupied positions of the 339 vehicle, except that this provision does not apply to private motor carriers when 340 persons occupying these positions are provided with special health supervision, 341 personnel radiation exposure monitoring devices, and training in accordance with 342 10.3; and 343 17.15.11 For shipments made under the provisions of Section 17.15.10, the shipper shall provide 344 specific written instructions to the carrier for maintenance of the exclusive use shipment 345 controls. The instructions must be included with the shipping paper information.
346 17.15.12 The written instructions required for exclusive use shipments must be sufficient so that, 347 when followed, they will cause the carrier to avoid actions that will:
348 17.15.12.1 Unnecessarily delay delivery; or 349 17.15.12.2 Unnecessarily result in increased radiation levels or radiation exposures to 350 transport workers or members of the general public.
351 17.15.13 A package must be prepared for transport so that in still air at 100 degrees Fahrenheit 352 (38 degrees Celsius) and in the shade, no accessible surface of a package would have a 353 temperature exceeding 50 degrees Celsius (122 degrees Fahrenheit) in a nonexclusive 354 use shipment or 82 degrees Celsius (185 degrees Fahrenheit) in an exclusive use 355 shipment. Accessible package surface temperatures shall not exceed these limits at any 356 time during transportation.
357 17.15.14 A package may not incorporate a feature intended to allow continuous venting during 358 transport.
359 17.15.15 Before delivery of a package to a carrier for transport, the licensee shall ensure that any 360 special instructions needed to safely open the package have been sent to the consignee, 361 or otherwise made available to the consignee, for the consignee's use in accordance with 362 4.32.5.2.
363 364 365 366 17.17.1.4 Type and quantity of licensed material in each package, and the total quantity of 367 each shipment; 368 369 17.17.1.10 Results of the determinations required by 17.15 and by the conditions of the 370 package approval.
371 372 373 Commented [JSJ11]: Formatted for alignment of text.
Commented [JSJ12]: Formtatted for alignment of text.
CODE OF COLORADO REGULATIONS 6 CCR 1007-1 Part 17 Hazardous Materials and Waste Management Division 11 Appendix 17A - Determination of A1 and A2 374 17A1 Values of A1 and A2 for individual radionuclides, which are the bases for many activity limits 375 elsewhere in these regulations are given in Table 17A1. The curie (Ci) values specified are 376 obtained by converting from the Terabecquerel (TBq) value. The Terabecquerel values are the 377 regulatory standard. The curie values are for information only and are not intended to be the 378 regulatory standard. Where values of A1 or A2 are unlimited, it is for radiation control purposes 379 only. For nuclear criticality safety, some materials are subject to controls placed on fissile 380 material.
381 17A2 For individual radionuclides whose identities are known, but which are:
382 17A2.1 Not listed in Table 17A1:
383 (1)
The A1 and A2 values Table 17A3 may be used.
384 (2)
Otherwise, the licensee shall obtain prior NRC approval of the A1 and A2 values 385 for radionuclides not listed in Table 17A1, before shipping the material. The 386 licensee shall submit such request for prior approval to NRC in accordance with 387 10 CFR Part 71.1.
388 389 390 391
[ NO CHANGES TO REMAINDER OF RULE OR SUBSEQUENT TABLES ]
392 Commented [JSJ13]: Prior to final publication, ensure that Appendix 7A begins on a new page.